ML033290434

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October 2003 Monthly Operating Reports for Oconee McGuire and Catawba Nuclear Stations
ML033290434
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 11/17/2003
From: Mccollum W
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML033290434 (28)
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Text

Duke Power Company

_DuAC ADWke Ened Compny WSPower. Energy Center A DukeEneV Company P.O. Box 1006 Charlotte, NC 28201-1006 November 17, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Subject:

Duke Energy Corporation Oconee Nuclear Station, Docket Nos. 50-269, -270, -287 McGuire Nuclear Station, Docket Nos. 50-369, -370 Catawba Nuclear Station, Docket Nos. 50-413, -414 Monthly Performance and Operation Status - October, 2003 Please find attached information concerning the performance and operation status of the Oconee, McGuire and Catawba Nuclear Stations for the month of October 2003.

Please direct any questions or comments to Roger A. Williams at (704) 382-5346.

Sincerely, W. R. McCollum, Jr Senior Vice President Nuclear Support

$1_

U.S. Nuclear Regulatory Commission Monthly Performance and Operation Status November 17, 2003 Page 2 xc: L. A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center 61 Forsythe Street SW, Suite 23T85 Atlanta, GA 30303-8931 R. E. Martin, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555 L. N. Olshan, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555 Ms. Margaret Aucoin Nuclear Assurance Corporation 3930 E. Jones Bridge Road #300 Norcross, GA 30092-2107 INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 Dottie Sherman, ANI Library American Nuclear Insurers Town Center, Suite 300S 29 South Main Street West Hartford, CT 06107-2445 M. Shannon, Senior Resident Inspector, Oconee Nuclear Station J. Brady, Senior Resident Inspector, McGuire Nuclear Station E. Guthrie, Senior Resident Inspector, Catawba Nuclear Station

U.S. Nuclear Regulatory Commission Monthly Performance and Operation Status November 17, 2003 Page 3 bxc: M. T. Cash - ECO50 C. J. Thomas - MG01 RC L. E. Nicholson - ON03RC R. A. Williams - ECO5Z (2 copies)

Catawba Date File - CN01 RC (Attn: Jill Ferguson)

North Carolina Municipal Power Piedmont Municipal Power Agency North Carolina Electric Membership Corp.

Saluda River Electric Catawba File 801.01 - CN04DM McGuire File 801.01 - MG01 DM Oconee File 801.01 - ON03DM ELL - ECO50

Operating Data Report Docket No. 50-269 Date November 17,2003 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Oconee I
2. Reporting Period: October 1, 2003 -October 31, 2003
3. Licensed Thermal Power (MNVt): 2568 Notes: Year-to-date
4. Nameplate Rating (Gross MWe): 934 and cumulative capacity factors are
5. Design Electrical Rating (Net Mwe): 886 calculated using a
6. Maximum Dependable Capacity (Gross MWe): 886 weighted average for
7. Maximum Dependable Capacity(Net MWe): 846 maximum dependable
8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons: capacity.
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month YTD Cumulative

11. Hours in Reporting Period 745.0 7296.0 265561.0
12. Number of Hours Reactor was Critical 0.0 6289.1 209852.2
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 0.0 6288.0 206348.1
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 0 15701986 510904640
17. Gross Electrical Energy Generated (MWH) 0 5497806 176749113
18. Net Electrical Energy Generated (MWH) 0 5256380 168130426
19. Unit Service Factor 0.0 86.2 77.7
20. Unit Availability Factor 0.0 86.2 77.7
21. Unit Capacity Factor (Using MDC Net) 0.0 85.2 74.2
22. Unit Capacity Factor (Using DER Net) 0.0 81.3 71.5
23. Unit Forced Outage Rate 0.0 0.0 9.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data:

1 037 937 KVA x 0.90 Pf=934 MW 3A - 11/17/2003

Page: 1 of I UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee I DATE: November 17,2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 2003 No. Date: Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F -Forced Hours Shutdown R/X Event Report S - Scheduled No.

i 10/01/034 S 745.00 C END OF CYCLE 21 REFUELING AND STEAM GENERATOR/REACTOR 1 10/01/03 S 745.00 C VESSEL HEAD REPLACEMENT OUTAGE Summary:

Oconee unit I began the month of October in a outage due to end-of-cycle 21 refueling and steam generator/reactor vessel head replacement. The unit remained in the end-of-cycle 21 refueling and steam generator/reactor vessel head replacement outage for the remainder of the month.

