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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_Duke f-Powere A Duke Energy Company HENRY B. BARRON Group VP, Nuclear Generation and Chief Nuclear Officer 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 hbarron@duke-energy.com February 15, 2005 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.

Date Completed By Telephone 50-269 February 15.2005 Roger Williams 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

4. Nameplate Rating (Gross MWe):

934

5. Design Electrical Rating (Net Mwe):

886

6. Maximum Dependable Capacity (Gross MWe):

886

7. Maximum Dependable Capacity(Net MWe):

846

8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:

Notes: Year-to-date and cumulative capacity factors are calculated using a weighted average for maximum dependable capacity.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month

11. Hours in Reporting Period 744.0
12. Number of Hours Reactor was Critical 744.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 744.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 1910592
17. Gross Electrical Energy Generated (MWH) 668001
18. Net Electrical Energy Generated (MWH) 640439
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 101.8
22. Unit Capacity Factor (Using DER Net) 97.2
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 744.0 744.0 0.0 744.0 0.0 1910592 668001 640439 100.0 100.0 101.8 97.2 0.0 Cumulative 276553.0 219326.8 0.0 215641.8 0.0 534650217 185010529 176019697 78.0 78.0 74.6 71.8 8.9

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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method I - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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.

Date Completed By Telephone 50-270 February 15.2005 Roger Williams 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

4. Nameplate Rating (Gross MWe):

934

5. Design Electrical Rating (Net Mwe):

886

6. Maximum Dependable Capacity (Gross MWe):

886

7. Maximum Dependable Capacity(Net MWe):

846

8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:

Notes: Year-to-date and cumulative capacity factors are calculated using a weighted average for maximum dependable capacity.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month

11. Hours in Reporting Period 744.0
12. Number of Hours Reactor was Critical 744.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 744.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 1909976
17. Gross Electrical Energy Generated (MWH) 677290
18. Net Electrical Energy Generated (MWH) 650712
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 103.4
22. Unit Capacity Factor (Using DER Net) 98.7
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 744.0 744.0 0.0 744.0 0.0 1909976 677290 650712 100.0 100.0 103.4 98.7 0.0 Cumulative 266473.0 217335.4 0.0 214663.5 0.0 531851310 183165391 174615749 80.6 80.6 76.8 74.0 8.1

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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method I - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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.

Date Completed By Telephone 50-287 February 15,2005 Roger Williams 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

4. Nameplate Rating (Gross MWe):

934

5. Design Electrical Rating (Net Mwe):

886

6. Maximum Dependable Capacity (Gross MWe):

886

7. Maximum Dependable Capacity(Net MWe):

846

8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:

Notes: Year-to-date and cumulative capacity factors are calculated using a weighted average for maximum dependable capacity.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month

11. Hours in Reporting Period 744.0
12. Number of Hours Reactor was Critical 721.7
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 671.5
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 1675774
17. Gross Electrical Energy Generated (MWH) 589198
18. Net Electrical Energy Generated (MWH) 563198
19. Unit Service Factor 90.3
20. Unit Availability Factor 90.3
21. Unit Capacity Factor (Using MDC Net) 89.5
22. Unit Capacity Factor (Using DER Net) 85.4
23. Unit Forced Outage Rate 3.8
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 744.0 721.7 0.0 671.5 0.0 1675774 589198 563198 90.3 90.3 89.5 85.4 3.8 Cumulative 264120.0 210094.7 0.0 207245.0 0.0 518992729 179745829 171515138 78.5 78.5 76.1 73.3 8.7

25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

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

1 037 937 KVA x 0.90 Pf=934 MW Achieved 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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method I - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method I - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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.

Date Completed By Telephone 50-369 February 15.2005 Roger Williams 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

4. Nameplate Rating (Gross MWe):

1305 *

5. Design Electrical Rating (Net Mwe):

1180

6. Maximum Dependable Capacity (Gross MWe):

1144

7. Maximum Dependable Capacity(Net MWe):

1100

8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:

Notes: *Nameplate Rating (GrossMWe) calculated as 1450.000 MVA *.90 power factor per Page iii, NUREG-0020.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month

11. Hours in Reporting Period 744.0
12. Number of Hours Reactor was Critical 744.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 744.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 2536823
17. Gross Electrical Energy Generated (MWH) 891767
18. Net Electrical Energy Generated (MWH) 861863
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 105.3
22. Unit Capacity Factor (Using DER Net) 98.2
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 744.0 744.0 0.0 744.0 0.0 2536823 891767 861863 100.0 100.0 105.3 98.2 0.0 Cumulative 203112.0 159876.1 0.0 158551.0 0.0 513959945 177243408 169928684 78.1 78.1 74.0 70.9 8.8

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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method I - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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.

