ML13331B268

Monthly Operating Rept for San Onofre Nuclear Generating Station,Unit 1

ML13331B268
Person / Time
Site:	San Onofre
Issue date:	05/31/1990
From:	Nandy F, Sarette T SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006190144
Download: ML13331B268 (8)

Text

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

Subject:

Docket No. 50-206 Monthly Operating Report for May 1990 San Onofre Nuclear Generating Station, Unit 1 Technical Specification 6.9.1.10 to Provisional Operating License DPR-13 for the San Onofre Nuclear Generating Station, Unit 1, requires SCE provide a Monthly Operating Report which includes: routine operating statistics and shutdown experience; and, all challenges to pressurizer safety and relief valves.

This letter transmits the May 1990 Monthly Operating Report for Unit 1.

There were no challenges to pressurizer safety or relief 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)

J. R. Tatum (NRR, SONGS Project Manager)

Institute of Nuclear Power Operations (INPO) 6~1

'O6A F'DC 1

NRC MONTHLY OPERATING REPORT DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

6-15-90 COMPLETED BY: T. M. Sarette TELEPHONE:

(714) 368-9335 OPERATING STATUS

1. Unit Name:

San Onofre Nuclear Generating Station, Unit 1

2. Reporting Period: May 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 744.00 3,623.00 201,271.00

12. Number Of Hours Reactor Was Critical 567.83 3,444.86 117,306.70

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 551.12 3,428.15 113,107.63

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 670,384.00 4,167,174.63 141,737,021.75

17. Gross Electrical Energy Generated (MWH) 215,002.86 1,367,002.86 47,787,331.28

18. Net Electrical Energy Generated (MWH) 199,280.00 1,287,078.00 45,049,498.00

19. Unit Service Factor 74.08%

94.62%

56.20%

20. Unit Availability Factor 74.08%

94.62%

56.20%

21. Unit Capacity Factor (Using MDC Net) 61.43%

81.48%

51.34%

22. Unit Capacity Factor (Using DER Net) 61.43%

81.48%

51.34%

23. Unit Forced Outage Rate 25.92%

5.38%

19.45%

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.may/2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

6-15-90 COMPLETED BY:

T. M. Sarette TELEPHONE:

(714) 368-9335 MONTH:

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

(MWe-Net) 1 0.00 17 0.00 2

0.00 18 0.00 3

0.00 19 0.00 4

325.50 20 136.42 5

374.83 21 371.25 6

376.17 22 374.58 7

376.63 23 379.17 8

376.88 24 380.71 9

375.13 25 379.75 10 374.54 26 378.21 11 375.63 27 376.96 12 375.50 28 377.00 13 374.33 29 377.75 14 372.00 30 377.79 15 30.50 31 377.92 16 0.00 mor.may/3

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 REPORT MONTH:

MAY 1990 DATE:

6-15-90 COMPLETED BY: T. M. Sarette TELEPHONE:

(714) 368-9335 Method of Shutting Cause & Corrective Duration Down LER Syste Compongnt Action to No.

Date Typel (Hours)

Reason2 Reactor3 No.

Code Code Prevent Recurrence 137 900430 F

68.90 A

4 90-007 JC CBL1 Continued from previous month.

138 900515 F

123.98 B

2 90-011 JB NA The reactor was manually tripped from 91.5% power due to decreasing steam generator (SG) "C" level resulting from loss of feedwater flow. An inadvertent short circuit to ground during maintenence on AFW pump G-10 control valve circuit caused a brief power interruption which spuriously actuated SG high level trip and closed the main feedwater control valve for SG "C". A design change is being developed to provide a high level trip of the main feedwater control valves with reduced susceptibility to single failure and spurious actuations. For additionS details, refer to LER 90-011, Dock No. 50-206.

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%

SIEEE 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.may/4

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

6-15-90 COMPLETED BY: T. M. Sarette TELEPHONE:

(714) 368-9335 Date Time Event May 1 0001 Unit is in Mode 3.

May 3 1439 Commenced reactor startup.

1514 Entered Mode 2.

1530 Reactor made critical.

2009 Entered Mode 1.

2054 Unit synchronized to the grid. Continued reactor power increase.

May 4 0653 Reactor at 92% power.

May 15 0442 Unit manually tripped from 91.5% power due to "C" steam generator low level indication.

Entered Mode 3.

May 17 2304 Entered Mode 2.

May 18 0543 Reactor startup terminated due to West Feedwater Pump thrust bearing high temperature.

0639 Entered Mode 3 to conduct investigation and repair of the West Feedwater Pump thrust bearing.

May 20 0432 Entered Mode 2 following repair of West Feedwater Pump thrust bearing.

0445 Reactor made critical.

0745 Entered Mode 1.

0841 Unit synchronized to the grid. Continued reactor power increase.

1356 Reactor at 70% power in preparation for circulating water system heat treatment.

mor.may/5

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

6-15-90 COMPLETED BY: T. M. Sarette TELEPHONE:

(714) 368-9335 Date Time Event 1718 Commenced circulating water system heat treatment.

1918 Completed circulating water system heat treatment.

2058 Commenced reactor power increase.

2148 Reactor at 91% power.

May 31 2400 Unit is in Mode 1 at 92% reactor power. Turbine load at 400 MWe gross.

mor.may/6

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

6-15-90 COMPLETED BY:

T. M. Sarette TELEPHONE:

(714) 368-9335 MONTH:

May 1990

1. Scheduled date for next refueling shutdown.

June 30, 1990

2. Scheduled date for restart following refueling.

November 16, 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 the thermal shield support replacement and monitoring program.

d) License amendment associated with increased spent fuel pool cooling heat loads.

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

a) The license amendment associated with the 480V breaker overload issue was submitted on April 19, 1990.

b) The license amendment associated with the TDI diesel generator license condition was submitted on June 5, 1990.

c) The license amendment associated with the thermal shield support replacement and monitoring program was submitted on April 20, 1990.

d) The license amendment associated with the spent fuel pool cooling system was submitted on May 16, 1990.

mor.may/7

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

6-15-90 COMPLETED BY:

T. M. Sarette TELEPHONE:

(714) 368-9335 MONTH:

May 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.may/8