(1) Reason (2) Method A - Equipment failure (Explain) E - Operator Training/License Examination I - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit 1
2. Scheduled next refueling shutdown: Currently Refueling
3. Scheduled restart following refueling: December 2003 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

5. Scheduled date(s) for submitting proposed licensing action and supporting information.
6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7. Number of Fuel assemblies (a) in the core: 177 (b) in the spent fuel pool: 938*

(c) in the ISFSI: 1848****

8. Present licensed fuel pool capacity: 1312 Size of requested or planned increase: **
9. Projected date of last refueling which can be accommodated by present capacity: January 2005***

DUKE POWER COMPANY DATE: November 17.2003 Name of

Contact:

R. A. Williams Phone: (704) - 382-5346

  • Represents the combined total for Units 1 and 2
    • On March 29, 1990, received a site specific license for ISFSI which will store 2112 assemblies (88 modules). Forty (40) site specific modules were constructed and loaded.
      • In 1999 Oconee transitioned to its general license. Forty-four (44) general license modules were installed and 30 modules have now been loaded.

Additional modules will be installed on an as-needed basis.

        • Represents the combined total for Units 1, 2, and 3

Operating Data Report Docket No. 50-270 Date November 17.2003 Completed By Roger Williams Telephone 704-382-5346 Operating Status 1.Unit Name: Oconee 2

2. Reporting Period: October 1, 2003 - October 31, 2003
3. Licensed Thermal Power (MWt): 2568 Notes: Year-to-date
4. Nameplate Rating (Gross MWe): 934 and cumulative -

capacity factors are

5. Design Electrical Rating (Net Mwe): 886 calculated using a
6. Maximum Dependable Capacity (Gross MWe): . 886 weighted average for
7. Maximum Dependable Capacity(Net MWe): 846 maximum dependable
8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons: capacity.
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month YTD Cumulative

11. Hours in Reporting Period 745.0 7296.0 255481.0
12. Number of Hours Reactor was Critical 745.0 7296.0 208381.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 745.0 7296.0 205802.7
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1909359 18734279 509287834
17. Gross Electrical Energy Generated (MWH) 669234 6575535 175228519
18. Net Electrical Energy Generated (MWH) 640218 6302287 167028605
19. Unit Service Factor 100.0 100.0 80.6
20. Unit Availability Factor 100.0 100.0 80.6
21. Unit Capacity Factor (Using MDC Net) 101.6 102.1 76.6
22. Unit Capacity Factor (Using DER Net) 97.0 97.5 73.8
23. Unit Forced Outage Rate 0.0 0.0 8.3
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data:

1 037 937 KVA x 0.90 Pf=934 MW 3A - 11/17/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: November 17.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October. 2003 No. Date: Type Duration (1)Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown R/X Event Report S - Scheduled No.

No Outages for the Month Summary:

(1) Reason (2) Method A - Equipment failure (Explain) E - Operator Training/License Examination I - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit 2
2. Scheduled next refueling shutdown: March, 2004
3. Scheduled restart following refueling: June, 2004 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

5. Scheduled date(s) for submitting proposed licensing action and supporting information.
6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7. Number of Fuel assemblies (a) in the core: 177 (b) in the spent fuel pool: 938*

(c) in the ISFSI: See unit I ****

8. Present licensed fuel pool capacity: 1312 Size of requested or planned increase: **
9. Projected date of last refueling which can be accommodated by present capacity: January 2005***

DUKE POWER COMPANY DATE: November 17.2003 Name of

Contact:

R. A. Williams Phone: (7041 - 382-5346

  • Represents the combined total for Units I and 2
    • See footnote on Unit I
      • In 1999 Oconee transitioned to its general license. Forty-four (44) general license modules were installed and 30 modules have now been loaded.

