ML13331B257
| ML13331B257 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/31/1990 |
| From: | Nandy F, Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9002220654 | |
| Download: ML13331B257 (7) | |
Text
Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R. NANDY TELEPHONE MANAGER OF NUCLEAR LICENSING (714) 587-5400 February 13, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-206 Monthly Operating Report for January 1990 San Onofre Nuclear Generating Station, Unit 1 The purpose of this letter is to provide the Monthly Operating Report required by Section 6.9.1.10 of Appendix A, Technical Specifications to Provisional Operating License DPR-13 for San Onofre Nuclear Generating Station, Unit 1.
If you require additional information, please let me know.
Very truly yours, Enclosures cc:
J. B. Martin (Regional Administrator, USNRC Region V)
C. W. Caldwell (USNRC Senior Resident Inspector, Units 1, 2 and 3)
Institute of Nuclear Power Operations (INPO) 9002220654 900131 PDR ADOCK 05000206, R
- PDC,
NRC MONTHLY OPERATING REPORT DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
2/13/90 COMPLETED BY: E. R. Siacor TELEPHONE:
(714) 368-6223 OPERATING STATUS
- 1. Unit Name:
San Onofre Nuclear Generating Station, Unit 1
- 2. Reporting Period:
January 1990
- 3. Licensed Thermal Power (MWt):
1347
- 4. Nameplate Rating (Gross MWe):
456
- 5. Design Electrical Rating (Net MWe):
436
- 6. Maximum Dependable Capacity (Gross MWe):
456
- 7. Maximum Dependable Capacity (Net MWe):
436
- 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
NA
- 9. Power Level To Which Restricted, If Any (Net MWe):
390
- 10. Reasons For Restrictions, If Any:
Self-imposed power level limit to control Steam Generator tube corrosion This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 744.00 744.00 198,392.00
- 12. Number Of Hours Reactor Was Critical 744.00 744.00 114,605.84
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 744.00 744.00 110,423.48
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 895,829.63 895,829.63 138,465,676.75
- 17. Gross Electrical Energy Generated (MWH) 293,400.00 293,400.00 46,713,728.42
- 18. Net Electrical Energy Generated (MWH) 276,692.00 276,692.00 44,039,112.00
- 19. Unit Service Factor 100.00%
100.00%
55.66%
- 20. Unit Availability Factor 100.00%
100.00%
55.66%
- 21. Unit Capacity Factor (Using MDC Net) 85.30%
85.30%
50.91%
- 22. Unit Capacity Factor (Using DER Net) 85.30%
85.30%
50.91%
- 23. Unit Forced Outage Rate 0.00%
0.00%
19.71%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Cycle 11 refueling outage scheduled to commence on June 30, 1990.
- 25. If Shutdown At End Of Report Period, Estimated Date of Startup:
NA
- 26. Units In Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA mor.jan/2
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE: 2/13/90 COMPLETED BY: E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
January 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 379.13 17 379.75 2
382.67 18 381.29 3
381.67 19 381.67 4
383.25 20 380.46 5
382.83 21 380.50 6
382.63 22 379.82 7
382.04 23 380.08 8
381.38 24 152.50 9
380.17 25 330.67 10 379.50 26 382.08 11 378.38 27 380.42 12 377.29 28 382.83 13 378.71 29 382.38 14 378.83 30 383.63 15 379.50 31 383.33 16 379.38 mor.jan/3
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 REPORT MONTH:
JANUARY 1990 DATE: 2113/0 COMPLETED BY: E. R. Siacor TELEPHONE:
(714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER Syste Compongnt Action to No.
Date Typel (Hours)
Reason 2 Reactor3 No.
Code 4 Code" Prevent Recurrence 136 900124 F
0.00 B
5 NA TA TRB Power reduction of greater than 20% to allow replacem of two high pressure turbin*
manway bolts found broken during manway leak repairs.
1F-Forced 2Reason:
3Method:
4IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.
C-Refueling 3-Automatic Scram.
D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20%
SIEEE Std 803A G-Operational Error (Explain) or greater in the H-Other (Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other (Explain) mor.jan/4
SUMMARY
OF OPERATING EXPERIENCE FOR TH MONTH DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
2/13/90 COMPLETED BY: E. R. Siacor TELEPHONE:
(714) 368-6223 Date Time Event January 1 0001 Unit is in Mode 1 at 91% reactor power. Turbine load at 402 MWe gross.
January 24 0500 Commenced reactor power decrease to allow replacement of two high pressure (HP), turbine manway bolts found broken during manway leak repairs.
0735 Reactor at 22% power.
January 25 0138 Commenced reactor power increase following completion of leak repairs to the HP turbine manway.
0204 Reactor at 70% power.
0405 Commenced heat treating operations.
0605 Completed heat treating operations.
0854 Commenced reactor power increase following completion of heat treating operations.
0930 Reactor at 91% power.
January 31 2400 Unit is in Mode 1 at 91% reactor power. Turbine load at 403 MWe gross.
mor.jan/5
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
2/13/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
January 1990
- 1. Scheduled date for next refueling shutdown.
June 30, 1990
- 2. Scheduled date for restart following refueling.
November 1990
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes.
What will these be?
a) License Amendment associated with the resolution of the 480V breaker overload issue.
b) License Amendment associated with removal of the license condition related to the TDI diesel generators.
c) License Amendment associated with revision of the basis to Technical Specification 3.3.1, "Safety Injection and Containment Spray", and resolution of other issues related to TS 3.3.1 which were identified during Cycle 10 refueling.
d) License Amendment associated with the provision of an alternate intermediate spent fuel cooling capability during the upcoming Cycle 11 refueling outage and concurrent CCW outage.
mor.jan/6
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
2/13/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
January 1990
- 4. Scheduled date for submitting proposed licensing action and supporting information.
a) SCE expects to submit the license amendment associated with the 480V breaker overload issue in February 1990.
b) SCE expects to submit the request to remove the TDI diesel generator license condition in March 1990.
c) SCE expects to submit the request to revise the basis and resolve other issues related to TS 3.3.1 in April 1990.
d) SCE expects to submit the license amendment associated with the alternate intermediate spent fuel pool cooling capability in March 1990.
- 5. Important Licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None have been identified at this time.
- 6. The number of fuel assemblies.
a) In the core.
157 b) In the spent fuel storage pool.
59
- 7. Licensed spent fuel storage capacity.
216 Intended change in spent fuel storage capacity.
None
- 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Approximately 1995 (refueling only)
Approximately 1991 (full off load capability) mor.jan/7