ML031120377
| ML031120377 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/15/2003 |
| From: | Dimmery T Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML031120377 (12) | |
Text
Duke Duke Energy Corporation 526 South Church Street nrgy.
P.O Box 1006 Charlotte, NC 28201-1006 April 15, 2003 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Subject:
Duke Energy Corporation Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers 50-269, 50-270 and 50-287 Monthly Performance and Operation Status-March, 2003 Please find attached information concerning the performance and operation status of the Oconee Nuclear Station for the month of March, 2003.
Any questions or comments may be directed to Roger A. Williams at (704) 382-5346.
Si r/erely, A eS rry/ Dimmery, nager Nuclear Business Support Attachment XC:
L. A. Reyes, Regional Administrator USNRC, Region II Dave LaBarge, Project Manager USNRC, ONRR INPO Records Center Ms. Margaret Aucoin Nuclear Assurance Corporation Dottie Sherman, ANI Library American Nuclear Insurers Oconee NRC Inspector 5gq
Document Control Desk U.S. NRC -
Oconee bxc:
L. E. Nicholson (ON03RC)
RGC Site Licensing File ELL (ECO50)
Operating Data Report Docket No.
Date Completed By Telephone 50-269 April 15,2003 Roger Williams 704-382-5346 Operating Status
- 1. Unit Name:
Oconee 1
- 2. Reporting Period:
March 1, 2003 - March 31, 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 744.0
- 12. Number of Hours Reactor was Critical 744.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 744.0
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 1843413
- 17. Gross Electrical Energy Generated (MWH) 648080
- 18. Net Electrical Energy Generated (MWH) 620972
- 19. Unit Service Factor 100.0
- 20. Unit Availability Factor 100 0
- 21. Unit Capacity Factor (Using MDC Net) 98.7
- 22. Unit Capacity Factor (Using DER Net) 94.2
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 2160.0 2160.0 0.0 2160.0 0.0 5479085 1926093 1847482 100.0 100.0 101.1 96.5 0.0 Cumulative 260425.0 205723.1 0.0 202220.1 0.0 500681739 173177400 164721528 77.7 77.7 74.1 71.4 9.2
- 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 - 4115/2003
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee 1 DATE: April 15. 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: March, 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 - 4/15/2003
MONTHLY REFUELING INFORMATION REQUEST
- 1.
Facility name:
Oconee Unit 1
- 2.
Scheduled next refueling shutdown: September 2003
- 3.
Scheduled restart following refueling: November 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: 926*
(c) in the ISFSI: 1800****
- 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: April 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 April 15.2003 Roger Williams 704-382-5346 Operating Status
- 1. Unit Name:
Oconee 2
- 2. Reporting Period:
March 1, 2003 -March 31, 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 744.0
- 12. Number of Hours Reactor was Critical 744.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 744.0
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 1909359
- 17. Gross Electrical Energy Generated (MWH) 674205
- 18. Net Electrical Energy Generated (MWH) 647670
- 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) 98.3
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 2160.0 2160.0 0.0 2160.0 0.0 11022267 1957040 1880123 100.0 100.0 102.9 98.2 0.0 Cumulative 250345.0 203245.8 0.0 200666.7 0.0 501575822 170610024 162606441 80.2 80.2 76.1 73.3 8.5
- 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 - 4/15/2003
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: April 15. 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: March, 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 (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-4/15/2003
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: 926*
(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: April 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 April 15.2003 Roger Williams 704-382-5346 Operating Status
- 1. Unit Name:
Oconee 3
- 2. Reporting Period:
March 1, 2003 -March 31, 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 744.0
- 12. Number of Hours Reactor was Critical 744.0
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 744.0
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 1900731
- 17. Gross Electrical Energy Generated (MWH) 669460
- 18. Net Electrical Energy Generated (MWH) 642771
- 19. Unit Service Factor 100.0
- 20. Unit Availability Factor 100.0
- 21. Unit Capacity Factor (Using MDC Net) 102.1
- 22. Unit Capacity Factor (Using DER Net) 97.5
- 23. Unit Forced Outage Rate 0.0
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date and Duration of Each)
YTD 2160.0 2160.0 0.0 2160.0 0.0 16559902 1952460 1874803 100.0 100.0 102.6 98.0 0.0 Cumulative 247992.0 197212.9 0.0 194566.1 0.0 497819562 168501735 160774448 78.5 78.5 76.0 73.2 8.9
- 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 - 4/15/2003
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO, 50-287 UNIT NAME: Oconee 3 DATE: April 15. 2003 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: March, 2003 No.
Date:
Type Duration (1) Reason (2) Method of Licensed Cause and Corrective Action to Prevent Recurrence F - Forced Hours Shutdown RX 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 TraininglLicense 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 - 4/15/2003
MONTHLY REFUELING INFORMATION REQUEST
- 1.
Facility name:
Oconee Unit 3
- 2.
Scheduled next refueling shutdown: Anril 2003
- 3.
Scheduled restart following refueling: May 2003 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE ?R 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: 416 (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: April 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 FEBRUARY 2003
- 1.
Personnel Exposure -
The total station liquid release for FEBRUARY 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 FEBRUARY has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.