ML13331B265
| ML13331B265 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/30/1990 |
| From: | Nandy F, Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9005210246 | |
| Download: ML13331B265 (7) | |
Text
Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R. NANDY Ma 1
10 TELEPHONE MANAGER OF NUCLEAR LICENSING Ma 14, (714) 587-5400 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-206 Monthly Operating Report for April 1990 San Onofre Nuclear Generating Station, Unit 1 This letter transmits 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) 9005210246. 90)C)430 PDR ADiOCK 05000206 R
NRC MONTHLY OPERATING REPORT DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
5/14/90 COMPLETED BY: E. R. Siacor TELEPHONE:
(714) 368-6223 OPERATING STATUS
- 1. Unit Name:
San Onofre Nuclear Generating Station, Unit 1
- 2. Reporting Period: April 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 719.00 2,879.00 200,527.00
- 12. Number Of Hours Reactor Was Critical 717.03 2,877.03 116,738.87
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 717.03 2,877.03 112,556.51
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 873,433.00 3,496,790.63 141,066,637.75
- 17. Gross Electrical Energy Generated (MWH) 288,600.00 1,152,000.00 47,572,328.42
- 18. Net Electrical Energy Generated (MWH) 272,180.00 1,087,798.00 44,850,218.00
- 19. Unit Service Factor 99.73%
99.93%
56.13%
- 20. Unit Availability Factor 99.73%
99.93%
56.13%
- 21. Unit Capacity Factor (Using MDC Net) 86.82%
86.66%
51.30%
- 22. Unit Capacity Factor (Using DER Net) 86.82%
86.66%
51.30%
- 23. Unit Forced Outage Rate 0.27%
0.07%
19.41%
- 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:
May 3, 1990
- 26. Units In Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA mor.apr/2
0 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE: 5/14/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
April 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 398.91 17 378.92 2
382.33 18 378.71 3
384.17 19 377.50 4
383.67 20 377.29 5
383.25 21 376.75 6
383.25 22 376.63 7
383.42 23 377.04 8
382.46 24 378.50 9
383.17 25 376.83 10 384.00 26 376.25 11 383.00 27 375.67 12 381.96 28 373.54 13 380.67 29 373.92 14 380.13 30 327.08 15 379.08 31 NA 16 378.38 mor.apr/3
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 REPORT MONTH:
APRIL 1990 DATE:
5/14/90 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.
Code4 Code" Prevent Recurrence 137 900430 F
1.97 A
3 1-90-007 JC CBL1 The reactor tripped from 91% power due to actuation of the Reactor Protection System on low RCS flow*
one loop. The loss of flow signal was due to loss of insulation resistance in the flow transmitter cable. The cable with the indicated loss of insulation resistance was replaced. The remaining two RCS loop flow instrumentation cables having similar insulation were tested and cables indicating loss of insulation resistance were replaced.
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.apr/4
SUMMtY OF OPERATING EXPERIENCE FOR T! MONTH DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE: 5/14/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 Date Time Event April 1 0001 Unit is in Mode 1 at 91% reactor power. Turbine load at 402 MWe gross.
April 30 2222 Reactor tripped from 91% power due to actuation of the Reactor Protection System on low RCS flow in one loop. Entered Mode 3.
2400 Unit is in Mode 3. Investigation and evaluation of the cause of the trip to determine appropriate corrective actions are in progress.
mor.apr/5
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
5/14/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
April 1990
- 1. Scheduled date for next refueling shutdown.
June 30, 1990
- 2. Scheduled date for restart following refueling.
November 17, 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) SCE expects to submit the licence amendment associated with the removal of the TDI diesel generator license condition by May 31, 1990.
c) The license amendment associated with the thermal shield support replacement and monitoring program was submitted on April 20, 1990.
d) SCE expects to submit the license amendment associated with the spent fuel cooling system by May 21, 1990.
mor.apr/6
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
5/14/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
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.apr/7