ML043280410
| ML043280410 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire |
| Issue date: | 11/15/2004 |
| From: | Mccollum W Duke Energy Corp, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML043280410 (26) | |
Text
_kDuke ftPower0 A Duke Energy Company WILLIAM R MCCOLLUM, JR.
VP, Nuclear Support Duke Energy Corporation 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 wrmccoll@duke-energy. corn November 15, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Subject:
Duke Energy Corporation Oconee Nuclear Station, Docket Nos. 50-269, -270, -287 McGuire Nuclear Station, Docket Nos. 50-369, -370 Catawba Nuclear Station, Docket Nos. 50-413, -414 Monthly Performance and Operation Status - October 2004 Please find attached information concerning the performance and operation status of the Oconee, McGuire and Catawba Nuclear Stations for the month of October 2004.
Please direct any questions or comments to Roger A. Williams at (704) 382-5346.
William R. McCollum, Jr.
Attachment
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U.S. Nuclear Regulatory Commission Monthly Performance and Operation Status November 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, 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 Operating Status
- 1. Unit Name:
Oconee 1
- 2. Reporting Period:
October 1, 2004 -October 31, 2004
- 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:
50-269 November 11,2004 Roger Williams 704-382-5346 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 745.0
- 12. Number of Hours Reactor was Critical 745.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 745.0
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 1913673
- 17. Gross Electrical Energy Generated (MWH) 664946
- 18. Net Electrical Energy Generated (MWH) 635347
- 19. Unit Service Factor 100.0
- 20. Unit Availability Factor 100.0
- 21. Unit Capacity Factor (Using MDC Net) 100.8
- 22. Unit Capacity Factor (Using DER Net) 96.3
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 7320.0 7209.6 0.0 7085.7 0.0 18058793 6279466 6002448 96.8 96.8 96.9 92.6 2.5 Cumulative 274345.0 217118.8 0.0 213433.8 0.0 528982539 183028579 174121473 77.8 77.8 74.4 71.6 9.0
- 25. If ShutDown At End Of Report Period, Estimated Date of Startup
- 26. Units in Test Status (Prior to Commercial Operation)
Forcast Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data:
1 037 937 KVA x 0.90 Pf=934 MW 3A - 11 t11/2004
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee I DATE: November 11, 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 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 fortheMonth Summary:I (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 - 11l 1/12004
MONTHLY REFUELING INFORMATION REOUEST
- 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: 1968**
- 8.
Present licensed fuel pool capacity: 1312 Size of requested or planned increase: **
- 9.
Projected date of last refueling which can be accommodated by present capacity: January 2005***
DUKE POWER COMPANY DATE: November 11. 2004 Name of
Contact:
R. A. Williams Phone: (704) - 382-5346 Represents the combined total for Units I 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 Operating Status
- 1. Unit Name:
Oconee 2
- 2. Reporting Period:
October 1, 2004-October 31, 2004
- 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:
50-270 November 11.2004 Roger Williams 704-382-5346 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:
I This Month
- 11. Hours in Reporting Period 745.0
- 12. Number of Hours Reactor was Critical 745.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 745.0
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 1909976
- 17. Gross Electrical Energy Generated (MWH) 670445
- 18. Net Electrical Energy Generated (MWH) 642244
- 19. Unit Service Factor 100.0
- 20. Unit Availability Factor 100.0
- 21. Unit Capacity Factor (Using MDC Net) 101.9
- 22. Unit Capacity Factor (Using DER Net) 97.3
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 7320.0 5281.6 0.0 5188.9 0.0 13136861 4611193 4398060 70.9 70.9 71.0 67.8 4.3 Cumulative 264265.0 215127.4 0.0 212455.5 0.0 526181782 181161118 172693098 80.4 80.4 76.6 73.8 8.2
- 25. If ShutDown At End Of Report Period, Estimated Date of Startup
- 26. Units in Test Status (Prior to Commercial Operation)
Forcast Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data:
1 037 937 KVA x 0.90 Pf=934 MW 3A - 11/11/2004
Page: 1 of I UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: November 11. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 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 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-11/11/2004
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 infornation.