Additional modules will be installed on an as-needed basis.

        • See footnote on Unit I

Operating Data Report Docket No. 50-287 Date November 17.2003 Completed By Rocer Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Oconee 3
2. Reporting Period: October 1, 2003 - October 31, 2003
3. Licensed Thermal Power (MWt): 2568 Notes: Year-to-date
4. Nameplate Rating (Gross MWe): 934 and cumulative capacity factors are
5. Design Electrical Rating (Net Mwe): 886 calculated using a
6. Maximum Dependable Capacity (Gross MWe): 886 weighted average for
7. Maximum Dependable Capacity(Net MWe): 846 maximum dependable
8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons: capacity.
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month YTD Cumulative

11. Hours in Reporting Period 745.0 7296.0 253128.0
12. Number of Hours Reactor was Critical 745.0 6102.7 201155.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 745.0 6003.9 198410.0
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1913057 15157773 496417433
17. Gross Electrical Energy Generated (MWH) 665711 5290327 171839602
18. Net Electrical Energy Generated (MWH) 636675 5052463 163952108
19. Unit Service Factor 100.0 82.3 78.4
20. Unit Availability Factor 100.0 82.3 78.4
21. Unit Capacity Factor (Using MDC Net) 101.0 81.9 75.9
22. Unit Capacity Factor (Using DER Net) 96.5 78.2 73.1
23. Unit Forced Outage Rate 0.0 7.0 9.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data:

1 037 937 KVA x 0.90 Pf=934 MW 3A- 11/17/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: November 17.2003 COMPLETED BY: Rocer Williams TELEPHONE: 704-382-5346 REPORT MONTH: October. 2003 No. Date: Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown RX Event Report S - Scheduled No.

No Outages for the Month Summary:

(1) Reason (2) Method A - Equipment failure (Explain) E - Operator Training/License Examination I - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit 3
2. Scheduled next refueling shutdown: October 2004
3. Scheduled restart following refueling: December 2004 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

5. Scheduled date(s) for submitting proposed licensing action and supporting information.
6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7. Number of Fuel assemblies (a) in the core: 177 (b) in the spent fuel pool: 476 (c) in the ISFSI: See Unit I ****
8. Present licensed fuel pool capacity: 825 Size of requested or planned increase: **
9. Projected date of last refueling which can be accommodated by present capacity: January 2005***

DUKE POWER COMPANY DATE: November 17,2003 Name of

Contact:

R. A. Williams Phone: (704) - 382-5346

    • See footnote of Unit 1
      • In 1999 Oconee transitioned to its general license. Forty-four (44) general license modules were installed and 30 modules have now been loaded.

Additional modules will be installed on an as-needed basis.

        • See footnote on Unit I

OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT SEPTEMBER 2003

1. Personnel Exposure -

The total station liquid release for SEPTEMBER has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

The total station gaseous release for SEPTEMBER has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

Operating Data Report Docket No. 50-369 Date November 17.2003 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: McGuire 1
2. Reporting Period: October 1, 2003 -October 31, 2003
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossMNVe)
5. Design Electrical Rating (Net Mwe): 1180 calculated as 1450.000
6. Maximum Dependable Capacity (Gross MWe): 1144 MVA * .90 power
7. Maximum Dependable Capacity(Net MWe): 1100 factor per Page iii, NUREG-0020.
8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month YTD Cumulative I 1. Hours in Reporting Period 745.0 7296.0 192120.0

12. Number of Hours Reactor was Critical 745.0 7296.0 150321.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 745.0 7296.0 149020.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2540181 24748856 481654111
17. Gross Electrical Energy Generated (MWH) 868042 8543800 166046458
18. Net Electrical Energy Generated (MWH) 835536 8236971 159152814
19. Unit Service Factor 100.0 100.0 77.6
20. Unit Availability Factor 100.0 100.0 77.6
21. Unit Capacity Factor (Using MDC Net) 102.0 102.6 73.1
22. Unit Capacity Factor (Using DER Net) 95.0 95.7 70.2
23. Unit Forced Outage Rate 0.0 0.0 9.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation 3A - 11/17/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-369 UNIT NAME: McGuire I DATE: November 17.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 2003 No. Date: Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown R/X Event Report S - Scheduled _ No.

