ML13331B216

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

ML13331B216
Person / Time
Site:	San Onofre
Issue date:	09/30/1989
From:	Nandy F, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8910270217
Download: ML13331B216 (9)

Text

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• V Southern California Edison Company P. O. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 F.R. NANDY Otbr TELEPHONE MANAGER OF NUCLEAR LICENSING October 16, 199 8

302-189 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Docket No. 50-206 Monthly Operating Report for September 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 advise.

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) 89' 0270217 890930 PR AD0cK 05000206 PNU

NRC MONTHLY OPERATING REPORT DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

1o..16..9 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 OPERATING STATUS

1. Unit Name:

San Onofre Nuclear Generating Station, Unit 1

2. Reporting Period:

September 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 6,551.00 195,439.00

12. Number Of Hours Reactor Was Critical 673.35 1,894.32 112,173.51

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 669.37 1,774.07 108,004.56

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 805,750.00 1,901,570.00 135,555,307.75

17. Gross Electrical Energy Generated (MWH) 261,000.00 608,400.00 45,760,328.42

18. Net Electrical Energy Generated (MWH) 245,604.00 547,537.00 43,143,555.00

19. Unit Service Factor 92.97%

27.08%

55.26%

20. Unit Availability Factor 92.97%

27.08%

55.26%

21. Unit Capacity Factor (Using MDC Net) 78.24%

19.17%

50.63%

22. Unit Capacity Factor (Using DER Net) 78.24%

19.17%

50.63%

23. Unit Forced Outage Rate 7.03%

42.68%

20.04%

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.sep/2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

10 16-89 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

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

(MWe-Net) 1 362.88 17 375.88 2

377.25 18 302.67 3

376.17 19 0.00 4

374.75 20 0.00 5

376.67 21 333.75 6

378.25 22 371.58 7

379.29 23 370.04 8

379.42 24 371.08 9

341.50 25 370.58 10 380.29 26 373.46 11 379.92 27 374.71 12 379.96 28 372.38 13 379.08 29 376.67 14 378.17 30 266.17 15 378.92 31 NA 16 376.08 mor.sep/3

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 REPORT MONTH: SEPTEMBER 1989 DATE:

10-16-89 COMPLETED BY:

E. R. Siacor TELEPHONE:

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

Date Typel (Hours)

Reason2 Reactor3 No.

Code" Code Prevent Recurrence 130 890918 F

50.63 A

2 89-023 AA CL The reactor was manually tripped 92% power when Shutdown Group 2 rw dropped into the core due to deenergization of the moveable gripper coils as a result of rod "holding" contactors (2MS1 and 2MS2) dropping out.

2MS1 and 2MS2 dropped out due to low resistance/short circuit condition in the coil of 2MS1, which is connected in parallel with 2MS2. Cause of the short circuit is not known at this time.

The failed coil was replaced and evaluation for the root cause of the failure is continuing to determine long term corrective action.

'F-Forced 2Reason:

3Method:

4IEEE Std 805-199 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.sep/4

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 MONTH:

SEPTEMBER 1989 DATE:

10-16-89 COMPLETED BY:

E. R. Siacor TELEPHONE:

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

Date Typel (Hours)

Reason 2 Reactor3 No.

Code Code Prevent Recurrence 131 890930 S

0.00 B

5 NA KE COND Power reduction of 20% or greater to perform condensew water box cleaning.

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.sep/5

SUAY OF OPERATING EXPERIENCE FOR 9 MONTH DOCKET NO:

50-206 UNIT NAME: SONGS - 1 DATE:

10-16-8 9 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 Date Time Event September 1 0001 Unit is in Mode 1 at 91% reactor power. Turbine load at 391 MWe gross.

September 9 0830 Commenced reactor power decrease to perform heat treating operations for the circulating water structure.

1703 Reactor power increased to 92% power following completion of heat treating operations.

September 18 1914 Reactor manually tripped from 92% power due to Shutdown Bank Group 2 rods dropping into the bottom of the core. Entered Mode 3.

September 20 1720 Commenced reactor startup following evaluation and repairs to the cause of the shutdown rod drop.

1751 Entered Mode 2.

1801 Reactor made critical.

2147 Entered Mode 1.

2200 Unit synchronized to the grid. Continuing reactor power increase.

September 21 0520 Reactor at 91% power.

mor.sep/6

0 0

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

10-16-39 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 Date Time Event September 30 0500 Commenced reactor power decrease to allow replacement of the North screen wash pump and to perform condenser water box cleaning.

0530 Reactor at 58% power.

2121 Commenced reactor power increase following completion of screen wash pump replacement and condenser water box cleaning.

2230 Reactor at 91% power.

2400 Unit is in Mode lat 91% power. Turbine load at 400 MWe gross.

mor.sep/7

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

10-16-89 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

September 1989

1. Scheduled date for next refueling shutdown.

June 30, 1990

2. Scheduled date for restart following refueling.

December 1990

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

Yes.

What will these be?

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

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.

The RVLIS license amendment request is scheduled to be submitted October 31, 1989. Not yet specifically determined for others.

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 mor.sep/8

REFUELING INFORMATION DOCKET NO:

50-206 UNIT NAME:

SONGS - 1 DATE:

10-16--89 COMPLETED BY:

E. R. Siacor TELEPHONE:

(714) 368-6223 MONTH:

September 1989

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.sep/9