- 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: November 11. 2004 Name of
Contact:
R. A. Williams Phone: (704) - 382-5346 Represents the combined total for Units 1 and 2 See footnote on Unit I In 1999 Oconee transitioned to its general license. Forty-four (44) general license modules were installed and 30 modules have now been loaded.
Additional modules will be installed on an as-needed basis.
See footnote on Unit I
Operating Data Report Docket No.
Date Completed By Telephone Operating Status
- 1. Unit Name:
Oconee 3
- 2. Reporting Period:
October 1, 2004 -October 31, 2004
- 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:
50-287 November 11.2004 Roger Williams 704-382-5346 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 745.0
- 12. Number of Hours Reactor was Critical 194.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 192.9
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 485660
-17. Gross Electrical Energy Generated (MWH) 168186
- 18. Net Electrical Energy Generated (MWH) 158537
- 19. Unit Service Factor 25.9
- 20. Unit Availability Factor 25.9
- 21. Unit Capacity Factor (Using MDC Net) 25.2
- 22. Unit Capacity Factor (Using DER Net) 24.0
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 7320.0 6734.3 0.0 6699.4 0.0 17141092 5999455 5747048 91.5 91.5 92.8 88.6 1.0 Cumulative 261912.0 209353.9 0.0 206573.5 0.0 517316844 179156631 170961725 78.9 78.9 76.5 73.7 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 Achieved NRC Calculated from Generator Nameplate Data:
1 037 937 KVA x 0.90 Pf=934 MW 3A - 11/11/2004
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: November 11, 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 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.
3 10/09/04 S
552.07 C
1 END-OF-CYCLE 21 REFUELING OUTAGE Summary:
Oconee unit 3 began the month of October operating at 100% power until 100204 at 1339 when the unit began decreasing power from 100% to gain flow-induced-vibration margin to prepare for T-AVE reduction. On 10/03/04 from 0742 to 2130 the unit held at 98% power prior to beginning T-AVE reduction. The unit was taken off-line 10/09/04 at 0056 to begin end-of-cycle 21 refueling outage. The unit was in the end-of-cycle 21 refueling outage 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-11/11/2004
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: 484 (c) in the ISFSI: See Unit I ****
- 8.
Present licensed fuel pool capacity: 825 Size of requested or planned increase: **
9;
-- - Projected date of last refueling which can be accommodated by present capacity: January 2005***
DUKE POWER COMPANY DATE: November 11. 2004 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 I
OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT SEPTEMBER 2004
- 1.
Personnel Exposure -
The total station liquid release for SEPTEMBER has been
-compared with the Technical. Specifications -maximum annual dose commitment and was less than 10 percent of this limit.
..The total-station gaseous.-release for-SEPTEMBER has been compared with the Technical Specifications maximum annual
.dose..commitment andvwas less-than 10 percent of this limit.
Operating Data Report Docket No.
Date Completed By Telephone Operating Status
- 1. Unit Name:
McGuire I
- 2. Reporting Period:
October 1, 2004 - October 31, 2004
- 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:
50-369 November 11.2004 Roger Williams 704-382-5346 Notes: *Nameplate Rating (GrossMWe) calculated as 1450.000 MVA *.90 power factor per Page iii, NUREG-0020.
- I
- 9. Power Level To Which Restricted, If Any (Net MWe):
- 10. Reason for Restrictions, If any: _
This Month
- 11. Hours in Reporting Period 745.0
- 12. Number of Hours Reactor was Critical 413.3
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 413.3
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 1395730
- 17. Gross Electrical Energy Generated (MWH) 481457
- 18. Net Electrical Energy Generated (MWH) 456034
- 19. Unit Service Factor 55.5
- 20. Unit Availability Factor 55.5
- 21. Unit Capacity Factor (Using MDC Net) 55.6
- 22. Unit Capacity Factor (Using DER Net) 51.9
- 23. Unit Forced Outage Rate 36.8
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 7320.0 6119.3 0.0 6100.8 0.0 20692506 7138054 6865946 83.3 83.3 85.3 79.5 5.8 Cumulative 200904.0 157904.8 0.0 156585.4 0.0 507337318 174922249 167694257 77.9 77.9 73.8 70.7 8.8
- 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 - 11111/2004
Page: l of I UNIT SHUTDOWNS DOCKET NO. 50-369 UNIT NAME: McGuire 1 DATE: November 11. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 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.
