ML13333A697
| ML13333A697 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/30/1988 |
| From: | Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8810210507 | |
| Download: ML13333A697 (7) | |
Text
NRC MONTHLY OPERATING REPORT DOCKET NO. 50-206 UNIT SONGS - 1 DATE October 17, 1988 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 1988
- 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 6,575.00 186,679.00
- 12. Number Of Hours Reactor Was Critical 720.00 2,422.84 108,884.36
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 720.00 2,409.08 104,835.77
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 870,467.84 2,839,140.70 131,968,108.75
- 17. Gross Electrical Energy Generated (MWH) 277,800.00 925,800.00 44,603,528.42
- 18. Net Electrical Energy Generated (MWH) 261,200.00 858,977.00 42,081,640.00
- 19. Unit Service Factor 100.00%
36.64%
56.16%
- 20. Unit Availability Factor 100.00%
36.64%
56.16%
- 21. Unit Capacity Factor (Using MDC Net) 83.21%
29.96%
51.70%
- 22. Unit Capacity Factor (Using DER Net) 83.21%
29.96%
51.70%
- 23. Unit Forced Outage Rate 0.00%
0.00%
19.72%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Cycle 10 refueling outage scheduled for November 27, 1988
- 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 7596u.rpt/3
'8810210507.80930 PDR ADOCK 05000206 R
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-206 UNIT SONGS - 1 DATE October 17, 1988 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH:
September 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 375.63 17 382.08 2
375.75 18 382.08 3
375.38 19 381.04 4
375.00 20 380.29 5
374.33 21 377.71 6
375.08 22 377.54 7
375.42 23 376.33 8
368.58 24 376.25 9
368.75 25 377.17 10 235.92 26 376.71 11 220.25 27 376.00 12 338.92 28 374.83 13 305.67 29 365.71 14 377.63 30 373.96 15 381.92 31 N/A 16 381.42 7596u.rpt/4
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-206 UNIT NAME SONGS - 1 REPORT MONTH SEPTEMBER 1988 DATE October 17, 1988 COMPLETED BY E. R. Siacor' TELEPHONE (714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER Syste Compongnt Action to No.
Date Type1 (Hours)
Reason2 Reactor3 No.
Code Code Prevent Recurrence 121 880910 S
0.00 B
5 NA KE COND Power reduction of 20% orP greater to peform condenser water box cleaning.
122 880913 S
0.00 B
5 NA KE COND Power reduction of 20% or greater to perform condenser water box cleaning and shear pin repair.
1F-Forced 2Reason:
3Method:
4 1EEE 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%
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) 7596u/5
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-206 UNIT SONGS - 1 DATE October 17, 1988 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 Date Time Event September 1 0001 Unit is in Mode 1 at 92% reactor power. Turbine load at 396 MWe.
September 10 0030 Commenced load reduction to 250 MWe for circulating water box cleaning, circulating water system heat treat, circulating water box screen repair and turbine stop valve testing.
0545 Turbine load at 250 MWe.
September 12 0300 Commenced power ramp up to full power after satisfactory completion of condenser water box cleaning, heat treat of circulating water system, repairs to condenser water box screens and turbine stop valve testing.
0931 Reactor at 92% power. Turbine load at 405 MWe.
September 13 1115 Commenced load reduction due to a broken shear pin on the circulating water intake system traveling screen resulting in a high differential pressure and a potential loss of the South Circulating Water Pump.
1125 A new shear pin was installed and the Unit power reduction stopped at 297 MWe.
1200 Commenced power reduction to 243 MWe for south circulating water box cleaning.
1330 Turbine load at 243 MWe.
1919 Commenced power increase to 92% reactor power after repair to the south screens and completion of water box cleaning.
September 14 0230 Reactor at 92% power. Turbine load at 406 MWe.
September 30 2400 Unit is in Mode 1 at 92% power. Turbine load at 395 MWe.
REFUELING INFORMATION DOCKET NO.
50-206 UNIT SONGS - 1 DATE October 17, 1988 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH:
September 1988
- 1. Scheduled date for next refueling shutdown.
November 27, 1988
- 2.
Scheduled date for restart following refueling.
Under Evaluation
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes.
What will these be?
Proposed Technical Specification Changes are as follows:
Proposed Change Number (PCN) 169 revises Technical Specification (TS) 3.5.2, "Control Group Insertion Limits" to delete Control Group 1 allowable insertion and to incorporate Standard Technical Specification (STS) format and Action Statements.
Proposed Change Number (PCN) 182 revises TS 4.16, "Inservice Inspection of Steam Generator Tubing" to include an alternate tube plugging criteria.
Proposed Change Number (PCN) 184 revises the demonstration of Control Element Assembly trippability to 7 days prior to reducing shutdown margin below the limits.
Proposed Change Number (PCN) 185 revises Appendix A TS 2.1 and 3.5.1 to include the revised steam/feedwater flow mismatch trip setpoints and associated Limiting Conditions for Operations.
Proposed Change Number (PCN) 186 revises TS 4.2, "Safety Injection and Containment Spray System" periodic testing to include surveillance of a planned modification to add Safety Injection/Feedwater Pump trip on low-low Refueling Water Storage Tank (RWST) level.
Proposed Change Number (PCN) 194 modifies the positive isolation barrier requirements in TS 3.3.2 due to modifications to include MOV-358 onto the Uninterruptible Power Supply (UPS) for MOV-850C.
7596u.rpt/8
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REFUELING INFORMATION DOCKET NO.
50-206 UNIT SONGS - 1 DATE October 17, 1988 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH:
September 1988 Proposed Change Number (PCN) 197 increases the load limit to 6000 KW for each of the two Emergency Diesel Generators.
- 4.
Scheduled date for submitting proposed licensing action and supporting information.
PCN 169 - submitted to the NRC on 05/26/88 PCN 182 - submitted to the NRC on 03/10/88 PCN 184 - scheduled for submittal to the NRC by mid-October 1988 PCN 185 - scheduled for submittal to the NRC by mid-October 1988 PCN 186 - scheduled for submittal to the NRC by mid-October 1988 PCN 194 - scheduled for submittal to the NRC by mid-October 1988 PCN 197 - scheduled for submittal to the NRC by mid-October 1988
- 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
- 6. The number of fuel assemblies.
a) In the core.
157 b) In the spent fuel storage pool.
146
- 7.
Licensed spent fuel storage capacity.
216 Intended change in spent fuel storage capacity. Under review
- 8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Under Evaluation 7596u.rpt/9
Southern California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. 0.
BOX 128 SAN CLEMENTE, CALIFORNIA 92672 H.E.MORGAN TELEPHONE STATION MANAGER (714) 368-6241 October 17, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
Docket No. 50-206 Monthly Operating Report for September 1988 San Onofre Nuclear Generating Station, Unit 1 Enclosed is the Monthly Operating Report as 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.
Please contact us if we can be of further assistance.
Sincerely, H. E. MORGAN STATION MANAGER ERSiacor:rpt/aug Enclosures cc:
J. B. Martin (Regional Administrator, USNRC Region V)
F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)
Institute of Nuclear Power Operations (INPO)