No Outages for the Month Summary:

(1) Reason (2) Method A - Equipment failure (Explain) E - Operator Training/License Examination I - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: McGuire Unit 1
2. Scheduled next refueling shutdown: March 2004
3. Scheduled restart following refueling: April 2004 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

5. Scheduled date(s) for submitting proposed licensing action and supporting information.
6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7. Number of Fuel assemblies (a) in the core: 193 (b) inthespentfuelpool: 1011
8. Present licensed fuel pool capacity: 1463 Size of requested or planned increase: =-
9. Projected date of last refueling which can be accommodated by present license capacity:

November 2005 DUKE POWER COMPANY DATE: November 17.2003 Name of

Contact:

R. A. Williams Phone: (704) - 382-5346

Operating Data Report Docket No. 50-370 Date November 17,2003 Completed By Rocer Williams Telephone 704-382-5346 Operating Status

1. Unit Name: McGuire 2
2. Reporting Period: October 1, 2003-October 31, 2003
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossMNN'e)
5. Design Electrical Rating (Net Mwe): 1180 calculated as 1450.000
6. Maximum Dependable Capacity (Gross MWe): 1144 MVA * .90 power
7. Maximum Dependable Capacity(Net MWe): 1100 factor per Pagc iii, NUREG-0020.
8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month YTD Cumulative

11. Hours in Reporting Period 745.0 7296.0 172416.0
12. Number of Hours Reactor was Critical 610.5 6560.7 142347.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 610.5 6560.7 141093.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1930162 22023776 466212136
17. Gross Electrical Energy Generated (MWH) 663331 7624332 162180437
18. Net Electrical Energy Generated (MWH) 633383 7343543 155726337
19. Unit Service Factor 81.9 89.9 81.8
20. Unit Availability Factor 81.9 89.9 81.8
21. Unit Capacity Factor (Using MDC Net) 77.3 91.5 80.1
22. Unit Capacity Factor (Using DER Net) 72.0 85.3 76.5
23. Unit Forced Outage Rate 7.0 0.7 5.3
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation 3A - 11/17/2003

Page: 1 of 2 UNIT SHUTDOWNS DOCKET NO. 50-370 UNIT NAME: McGuire 2 DATE: November 17,2003 COMPLETED BY: RogerWilliams TELEPHONE: 704-382-5346 REPORT MONTH: October. 2003 No. Date: Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown R/X Event Report S - Scheduled No.

1 10/01/03 S 87.97 C 4 END OF CYCLE 15 REFUELING OUTAGE OUTAGE DELAY OF 0.38 DAYS DUE TO 2A REACTOR COOLANT 2 10/04/03 F 9.00 A 4 FILTER VENT VALVE LEAK OUTAGE DELAY OF 0.25 DAYS DUE TO REACTOR COOLANT SYSTEM 3 10/05/03 F 6.00 A 4 CLEAN-UP EXTENDED OUTAGE DELAY OF 0.25 DAYS DUE TO REACTOR COOLANT SYSTEM 4 10/05/03 F 6.00 A 4 LEVEL INSTRUMENTATION PROBLEM OUTAGE DELAY OF 0.29 DAYS DUE TO N32 AND N36 NEUTRON 5 10/05/03 F 7.00 A 4 DETECTOR PROBLEMS OUTAGE DELAY OF 0.29 DAYS DUE TO UPPER CONTAINMENT 6 10/05/03 F 7.00 A CONTAMINATION Summary:

