ML042040263

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June 2004 Monthly Operating Report for Oconee, Units 1, 2 and 3, McGuire, Units 1 and 2 & Catawba, Units 1 and 2
ML042040263
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 07/15/2004
From: Mccollum W
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML042040263 (27)
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Text

MkDuke WILLIAM R MCCOLLUM, JR.

EP-Owere VP, Nuclear Support Duke Energy Corporation 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 8983 704 382 6056 fax July 15, 2004 wrmccoll@duke-energy. corn 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, 2004 Please find attached information concerning the performance and operation status of the Oconee, McGuire and Catawba Nuclear Stations for the month of June 2004.

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

William R. McCollum, Jr.

Attachment

  • c' ~2YF1 www. dukepower. corn

U.S. Nuclear Regulatory Commission Monthly Performance and Operation Status July 15, 2004 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, Senior 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 July 14.2004 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Oconee I
2. Reporting Period: June 1, 2004 -June 30, 2004
3. Licensed Thermal Power (MWt): 2568 Notes: Year-to-date
4. Nameplate Rating (Gross MlVe): 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 _ 720.0 4367.0 271392.0
12. Number of Hours Reactor was Critical 720.0 4256.6 214165.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 4185.1 210533.2
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1842181 10609333 521533079
17. Gross Electrical Energy Generated (MWH) 639434 3705338 180454451
18. Net Electrical Energy Generated (MWH) 612017 3545325 171664350
19. Unit Service Factor 100.0 95.8 77.6
20. Unit Availability Factor 100.0 95.8 77.6
21. Unit Capacity Factor (Using MDC Net) 100.5 96.0 74.1
22. Unit Capacity Factor (Using DER Net) 95.9 91.6 71.4
23. Unit Forced Outage Rate 0.0 4.1 9.1
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 KXiA x 0.90 Pfr934 MW 3A - 7/14/2004

Page: 1 of t UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee I DATE: July 15. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June, 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.

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- 7/14/2004

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit 1
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: 1920****

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. 2004 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 July 14.2004 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Oconee 2
2. Reporting Period: June 1, 2004 -June 30, 2004
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 720.0 4367.0 261312.0
12. Number of Hours Reactor was Critical 429.8 2328.6 212174.4
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 339.3 2235.9 209502.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 827101 5562288 518607209
17. Gross Electrical Energy Generated (MWH) 278519 1954590 178504515
18. Net Electrical Energy Generated (MWH) 254348 1854523 170149561
19. Unit Service Factor 47.1 51.2 80.2
20. Unit Availability Factor 47.1 51.2 80.2
21. Unit Capacity Factor (Using MDC Net) 41.8 50.2 76.3
22. Unit Capacity Factor (Using DER Net) 39.9 47.9 73.5
23. Unit Forced Outage Rate 40.9 9.5 8.3
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDovn 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 M1W 3A - 7/14/2004

Page: 1 of 2 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: July 15. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June, 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.

l 0 0 END-OF-CYCLE 20 REFUELING AND STEAM GENERATOR/REACTOR 1 06/01/04 S 102.23 C 4VESSEL HEAD REPLACEMENT OUTAGE OUTAGE DELAY OF 8.58 DAYS DUE TO "2A" REACTOR BUILDING 2 06/05/04 F 205.95 A 4 COOLING UNIT FAN ASSEMBLY FAILURE OUTAGE DELAY OF 1.19 DAYS DUE TO MAIN TURBINE TRIP DUE TO 3 06/13/04 F 28.57 A 4 LOW BEARING OIL PRESSURE 4 06/26/04 43.95 A REPAIR MOTOR SUCTION OIL PUMP DISCHARGE CHECK VALVE Summary:

Oconee unit 2 began the month of June, 2004 in end-of-cycle 20 refueling and steam generator/reactor vessel head replacement outage. The refueling outage was delayed due to the following reasons; 8.58 days due to "2A" reactor building cooling unit fan assembly failure, 1.19 days due to main turbine trip due to low bearing oil pressure. The refueling outage spanned 86.97 days. The unit was placed on-line 06/15/04 at 0045 holding at 19% power. The unit began increasing power 06/15/04 at 0100 and held at 25%

power from 0205 to 06/16/04 at 0018 to evaluate the turbine lube oil system. The unit resume power escalation, and held at 40% power from 0141 to 0203 and at 50% power from 0253 to 0256 due to intermediate power testing. On 06/16/04 from 0735 to 1934 the unit held at 73% power due to imbalance detector correlation slope testing. The unit experienced heater panel troubles "LPEI0" and held at 76% power from 1955 to 2014. The unit held at 90% power from 2317 to 06/17/04 at 0119 due to nuclear (Cont'd)

(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- 7/1512004

Page: 2 of 2 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: July 15. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June, 2004 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.

Summary:

instrumentation calibration. On 06/17/04 at 1639 the unit returned to 100% full power and operated at or near 100% power until 06/25/04 at 2103 when the unit began decreasing power power and was taken off-line 06/26/04 at 0010 to repair motor suction oil pump discharge check valve. The unit returned to service 06/27/04 at 2007 at approximately 18% power.

The unit returned to 100% full power on 06/28/04 at 0543 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- 7/15/2004

MONTHLY REFUELING INFORMATION REOUEST

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: July 15. 2004 Name of

Contact:

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

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

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

        • See footnote on Unit 1

Operating Data Report Docket No. 50-287 Date July 14.2004 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Oconee 3
2. Reporting Period: June 1, 2004 -June 30, 2004
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 720.0 4367.0 258959.0
12. Number of Hours Reactor was Critical 720.0 4332.3 206951.9
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 4298.5 204172.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1848960 10990218 511165970
17. Gross Electrical Energy Generated (MWH) 649368 3860343 177017519
18. Net Electrical Energy Generated (MWH) 622690 3702213 168916890
19. Unit Service Factor 100.0 98.4 78.8
20. Unit Availability Factor 100.0 98.4 78.8
21. Unit Capacity Factor (Using MDC Net) 102.2 100.2 76.5
22. Unit Capacity Factor (Using DER Net) 97.6 95.7 73.6
23. Unit Forced Outage Rate 0.0 1.6 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 NRC Calculated from Generator Nameplate Data:

1 037 937 KXVA x 0.90 Pf=934 MW 3A - 7/1412004

Page: 1 of I UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: July 15. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June, 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.

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- 7/14/2004

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee Unit 3
2. Scheduled next refueling shutdown: October 2004
3. Scheduled restart following refueling: January 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: 476 (c) in the ISFSI: See Unit I *
8. Present licensed fuel pool capacity: 825 Size of requested or planned increase: **
9. Projected date of last refueling which can be accommodated by present capacity: January 2005***

DUKE POWER COMPANY DATE: July 15. 2004 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 2004

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. 50-369 Date July 14.2004 Completed By Roier Williams Telephone 704-382-5346 Operating Status

1. Unit Name: McGuire 1
2. Reporting Period: June 1, 2004 -June 30, 2004
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossM We)
5. Design Electrical Rating (Net Mwe): 1180 calculated as 1450.000
6. Maximum Dependable Capacity (Gross MWe): 1144 MIVA * .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 720.0 4367.0 197951.0
12. Number of Hours Reactor was Critical 720.0 3498.0 155283.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 3479.5 153964.1
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2455257 11773857 498418669
17. Gross Electrical Energy Generated (MWH) 839707 4098140 171882335
18. Net Electrical Energy Generated (MWH) 809350 3944831 164773142
19. Unit Service Factor 100.0 79.7 77.8
20. Unit Availability Factor 100.0 79.7 77.8
21. Unit Capacity Factor (Using MDC Net) 102.2 82.1 73.5
22. Unit Capacity Factor (Using DER Net) 95.3 76.6 70.5
23. Unit Forced Outage Rate 0.0 3.6 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 - 7/14/2004

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-369 UNIT NAME: McGuire I DATE: July 15. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June. 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.

