ML13331B300
| ML13331B300 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/30/1990 |
| From: | Vittum S Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13331B299 | List: |
| References | |
| NUDOCS 9012260015 | |
| Download: ML13331B300 (7) | |
Text
NRC MONTHLY OPERATING REPORT DOCKET NO:
50-206 UNIT NAME: SONGS - 1 DATE:
12/17/90 COMPLETED BY: S. L. Vittum TELEPHONE:
(714) 368-9230 OPERATING STATUS
- 1. Unit Name:
San Onofre Nuclear Generating Station, Unit 1
- 2. Reporting Period:
November 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 720.00 8,016.00 200,877.00*
- 12.
Number Of Hours Reactor Was Critical 0.00 4,162.86 116,166.70*
- 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14.
Hours Generator On-Line 0.00 4,145.90 112,356.38*
- 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16.
Gross Thermal Energy Generated (MWH) 0.00 5,040,285.33 141,439,501.61*
- 17.
Gross Electrical Energy Generated (MWH) 0.00 1,649,602.86 47,675,344.00*
- 18.
Net Electrical Energy Generated (MWH)
(1,376.00) 1,546,073.00 44,995,202.00*
- 19.
Unit Service Factor 0.00%
51.72%
55.93%*
- 20.
Unit Availability Factor 0.00%
51.72%
55.93%*
- 21.
Unit Capacity Factor (Using MDC Net) 0.00%
44.24%
51.37%*
- 22.
Unit Capacity Factor (Using DER Net) 0.00%
44.24%
51.37%*
- 23.
Unit Forced Outage Rate 0.00%
4.49%
19.55%
- 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Reactor thermal shield support replacement and cycle 11 refueling outage commenced on June 30, 1990. Outage duration scheduled for 243 days.
- 25.
If Shutdown At End Of Report Period, Estimated Date of Startup:February 28,1991
- 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 9012260015 901217 PDTR ADOCK 05000206 R
0I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
12/17/90 COMPLETED BY:
S. L. Vittum TELEPHONE:
(714) 368-9230 MONTH: November 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0.00 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 0.00 6
0.00 22 0.00 7
0.00 23 0.00 8
0.00 24 0.00 9
0.00 25 0.00 10 0.00 26 0.00 11 0.00 27 0.00 12 0.00 28 0.00 13 0.00 29 0.00 14 0.00 30 0.00 15 0.00 16 0.00 mor.nov/3
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 REPORT MONTH:
November 1990 DATE:
12/17/90 COMPLETED BY:
S. L. Vittum TELEPHONE:
(714) 368-9230 Method of Shutting Cause & Corrective Duration Down LER System Component Action to No.
Date Type' (Hours) Reason2 Reactor3 No.
Code 4 Code5 Prevent Recurrence 139 900630 S
720 C,D 4
NA NA NA Reactor thermal shield support replacement and cycle 11 refueling outage.
'F-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.nov/4
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
12/17/90 COMPLETED BY: S. L. Vittum TELEPHONE:
(714) 368-9230 Date Time Event November 1
0001 Unit is defueled, day 126 of the reactor thermal shield repair and Cycle 11 refueling outage.
November 7
0047 Unusual Event declared due to fire on west side of Interstate 5.
1430 Unusual Event terminated.
November 30 2400 Unit is defueled, day 155 of the reactor thermal shield repair and Cycle 11 refueling outage.
mor.nov/5
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS - 1 DATE:
12/17/90 COMPLETED BY:
S. L. Vittum TELEPHONE:
(714) 368-9230 MONTH:
November 1990
- 1. Scheduled date for next refueling shutdown.
The Cycle 11 refueling outage, commenced on June 30, 1990, is currently in progress.
The Cycle 12 refueling outage is forecast to commence in September 1992.
- 2. Scheduled date for restart following refueling.
Restart from the Cycle 11 refueling outage is forecast for February 28, 1991.
Restart from the Cycle 12 refueling outage is forecast for February 1993.
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes, for Cycle 11 refueling.
Not yet specifically determined for Cycle 12 refueling.
What will these be?
For Cycle 11 refueling:
a) License Amendment Application No. 181, associated with the thermal shield support replacement and monitoring program.
b) License Amendment Application No. 183, associated with the conversion of the license conditions related to the TDI diesel generators into Technical Specifications.
Amendment 136 issued by the NRC Nov. 8, 1990.
c) License Amendment Application No. 185, associated with reduced minimum Auxiliary Feedwater Flow resulting from the cavitating venturi resizing.
Amendment 138 issued by the NRC Nov. 15, 1990.
d) License Amendment Application No. 189, to resolve single failure susceptibilities of the 4160 volt electrical distribution system and the Safeguards Load Sequencing System (SLSS).
mor.nov/6
e)
License Amendment Application No. 190, to revise the Provisional Operating License to allow a schedular extension for Items 5 and 18 of the Cycle 11 Full Term Operating License (FTOL) Projects.
f)
License Amendment Application No. 191, to revise the Technical Specification Table 4.1.2 to reflect changes to the Volume Control and Charging System resulting from the addition of MOV-1100E.
For Cycle 12 refueling:
Not yet specifically determined. Under evaluation.
- 4. Scheduled date for submitting proposed licensing action and supporting information.
For Cycle 11 refueling outage:
a)
License Amendment Application No. 181, thermal shield support replacement and monitoring program, was submitted on April 20, 1990.
b)
License Amendment Application No. 183, TDI diesel generator license condition, was submitted on June 5, 1990. This amendment was approved as Amendment 136 by the NRC on Nov. 8, 1990.
c)
License Amendment Application No. 185, auxiliary feedwater system minimum flow requirements, was submitted on July 3, 1990.
This amendment was approved as Amendment 138 by the NRC on Nov. 15, 1990.
d)
License Amendment Application No. 189, to resolve single failure susceptibilities of the 4160 volt electrical distribution system and the SLSS, was submitted on September 28, 1990.
e)
License Amendment Application No. 190, to revise the Provisional Operating License to allow a schedular extension for Items 5 and 18 of the Cycle 11 Full Term Operating License (FTOL) Projects, was submitted on November 7, 1990.
f)
License Amendment Application No. 191, to revise the Technical Specification Table 4.1.2 to reflect changes to the Volume Control and Charging System resulting from the addition of MOV-1100E.
For Cycle 12 refueling outage:
Not yet specifically determined.
Under evaluation.
mor.nov/7
REFUELING INFORMATION DOCKET NO:
50-206 UNIT NAME:
SONGS -
1 DATE:
12/17/90 COMPLETED BY:
S. L. Vittum TELEPHONE:
(714) 368-9230 MONTH:
November 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.
For Cycle 11 refueling, none have been identified.
For Cycle 12 refueling, not yet specifically determined. Under evaluation.
- 6. The number of fuel assemblies.
a) In the core.
0 b) In the spent fuel storage pool.
216
- 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