McGuire unit 2 began the month of October, 2003 in end-of-cycle 15 refueling outage. The refueling outage was delayed due to the following reasons; 0.38 days due to 2A reactor coolant filter vent valve leak, 0.25 days due to reactor coolant system clean-up extended, 0.25 days due to reactor coolant system level instrumentation problem, 0.29 days due to N32 and N36 neutron detector problems, 0.29 days due to upper containment contamination, 0.38 days due to 2ND15B residual heat removal valve failed, 0.08 days due to zero power physics testing delays. The refueling outage spanned 30.61 days. The unit was placed on-line 10/06/03 at 1349 holding at 16% power due to turbine soak. The turbine overspeed trip test was performed 10/06/03 at 1746 and the unit placed on-line 10/06/03 at 1828. During power escalation, the unit held at 25% power from 10/07/03 at 0427 to 0633 to place 2A feedwater pump in auto. The unit held at 29% power from 0800 to 10/08/03 at 0454 due to flux mapping, turbine driven auxiliary feedwater pump run and trouble with extraction steam. The unit held at 44% power from 0920 to 1358 to place 2B feedwater pump in-service. Cont'd (1) Reason (2) Method A - Equipment failure (Explain) E - Operator Training/License Examination 1 - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

Page: 2 of 2 UNIT SHUTDOWNS DOCKET NO. 50-370 UNIT NAME: McGuire 2 DATE: November 13, 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH!: October. 2003 No. Date: Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown R/X Event Report S - Scheduled No. l OUTAGE DELAY OF 0.38 DAYS DUE TO 2ND15B RESIDUAL HEAT 7 10/06/03 F 9.00 A 4 REMOVAL VALVE FAILED OUTAGE DELAY OF 0.08 DAYS DUE TO ZERO POWER PHYSICS 8 10/06/03 F 1.85 B 4 TESTING DELAYS 9 10/06/03 S 0.70 B TURBINE OVERSPEED TRIP TEST Summary:

On 10/09/03 from 0501 to 2232 the unit held at 78% power due to flux mapping, main condensate valve 2CM-85 (Gland steam condenser bypass control) problems and leakage calculation. The unit held at 90% power on 10/10/03 from 0233 to 1007 for thermal power output calculation. The unit held at 95% power from 1156 to 1300 for axial flux difference control. The unit returned to 100% full power on 10/11/03 at 0630 and operated at or near 100% full power the remainder of the month.

(1) Reason (2) Method A - Equipment failure (Explain) E - Operator Training/License Examination I - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

MONTHLY REFUELING INFORMATION REOUEST

1. Facility name: McGuire Unit 2
2. Scheduled next refueling shutdown: March 2005
3. Scheduled restart following refueling: April 2005 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

5. Scheduled date(s) for submitting proposed licensing action and supporting information.
6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7. Number of Fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 1138 (c) in the ISFSI: 320
8. Present licensed fuel pool capacity: 1463 Size of requested or planned increase: -
9. Projected date of last refueling which can be accommodated by present license capacity:

June 2003 DUKE POWER COMPANY DATE: November 17.2003 Name of

Contact:

R. A. Williams Phone: (704) - 382-5346

McGUIRE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT SEPTEMBER 2003

1. Personnel Exposure -

The total station liquid release for SEPTEMBER has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

The total station gaseous release for SEPTEMBER has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

Operating Data Report Docket No. 50-413 Date November 17.2003 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Catawba I
2. Reporting Period: October 1, 2003 - October 31, 2003
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossM We)
5. Design Electrical Rating (Net Mwe): 1145 calculated as 1450.000
6. Maximum Dependable Capacity (Gross MWe): 1192 MVA * .90 power
7. Maximum Dependable Capacity(Net MWe): 1129 factor per Page iii, NUREG-0020.
8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month YTD Cumulative

