ML20206P307

Monthly Operating Rept for Mar 1987

ML20206P307
Person / Time
Site:	San Onofre
Issue date:	03/31/1987
From:	Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8704210146
Download: ML20206P307 (6)

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1 NRC MONTHLY OPERATING REPORT DOCKET NO. 50-206 UNIT NAME SONGS - 1 DATE April 14, 1987

) COMPLETED BY E. R. Stacor 7

TELEPHONE (714) 368-6223 OPERATING STATUS q-ll o

y

1. Unit Name:

San Onofre Nuclear Generating Station, Unit 1

2. Reporting Period: March 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 3

7. Maximum Ospendable Capacity (Net MWe):

436

8. If Changes Occur In tapacity 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 Nonth:

Yr.-to-Date Cumulative 3

11. Hours In Reporting Period 744.00 2,160.00 173,504.00

12. Number Of Hours Reactor Was Critical 684.90 2,100.90 101,179.52

13. Reactor Reserve Shutdown Hours 0.00_I_

0.00 0.00

14. Hours Generator On-Line 674.57 2,090.57 97,193.85

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 825,764.83 2,551,101.19 122,857,010.05

17. Gross Electrical Energy Generated (MWH) 274,200.00 843,000.00 41,636,196.38

18. Net Electrical Energy Generated (MWH) 257,386.00 793,153.00 39,307,315.00

19. Unit Service Factor 90.67%

96.79%

56.02%

20. Unit Availability Factor 90.67%

96.79%

56.02%

21. Unit Capacity Factor (Using MDC Net) 79.35%

84.22%

51.96%

22. Unit Capacity Factor (Using DER Net) 79.35%

84.22%

51.96%

23. Unit Forced Outage Rate 9.33%

3.21%

20.90%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Mid-Cycle outage-May 8, 1987, 42-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 7596u/3 k

kOON ho6 R

PDR

AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO.

50-206 UNIT SONGS - 1 DATE April 14, 1987 i

COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH: March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 389.58 17 387.63 2

389.04 18 388.04 3

389.88 19 387.79 4

388.96 20 388.13 5

388.67 21 387.08 6

387.63 22 389.17 7

387.92 23 389.29 8

388.29 24 388.13 9

387.58 25 388.04 10 160.79 26 387.75 11 0.00 27 387.58 12 0.00 28 387.71 13 117.17 29 387.42 14 382.63 30 387.50 15 384.58 31 388.25 16 388.04 7596u/4

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKE[NO. 50-206 UNIT NAME SONGS - 1 REPORT MONTH MARCH.1987 DATE. Anril 14. 1987 COMPLETED BY E.'R.

Slacor TELEPHONE ( 7141 368-6223 Method of Shutting Down System Component Cause & Corrective 1

Du ra t i on 2

3 LER 4

5 Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence 109 870310 F

69.43 B

3 87-003 TL EXC The reactor tripped f rom 92% power during routine main generator exciter

' brush replacement due to a loss of generator field.

Loss of generator field was due to an electrical short resulting f rom a brush being inadvertently dropped into the exciter commutator assembly.

Although the immediate cause was accidental dropping of the brush, inadequate commutator enclosure lighting was a contributing factor.

As corrective action, enhancements to the commutator enclosure lighting have been made. Additionally, this incident is being discussed with all electricians who may be involved with simila r work.

1 2

3 4

F-f o rced Reason:

Method:

IEEE Std. 805-1984 S-Scheduled A-Equipment Fa ilure (Expla in) 1-Manual B-Ma intenance or Test 2-Manual Sc ram.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation f rom E-Operator Training & License Examination Previous Month F-Adm i n i st ra t ive 5-Reduction of 20%

5 G-Ope ra t iona l Error (Explain) or Greater in the IEEE Std. 803A-1983 H-Othe r ( Expla in)

Past 24 Hours 6-Other (Expla in) 7596u/5

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET 50-206 UNIT SONGS - 1 DATE April 14, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 DATE TIME EVENT March 1 0001 The Unit is in Mode 1 at 92% reactor power.

Turbine load at 410 MWe gross.

March 10 1024 The reactor tripped from 92% power during routine main generator exciter brush replacement due to a loss of generator field.

Loss of generator field was due to an electrical short resulting from a brush being inadvertently dropped into the exciter commutator assembly. Entered Mode 3.

March 12 2129 Entered Mode 2 following inspection and repairs to the commutator assembly.

2130 Reactor made critical.

March 13 0749 Entered Mode 1.

0750 Unit synchronized to the grid. Reactor power increase is continuing.

March 31 2400 Unit is in Mode 1 at 92% reactor power. Turbine load at 409 MWe gross.

7596u/6

a REFUELING INFORMATION DOCKET NO.

50-206 UNIT SONGS - 1 DATE April 14, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH:

March 1987 1.

Scheduled date for next refueling shutdown.

June 1988 2.

Scheduled date for restart following refueling.

September 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.

l None 6.

The number of fuel assemblies.

a)

In the core.

157 b)

In the spent fuel storage pool.

146 i

7.

Licensed spent fuel storage capacity. 216 Intended change in spent fuel storage capacity. Under review 8.

Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

June 1988 l

l 7596u/7 l

J"O?

Southern California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 4 28 SAN CLEMENTE CALIFORNIA 92672 H.E. MORGAN TELEPHONE April 14, 1987 im = m' mren unsaaEn Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Docket No. 50-206 Monthly Operating Report for March 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, MbN 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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