ML20207S901

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Monthly Operating Rept for Feb 1987
ML20207S901
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 02/28/1987
From: Morgan H, Siacor E
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8703200384
Download: ML20207S901 (6)


Text

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-206 UNIT NAME SONGS - 1 DATE March 16, 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 1
2. Reporting Period:

February 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.

l This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 672.00 1,416.00 172,760.00
12. Number Of Hours Reactor Was Critical 672.00 1,416.00 100,494.62
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 672.00 1,416.00 96,519.28
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 819,737.82 1,725,336.36 122,031,245.22
17. Gross Electrical Energy Generated (MWH) 271,200.00 568,800.00 41,361,996.38
18. Net Electrical Energy Generated (MWH) 255,389.00 535,767.00 39,050,429.00
19. Unit Service Facter 100.00%

100.00%

55.87%

20. Unit Availability Factor 100.00%

100.00%

55.87%

21. Unit Capacity Factor (Using MDC Net) 87.17%

86.78%

51.84%

22. Unit Capacity Factor (Using DER Net) 87.17%

86.78%

51.84%

23. Unit Forced Outage Rate 0.00%

0.00%

20.97%

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 ifr r,

8703200384 870228 A

k 7596u/3

{DR ADOCK 05000206

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PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-206 UNIT SONGS - 1 DATE March 16, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH:

February 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 386.92 17 387.08 2_

387.00 18

__387.54 3

386.83 19 387.25 4

386.13 20 227.50 5

386.38 21 385.71 6

386.75 22 389.21 7

387.79 23 381.13 8

388.29 24 389.50 9

387.63 25 390.92 10 385.88 26 390.83 11 385.88 27 389.88 12 386.92 28 389.50 13 344.79 29 NA 14 384.79 30 NA 15 386.46 31 NA 16 386.75 7596u/4

.. ~ -

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' UNIT SHUTDOWNS AND POWER REDUCTIONS:

DOCKET NO. 50-206 UNIT NAME SONGS

'I REPORT MONTH FEBRUARY 1987 DATE Ftarch 10, 1957 COMPLETED BY E.

R.

Slacor

. TELEPHONE 1714) 368-6223 Method or Shutting Down System Component Cause & Correctivo 1

Du ra t ion 2

3 LER 4

4 Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence i

108 870220 F

0.00 A

5 NA BA P

Plant. shutdown was initiated as requi red by Technica l Specification 3.4.3 due to inoperability of Turbine 1

Driven Auxilia ry feedvater Pump G-10.

The pump tripped on overspeed during post maintenance testing due to water in the steam line and turbine casing. The cause was plugging or casing. drain lino y

orifices with carbon steel piping corrosion products. The orifices were unplugged, the pump was tested satisfactorily and declared operable a

before plant shutdown could be completed. Long term corrective

.t actions a re under eva luation, f

?

1 2

3 4-F-forced Reason:

Method:

IEEE Std. 803-1983 S-Scheduled A-Equipment failure (Explain) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling 3-Au toma t ic Sc ram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination

. 5-Reduction or 20%

Previous Month F-Adm i n i s t ra t ive G-Ope ra t iona l Error (Explain) or Greater in the l

H-Other ( Expla in)

Past 24 Hours 6-Other ( Explain) 7596u/5 I

f 1

i I

O

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET 50-206 UNIT SONGS - 1 DATE March 16, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 DATE TIME EVENT February 1 0001 The Unit is in Mode 1 at 93% reactor power.

Turbine load at 409 MWe gross.

February 20 0815 Commenced plant shutdown as required by Technical Specification 3.4.3 due to inoperability of Turbine Driven Auxiliary Feedwater Pump (TDAFWP) G-10.

1400 TDAFWP G-10 declared operable following completion of repairs and satisfactory operability testing. Plant shutdown halted with the reactor at 20% power and turbine load at 75MWe gross.

1407 Commenced reactor power increase to 35%.

1415 Reactor power at 35% and turbine load at 150 MWe gross. Performed condenser waterbox cleaning.

2314 Commenced power increase following completion of condenser waterbox cleaning.

February 21 0100 Reactor power at 93.5%. Turbine load at 410 MWe gross.

February 28 2400 Unit is in Mode 1 at 92% reactor power. Turbine load at 410 MWe gross.

7596u/6

r w-REFUELING INFORMATION DOCKET NO.

50-206 UNIT SONGS - 1 DATE March 16, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH:

February 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 i

5. 'Important Licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis r.,ethods, significant changes in fuel design, new operating procedures.

None 6.

The number of fuel assemblies.

a)

In the core.

157 b)

In the spent fuel storage pool.

146 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 7596u/7

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Southem Califomia Edison Company SAN ONOFRE NUCLEAR GENERATING FTATION P. O. BOX 128 SAN CLEMENTE. CALIFORNIA 92672 H.E. MORGAN TELEPHONE STATCNSAANAGER (714) 368 6249 March 16, 1987 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Docket No. 50-206 Monthly Operating Report for February 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, MkM 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

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