ML20087G555
| ML20087G555 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/29/1984 |
| From: | Morris C SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20087G540 | List: |
| References | |
| NUDOCS 8403200057 | |
| Download: ML20087G555 (10) | |
Text
NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT SONGS - 2 DATE March 15, 1984 1
COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 5626'4 OPERATING STATUS 1.
Unit Name:
San Onofre Nuclear Generating Station, Unit 2 2.
Reporting Period:
1 February 1984 through 29 February 1984 3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Rating (Gross MWe):
1127 5.
Design Electrical Rati :g (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 696 1,440 4,945
- 12. Number Of Hours Reactor Was Critical 363.7 662.3 3,275.0 13.
Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On-Line 330.5 610.4 3,172.1 15.
Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1,031,289 1,910,666 10,404,201
- 17. Gross Electrical Ener.jy Generated (MWH) 348,887 651,467 3,563,432___
18.
Net Electrical Energy Generated (MWH) 323,201 605,431 3,381,076 19.
Unit Service Factor 47.5 42.4 64.2 20.
Unit Availability Factor 47.5 42.4 64.2
- 21. Unit Capacity Factor (Using MDC Net) 43.4 39.3 63.9 22.
Unit Capacity Factor (Using DER Net) 43.4 39.3 63.9
- 23. Unit Forced Outage Rate 0
2.2 4.0 24.
Shutdowns Scheduled Over Next 6 Months (Type, Dat E and Duration of Elch):
NA 25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
NA 26.
Units In Test Status (Prior Tc Commercial Operation):
Forecast Achieved NITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 8403200057 840315 PDR ADOCK 05000361-R PDR
I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-361 UNIT SONGS - 2 DATE March 15.1984 COM 'LETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL-DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 682.29 2
0 18 869.65 3
0 19 1066.48 4
0 20 1103.60 5
0 21 1108.92 6
0 22 1089.17 7
0 23 1101.07 8
0 24 1144.31 9
0 25 1105.10 10 0
26 1120.27 11 0
27 1116.15 12 0
28 1119.17 13 0
29 1115.83 1
14 0
30 NA 15 0
31 NA 16 99.23 0565u l
UNIT SHUTDOWNS AND POWER REQUCTIONS DOCKET No. 50-361 t;NlT NAME SONG {73
-2 DATE M8VCn
_ _..I 30'+
REPORT MONTH FEBRUARY, 1984 COMPLETED BY C. A.
Morrl s TELEPHONE f7141 492-?700 Ext. 56264 Method of Shutting Du ra t ion Down LER System Component Cause & Correctivo 1
2 3
4 4
Action to No.
Date Type (Hours)
Reason Reactor No.
Code Code Prevent Recurrence 2
840113 S
332.3 B
4 NA AB P
Unit was shut down afor reactor coolant pump seal s.tp l a cemen t.
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-Au toma t ic Sc ram.
D-Regulatory Restriction 4-Continuation from E-0;erator Training & License Examination
.Provious Month F-Admin i st ra t ive 5-Reduction of 20%
G-Ope ra t iona l Error (Explain) 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 /> 0565u 9-Other ( Explain) t
\\;
L l
l 1 -
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-361 UNIT SONGS - 2 DATE March 15.1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 Date/ Time Event February 1, 0001 The unit is in Mode 5 at 105 F.
The Reactor Coolant System is depressurized and drained to midloop and a reactor coolant pump seal outage is in progress.
February 10, 0742 Unit entered Mode 4.
February 11, 2215 Unit inadvertently entered Mode 3.
Event was reported to the NRC in Licensee Event Report 83-008, Docket No. 50-361.
February 11, 2217 Returned to Mode 4.
February 12, 0630 Entered Mode 3.
February 14, 1938 Entered Mode 2.
February 14, 2020 Reactor critical.
February 16, 0145 Entered Mode 1.
February 16, 0530 Synchronized generator and applied block load.
February 19, 0510 Reached 100% reactor power; turbine load is 1140 MWe gross.
February 25, 1955 Reduced turbine load to 1050 MWe gross in preparation for turbine stop and governor valve testing.
February 25, 2215 Raised turbipe load to 1170 MWe gross following satisfactory completion of turbine stop and governor valve testing.
I February 29, 2359 Unit is in Mode 1 at 100% reactor puwer; turbine load is 1166 MWe gross.
Full power operation is planned.
i i
+-.,-..
REFUELING INFORMATION DOCKET NO.
50-361 UNIT SONGS - 2 DATE fiarch 15, 1984.
COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 1.
Scheduled date for next refueling shutdown.
September 1984 2.
Scheduled date for restart following refueling.
