ML023540432
ML023540432 | |
Person / Time | |
---|---|
Site: | Oconee |
Issue date: | 12/13/2002 |
From: | Dimmery T Duke Power Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML023540432 (13) | |
Text
Duke Power k Duke 526 South Church Street E Power PO. Box 1006 A Duke Energy Company Charlotte, NC 28201-1006 December 13, 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-November, 2002 Please find attached information concerning the performance and operation status of the Oconee Nuclear Station for the month of November, 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 USNRC, ONRR INPO Records Center Ms. 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 (EC050)
Operating Data Report Docket No. 50-269 Date December 13,2002 Completed By Roger Williams Telephone 704-382-5346 Operating Status
- 1. Unit Name: Oconee 1
- 2. Reporting Period: November 1, 2002 - November 30, 2002 Notes: Year-to-date
- 3. Licensed Thermal Power (MWt) 2568 and cumulative
- 4. Nameplate Rating (Gross MWe): 934 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 720.0 8016.0 257521.0
- 11. Hours in Reporting Period
- 12. Number of Hours Reactor was Critical 720.0 7105.6 202819.1
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 720.0 7045.0 199316.1
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 1847727 17974355 493293295
- 16. Gross Thermal Energy Generated (MWH) 643140 6243118 170579890
- 17. Gross Electrical Energy Generated (MWH) 615136 5964533 162231122
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor 100.0 87.9 77.4
- 20. Unit Availability Factor 100.0 87.9 77.4
- 21. Unit Capacity Factor (Using MDC Net) 101.0 88.0 73.8 96.4 84.0 71.1
- 22. Unit Capacity Factor (Using DER Net) 0.0 1.2 9.3
- 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 Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data:
1 037 937 KVA x 0.90 Pf=934 MW 3A - 12/13/2002
Page: 1 of 1 UNIT SHUTDOWNS DOCKET NO. 50-269 UNIT NAME: Oconee 1 DATE: December 13. 2002 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: November. 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:
(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- 12/13/2002
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) m the ISFSI: 1728****
- 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: December 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 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
I : I, Operating Data Report Docket No. 50-270 Date December 13,2002 Completed By Roger Williams Telephone 704-382-5346 Operating Status
- 1. Unit Name: Oconee 2
- 2. Reporting Period: November 1, 2002 - November 30, 2002 Notes: Year-to-date
- 3. Licensed Thermal Power (MWt): 2568 and cumulative
- 4. Nameplate Rating (Gross MWe): 934 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 8016.0 247441.0
- 12. Number of Hours Reactor was Critical 207.9 7026.5 200341.8 0.0 0.0 0.0
- 13. Reactor Reserve Shutdown Hours 183.9 6999.9 197762.7
- 14. Hours Generator On-Line 0.0 0.0 0.0
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 432657 35887696 506632110
- 17. Gross Electrical Energy Generated (MWH) 150404 6234756 167979881 138490 5965273 160080477
- 18. Net Electrical Energy Generated (MWH) 25.5 87.3 79.9
- 19. Unit Service Factor 25.5 87.3 79.9
- 20. Unit Availability Factor 22.7 88.0 75.8
- 21. Unit Capacity Factor (Using MDC Net) 21.7 84.0 73.0
- 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 8.6
- 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 Achieved Initial Criticality Initial Electricity Commercial Operation NRC Calculated from Generator Nameplate Data 1 037 937 KVA x 0.90 Pf=934 MW 3A- 12/13/2002
Page: 1 of 2 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: December 13, 2002 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: November, 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.
