ML20214L560
| ML20214L560 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/30/1986 |
| From: | Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8609100266 | |
| Download: ML20214L560 (12) | |
Text
___ _ ___ - _________--______ _ _____ _ __.___.
NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE July 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS 1.
Unit Name:
San Onofre Nuclear Generating Station, Unit 2 2.
Reporting Period:
June 1986 3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Rating (Gross MWe):
1127 5.
Design Electrical Rating (Net MWe):
1070 6.
Maximum Dependable Capacity (Gross MWe):
1127 7.
Maximum Dependable Capacity (Net MWe):
1070 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):
NA 10.
Reasons For Restrictions, If Any:
NA This Month Yr.-to-Date
-Cumulative 11.
Hours In Reporting Period 720.00 4,343.00 25,152.00 12.
Number Of Hours Reactor Was Critical 567.05 2,273.60 15,154.52 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 393 85 2,094.82 14,7_04.57
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 1,167,88f.45 6,340,623.7_2 47,071,009.85
- 17. Gross Electrical Energy Generated (MWH) 368,301.00 2.095,253.50 15,789,336.00
- 18. Net Electrical Energy Generated (MWH) 334,837.00 1,959,389.55 14,882,894.55
- 19. Unit Service Factor 54.70%
48.23%
58.46%
- 20. Unit Availability Factor 54.70%
48.23%
58.4M
- 21. Unit Capacity Factor (Using MDC Net) 43.46%
42.16%
55.30%
- 22. Unit Capacity Factor (Using DER Net) 43.46%
42.16%
55.30%
- 23. Unit Forced Outage Rate 11.61%
4.81%
5.45%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
NA 25.
If Shut Down 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 7435u/3 8609100266 860630 k/
PDR ADOCK 05000361 R
\\
r o.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-361 UNIT SONGS - 2 0 ATE July 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0.00 17 849.08 2
0.00 18 934.08 3
0.00 19 568.83 4
0.00 20 0.00 5
0.00 21 53.67 6
0.00 22 833.00 7
0.00 23 1072.79 8
0.00 24 1024.17 9
0.00 25 1054.75 10 0.00 26 1064.38 11 0.00 27 1006.42 12 39.17 28 1060.00 13 529.38 29 1071.67 14 688.08 30 1060.67 15 728.38 31 NA 16 813.04 7435u/4
_ _ _ _ ~.
i
. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-361 UNIT NAME SONGS
_2.
REPORT MONTH JUNE 1986 DATE Ju1V 14.
1950 COMPLETED BY E.
R.' Siacor TELEPHONE ( 7141 368-6223 4
Method of Shutting Dura t ion Down LER System Component.
Cause & Corrective 1
2 3
4 4
Action to v
No.
Date Type (Hours)
Reason Reactor No.
Code Code Prevent Recurrence' 5
)
25 860315 S
274.40 C
4 NA NA NA Refueling j
26 860619 F
51.75 A
3 86-015
-EF INVT The reactor tripped when i
120VAC Vital Bus No. 3 was 4
de-energized due to the failure of Inverter 2Y003.
De-energization of Vital Bus No. 3 caused a loss of power to Control Element Assembly 4
Ca lculator (CEAC) No. 2.
CEAC No. 1 had been removed previously for surveillance testing. With both CEACs i
l Inoperable, the Core i
Protection Calculators (CPC) generated a la rge pena l ty factor resulting in the reactor trip.
Cause of the i
inverter failure was due to an internally shorted output waveshaping capacitor. The capacitor was replaced and inverter 2Y003 was returned to service, i
1 1
1 2
3 4
F-Fo rced Reason:
Method:
IEEE Std 803-1983 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.
C-Refueling 3-Automat ic Scram.
1 D-Regulatory Restriction 4-Continuation f rom E-Operator Training & License Examination Previous Month F-Adm i n i s t ra t ive
.5-Reduction of 20%
C-Ope ra t iona l Error ( Expla in) 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 (Expla in) 7435u/5
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-361 UNIT SONGS - 2
'~
DATE July 14, 1986 COMPLETED BY E. R. Siacor l
l TELEPHONE (714) 368-6223 Date Time Event June 1 0001 Unit is in Mode 4, day 78 of Cycle 3 refueling outage.
