ML20210V377
| ML20210V377 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/31/1987 |
| From: | Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8702190008 | |
| Download: ML20210V377 (6) | |
Text
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4-NRC MONTHLY OPERATING REPORT DOCKET NO.
50-206 UNIT NAME SONGS - 1 DATE February 13, 1987 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 1987
- 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 744.00 744.00 172,088.00_
- 12. Number Of Hours Reactor Was Critical 744.00 744.00 99,822.62
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 744.00 744.00 95,847.28
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 905,598.54 905,598.54 121,211,507.40
- 17. Gross Electrical Energy Generated (MWH) 297,600.00
~~297,600.00 41,090,796.38
- 18. Net Electrical Energy Generated (MWH) 280,378.00 280,378.00 38,795,040.00
- 19. Unit Service Factor 100.00%
100.00%
55.70%
- 20. Unit Availability Factor 100.00%
100.00%
55.70%
- 21. Unit Capacity Factor (Using MDC Net) 86.43%
86.43%
51.71%
- 22. Unit Capacity Factor (Using DER Net) 86.43%
86.43%
51.71%
- 23. Unit Forced Outage Rate 0.00% _
0.00%
21.08%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Mid-Cycle outage-April 10, 1987, 45-day duration
- 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 NOchk$ggj f
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-206 UNIT SONGS - 1 DATE February 13, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH: January 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 383.00 17 374.58 2
383.96 18 375.42 3
383.42 19 377.21 4
383.67 20 378.67 5
383.79-21 190.04 6
384.13 22 384.13 7
384.63 23 384.17 8
385.08 24 386.96 9
385.08 25 387.63 10 386.04 26 387.17 11 385.42 27 385.63 12 385.71 28 386.50 13 385.33 29 387.08 14 375.38 30 388.29 15 373.50 31 387.29 16 373.54 7596u/4
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SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET 50-206 UNIT SONGS - 1 DATE February 13, 1987 COMPLETED BY' E. R. Siacor TELEPHONE (714) 368-6223 DATE TIME EVENT Janus y 1 0001 The Unit is in Mode I at 92% reactor power.
Turbine load at 405 MWe gross.
January 21 0100 Commenced reactor power reduction from 92% power for ALARA considerations during repairs to Control Rod Drive Mechanism (CRDM) Cooling System Fan A8.
0236 Reactor power at 36%.
Turbine load at 150 MWe gross.
1940 Commenced power increase following completion of repairs to CRDM Fan A8.
2055 Reactor power at 92%. Turbine load at 405 MWe gross.
.lanuary 31 2400 Unit is in Mode 1 at 93% reactor power. Turbine load at 409 MWe.
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7596u/6
REFUELING INFORMATION DOCKET NO.
50-206 UNIT SONGS - 1 DATE February 13, 1987 COMPLETED BY-E. R. Siacor TELEPHONE (714) 368-6223 MONTH:
January 1987 1.
Scheduled date for next refueling shutdown.
March 1988 2.
Scheduled date for restart following refueling.
June 1988 3.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Not yet determined What will these be?
Not yet determined 4.
Scheduled date for submitting proposed licensing action and supporting information.
Not yet determined 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 6.
The number of fuel assemblies.
a)
In the core.
157 b)
I.i the spent fuel storage pool.
146 7.
Licersed spent fuel storage capacity.
216 Intended change in spent fuel storage capacity. Under review 8.
Projected date of last ref ueling that can be discharged to spent fuel storage pool assuming present capacity.
March 1988 7596u/7
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Southern California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE, CALIFORNIA 92672 H E. MORGAN TE W HONE February 13, 1987 i
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Docket No. 50-206 Monthly Operating Report for January 1987 San Onofre Nuclear Generating Station, Unit 1 Enclosed is the Monthly Operating Report as 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.
Please contact us if we can be of further assistance.
Sincerely, MF_.Mup Enclosures cc:
J. B. Martin (Regional Administrator, USNRC Region V)
F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)
R. F. Dudley, Jr. (USNRC Unit 1 Project Manager, Office of Nuclear Reactor Regulation)
Institute of Nuclear Power Operations (INPO) i V
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