6 10/18/04 S
90.72 A
I REPAIR 1B STEAM GENERATOR INSTRUMENT LINE LEAK-OUTAGE DELAYED TO REPAIR AND EVALUATE MAIN STEAM 7ISOLATION VALVES 1SM-1 AND ISM-7 Summary:
McGuire unit I began the month of October operating at 100% power until 10/17/04 at 2223 when the unit began decreasing power from 100% to repair lB steam generator instrument line leak. The unit held at 55% power from 10/18/04 at 0000 to 0045 due to excore detector calibration. The unit continued decreasing power and was taken off-line 10/18/04 at 0517 to begin the maintenance outage to repair lB steam generator instrument line leak. The outage was delayed to evaluate and repair main steam isolation valves I SM-I and I SM-7. The unit was in the outage 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-1I1/12oo4
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: November 11. 2004 Name of
Contact:
R. A. Williams Phone: (704) - 382-5346
Operating Data Report Docket No.
Date Completed By Telephone Operating Status
- 1. Unit Name:
McGuire 2
- 2. Reporting Period:
October 1, 2004 - October 31, 2004
- 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:
50-370 November 11.2004 Roger Williams 704-382-5346 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 745.0
- 12. Number of Hours Reactor was Critical 745.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 745.0
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 2539416
- 17. Gross Electrical Energy Generated (MWH) 878085
- 18. Net Electrical Energy Generated (MWH) 846384
- 19. Unit Service Factor 100.0
- 20. Unit Availability Factor 100.0
- 21. Unit Capacity Factor (Using MDC Net) 103.3
- 22. Unit Capacity Factor (Using DER Net) 96.3
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 7320.0 7320.0 0.0 7320.0 0.0 24942083 8622334 8313838 100.0 100.0 103.3 96.3 0.0 Cumulative
- 181200.0 151160.0 0.0 149877.6 0.0
- 496143957 165724440 82.7 82.7 81.2 77.5 5.0
- 25. If ShutDown At End Of Report Period, Estimated Date of Startup
- 26. Units in Test Status (Prior to Commercial Operation)
Forcast Achieved Initial Criticality Initial Electricity Commercial Operation 3A - 11/11/2004
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-370 UNIT NAME: McGuire 2 DATE: November 11. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: October, 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 Summary:
(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-1 1/ 1/2004
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 Committee regarding unreviewed safety questions?
- 5.
-Scheduled date(s) for submitting proposed licensing action and supporting information.
- 6.
Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
- 7.
Number of Fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 1138 (c) in the ISFSI: 320
- 8.
Present licensed fuel pool capacity: 1463 Size of requested or planned increase:
- 9.
Projected date of last refueling which can be accommodated by present license capacity:
June 2003 DUKE POWER COMPANY DATE: November 11. 2004 Name of
Contact:
R. A. Williams Phone: (704) - 382-5346
McGUIRE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT SEPTEMBER 2004
- 1.
Personnel Exposure -
The total station liquid.release for SEPTEMBER has been compared with the Technical Specifications maximum annual
... dose.commitmentand was.less.than 10 percent of this.limit.
The total-station gaseous release-for.-SEPTEMBER has been
.....compared with the Technical.Specifications maximum annual
....-dose.commitment and was.less.than 10 percent.of this-limit.
Operating Data Report Docket No.
Date Completed By Telephone Operating Status
- 1. Unit Name:
Catawba 1
- 2. Reporting Period:
October 1, 2004 -October 31, 2004
- 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:
50-413 November 11.2004 Roger Williams 704-382-5346 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 I 1. Hours in Reporting Period 745.0
- 12. Number of Hours Reactor was Critical 745.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 745.0
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 2535305 17: Gross Electrical Energy Generated (MWH) 904822
- 18. Net Electrical Energy Generated (MWVH) 857686
- 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) 100.5
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 7320.0 7210.1 0.0 7204.6 0.0 23988388 8549845 8099615 98.4 98.4 98.0 96.6 1.6 Cumulative 169561.0 141799.5 0.0 139965.1 0.0 463180554 164450278 155175221 82.5 82.5 80.9 79.9 5.5
- 25. If ShutDown At End Of Report Period, Estimated Date of Startup
- 26. Units in Test Status (Prior to Commercial Operation)
Forcast Achieved Initial Criticality Initial Electricity Commercial Operation 3A - 11/11/2004
Page: l of 1 UNIT SHUTDOWNS DOCKET NO. 50-413 UNIT NAME: Catawvba I DATE: November 11. 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 I
4 REPORT MONTHI: October, 2004 i
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-I / 11/2004
MONTHLY REFUELING INFORMATION REQUEST I.
