ML20234D210

Monthly Operating Rept for Aug 1987

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.

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7596u/6

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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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