11. Hours in Reporting Period 745.0 7296.0 160777.0
12. Number of Hours Reactor was Critical 745.0 7002.3 134107.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 745.0 6990.8 132586.4
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2538398 23683216 438547701
17. Gross Electrical Energy Generated (MWH) 908004 8457502 155703425
18. Net Electrical Energy Generated (MWH) 862977 8015614 146913300
19. Unit Service Factor 100.0 95.8 82.5
20. Unit Availability Factor 100.0 95.8 82.5
21. Unit Capacity Factor (Using MDC Net) 102.6 97.3 80.8
22. Unit Capacity Factor (Using DER Net) 101.2 96.0 79.8
23. Unit Forced Outage Rate 0.0 4.2 5.5
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation 3A - 11/17/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-413 UNIT NAME: Catawba I DATE: November 17.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 2003 No. Date: Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown RX Event Report S - Scheduled No.

No Outages for the Month Summary:

(1) Reason (2) Method A - Equipment failure (Explain) E - Operator Training/License Examination I - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Catawba Unit I
2. Scheduled next refueling shutdown: November 2003
3. Scheduled restart following refueling: December 2003 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

5. Scheduled date(s) for submitting proposed licensing action and supporting information.
6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7. Number of Fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 944
8. Present licensed fuel pool capacity: 1418 Size of requested or planned increase: =
9. Projected date of last refueling which can be accommodated by present license capacity:

November 2009 DUKE POWER COMPANY DATE: November 17.2003 Name of

Contact:

R. A. Williams Phone: (704) - 382-5346

Operating Data Report Docket No. 50-414 Date November 17.2003 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Catawba 2
2. Reporting Period: October 1, 2003 - October 31, 2003
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossMWe)
5. Design Electrical Rating (Net Mwe): 1145 calculated as 1450.000
6. Maximum Dependable Capacity (Gross MWe): 1192 MVA * .90 power
7. Maximum Dependable Capacity(Net MWe): 1129 factor per Page iii, NUREG-0020.
8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month YTD Cumulative

11. Hours in Reporting Period 745.0 7296.0 150793.0
12. Number of Hours Reactor was Critical 745.0 6684.5 126489.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 745.0 6653.0 125033.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2539512 22442746 411412573
17. Gross Electrical Energy Generated (MWH) 912737 8037686 146683735
18. Net Electrical Energy Generated (MWH) 866982 7631525
  • 138616340
19. Unit Service Factor 100.0 91.2 82.9
20. Unit Availability Factor 100.0 91.2 82.9
21. Unit Capacity Factor (Using MDC Net) 103.1 92.6 81.3
22. Unit Capacity Factor (Using DER Net) 101.6 91.4 80.3
23. Unit Forced Outage Rate 0.0 0.2 6.5
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation 3A- 11/17/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-414 UNIT NAME: Catawba 2 DATE: November 17. 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October. 2003 No. Date: Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown R/X Event Report S - Scheduled No.

No Outages for the Month Summary:

(1) Reason (2) Method A - Equipment failure (Explain) E - Operator TraininglLicense Examination 1 - Manual 2 - Manual Trip/Scram B - Maintenance or Test F - Administrative 3 - Automatic Trip/Scram 4 - Continuation C - Refueling G - Operator Error (Explain) 5 - Other (Explain)

D - Regulatory restriction H - Other (Explain) 3C- 11/17/2003

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Catawba Unit 2
2. Scheduled next refueling shutdown: September 2004
3. Scheduled restart following refueling: October 2004 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

5. Scheduled date(s) for submitting proposed licensing action and supporting information.
6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7. Number of Fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 917
8. Present licensed fuel pool capacity: 1418 Size of requested or planned increase: --
9. Projected date of last refueling which can be accommodated by present license capacity:

May 2012 DUKE POWER COMPANY DATE: November 17.2003 Name of

Contact:

R. A. Williams Phone: (704) - 382-5346

CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT SEPTEMBER 2003

1. Personnel Exposure -

The total station liquid release for SEPTEMBER has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

The total station gaseous release for SEPTEMBER-has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

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