ML032120517

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June 2003 Monthly Operating Report for Oconee, McGuire and Catawba
ML032120517
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 07/17/2003
From: Tuckman M
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032120517 (28)
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Text

i I

Duke

  • rPowere A Duke Energy Company MICHAEL S. TUCKMAN Executive Vice President Nuclear Generation Duke Power P.O. Box 1006 Charlotte, NC 28201-1006 Mailing Address:

526 South Church Street Charlotte, NC 28202 704 382 2200 704 382 4360 fax July 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 - June,-2003 Please find attached information concerning the performance and operation status of the Oconee, McGuire and Catawba Nuclear Stations for the month of June, 2003.

Any questions or comments may be directed to Roger A. Williams at (704) 382-5346.

Sincerely, M. S. Tuckman

"::Ceo www. duke-energy. corn

Page 2 U.S. Nuclear Regulatory Commission Monthly Performance and Operation Status July 17, 2003 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

Operating Data Report Docket No.

Date Completed By Telephone 50-269 July 15.2003 Roger Williams 704-382-5346 Operating Status

1. Unit Name:

Oconee 1

2. Reporting Period:

June 1, 2003 -June 30, 2003

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 720.0
12. Number of Hours Reactor was Critical 720.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 720.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 1848344
17. Gross Electrical Energy Generated (MWH) 648607
18. Net Electrical Energy Generated (MWH) 621213
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 102.0
22. Unit Capacity Factor (Using DER Net) 97.4
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 4343.0 4343.0 0.0 4343.0 0.0 11058015 3886259 3725087 100.0 100.0 101.4 96.8 0.0 Cumulative 262608.0 207906.1 0.0 204403.1 0.0 506260669 175137566 166599133 77.8 77.8 74.3 71.6 9.1

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 Achieved NRC Calculated from Generator Nameplate Data:

1 037 937 KVA x 0.90 Pf=934 MW 3A - 7/15/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee 1 DATE: June 16. 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: Mav. 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 A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training/License Examination F - Administrative

- Operator Error (Explain)

H - Other (Explain)

(2) Method 1 - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - Other (Explain) 3C - 7/15/2oo3

MONTHLY REFUELING INFORMATION REOUEST

1.

Facility name:

Oconee Unit I

2.

Scheduled next refueling shutdown: Seotember 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: 177 (b) in the spent fuel pool: 902*

(c) in the ISFSI: 1824****

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: July 15. 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.

Date Completed By Telephone 50-270 July 15.2003 Roger Williams 704-382-5346 Operating Status

1. Unit Name:

Oconee 2

2. Reporting Period:

June 1, 2003 - June 30, 2003

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 720.0
12. Number of Hours Reactor was Critical 720.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 720.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 1846495
17. Gross Electrical Energy Generated (MWH) 646251
18. Net Electrical Energy Generated (MWH) 619460
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 101.7
22. Unit Capacity Factor (Using DER Net) 97.1
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 4343.0 4343.0 0.0 4343.0 0.0 11143682 3927614 3769394 100.0 100.0 102.6 98.0 0.0 Cumulative 252528.0 205428.8 0.0 202849.7 0.0 501697237 172580598 164495712 80.3 80.3 76.3 73.5 8.4

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 - 7/15/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: July 15.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June, 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 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) 3 - 71512003

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: 902*

(c) in the ISFSI: See unit 1 ****

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: July 15.2003 Name of

Contact:

R. A. Williams Phone: (704) - 382-5346 Represents the combined total for Units 1 and 2 See footnote on 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 1

Operating Data Report Docket No.

Date Completed By Telephone 50-287 July 15.2003 Roger Williams 704-382-5346 Operating Status

1. Unit Name:

Oconee 3

2. Reporting Period:

June 1, 2003 -June 30, 2003

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 720.0
12. Number of Hours Reactor was Critical 360.8
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 289.9
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 726641
17. Gross Electrical Energy Generated (MWH) 242427
18. Net Electrical Energy Generated (MWH) 222456
19. Unit Service Factor 40.3
20. Unit Availability Factor 40.3
21. Unit Capacity Factor (Using MDC Net) 36.5
22. Unit Capacity Factor (Using DER Net) 34.9
23. Unit Forced Outage Rate 59.7
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 4343.0 3123.8 0.0 3050.9 0.0 7578270 2656563 2533371 70.2 70.2 69.0 65.8 12.4 Cumulative 250175.0 198176.6 0.0 195457.0 0.0 488837930 169205838 161433016 78.1 78.1 75.6 72.8 9.1

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 - 7/15/2003

Page: 1 of 2 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: July 15.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June. 2003 No.

Date:

Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown RIX Event Report S - Scheduled No.

