ML13331B262

Monthly Operating Rept for Feb 1990 for San Onofre Nuclear Generating Station Unit 1

ML13331B262
Person / Time
Site:	San Onofre
Issue date:	02/28/1990
From:	Nandy F, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003200124
Download: ML13331B262 (7)

Text

Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R. NANDY TELEPHONE MANAGER OF NUCLEAR LICENSING (714) 587-5400 March 13, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Docket No. 50-206 Monthly Operating Report for February 1990 San Onofre Nuclear Generating Station, Unit 1 The purpose of this letter is to provide the Monthly Operating Report required by Section 6.9.1.10 of Appendix A, Technical Specifications (TS) to Provisional Operating License DPR-13 for San Onofre Nuclear Generating Station, Unit 1. The report covers routine operating statistics and shutdown experience for the reporting period.

TS Section 6.9.1.10 also requires reporting all challenges to the pressurizer safety and relief valves. Unit 1 did not experience a challenge to any of these valves during the reporting period.

If you require additional information, please let me know.

Very truly yours, Enclosures cc:

J. B. Martin (Regional Administrator, USNRC Region V)

C. W. Caldwell (USNRC Senior Resident Inspector, Units 1, 2 and 3)

Institute of Nuclear Power Operations (INPO) oo~c)Q..

)00O22:

F-DR ADOCK FDC R______________

I

NRC MONTHLY OPERATING REPORT DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

3-13-90 COMPLETED BY: E. R. Siacor TELEPHONE:

(714) 368-6223 OPERATING STATUS

1. Unit Name:

San Onofre Nuclear Generating Station, Unit 1

2. Reporting Period: February 1990

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 672.00 1,416.00 199,064.00

12. Number Of Hours Reactor Was Critical 672.00 1,416.00 115,277.84

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 672.00 1,416.00 111,095.48

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 817,513.95 1,713,343.58 139,283,190.70

17. Gross Electrical Energy Generated (MWH) 270,000.00 563,400.00 46,983,728.42

18. Net Electrical Energy Generated (MWH) 255,511.00 532,203.00 44,294,623.00

19. Unit Service Factor 100.00%

100.00%

55.81%

20. Unit Availability Factor 100.00%

100.00%

55.81%

21. Unit Capacity Factor (Using MDC Net) 87.21%

86.20%

51.04%

22. Unit Capacity Factor (Using DER Net) 87.21%

86.20%

51.04%

23. Unit Forced Outage Rate 0.00%

0.00%

19.62%

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

Cycle 11 refueling outage scheduled to commence on June 30, 1990.

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 mor.feb/2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-206 UNIT NAME:

SONGS -

1 DATE: 3-13-90 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

February 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 385.71 17 386.58 2

384.29 18 386.63 3

384.83 19 386.25 4

384.96 20 386.17 5

384.71 21 385.92 6

384.63 22 385.54 7

384.96 23 385.29 8

384.13 24 385.58 9

384.17 25 384.88 10 384.00 26 384.29 11 382.96 27 384.46 12 345.54 28 383.63 13 290.63 29 NA 14 384.96 30 NA 15 385.29 31 NA 16 385.33 mor.feb/3

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 REPORT MONTH:

FEBRUARY 1990 DATE:

3-13-90 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER SysteT Compongnt Action to No.

Date Typel (Hours)

Reason 2 Reactor3 No.

Code 4 Code" Prevent Recurrence NA NA NA NA NA NA NA NA NA NA 1F-Forced 2Reason:

3Method:

4IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20%

51EEE Std 803A G-Operational Error (Explain) or greater in the H-Other (Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other (Explain) mor.feb/4

SUMtRY OF OPERATING EXPERIENCE FOR 9 E MONTH DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE: 3-13-90 COMPLETED BY: E. R. Siacor TELEPHONE:

(714) 368-6223 Date Time Event February 1 0001 Unit is in Mode 1 at 91% reactor power. Turbine load at 403 MWe gross.

February 12 1900 Commenced reactor power decrease to allow removal from service of the South circulating water pump for inspection and repair of the No. 4 condenser water box tube leakage.

1932 Reactor at 60% power.

February 13 1019 Commenced reactor power increase following completion of tube plugging repairs to no. 4 condenser water box.

1200 Reactor at 92% power.

February 28 1548 Unusual Event declared due to seismic activity.

1710 Unusual Event terminated.

2400 Unit is in Mode 1 at 92% reactor power. Turbine load at 404 MWe gross.

mor.feb/5

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

3-13-90 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

February 1990

1. Scheduled date for next refueling shutdown.

June 30, 1990

2. Scheduled date for restart following refueling.

November 1990

3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes.

What will these be?

a) License Amendment associated with the resolution of the 480V breaker overload issue.

b) License Amendment associated with removal of the license condition related to the TDI diesel generators.

c) License Amendment associated with revision of the basis to Technical Specification 3.3.1, "Safety Injection and Containment Spray", and resolution of other issues related to TS 3.3.1 which were identified during Cycle 10 refueling.

d) License Amendment associated with the provision of an alternate intermediate spent fuel cooling capability during the upcoming Cycle 11 refueling outage and concurrent CCW outage.

mor.feb/6

-g g

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE: 31-90 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

February 1990

4. Scheduled date for submitting proposed licensing action and supporting information.

a) SCE expects to submit the license amendment associated with the 480V breaker overload issue no later than March 30, 1990 in accordance with the delay letter from SCE to the NRC, dated February 6, 1990.

b) SCE expects to submit the request to remove the TDI diesel generator license condition no later than April 30, 1990 in accordance with the delay letter from SCE to the NRC, dated February 21, 1990.

c) SCE expects to submit the request to revise the basis and resolve other issues related to TS 3.3.1 in April 1990.

d) SCE expects to submit the license amendment associated with the alternate intermediate spent fuel pool cooling capability by April 30, 1990.

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 have been identified at this time.

6. The number of fuel assemblies.

a) In the core.

157 b) In the spent fuel storage pool.

59

7. Licensed spent fuel storage capacity.

216 Intended change in spent fuel storage capacity.

None

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

Approximately 1995 (refueling only)

Approximately 1991 (full off load capability) mor.feb/7