Facility name:
Catawba Unit ]
- 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 Name of
Contact:
R. A. Williams DATE: November 11, 2004 Phone: (704) - 382-5346
Operating Data Report Docket No.
Date Completed By Telephone Operating Status
- 1. Unit Name:
Catawba 2
- 2. Reporting Period:
October 1, 2004-October 31, 2004
- 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:
50-414 November 11.2004 Roger Williams 704-382-5346 Notes: *Nameplate Rating (GrossMWe) calculated as 1450.000 MIVA *.90 power factor per Page iii, NUREG-0020.
I9. Power Level To Which Restricted, If Any (Net MWe):
- 10. Reason for Restrictions, If any:
This Month
- 11. Hours in Reporting Period 745.0
- 12. Number of Hours Reactor was Critical 134.2
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 128.7
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 343694
- 17. Gross Electrical Energy Generated (MWH) 117072
- 18. Net Electrical Energy Generated (MWH) 100637
- 19. Unit Service Factor 17.3
- 20. Unit Availability Factor 17.3
- 21. Unit Capacity Factor (Using MDC Net) 12.0
- 22. Unit Capacity Factor (Using DER Net) 11.8
- 23. Unit Forced Outage Rate 25.3
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 7320.0 6234.4 0.0 6228.7 0.0 21094931 7546430 7160340 85.1 85.1 86.6 85.4 0.7 Cumulative 159577.0 134187.9 0.0 132726.4 0.0 437449600 156007704 147463320 83.2 83.2 81.8 80.7 6.2
- 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 - 11/1 1/2004
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50414 UNIT NAME: Catawba 2 DATE: November 11, 2004 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346.
i REPORT MfONTIL October. 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.
1 10/01/04 5
532.00 C
4 END-OF-CYCLE 13 REFUELING OUTAGE OUTAGE EXTENDED DUE TO STEAM GENERATOR EDDY CURRENT 2
10/23/04 S
38.87 B
4 TESTING 3
10/24/04 S
1.80 B
MAIN TURBINE OVERSPEED TRIP TEST 4
10/28/04 F
43.60 A
SHUTDOWN BANK D CONTOL RODS DROPPED INTO CORE Summary:
Catawba unit 2 began the month of October in the end-of-cycle 13 refueling outage spanned 43.58 days and was extended 1.62 days due to increased eddy current testing scope. The unit was placed on-line 10/24/04 atl852 and held at 18% power to performn the turbine soak. The unit began decreasing power 10/24/04 at 2320 and the unit was taken off-line at 2355 due to the turbine overspeed trip test. The unit was placed on-line 10/25/04 at 0143. During power escalation, the unit held at 17% power from 0213 to 0337 due to main feedwater nozzle swap. The unit held at 54% power from 1208 to 1732 due to power ascension testing. On 10/26/04 at 1225 the unit held at 99% power pending evaluation of full power delta T constraints. On 10/28/04 at 0101 a manual reactor trip was initiated due to all shutdown bank D control rods dropping into core. The unit returned to service on 10/29/04 at 2037. During power escalation the unit held at 17% power from 2120 to 2203 due to main feedwater nozzle swap. The unit returned to 100% full power on 10/31/04 at 0247 and operated at or near 100% full powerthe 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-11/15/2004 I
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: November 11. 2004 Name of
Contact:
R. A. Williams Phone: (704) - 382-5346
CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT SEPTEMBER 2004
- 1.
Personnel Exposure -
The total station liquid release for SEPTEMBER has been compared-with.the. Technical..;.Specifications maximum._annual dose commitment:and was:.less.than 10 percent-of-this limit.
The total.station gaseous'.release for SEPTEMBER has:-beenf,.
compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.