ML021140310
| ML021140310 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/15/2002 |
| From: | Dimmery T Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML021140310 (12) | |
Text
Duke Duke Power Power.
526 South Church Street A Pow er P.O. Box 1006 Eu mgv
~Charlotte, NC 28201-1006 April 15, 2002 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, 2002 Please find attached information concerning the performance and operation status of the Oconee Nuclear Station for the month of March, 2002.
Any questions or comments may be directed to Roger A. Williams at (704) 382-5346.
Sincerely, Terry Dimmery, Manager Nuclear Business Support Attachment XC:
L.
A. Reyes, Regional Administrator
- USNRC, Region II Dave LaBarge, Project Manager
Margaret Aucoin Nuclear Assurance Corporation Dottie Sherman, ANI Library American Nuclear Insurers Oconee NRC Inspector
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 Operating Status
- 1. Unit Name:
Oconee 1
- 2. Reporting Period:
March 1, 2002 - March 31, 2002
- 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 April 15,2002 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:
- 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 744.0 533.4 0.0 532.1 0.0 1364532 480046 458826 71.5 71.5 72.9 69.6 0.0 YTD 2160.0 1949.4 0.0 1948.1 0.0 5004518 1760811 1687059 90.2 90.2 92.3 88.2 0.0 Cumulative 251665.0 197662.9 0.0 194219.2 0.0 480323458 166097583 157953648 77.2 77.2 73.5 70.8 9.5
- 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 NRC Calculated from Generator Nameplate Data:
1 037 937 KVA x 0.90 Pf=934 MW 3A - 4/15/2002
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee 1 DATE: April 15, 2002 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: March, 2002 (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 - 4/15/2002 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 03/23/02 S
211.90 C
I END-OF-CYCLE 20 REFUELING OUTAGE Summary:
Oconee unit I began the month of March operating at approximately 100% full power. The unit began decreasing power on 03/22/02 at 2135 to end-of-cycle 20 refueling outage The unit was taken off-line on 03/23/02 at 0406 to begin end-of-cycle 20 refueling outage. The unit was in the end-of-cycle 20 refueling outage the remainder of the month
MONTHLY REFUELING INFORMATION REOUEST
- 1.
Facility name:
Oconee Unit 1
- 2.
Scheduled next refueling shutdown: Currently Refueling
- 3.
Scheduled restart following refueling: April 2002 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: 974*
(c) in the ISFSI: 1512****
- 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: March 13, 2002 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 license for ISFSI which will store 2112 assemblies We currently have 60 modules of which 49 modules are loaded.
Additional modules will be built 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:
March 1, 2002-March 31, 2002
- 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 April 15,2002 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:
- 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 744.0 744.0 0.0 744.0 0.0 1910592 671701 643872 100.0 100.0 102.3 97.7 0.0 YTD 2160.0 2160.0 0.0 2160.0 0.0 10553863 1946006 1866908 100.0 100.0 102.2 97.6 0.0 Cumulative 241585.0 195475.4 0.0 192922.8 0.0 481298277 163691131 155982112 79.9 79.9 75.6 72.9 8.8
- 25. If ShutDown At End Of Report Period, Estimated Date of Startup
- 26. Units in Test Status (Prior to Commercial Operation)
Forcast Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data:
1 037 937 KVA x 0.90 Pf=934 MW 3A - 4/15/2002
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: April 15, 2002 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: March, 2002 (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 - 4/15/2002 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:
MONTHLY REFUELING INFORMATION REOUEST
- 1.
Facility name:
Oconee Unit 2
- 2.
Scheduled next refueling shutdown: October, 2002
- 3.
Scheduled restart following refueling: November, 2002 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: 974*
(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: March 13, 2002 Name of
Contact:
R. A. Williams Phone: (704) - 382-5346 Represents the combined total for Units 1 and 2 See footnote on Unit 1 We currently have 60 modules of which 49 modules are loaded.
Additional modules will be built on an as needed basis.
See footnote on Unit 1
Operating Data Report Docket No.
Date Completed By Telephone Operating Status
- 1. Unit Name:
Oconee 3
- 2. Reporting Period:
March 1, 2002 - March 31, 2002
- 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 April 15,2002 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:
- 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)
- 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 This Month 744.0 744.0 0.0 744.0 0.0 1910592 673086 645330 100.0 100.0 102.5 97.9 0.0 YTD 2160.0 2160.0 0.0 2160.0 0.0 16089033 1952207 1872869 100.0 100.0 102.5 97.9 0.0 Cumulative 239232.0 188517.8 0.0 185878.2 0.0 475098924 160706118 153306993 77.7 77.7 75.1 72.3 9.3 Achieved NRC Calculated from Generator Nameplate Data:
1 037 937 KVA x 0.90 Pf=934 MW 3A - 4/15/2002
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: April 15, 2002 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: March, 2002 (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 - 4/15/2002 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:
MONTHLY REFUELING INFORMATION REOUEST
- 1.
Facility name:
Oconee Unit 3
- 2.
Scheduled next refueling shutdown: April 2003
- 3.
Scheduled restart following refueling: May 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: 536 (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: March 13, 2002 Name of
Contact:
R. A. Williams Phone:
(704) - 382-5346 See footnote of Unit 1 We currently have 60 modules of which 49 modules are loaded.
Additional modules will be built on an as needed basis.
See footnote on Unit 1
OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT FEBRUARY 2002
- 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.