1 11/01/02 S 264.00 C 4 END-OF-CYCLE 19 REFUELING OUTAGE OUTAGE DELAY OF 11.24 DAYS DUE TO REACTOR VESSEL HEAD 211/12/02 5 269.73 A CONTROL ROD DRIVE MECHANISM PENETRATION REPAIRS 3 11/23/02 S 2.37 B TURBINE OVERSPEED TRIP TEST Summary:
Oconee unit 2 began the month of November, 2003 in end-of-cycle 19 refueling outage. The refueling outage was delayed 11.24 days due to reactor vessel head control rod drive penetration repairs. The unit was placed on-line 11/23/01 at 0544 holding at approximately 16% power. The turbine overspeed trip test was performed 11/23/02 at 1000. The unit was placed on-line 11/23/02 at 1222. During power escalation, the unit held at 33% power from 11/23/02 at 1340 to 1417 due to (2HPE-10) high pressure extraction valve repairs.
The unit held at 41% power from 1526 to 2051 due to main turbine bearing vibration analysis. On 11/24/02 the unit held at 70% power from 0253 to 0501 due nuclear instrumentation calibration. The unit held at 73% power from 0542 to 1528 due to power imbalance detector correlation test. On 11/24/02 the unit held at 93.2% power from 2101 to 11/25/02 at 0121 due to nuclear instrumentation calibration. The unit returned to 100% full power on 11/25/02 at 0347 and operated at or (Cont'd)
(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- 12/13/2002
Page: 2 of 2 UNIT SHUTDOWNS DOCKET NO. 50-270 UNIT NAME: Oconee 2 DATE: December 13, 2002 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: November. 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.
I _______ I _______ J. _____ J. ______ .L __________ I _______ I Summary:
near 100% full power until 11/28/02 at 1501 when the unit began decreasing to approximately 97% power in effort to maintain T-AVE set point. The unit returned to 100% full power on 11/28/02 at 2209 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 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- 12/13/2002
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: December 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 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. 50-287 Date December 13,2002 Completed By Roger Williams Telephone 704-382-5346 Operating Status
- 1. Unit Name: Oconee 3
- 2. Reporting Period: November 1, 2002 - November 30, 2002
- 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 8016.0 245088.0
- 12. Number of Hours Reactor was Critical 655.1 7951.1 194308.9
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 648.0 7944.0 191662.1
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1650505 56226873 515236764
- 17. Gross Electrical Energy Generated (MWH) 579609 7121340 165875251
- 18. Net Electrical Energy Generated (MWH) 552141 6819394 158253518
- 19. Unit Service Factor 90.0 99.1 78.2
- 20. Unit Availability Factor 90.0 99.1 78.2
- 21. Unit Capacity Factor (Using MDC Net) 90.6 100.6 75.7
- 22. Unit Capacity Factor (Using DER Net) 86.6 96.0 72.9
- 23. Unit Forced Outage Rate 10.0 0.9 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 KVA x 0.90 Pf=934 MW 3A - 12/13/2002
Page: 1 of I UNIT SHUTDOWNS DOCKET NO. 50-287 UNIT NAME: Oconee 3 DATE: December 13, 2002 COMPLETED BY: Roger Williams TELEPHONE: 704-382-5346 REPORT MONTH: November. 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.
1 11/14/02 F 72.03 A 3 HIGH MOISTURE SEPARATOR REHEATER LEVEL Summary:
Oconee unit 3 began the month of November operating at or near 100% full power. On 11/14/02 at 0420 an automatic reactor trip occurred due to high moisture separator reheater level. The unit was placed on-line 11/17/02 at 0422. During power escalation, the unit held at 88% power from 1120 to 1352 due to nuclear instrumentation calibration check.
The unit held at 91% power from 11/17/02 at 1406 to 1502 to evaluate the need to perform turbine valve movement test. The unit held at 99.5% power from 1657 to 11/18/02 to 1655 to start 3E1 and 3E2 heater drain pumps. The unit returned to 100% full power on 11/18/02 at 1700 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- 12/13/2002
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: 488 (c) in the ISFSI: See Unit 1 ***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: December 13, 2002 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 I
OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT OCTOBER 2002
- 1. Personnel Exposure The total station liquid release for OCTOBER 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 OCTOBER has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.