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- 7/14/2004

MONTHLY REFUELING INFORMATION REOUEST

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: July 15. 2004 Name of

Contact:

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

Operating Data Report Docket No. 50-370 Date July 14.2004 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: McGuire 2
2. Reporting Period: June 1, 2004 -June 30, 2004
3. Licensed Thermal Power (MWt): 3411 Notes: *Nameplate
4. Nameplate Rating (Gross MWe): 1305
  • Rating (GrossM\We)
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 I1. Hours in Reporting Period 720.0 4367.0 178247.0

12. Number of Hours Reactor was Critical 720.0 4367.0 148207.0
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 4367.0 146924.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MW-H) 2454612 14879203 486081077
17. Gross Electrical Energy Generated (MWH) 841232 5186286 169112723
18. Net Electrical Energy Generated (MWH) 810390 5003738 162414340
19. Unit Service Factor 100.0 100.0 82.4
20. Unit Availability Factor 100.0 100.0 82.4
21. Unit Capacity Factor (Using MDC Net) 102.3 104.2 80.9
22. Unit Capacity Factor (Using DER Net) 95.4 97.1 77.2
23. Unit Forced Outage Rate 0.0 0.0 5.1
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 - 7/14/2004

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-370 UNIT NAME: McGuire 2 DATE: July 15. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: June. 2004 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 SumaI 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- 7/14/2004

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 Comrmittee 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: 1138 (c) in the ISFSI: 320
8. Present licensed fuel pool capacity: 1463 Size of requested or planned increase: =-
9. Projected date of last refueling which can be accommodated by present license capacity:

June 2003 DUKE POWER COMPANY DATE: July 15. 2004 Name of

Contact:

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

McGUIRE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT MAY 2004

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. 50-413 Date July 14.2004 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Catawba I
2. Reporting Period: June 1, 2004 -June 30, 2004
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 720.0 4367.0 166608.0
12. Number of Hours Reactor was Critical 720.0 4257.1 138846.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 4251.6 137012.1
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2452433 14009380 453201546
17. Gross Electrical Energy Generated (MWII) 870224 5005683 160906116
18. Net Electrical Energy Generated (MWH) 825398 4741942 151817548
19. Unit Service Factor 100.0 97.4 82.2
20. Unit Availability Factor 100.0 97.4 82.2
21. Unit Capacity Factor (Using MDC Net) 101.5 96.2 80.6
22. Unit Capacity Factor (Using DER Net) 100.1 94.8 79.6
23. Unit Forced Outage Rate 0.0 2.6 5.6
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 - 7/14/2004

Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-413 UNIT NAME: Catawba 1 DATE: July 15. 2004 COMPLETED BY: Roner Williams TELEPHONE: 704-382-5346 REPORT MONTH: June, 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.

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- 7/14/2004

MONTHLY REFUELING INFORMATION REOUEST

1. Facility name: Catawba Unit I
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: July 15. 2004 Name of

Contact:

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

Operating Data Report Docket No. 50-414 Date July 14.2004 Completed By Roger Williams Telephone 704-382-5346 Operating Status

1. Unit Name: Catawba 2
2. Reporting Period: June 1, 2004 -June 30, 2004
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 720.0 4367.0 156624.0
12. Number of Hours Reactor wvas Critical 720.0 4367.0 132320.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 4367.0 130864.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2450666 14874329 431228998
17. Gross Electrical Energy Generated (MWH) 871559 5340S16 153802090
18. Net Electrical Energy Generated (MNWII) 827710 5078943 145381923
19. Unit Service Factor 100.0 100.0 83.6
20. Unit Availability Factor 100.0 100.0 83.6
21. Unit Capacity Factor (Using MDC Net) 101.8 103.0 82.1
22. Unit Capacity Factor (Using DER Net) 100.4 101.6 81.1
23. Unit Forced Outage Rate 0.0 0.0 6.3
24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
25. If ShutDown At End Of Report Period, Estimated Date of Startup
26. Units in Test Status (Prior to Commercial Operation)

Forcast Achieved Initial Criticality Initial Electricity Commercial Operation _ __

3A - 7/14/2004

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MONTHLY REFUELING INFORMATION REOUEST

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. 2004 Name of

Contact:

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

CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT MAY 2004

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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