ML13331B250

Monthly Operating Rept for Dec 1989 for San Onofre Nuclear Generating Station Unit 1

ML13331B250
Person / Time
Site:	San Onofre
Issue date:	12/31/1989
From:	Nandy F, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9001230124
Download: ML13331B250 (8)

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'7 Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R-NANDY January 15, 1990 TELEPHONE MANAGER OF NUCLEAR LICENSING (714) 587-5400 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Docket No. 50-206 Monthly Operating Report for December 1989 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 to Provisional Operating License DPR-13 for San Onofre Nuclear Generating Station, Unit 1.

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) 9001230124 891231

/,

PER ADOCK 0500020.6 R

PDC

NRC MONTHLY OPERATING REPORT DOCKET NO:

50-206 UNIT NAME:

SONGS -

1 DATE:

Tanuary 15 1990 COMPLETED BY: E. R. Siacor TELEPHONE:

(714) 368-6223 OPERATING STATUS

1. Unit Name:

San Onofre Nuclear Generating Station, Unit 1

2. Reporting Period:

December 1989

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 744.00 8,760.00 197,648.00

12. Number Of Hours Reactor Was Critical 702.58 3,582.65 113,861.84

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 696.42 3,458.99 109,679.48

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 844,387.32 3,916,109.37 137,569,847.12

17. Gross Electrical Energy Generated (MWH) 278,400.00 1,268,400.00 46,420,328.42

18. Net Electrical Energy Generated (MWH) 262,258.00 1,166,402.00 43,762,420.00

19. Unit Service Factor 93.60%

39.37%

55.49%

20. Unit Availability Factor 93.60%

39.37%

55.49%

21. Unit Capacity Factor (Using MDC Net) 80.85%

30.54%

50.78%

22. Unit Capacity Factor (Using DER Net) 80.85%

30.54%

50.78%

23. Unit Forced Outage Rate 6.40%

28.41%

19.82%

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

NA

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.1dec/2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

January 15, 1990 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

December 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 380.71 17 381.67 2

382.50 18 381.54 3

383.00 19 382.00 4

383.11 20 381.54 5

382.83 21 381.29 6

345.83 22 382.04 7

0.00 23 382.13 8

0.00 24 382.92 9

296.04 25 382.79 10 378.17 26 383.42 11 380.83 27 383.50 12 381.88 28 383.00 13 382.08 29 382.71 14 382.00 30 382.75 15 382.63 31 381.58 16 381.92 mor.dec/3

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 REPORT MONTH:

DECEMBER 1989 DATE: January 15, 1990 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" Code Prevent Recurrence 135 891206 F

47.58 A

1 89-028 LE RG A TS required shutdown from 91%

power was completed due to HV-851A containment isolation function being inoperable for greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to inadequate backup nitrogen system (BNS) supply. Cyclic lifting

& reseating of BNS relief valve, due to leakage past the valve seats of 3 out of 5 pressure regulators, was determined to have resulted in the loss of nitrogen exceeding the loss assumed in the accident analysis.

The 3 regulators were repaired and returned to service. During the next refueling outage new regulators, designed to reduce BNS susceptibility to failure due to leakage past the valve seats, will replace the existing regulators.

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%

5IEEE Std 803A-1983 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.dec/4

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-206 UNIT NAME: SONGS - 1 DATE:

Tanuary 15 1990 COMPLETED BY:

E. R. Sfacor TELEPHONE:

(714) 368-6223 Date Time Event December 1 0001 Unit is in Mode 1 at 91% reactor power. Turbine load at 401 MWe gross.

December 6 2018 Commenced a Technical Specification required shutdown from 91% reactor power to perform repairs on the backup nitrogen system regulators (BNS) for HV-851A.

2043 Unusual Event declared.

2130 Unusual Event terminated.

2343 Turbine manually tripped. Unit off line.

2349 Entered Mode 3.

December 8 1655 Commenced reactor startup following completion of repairs to the BNS regulators for HV-851A.

1735 Entered Mode 2.

1747 Reactor made critical.

2130 Entered Mode 1.

2318 Unit synchronized to the grid. Continuing reactor power increase to 70%.

mor.dec/5

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

January 15, 1990 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 Date Time Event December 9 0405 Reactor at 70% power. Commenced heat treating operations for the circulating water tunnels.

0934 Completed heat treating operations. Commenced reactor power increase.

1110 Reactor at 92% power.

December 31 2400 Unit is in Mode 1 at 91% power. Turbine load at 402 MWe gross.

mor.dec/6

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

January 15, 1990 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

December 1989

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.

mor.dec/7

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - I DATE:

January 15, 1990 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

December 1989

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 in February 1990.

b) SCE expects to submit the request to remove the TDI diesel generator license condition in February 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.

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.dec/8