OUTAGE DELAY OF 4.54 DAYS DUE TO CHROMATE CONTAMINATION 2

06/01/03 F

108.97 A

4 IN REACTOR BUILDING OUTAGE DELAY OF 5.50 DAYS DUE TO POWER OPERATED RELIEF 3

06/05/03 F

132.00 A

4 BLOCK VALVE 3RC4 LEAK OUTAGE DELAY OF 1.25 DAYS DUE TO REHEATER STEAM SUPPLY 4

06/11/03 F

30.00 A

4 VALVE CONTROL PROBLEM OUTAGE DELAY OF 0.77 DAYS DUE TO REACTOR VESSEL HEAD 5

06/12/03 F

18.50 A

4REMOVAL PROBLEM OUTAGE DELAY OF 1.96 DAYS DUE TO PROBLEM LOADING FUEL 6

06/13/03 F

47.00 A

4 ASSEMBLIES 7

06/15/03 F

24.00 A

4 OUTAGE DELAY OF 1 DAY DUE TO TURBINE LUBE OIL SYSTEM Summary:

The unit began the month of June in end-of-cycle 20 refueling outage. The refueling outage was delayed due to the following; 5.46 days due to chromate contamination in the reactor building, 5.50 days due to power operated relief block valve 3RC4 leak, 1.25 days due to reheater steam supply valve control problem, 0.77 days due to reactor vessel head removal problem, 1.96 days due to problem loading fuel assemblies, 1 day due to turbine lube oil system, 0.17 days due to reactor building polar crane, 0.54 days due to low pressure service water valve control problem, 0.56 days due to control drive system relay problem. The refueling outage spanned 52.20 days. The unit was placed on-line 06/17/03 at 0647 holding at 17% power until 06/17/03 at 0712. The unit held at 26% power from 0839 to 0924 to place turbine steam extractions in service.The unit held at 37% power from 1024 to 1327 due to stator coolant pressure low alarm and main generator pressure decreasing. The unit held at 73% power from 1956 to 06/18/03 (Con'td)

(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 - 7/15/2003

Page: 2 of 2 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: July 7. 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June. 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.

OUTAGE DELAY OF 0.17 DAYS DUE TO REACTOR BUILDING POLAR 8

06/16/03 F

4.00 A

4 CRANE OUTAGE DELAY OF 0.54 DAYS DUE TO LOW PRESSURE SERVICE 9

06/16/03 F

13.00 A

4 WATER VALVE CONTROL PROBLEM OUTAGE DELAY OF 0.56 DAYS DUE TO CONTROL DRIVE SYSTEM 10 06/16/03 F

13.32 A

4 RELAY PROBLEM 11 06t28/03 F

39.28 A

-BALANCE TURBINE DUE TO VIBRATION Summary:

at 0524 due to power escalation testing. The unit resumed power escalation, and held at 89% power from 0854 to 0921 due to nuclear instrumentation calibration check. The unit held at 90% power from 06/18/03 at 0929 to 1028 to evaluate 3D1/3D2 heater drain pump leak. The unit held at 93% pwer from 1151 to 1430 due to nuclear instrumentation calibration. The unit returned to 100% full power on 06/18/03 at 1932 and operated at or near 100% full power until 06/28/03 at 0049 when the unit began decreasing power due to turbine vibration. The unit was taken off-line 06/28/03 at 0344 to balance turbine due to vibration. The unit was placed on-line 06/29/03 at 1901 holding at 15% power until 2008..The unit held at 90% power from 06/30/03 at 0311 to 0428 and at 99% power from 0525 to 0535 due to nuclear instrumentation calibration check..

The unit returned to 100% full power on 06/30/03 at 0550 and operated at or near 100% 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 1 - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - Other (Explain) 3C - 715/2003

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 1 ****

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: July 15.2003 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 1

OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT MAY 2003

1.

Personnel Exposure -

The total station liquid release for MAY 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 MAY 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 1 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: June 16.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: May, 2003 No.

Date:

Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown RIX Event Report S - Scheduled No.

