ML050540524

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January 2005 Monthly Operating Report for Oconee McGuire and Catawba Nuclear Stations
ML050540524
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 02/15/2005
From: Barron H
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050540524 (28)
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Text

_Duke HENRY B. BARRON f-Powere Group VP, Nuclear Generation and Chief Nuclear Officer A Duke Energy Company Duke Power EC07H / 526 South Church Street Charlotte, NC 28202-1802 Mailing Address:

P. 0. Box 1006 - EC07H Charlotte, NC 28201-1006 704 382 2200 704 382 6056 fax February 15, 2005 hbarron@duke-energy.com 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 - January 2005 Please find attached information concerning the performance and operation status of the Oconee, McGuire and Catawba Nuclear Stations for the month of January 2005 and Revision 1 of McGuire Unit 1 for the period November 2004 on Unit Shutdowns.

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

Henry B. Barron Attachment

/007 And Igob I- '(X) 1l Heritage - Service . Vision www.dukepower.comr

U.S. Nuclear Regulatory Commission Monthly Performance and Operation Status February 15, 2005 Page 2 xc: W. D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center 61 Forsythe Street SW, Suite 23T85 Atlanta, GA 30303-8931 L. N. Olshan, Senior Project Manager (ONS)

U.S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555 J. J. Shea, Project Manager (MNS)

U.S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555 S. E. Peters, Project Manager (CNS)

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

Operating Data Report Docket No. 50-269 Date February 15.2005 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Oconee 1
2. Reporting Period: January 1, 2005 -January 31, 2005
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 744.0 744.0 276553.0
12. Number of Hours Reactor was Critical 744.0 744.0 219326.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 744.0 215641.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1910592 1910592 534650217
17. Gross Electrical Energy Generated (MWH) 668001 668001 185010529
18. Net Electrical Energy Generated (MWH) 640439 640439 176019697
19. Unit Service Factor 100.0 100.0 78.0
20. Unit Availability Factor 100.0 100.0 78.0
21. Unit Capacity Factor (Using MDC Net) 101.8 101.8 74.6
22. Unit Capacity Factor (Using DER Net) 97.2 97.2 71.8
23. Unit Forced Outage Rate 0.0 0.0 8.9
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 - 2/15/2005

Page: I of 1 UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee I DATE: February 15.2005 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: January, 2005 No. Date: Type Duration (I) 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- 2115/2005

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit I
2. Scheduled next refueling shutdown: April 2005
3. Scheduled restart following refueling: May 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: 177 (b) in the spent fuel pool: 926*

(c) in the ISFSI: 1992**

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: February 15. 2005 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 February 15.2005 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Oconee 2
2. Reporting Period: January 1, 2005 -January 31, 2005
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 744.0 744.0 266473.0
12. Number of Hours Reactor was Critical 744.0 744.0 217335.4
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 744.0 214663.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1909976 1909976 531851310
17. Gross Electrical Energy Generated (MWH) 677290 677290 183165391
18. Net Electrical Energy Generated (MWH) 650712 650712 174615749
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) 103.4 103.4 76.8
22. Unit Capacity Factor (Using DER Net) 98.7 98.7 74.0
23. Unit Forced Outage Rate 0.0 0.0 8.1
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 - 2/15/2005

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: February 15.2005 COMPLETED BY: Rozer Williams TELEPHONE: 704-382-5346 REPORT MONTH: January, 2005 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 - 2/15/2005

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit 2
2. Scheduled next refueling shutdown: October, 2005
3. Scheduled restart following refueling: November, 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: .177 (b) in the spent fuel pool: 926*

(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: February 15. 2005 Name of

Contact:

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

  • Represents the combined total for Units 1 and 2
    • See footnote on Unit 1
      • a 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 February 15,2005 Completed By Roger Williams Telephone 704-382-5346 Operating Status 1.Unit Name: Oconee 3

2. Reporting Period: January 1, 2005 - January 31, 2005
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 744.0 744.0 264120.0
12. Number of Hours Reactor was Critical 721.7 721.7 210094.7
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 671.5 671.5 207245.0
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1675774 1675774 518992729
17. Gross Electrical Energy Generated (MWH) 589198 589198 179745829
18. Net Electrical Energy Generated (MWH) 563198 563198 171515138
19. Unit Service Factor 90.3 90.3 78.5
20. Unit Availability Factor 90.3 90.3 78.5
21. Unit Capacity Factor (Using MDC Net) 89.5 89.5 76.1
22. Unit Capacity Factor (Using DER Net) 85.4 85.4 73.3
23. Unit Forced Outage Rate 3.8 3.8 8.7
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 - 2/15/2005

Page: 1 of 2 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: February 15.2005 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: January, 2005 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.

