ML20234D210
| ML20234D210 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/31/1987 |
| From: | Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709220012 | |
| Download: ML20234D210 (6) | |
Text
7 NRC MONTHLY OPERATING REPORT DOCKET.NO. 50-206 UNIT NAME SONGS - 1 DATE september 15, 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: August 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
- l. 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)L
.- Since Last Report, Give Reasons:
NA j
- 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.
l This Month Yr.-to-Date' Cumulative
!. 11. Hours In Reporting Period 744.00 5,831.00 177,175.00
- 12. Number Of Hours Reactor Was Critical 744.00 4,521.40 103,600.02-
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 744.00 4,466.85 99,570.13
- 15. Unit Reserve Shutdown Hours- . 0.00 0.00 0.00 l 16. Gross Thermal Energy Generated (MWH) 908,886.00 5,445,355.19 125,751,264.05
- 17. Gross Electrical Energy Generated (MWH) 294,600.00 1,783,800.00 :42,576,996.38
) 18. Net Electrical Energy Generated (MWH) 276,804.00 1,673,611.00 40,188,273.00
- 19. Unit Service Factor 100.00% 76.61% 56.20%
I 20, Unit Availability Factor 100.00% 76.61% 56.20%
- 21. Unit Capacity Factor (Using MDC Net) 85.33% 65.83% 52.02%
- 22. Unit Capacity Factor (Using DER Net) 85.33% 65.83% 52.02%
- 23. Unit Forced Outage Rate 0.00% 1.53% 20.50%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration-of Each):
NA l
- 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 8709220012 870831 w PDR ADDCK 05000206 cri -
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AVERAGE DAILY UNIT POWER LEVEL ll DOCKET NO. 50-206 3 UNIT SONGS - 1 DATE September 15, 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223
) MONTH: August 1987
'l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j (MWe-Net) (MWe-Net) 1 378.42 17 376.38 2 377.71 18 363.04 3 379.71 19 378.50 4 379.67 20 376.04 5 377.83 21 375.58 6 374.71 22 375.71 7 370 46 23 379.63 8 371.33 24 378.13 1 1
9 372.67 25 377.33 l
l 10 373.46 26 376.67 11 373.00 27 376.96 12 374.54 28 376.50 13 376.00 29 356.29 14 378.33 30 276.21 15 376.33 31 381.33 i
16 375.04 l
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SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTjj DOCKET ?.-206 i i
UNIT SONGS - 1 I DATE September 15, 1987 ]
l COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 DATE TIME EVENT r .)
I August 1 0001 Unit is in Mode 1. Reactor at 92% power and turbine [
load at 400 MWe gross.
l ,
August 29 2140 Commenced power reduction for Condenser Water Box l Cleaning. '4 2226 Reactor at 40% power. Turbine load at 160 MWe gross.
l August 30 0444 Commenced power increase following completion of I Condenser Water Box cleaning, to perform heat treating operations and turbine stop valve testing. )
0600 Reactor at 70% power. Turbine load at 300 MWe gross. .
1243 Commenced power increase following completion of heat i treating operations and turbine stop valve testing.
1846 Reactor at 92% power. Turbine load at 398 MWe gross. )
August 31 2400 Reactor at 92% power. Turbine load at 404 MWe gross.
l l
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i REFUELING INFORMATION
]
DOCKET NO. 50-206
(
UNIT SONGS - 1 l DATE september 15, 1987 COMPLETED BY E. R. Siacor ,
i TELEPHONE (714) 368-6223 MONTA August 1987 y l
- 1. Scheduled date for next refueling shutdown.
)
June 1988 '
- 2. Scheduled date for restart following refueling.
[
September 1988 l
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment 7 Not yet determined What will these be?
Not yet determined
- 4. Scheduled date for submitting proposed licensing action and supporting information. ;
1 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. 1 i
None !
- 6. The number of fuel assemblies. j a) In the core. 157 b) In the spent fuel storage pool. 146
- 7. Licensed spent fuel storage capacity. 216 l Intended change in spent fuel storage capacity. Under review i
- 8. Projected date of last~ refueling that can be discharged to spent fuel storage ,
pool assuming present capacity.
l June 1988 7596u/7
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Southern California Edison Company.
SAN ONOFRE NUCLEAR GENER ATING ST ATION P. O. BOX 120 SAN CLEMENTE. CALIFORNIA 92672 H E. MORGAN TELEPHONE ST ATION MAN AGER (714) 368-6241 September 15, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 i
i
Subject:
Docket No. 50-206 Monthly Operating Report for August 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 q for San Onofre Nuclear Generating Station, Unit 1. >
Please contact us if we can be of further assistance.
1
'SThgerel , i l
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//E^)tlyy l 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)
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