ML13331B245

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

ML13331B245
Person / Time
Site:	San Onofre
Issue date:	11/30/1989
From:	Nandy F, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8912280104
Download: ML13331B245 (8)

Text

Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R. NANDY December 14, 1989 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 November 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) 8912280104 891130 PDR ADOCK 05000206 R

PNU

NRC MONTHLY OPERATING REPORT DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

12/14/89 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 OPERATING STATUS

1. Unit Name:

San Onofre Nuclear Generating Station, Unit 1

2. Reporting Period:

November 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 720.00 8,016.00 196,904.00

12. Number Of Hours Reactor Was Critical 240.75 2,880.07 113,159.26

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 233.50 2,752.57 108,983.06

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 296,719.05 3,07 136,725,459.80

17. Gross Electrical Energy Generated (MWH) 91,200.00 990,000.00 46,141,928.42

18. Net Electrical Energy Generated (MWH) 82,707.00 904,144.00 43,500,162.00

19. Unit Service Factor 32.43%

34.34%

55.35%

20. Unit Availability Factor 32.43%

34.34%

55.35%

21. Unit Capacity Factor (Using MDC Net) 26.35%

25.87%

50.67%

22. Unit Capacity Factor (Using DER Net) 26.35%

25.87%

50.67%

23. Unit Forced Outage Rate 0.00%

32.43%

19.89%

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.nov/2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

12/14/89 COMPLETED BY: E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

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

(MWe-Net) 1 28.95 17 0.00 2

0.00 18 0.00 3

0.00 19 0.00 4

0.00 20 0.00 5

0.00 21 108.73 6

0.00 22 375.75 7

0.00 23 378.56 8

0.00 24 380.56 9

0.00 25 381.17 10 0.00 26 380.51 11 0.00 27 382.48 12 0.00 28 383.63 13 0.00 29 381.39 14 0.00 30 383.02 15 0.00 31 NA 16 0.00 mor.nov/3

UNIT -SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 REPORT MONTH:

NOVEMBER 1989 DATE:

12/14/89 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)

Reason2 Reactor3 No.

Code Codes Prevent Recurrence 134 891101 S

486.50 H

1 NA BP FT, SW Normal plant shutdown from 67%

reactor power following completion of heat treating operations to perform environmentally qualified modifications on the Hot Leg Recirculation System.

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 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. nov/4

SUMM*OF OPERATING EXPERIENCE FOR TH ONTH DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

12/14/89 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 Date Time Event November 1 0001 Unit is in Mode 1 at 67% reactor power. Turbine load at 259 MWe gross. Heat treating operations in progress.

0118 Completed circulating water system heat treating operations.

0240 Commenced Unit shutdown from 67% reactor power for a scheduled Hot Leg Recirculation System modification outage.

0531 Main generator taken off line.

Entered Mode 2.

0601 Entered Mode 3.

0625 Reactor tripped manually.

November 2 1303 Entered Mode 4.

1825 Entered Mode 5.

November 13 2346 Entered Mode 4.

November 14 2055 Entered Mode 3.

November 17 0025 Commenced cooldown to Mode 5 to repair pressurizer power operated relief valve (PORV) CV-531. Valve failed to indicate the desired change of position.

0442 Entered Mode 4.

0742 Entered Mode 5.

mor.nov/5

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

12114/89 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 Date Time Event November 19 2120 Entered Mode 4 following completion of repairs to CV-531.

November 20 0915 Entered Mode 3.

November 21 0340 Commenced reactor startup.

0421 Entered Mode 2.

0446 Reactor made critical.

1048 Entered Mode 1.

1201 Unit synchronized to the grid. Continue reactor power increase to full power.

1955 Reactor at 90% power. Turbine load at 393 MWe gross.

November 30 2400 Unit is in Mode 1 at 90% power. Turbine load at 401 MWe gross.

mor.nov/6

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE; 19/14/89 COMPLETED BY:

E. R. SIACOR TELEPHONE:

(714) 368-6223 MONTH:

November 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 requesting an extension of the steam generator inspection interval such that the inspection can be deferred to the Cycle 11 refueling outage.

b) License Amendment associated with the implementation schedule for the Reactor Vessel Level Instrumentation System (RVLIS).

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

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

e) Evaluation is underway for other Technical Specification change(s) or license amendment(s) which may be required for refueling or subsequent operation.

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

a) The steam generator inspection interval License Amendment was submitted on October 31, 1989.

b) The RVLIS License Amendment was submitted on November 1, 1989.

c) SCE expects to submit the license amendment associated with the 480V breaker overload issue in February 1990.

d) SCE expects to submit the request to remove the TDI diesel generator license condition in February 1990.

e) Not yet specifically determined for others.

mor.nov/7

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

12/14/89 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

November 1989

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.

Not yet determined. Under evaluation.

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.nov/8