0101/05 5 40.28 A 4 OUTAGE EXTENDED DUE TO CORE RELOAD PROBLEMS 2 01/02/05 S 4.00 B TURBINE OVERSPEED TRIP TEST OUTAGE DELAYED TO PERFORM TURBINE GENERATOR BALANCING 3 01103/05 F 26.28 A _DET IRTO DUE TO VIBRATION 4 01/04105 S 1.93 B TURBINE OVERSPEED TRIP TEST Summary:

Oconee unit 3 began the month of January in a outage extended 5.77 days due to core reload problems. The unit was placed on-line 01/02/05 at 1617 holding at approximately 18% power to perform the turbine overspeed trip test. The unit was taken off-line 01/02/05 at 2202 when the turbine overspeed trip failed due to #3 motor operated disconnect not opening during the test. On 01/03/05 at 0202 the outage was delayed to perform turbine generator balancing due to vibration and main steam valve #3 failed to open 01/03/05 at 1647. The unit was placed on-line 01104/05 at 0419 holding at approximately 18% power and the turbine overspeed trip test was performed at 1026. The unit returned to service on 01/04/05 at 1222 operating at approximately 18% power until 1401. During power escalation, the unit held at 40% power from 1800 to 1923 due to power escalation testing.

The unit held at 60% power from 2307 to 01105105 at 1235 for power imbalance detector correlation slope testing. The unit held at 73% power from 1536 to 2002 due to (Cont'd)

(I) 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- 2/15/2005

Page: 2 of 2 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: February 15,2005 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: January. 2005 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.

Summary:

reactor coolant flow check. On 01/05/05 from 2345 to 01/06/05 at 0021 the unit held at 90% power due to nuclear instrumentation calibration check and decrease rate of power assent. The unit returned to 100% full power on 01/06/05 at 0650 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- 2/I52005

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit 3
2. Scheduled next refueling shutdown: April 2006
3. Scheduled restart following refueling: May 2006 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: 460 (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: February 15.2005 Name of

Contact:

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

    • See footnote of 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 1

OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT DECEMBER 2004

1. Personnel Exposure -

The total station liquid release for DECEMBER 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 DECEMBER 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 February 15.2005 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: McGuire 1
2. Reporting Period: January 1, 2005-January 31, 2005
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossMWe)
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

11. Hours in Reporting Period 744.0 744.0 203112.0
12. Number of Hours Reactor was Critical 744.0 744.0 159876.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 744.0 158551.0
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2536823 2536823 513959945
17. Gross Electrical Energy Generated (MWH) 891767 891767 177243408
18. Net Electrical Energy Generated (MWH) 861863 861863 169928684
19. Unit Service Factor 100.0 100.0 78.1
20. Unit Availability Factor 100.0 100.0 78.1
21. Unit Capacity Factor (Using MDC Net) 105.3 105.3 74.0
22. Unit Capacity Factor (Using DER Net) 98.2 98.2 70.9
23. Unit Forced Outage Rate 0.0 0.0 8.8
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 - 2/15/2005

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-369 UNIT NAME: McGuire I DATE: February 15.2005 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: January, 2005 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- 2/15/2005

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: McGuire Unit I
2. Scheduled next refueling shutdown: September 2005
3. Scheduled restart following refueling: October 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: 1091
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: February 15.2005 Name of

Contact:

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

Operating Data Report Docket No. 50-370 Date February 15.2005 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: McGuire 2
2. Reporting Period: January 1, 2005 -January 31, 2005
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossMWe)
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

11. Hours in Reporting Period 744.0 744.0 183408.0
12. Number of Hours Reactor was Critical 744.0 744.0 153368.0
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 744.0 152085.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2536260 2536260 503667570
17. Gross Electrical Energy Generated (MWH) 889596 889596 175179385
18. Net Electrical Energy Generated (MWH) 859203 859203 168263830
19. Unit Service Factor 100.0 100.0 82.9
20. Unit Availability Factor 100.0 100.0 82.9
21. Unit Capacity Factor (Using MDC Net) 105.0 105.0 81.5
22. Unit Capacity Factor (Using DER Net) 97.9 97.9 77.7
23. Unit Forced Outage Rate 0.0 0.0 4.9
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 - 2/15/2005