December 1984 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 will be submitted to the NRC for Shutdown Cooling System Modifications (Proposed Change Number (PCN) 126), for the reload analysis (PCN 147-153), for inclusion of heated junction thermocouples (PCN 128), and for Steam Generator tube wall thinning criteria (PCN 141).
4.
Scheduled date for submitting proposed licensing action and supporting 1
l information.
Not yet determined.
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.
Not yet determined.
6.
The number of fuel assemblies.
a)
In the core.
217 b)
In the spent fuel storage pool.
0 7.
Licensed spent fuel storage capacity.
800 Intended change in spent fuel storage capacity.
NA 8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Approximately 1997.
0565u
l NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT SONGS - 3 DATE 3/15/84 COMPLETED BY C. A. Morris TELEPHONE (714) 49?-7700 Ext. 56264 OPERATING STATUS 1.
Unit Name: San Onofre Nuclear Generating Station, Unit 3 2.
Reporting Period:
1 February 1984 through 29 February 1984 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) 4 Since Last Report, Give Reasons:
NA 9.
Power Level To Wnich Restricted, if Any (Not MWe):
NA 10.
Reasons For Restrictions, If Any:
NA This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 696 1440 3774
- 12. Number Of Hours Reactor Was Critical 0
142.8 2222.0 13.
Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 0
123.0 1766.7
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 415,741 3,964,610
- 17. Gross Electrical Energy Generated (MWH) 0 140,226 - 1,238,514
- 18. Net Electrical Energy Generated (MWH)
-5,210 121,446 1,118,504
- 19. Unit Service Factor NA NA NA
- 20. Unit Availability Factor NA NA NA
- 21. Unit Capacity Factor (Using MDC Net)
NA NA NA
- 22. Unit Capacity Factor (Using DER Net)
NA NA NA
- 23. Unit Forced Outage Rate NA NA NA 24.
Shutdowns Scheduled Over Next 6 Months (Type, Cate, and Duration of Each):
NA i
25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
3/8/84
- 26. Units In Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 8/29/83 INITIAL ELECTRICITY 9/25/83 COMMERCIAL OPERATION Under Review i
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-362 UNIT SONGS - 3 DATE Parch 15,1484 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28-0 f
13 0
29 0
14 0
30 NA 15 0
31 NA 16 0
0565u 4
._m.
O UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. SA-36_2
-UNIT NAME SONGS - 3 REPORT MONTH FEBRUARY, 1984 DAT E T71 M / A.1 COMPLETED BY Gj A." fio r r i s TELEPHONE f714) 492-7700 Ext. 56264 Method of Shutting Du ra t ion Down LER System Component Cause & Corrective 1
2 3
4 4
Action to No.
Date Type.
( Hou rs )
Reason Reactor No.
Code Code Prevent Recurrence
-1 840106 S
696 B
4 NA NA NA Unit is shutdown for a surveillance and reactor coolant pump seal outage.
1 2
1' 2
3 4
F-Fo rced
. Reason:
Method:
IEEE Std 803-1983 S-Schedu led A-Equ i pment Fa i l u re ( Exp la i n )
1-Manual B-Ma intenance or Test 2-Manual Sc ra m.
-C-Refueling 3-Automatic Scram.
D-Regulatory Restriction-4-Continuation from i
E-Operator Training.& License Examination Previous Month F-Adm i n i st ra t ive 5-Reduction of 20%
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 />
'0565u 9-Other (Explain) 4 4
i 4
4 m- - -
m
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-362 UNIT SONGS - 3 j.
DATE March 15,1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 Date/ Time Event 4.
February 1, 0001 Unit is in Mode 5 at 127 F.
The Reactor Coolant System is depressurized and drained to midloop. A i
surveillance and reactor coolant pump seal outage is in progress.
February 27, 0520 Entered Mode 4.
February 29, 0029 Returned to Mode 5 for repair of 3HV-9327 due to valve binding problems.
February 29, 2359 Unit is in Mode 5, at 183 F, and continuing in the surveillance-outage.
f 4
1 I,
i 0565u 1
l 1
l
i REFUELING INFORMATION DOCKET NO.
50-362 UNIT SONGS - 3 DATE lbrch 15.1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264
>1.
Scheduled date for next refueling shutdown.
Not yet determined.
2.
Scheduled date for restart following refueling.
Not yet determined.
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 4.
Scheduled date for submitting proposed licensing action and supporting information.
i Not yet determined.
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.
2 Not yet determined.
6.
The number of fuel assemblies, i
a) In the core.
217 b) In the spent fuel storage pool.
O 7.
Licensed spent fuel storage capacity.
800 Intended change in spent fuel storage capacity.
NA 8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
NA 0565u n
--..n..
-,