June 2 1707 Entered Mode 3.
June 5 0844 Entered Mode 2.
0935 Reactor is critical.
1130 Commenced low power physics testing.
June 10 2200 Completed low power physics testing.
Entered Mode 1.
2208 Reactor tripped due to high steam generator level.
June 11 0435 Entered Mode 2.
0500 Reactor is critical.
0809 Entered Mode 1.
June 12 1024 Unit synchronized to the grid, ending Cycle 3 refueling outage.
June 13 1230 Reactor power at 60%.
1321 Commenced power increase to 68% for calorimetric and physics testing.
June 15 1610 Commenced power increase to 80% for heat treatment of intake structure.
2120 Reactor power at 80%.
Commenced heat treating of intake structure.
June 16 1750 Commenced power reduction to 75% power for atmospheric dump valve flow testing and main condenser inlet waterbox cleaning, following completion of heat treating.
7435u/6
SUMMARY
OF CPERATING EXPERIENCE FOR THE MONTH (Continued)
I Date
, Time Event June 18 1055 Commenced power increase to 100% following completion of atmospheric dump valve flow testing and condenser waterbox cleaning.
June 19 0443 Reactor power at 100%.
1355 Reactor tripped due to failure of 120VAC Vital Bus No. 3 power supply inverter 2Y003.
June 21 0545 Entered Mode 2 following return to service of inverter 2Y003.
0625 Reactor is critical.
1350 Entered Mode 1.
1740 Unit synchronized to the grid.
June 23 0150 Reactor power at 100%.
June 24 1645 Commenced power reduction to approximately 83% power for condenser waterbox cleaning.
June 25 0332 Commenced power increase to 100% power.
0553 Reactor power at 100%.
0615 Commenced power reduction to 98% power for completion of reactor physics testing.
June 26 2000 Commenced power reduction for condenser water box cleaning.
2130 Reactor power at 85%.
June 27 1253 Reactor power increased to 100%.
June 28 1020 Reactor power reduced to 85% for condenser water box cleaning.
1717 Reactor power increased to 100%.
June 29 1115 Reactor power reduced to 85% for condenser water box cleaning.
1610 Reactor power increased to 100%.
June 30 1915 Reactor power reduced to 85% for condenser water box cleaning.
2400 Unit is in Mode 1 at 85% reactor power.
Turbine load is 940 MWe gross.
7435u/7
REFUELING INFORMATION DOCKET NO.
50-361 UNIT SONGS - 2 DATE July 14, 1986 MONTH: June 1986 COMPLETED BY E. R. Siacor 1
TELEPHONE (714) 368-6223 1.
Scheduled date for next refueling shutdown.
January 1988 2.
Scheduled date for restart following refueling.
April 1988 l
3.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Not yet determined What will these be?
Not yet determined 4.
Scheduled date for submitting proposed licensing action and supporting information.
Not Applicable 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.
___217 b) In the spent fuel storage pool.
160 7.
Licensed spent fuel storage capacity.
800 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 1997 (refueling only)
Approximately 1993 (full offload capability) 7435u/8 l
NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE July 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS 1.
Unit Name:
San Onofre Nuclear Generating Station, Unit 3 2.
Reporting Period:
June 1986 3.
Licensed Thermal Power (MWt):
3390
~4.
Nameplate Rating (Gross MWe):
1127 5.
Design Electrical Rating (Net MWe):
1080 6.
Maximum Dependable Capacity (Gross MWe):
1127 7.
Maximum Dependable Capacity (Nat MWe):
1080 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):
NA 10.
Reasons For Restrictions, If Any:
NA This Month Yr.-to-Date Cumulative 11.
Hours In Reporting Period 720.00 4,343.00 19,703.00 12.
Number Of Hours Reactor Was Critical 720.00 3,554.59 12,764.68 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.
Hours Generator On-Line 720.0_0 3,245.26 12,060.71 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 2,422,034.69 10,388,317.34 35,533,504.68
- 17. Gross Electrical Energy Generated (MWH) 814,094.50 3,495,788.00 11,867,193.00 18.
Net Electrical Energy Generated (MWH) 774,289.00 3,283,278.00 11,090,623.42 19.