Page: I of I UNIT SHUTDOWNS DOCKET NO. 50-370 UNIT NAME: McGuire 2 DATE: February 15.2005 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: January, 2005 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 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 - 2/15/2005

MONTHLY REFUELING INFORMATION REQUEST

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: 1090 (c) in the ISFSI: 368
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: February 15,2005 Name of

Contact:

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

McGUIRE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT DECEMBER 2004

1. Personnel Exposure -

The total station liquid release for DECEMBER 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 DECEMBER 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 February 15.2005 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Catawba 1
2. Reporting Period: January 1, 2005 -January 31, 2005
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 744.0 744.0 171769.0
12. Number of Hours Reactor was Critical 744.0 744.0 143978.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 744.0 142113.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2333549 2333549 470249869
17. Gross Electrical Energy Generated (MWH) 834182 834182 166983048
18. Net Electrical Energy Generated (MWH) 789149 789149 157575828
19. Unit Service Factor 100.0 100.0 82.7
20. Unit Availability Factor 100.0 100.0 82.7
21. Unit Capacity Factor (Using MDC Net) 93.9 93.9 81.1
22. Unit Capacity Factor (Using DER Net) 92.6 92.6 80.1
23. Unit Forced Outage Rate 0.0 0.0 5.4
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 - 2/15/2005

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-413 UNIT NAME: Catawba I DATE: February 15.2005 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: January. 2005 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- 2/1512005

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Catawba Unit 1
2. Scheduled next refueling shutdown: May 2005
3. Scheduled restart following refueling: June 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: 1021
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: February 15.2005 Name of

Contact:

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

Operating Data Report Docket No. 50-414 Date February 15.2005 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Catawba 2
2. Reporting Period: January 1, 2005 - January 31, 2005
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 744.0 744.0 161785.0
12. Number of Hours Reactor was Critical 744.0 744.0 136395.9
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 744.0 134915.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2534016 2534016 444890485
17. Gross Electrical Energy Generated (MWH) 913443 913443 158684079
18. Net Electrical Energy Generated (MWH) 869468 869468 150008184
19. Unit Service Factor 100.0 100.0 83.4
20. Unit Availability Factor 100.0 100.0 83.4
21. Unit Capacity Factor (Using MDC Net) 103.5 103.5 82.0
22. Unit Capacity Factor (Using DER Net) 102.1 102.1 81.0
23. Unit Forced Outage Rate 0.0 0.0 6.1
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 - 2/15/2005

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-414 UNIT NAME: Catawba 2 DATE: February 15,2005 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: January. 2005 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- 2/15l2005

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Catawba Unit 2
2. Scheduled next refueling shutdown: March 2006
3. Scheduled restart following refueling: April 2006 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: 993
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: February 15.2005 Name of

Contact:

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

CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT DECEMBER 2004

1. Personnel Exposure -

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

REVISION 1 Page: 1 of I UNIT SHUTDOWNS DOCKET NO. 50-369 UNIT NAME: McGuire I DATE: December 15.2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTh: November. 2004 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.

7 11/01/04 24233 A4OUTAGE DELAYED TO REPAIR AND EVALUATE MAIN STEAM 7FISOLATION VALVES ISM-1, ISM-3 AND SM-7 Summary:

McGuire began the month of November in an outage delayed to repair and evaluate main steam isolation valves lSM-1, 1SM-3 and ISM-7. On 11/11/04 at 0220 the unit was placed on-line holding at 13% power until 0250. The unit began power escalation and held at 23.5% from 0420 to 1037 to evaluate containment sump issue and secondary side power excursion due to "B" feedwater pump turbine. On 11/11/04 from 1202 to 1334 the unit held at 15.5% power to swap lB feedwater pump turbine from aux steam to main steam.

The unit held at 24% power from 1458 to 1651 to investigate lowercontainment sump input. The unit held at 34% power from 1823 to 11/12/04 at 0200 due to feedwater valve tuning and reactor coolant leakage calculations. The load was secured at 43% power from 0407 to 0541 to place "A" feedwater pump turbine in service. The unit held from 0710 to 0858 at 50% power due to feedwater valve tuning. The unit held at 90% power from 1430 to 1538 due to thermal power check. The unit returned to 100% full power on 11/12/04 at 2034 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- 2/1512005

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