Date Completed By Telephone 50-370 February 15.2005 Roger Williams 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

4. Nameplate Rating (Gross MWe):

1305 *

5. Design Electrical Rating (Net Mwe):

1180

6. Maximum Dependable Capacity (Gross MWe):

1144

7. Maximum Dependable Capacity(Net MWe):

1100

8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:

Notes: *Nameplate Rating (GrossMWe) calculated as 1450.000 MVA *.90 power factor per Page iii, NUREG-0020.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month

11. Hours in Reporting Period 744.0
12. Number of Hours Reactor was Critical 744.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 744.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 2536260
17. Gross Electrical Energy Generated (MWH) 889596
18. Net Electrical Energy Generated (MWH) 859203
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 105.0
22. Unit Capacity Factor (Using DER Net) 97.9
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 744.0 744.0 0.0 744.0 0.0 2536260 889596 859203 100.0 100.0 105.0 97.9 0.0 Cumulative 183408.0 153368.0 0.0 152085.6 0.0 503667570 175179385 168263830 82.9 82.9 81.5 77.7 4.9

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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method 1 - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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.

Date Completed By Telephone 50-413 February 15.2005 Roger Williams 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

4. Nameplate Rating (Gross MWe):

1305 *

5. Design Electrical Rating (Net Mwe):

1145

6. Maximum Dependable Capacity (Gross MWe):

1192

7. Maximum Dependable Capacity(Net MWe):

1129

8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:

Notes: *Nameplate Rating (GrossM We) calculated as 1450.000 MVA *.90 power factor per Page iii, NUREG-0020.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month

11. Hours in Reporting Period 744.0
12. Number of Hours Reactor was Critical 744.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 744.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 2333549
17. Gross Electrical Energy Generated (MWH) 834182
18. Net Electrical Energy Generated (MWH) 789149
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 93.9
22. Unit Capacity Factor (Using DER Net) 92.6
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 744.0 744.0 0.0 744.0 0.0 2333549 834182 789149 100.0 100.0 93.9 92.6 0.0 Cumulative 171769.0 143978.1 0.0 142113.5 0.0 470249869 166983048 157575828 82.7 82.7 81.1 80.1 5.4

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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction (2) Method I - Manual

  • E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain) 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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.

Date Completed By Telephone 50-414 February 15.2005 Roger Williams 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

4. Nameplate Rating (Gross MWe):

1305 *

5. Design Electrical Rating (Net Mwe):

1145

6. Maximum Dependable Capacity (Gross MWe):

1192

7. Maximum Dependable Capacity(Net MWe):

1129

8. If Changes Occured in Capacity Ratings (Items Number 3-7) Since Last Report, Give Reasons:

Notes: *Nameplate Rating (GrossMWe) calculated as 1450.000 MVA *.90 power factor per Page iii, NUREG-0020.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reason for Restrictions, If any:

This Month

11. Hours in Reporting Period 744.0
12. Number of Hours Reactor was Critical 744.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 744.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 2534016
17. Gross Electrical Energy Generated (MWH) 913443
18. Net Electrical Energy Generated (MWH) 869468
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 103.5
22. Unit Capacity Factor (Using DER Net) 102.1
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 744.0 744.0 0.0 744.0 0.0 2534016 913443 869468 100.0 100.0 103.5 102.1 0.0 Cumulative 161785.0 136395.9 0.0 134915.6 0.0 444890485 158684079 150008184 83.4 83.4 82.0 81.0 6.1

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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method I - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - 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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E -Operator Training/License Examination F - Administrative G - Operator Error (Explain)

H - Other (Explain)

(2) Method I - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - Other (Explain) 3c-2/1512005

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