ML13331B264
| ML13331B264 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/31/1990 |
| From: | Nandy F, Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9004170013 | |
| Download: ML13331B264 (7) | |
Text
Southem California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R. NANDY April 12, 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 March 1990 San Onofre Nuclear Generating Station, Unit 1 This letter provides 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 your,
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) 9004170013 900331 PDR ADOCK 05000:206 R
NRC MONTHLY OPERATING REPORT DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE: 4/12/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 OPERATING STATUS
- 1. Unit Name:
San Onofre Nuclear Generating Station, Unit 1
- 2. Reporting Period: March 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 2,160.00 199,808.00
- 12. Number Of Hours Reactor Was Critical 744.00 2,160.00 116,021.84
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 744.00 2,160.00 111,839.48
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 910,014.05 2,623,357.63 140,193,204.75
- 17. Gross Electrical Energy Generated (MWH) 300,000.00 863,400.00 47,283,728.42
- 18. Net Electrical Energy Generated (MWH) 283,415.00 815,618.00 44,578,038.00
- 19. Unit Service Factor 100.00%
100.00%
55.97%
- 20. Unit Availability Factor 100.00%
100.00%
55.97%
- 21. Unit Capacity Factor (Using MDC Net) 87.37%
86.61%
51.17%
- 22. Unit Capacity Factor (Using DER Net) 87.37%
86.61%
51.17%
- 23. Unit Forced Outage Rate 0.00%
0.00%
19.51%
- 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.mar/2
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
4/12/90 COMPLETED BY: E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH: March 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 383.00 17 383.58 2
383.29 18 384.04 3
384.08 19 384.04 4
383.25 20 385.33 5
383.67 21 385.17 6
384.71 22 384.17 7
384.54 23 383.13 8
382.71 24 382.50 9
383.50 25 382.58 10 383.79 26 382.08 11 383.75 27 381.71 12 384.33 28 381.75 13 384.88 29 381.96 14 384.33 30 381.83 15 384.58 31 302.92 16 383.75 mor.mar/3
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 REPORT MONTH:
MARCH 1990 DATE: 4/12/90 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 Code Prevent Recurrence NA NA NA NA NA NA NA NA NA NA
- 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-3 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.mar/4
SUMNY OF OPERATING EXPERIENCE FOR MONTH DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
4-12-90 COMPLETED BY: E. R. Siacor TELEPHONE:
(714) 368-6223 Date Time Event March 1 0001 Unit is in Mode 1 at 92% reactor power. Turbine load at 404 MWe gross.
March 31 0515 Commenced reactor power decrease to approximately 50% to perform quarterly reactor coolant flow instrumentation channel test required by Technical Specification 4.1.1. In addition, circulating water heat treating, turbine stop valve testing and South condenser water box cleaning were scheduled to be performed.
0615 Reactor at 47% power. Scheduled evolutions were initiated.
0655 Completed turbine stop valve testing satisfactorily.
0900 Completed quarterly reactor coolant flow instrumentation channel test satisfactorily.
1202 Completed South condenser water box cleaning.
1226 Reactor power increased to 68% to perform circulating water heat treat.
1352 Commenced heat treat operations.
1756 Commenced reactor power increase following completion of heat treat operations.
1938 Reactor at 91% power.
2400 Unit is in Mode 1 at 91% power. Turbine load at 402 MWe gross.
mor.mar/5
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
4/12/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
March 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 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.
d) License Amendment associated with the provision of an alternate intermediate spent fuel cooling capability during the upcoming Cycle 11 refueling outage and concurrent CCW outage.
Will not be included in next month's report - Although this license amendment will be submitted by April 30,1990, as indicated in last month's report, re-evaluation concluded that NRC approval of the change is not required prior to refueling or resumption of operation.
Will not be included in next month's report - CCW outage will not be conducted during Cycle 11 refueling.
mor.mar/6
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
4/12/90 COMPLETED BY:
E. R. Siacor TELEPHONE:
(714) 368-6223 MONTH:
March 1990
- 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 by April 30, 1990.
b) SCE expects to submit the request to remove the TDI diesel generator license condition by April 30, 1990, in accordance with the letter from SCE to the NRC, dated February 21, 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.mar/7