1 05/01/03 S

744.00 C

4 END-OF-CYCLE 20 REFUELING OUTAGE OUTAGE DELAY OF 0.92 DAYS DUE TO CHROMATE 2 06/01/03 F

22.03 A

~~~~~CONTAMINATION IN REACTOR BUILDING Summary:

The unit began the month of May in end-of-cycle 20 refueling outage. The unit remained in the outage the remainder of the month.

(1) Reason A - Equipment failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory restriction (2) Method 1 - 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 - 7/15/2003

Operating Data Report Docket No.

Date Completed By Telephone 50-369 July 15.2003 Roger Williams 704-382-5346 Operating Status

1. Unit Name:

McGuire 1

2. Reporting Period:

June 1, 2003 - June 30, 2003

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 ii, 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 720.0
12. Number of Hours Reactor was Critical 720.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 720.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 2453854
17. Gross Electrical Energy Generated (MWH) 843753
18. Net Electrical Energy Generated (MWH) 812940
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 102.6
22. Unit Capacity Factor (Using DER Net) 95.7
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 4343.0 4343.0 0.0 4343.0 0.0 14697461 5136339 4958304 100.0 100.0 103.8 96.8 0.0 Cumulative 189167.0 147368.5 0.0 146067.5 0.0 471602716 162638997 155874147 77.2 77.2 72.7 69.8 9.1

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 Achieved 3A - 7/15/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50369 UNIT NAME: McGuire 1 DATE: July 15.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June. 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 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 - 7/15/2003

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: July 15. 2003 Name of

Contact:

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

Operating Data Report Docket No.

Date Completed By Telephone 50-370 July 15.2003 Roger Williams 704-382-5346 Operating Status

1. Unit Name:

McGuire 2

2. Reporting Period:

June 1, 2003 - June 30, 2003

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 ii, 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 720.0
12. Number of Hours Reactor was Critical 720.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 720.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 2450478
17. Gross Electrical Energy Generated (MWH) 844976
18. Net Electrical Energy Generated (MWH) 814827
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 102.9
22. Unit Capacity Factor (Using DER Net) 95.9
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 4343.0 4343.0 0.0 4343.0 0.0 14625727 5108859 4929535 100.0 100.0 103.2 96.2 0.0 Cumulative 169463.0 140129.8 0.0 138876.0 0.0 458814087 159664964 153312329 82.0 82.0 80.2 76.7 5.3

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 Achieved 3A - 7/15/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-370 UNIT NAME: McGuire 2 DATE: July 15.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June. 2003 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 1 - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - Other (Explain) 3C-7/15/2003

MONTHLY REFUELING INFORMATION REQUEST

1.

Facility name:

McGuire Unit 2

2.

Scheduled next refueling shutdown: September 2003

3.

Scheduled restart following refueling: October 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: 1061 (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: July 15.2003 Name of

Contact:

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

McGUIRE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT MAY 2003

1.

Personnel Exposure -

The total station liquid release for MAY 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 MAY 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 July 15.2003 Roger Williams 704-382-5346 Operating Status

1. Unit Name:

Catawba 1

2. Reporting Period:

June 1, 2003 -June 30, 2003

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

This Month 720.0 720.0 0.0 720.0 0.0 2452047 872067 827166 100.0 100.0 101.8 100.3 0.0 YTD 4343.0 4312.6 0.0 4305.9 0.0 14642605 5244925 4978100 99.1 99.1 101.5 100.1 0.9 Cumulative 157824.0 131417.9 0.0 129901.5 0.0 429507090 152490848 143875786 82.3 82.3 80.6 79.6 5.4

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 Achieved 3A - 7/15/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50413 UNIT NAME: Catawba 1 DATE: July 15. 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: Jn%2 003 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 - 71512003

MONTHLY REFUELING INFORMATION REQUEST

1.

Facility name:

Catawba Unit 1

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: July 15,2003 Name of

Contact:

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

Operating Data Report Docket No.

Date Completed By Telephone 50-414 July 15.2003 Roger Williams 704-382-5346 Operating Status

1. Unit Name:

Catawba 2

2. Reporting Period:

June 1, 2003 -June 30, 2003

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 ii, 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 720.0
12. Number of Hours Reactor was Critical 720.0
13. Reactor Reserve Shutdown Hours 0.0
14. Hours Generator On-Line 720.0
15. Unit Reserve Shutdown Hours 0.0
16. Gross Thermal Energy Generated (MWH) 2425342
17. Gross Electrical Energy Generated (MWH) 865533
18. Net Electrical Energy Generated (MWH) 822952
19. Unit Service Factor 100.0
20. Unit Availability Factor 100.0
21. Unit Capacity Factor (Using MDC Net) 101.2
22. Unit Capacity Factor (Using DER Net) 99.8
23. Unit Forced Outage Rate 0.0
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)

YTD 4343.0 3731.5 0.0 3700.0 0.0 12414248 4460858 4233645 85.2 85.2 86.3 85.1 0.3 Cumulative 147840.0 123536.5 0.0 122080.8 0.0 401384075 143106907 135218460 82.6 82.6 80.9 79.9 6.7

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 Achieved 3A - 7/15/2003

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-414 UNIT NAME: Catawba 2 DATE: July 15.2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June. 2003 No.

Date:

Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown RIX Event Report S - Scheduled No.

No Outages for the Month

I.

I I

I I

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 - 715/2003

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: July 15.2003 Name of

Contact:

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

CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT MAY 2003

1.

Personnel Exposure -

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

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