Unit Service Factor 100.00%
74.72%
61.21%
20.
Unit Availability Factor 100.00%
74.72%
61.21%
21.
Unit Capacity Factor (Using MDC Net) 99.57%
70.00%
52.125 22.
Unit Capacity Factor (Using DER Net) 99.57%
70.00%
52.12%
23.
Unit Forced Outage Rate 0.00%
19.22%
15.55%
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Cycle 3 Refueling Outage, December 1986 25.
If Shut Down 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 7435u/9
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-362 UNIT SONGS - 3 DATE July 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH June 1986 s
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1098.04 17 1100.38 2
1096.63 18 1099.88 3
1077.96 19 1098.54 4
1001.21 20 1094.17 5
996.29 21 1099.17 6
984.71 22 1100.13 7
986.46 23 1101.38 8
988.33 24 1103.79 9
987.08 25 _
1107.08 l
10 1009.92 26 1110.75 11 1090.33 27 1104.13 12 1097.58 28 1110.88 13 1093.13 29 1109.29 14 1103.13 30 1106.54 l
15 1103.96 31 NA
[
16 1101.21 I
7435u/10 l
l
{
L
11 UNIT SHUTDOWNS AND POWER REDUCTIONS' DOCKET NO..$0'-362 UNIT NAME SOtiCS
=.3 A' N REPORT MONTH JUNE 1986 DATE JU17 AMe COMPLETED BY E.
R.
Slacor TELEPHONE f7141 368-6223-Method of
. Shutting Du ra t ion Down LER System Component Cause ac Corrective 1
2 3
4 4
Action to No.
-Date Type (Itou rs ) Reason Reactor No.
Code Code Prevent Recurrence NA NA NA NA NA NA NA NA NA NA 1
2 3
4 F-Fo rced Reason:
Method:
IEEE Std 803-1983 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Meintenance or Test 2-Manual Sc ram.
C-Refueling 3-Automatic Scram.
D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Admi n i st ra t ive 5-Reduction of 207, G-Ope ra t i ona l Error (Expla in) or greater in the H-Other ( Expla in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other (Expla in) 7435u/11 e
w
w.
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH
~
DOCKET NO.
50-362 UNIT SONGS - 3 DATE July 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 Date Time Event June 1 0001 Unit is in Mode 1 at 100% reactor power.
Turbine load is 1144 MWe gross.
June 3 1900 Commenced power reduction to 90% reactor power for investigation and repairs to Third Point Heater E041 tube leak.
June 4 1655 Reactor power increased to 100%.
June 5 0411 Commenced power reduction to 97% reactor power due to high differential temperature of the circulating water.
June 11 0300 Reactor power increased to 100%.
June 30 2400 Unit is in Mode 1 at 100% reactor power.
Turbine load is 1152 MWe gross.
7435u/12
(J,. :.
REFUELING INFORMATION DOCKET NO.
50-362 UNIT SONGS - 3 DATE July 14, 1986 MONTH: June 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 1.
Scheduled date for next refueling shutdown.
December 1986 2.
Scheduled date for restart following refueling.
March 1987 3.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No. All required Cycle 3 Amendments have been approved.
What will these be?
Not Applicable 4.
Scheduled date for submitting proposed licensing action and supporting information.
Not Applicable 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.
217 b)
In the spent fuel storage pool.
72 7.
Licensed spent fuel storage capacity.
800 Intended change in spent fuel storage capacity.
None c
l 8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Approximately 1997 (refueling only) l Approximately 1993 (Full offload capability) 7435u/13 I
I
.p
., ~.
k - *? 4 '. /
Southern California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE. CALIFORNIA 92672 H E MORGAN rnENONE July 14, 1986
'7'4'ss=*24'
. r.1,o~ u..ct.,
Director Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Subject:
Docket Nos. 50-361/50-362 Monthly Operating Reports for June 1986 Sa'n Onofre Nuclear Generating Station,~ Units 2 and 3 Enclosed are the Monthly Operating Reports as required by Section 6.9.1.10 of Appendix A, Technical Specifications to Facility Operating Licenses NPF-10 and NPF-15 for San Onofre Nuclear Generating Station, Units 2 and 3, respectively.
Please contact us if we can be of further assistance.
Sincerely, bb 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)
.