ML20137K256
| ML20137K256 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/30/1985 |
| From: | Farrell M SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20137K234 | List: |
| References | |
| NUDOCS 8509120108 | |
| Download: ML20137K256 (11) | |
Text
.
NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT NAME SONGS - 2 DATE 07/15/85 COMPLETED BY M. J. Farrell TELEPHONE [714) 49F7700-Ext. 56907~
OPERATING STATUS 1.
Unit Name: San Onofre Nuclear Generating Station. Unit 2 2.
Reporting Period: June 1985 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 16 392.00 1
- 12. Number Of Hours Reactor Was Critical 720.00 1,67C49 9,3BT71
- 13. Reactor Reserve Shutdown Hours 6
0~
0
- 14. Hours Generator On-Line 7T0.00 1,633.99 8,883.58
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2TfQ41.70 4 951 94.90 29,2 198.20 2
- 17. Gross Electrical Energy Generated (MWH) 803,662 60 1 661 4T 5D~
9,8 75 COD
- 18. Net Electrical Energy Generated (MWH) 770,40EoD li5TD,1875~
9.30
.Q
- 19. Unit Service Factor 100 dD~
37 6f' 5Tl9
- 20. Unit Availability Factor fD57DD-37~6T SCf9
- 21. Unit Capacity Factor (Using MDC Net) 100.00~
33;15~
SE05
- 22. Unit Capacity Factor (Using DER Net) fDE66-3CIS-5~3Td'5
- 23. Unit Forced Outage Rate 6~6'0'
- 6. 8T C61 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, aiid~ Duration of Each):
NA 25.
If Shut Ocwn 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 MI COMMERCIAL OPERATION MA NI 2941u I
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-361 UNIT SONGS - 2 DATE 07/15/85 COMPLETED BY M. J. Farrell TELEPHONE (714L492-7700 Ext. 56907
~
MONTH June 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Not)
(MWe-Net) 1 1050.75 17 1074.38 2
1084.96 18 1063.67 3
1085.21 19 __
_1080.96 4
1079.88 20 1086.04 5
1078.46 21 1084,67 6
1074.21 22 931.17 7
1073.46 23,
1086.79 8
1039.46 24 1092.33 9
1083.71 25 992.54 10 1082.71 26 1037.21 11 1077.38 27 1101.17 12 1066.79 28 1094.83 13 1_075.54 29 1098.29 14 1078.50 30 1100.92 15 1066.33 31 NA 16 1077.79 2941u i
UNIT SHUTDOWNS AND POhTR REDUCTIONS DOCKET NO. M-361 UNIT NAME 50MGS - ?
REPORT MONTH JUNE 1985 DATE D7/15/5)
COMPLETED BY M.
J.
Fa rrel i TELEPHONE 1718) 422-7700 ~
9 Ext. 56901 Method of Shutting Dura t ion Down LER System Component Cause & Corrective 1
2 3
4 4
Action to ho.
Date Type (Hours)
Reason Reactor No.
Code Code Prevent Recurrence NA NA MA MA MA NA NA NA MA NA 1
2 3
4 F-Forced Reason:
Method:
IEEE Std 803-1983 5-Scheduled A-Equipment Emilure (Explain) 1-Manual 8-Maintenance or Test 2-Manual Sc ra m.
C-Refueling 3-Automatic Scram.
D-Regulatory Restriction 4-Continuation f rom E-Operator Training & License Examination Previous Month F-Admi n i s t ra t ive 5-Reduction of 20%
C-Ope ra t iona l Error (Explain) or greater in the H-Other ( E.xplain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-Other (Expla in) 2941u e
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-361 UNIT SONGS - 2 DATE 07/15/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56967 Date Time Event June 1 0001 Unit in Mode 1 at 85% reactor power.
Returning to full power operations following turbine stop and governor valve testing.
June 1 0655 Reactor power at 100%.
June 7 1430 Commenced power reduction due to CEA #31 dropping to bottom of core.
June 7 1455 CEA #31 realigned, returning to 100% reactor power.
June 8 0202 Commenced power reduction to 90% for turbine stop and governor valve testing.
June 8 0525 Decreasing power further to 85% to " bump" circulating water pump 2p-115 to reduce high seawater differential pressure across main condenser.
June 8 1110 Reactor power returned to 100%.
June 12 2024 Reactor power reduced to 90% for testing of CEA #20.
June 12 2300 Reactor power at 100%.
June 15 0055 Commenced power reduction to 90% for turbine stop and governor valve testing.
June 15 0534 Reactor power at 100%.
June 18 2205 Reactor power reduced to 85% to " bump" all four circulating water pump,s to reduce high differential seawater pressure acr6ss main condenser.
June 18 2340 Reactor power at 100%.
2941u r
i
Summary of Operating Experience for the Month (Continued)
Unit 2 Date Time Event June 22 0400 Commenced power reduction to 80% for turbine stop and governor valve testing and heat treating of intake structure.
June 22 2155 Commenced power increase to 100%.
June 23 0140 Reactor power at 100%.
June 25 1215 Reactor power reduced to 85% to repair condenser tube leak.
June 26 0910 Reactor power at 100%.
June 30 2359 Unit in Mode 1 at 100% reactor power.
Full power operations are planned.
2941u
REFUELING INFORMATION DOCKET NO.
50-361 UNIT SONGS - 2 DATE 07/15/85 COMPLETED BY M. J. Farrell
-TELEPHONE (714)_UtTlM19
~~ 492-7700 1.
Scheduled date for next refueling shutdown.
April 1986 2.
Scheduled date for restart following refueling.
July 1986 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.
I 4.
Scheduled date for submitting proposed Itcen>fng action and supporting information.
Not yet determined.
5.
Important Licensing considerations associated with refueling, e.g. new or dif ferent 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.
72 _
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 captcity.
Approximately 1997.
2941u
}
i j
NRC MONTHLY OPERATING REPORT l
f I
DOCKET NO. 50-362 i
j UNIT SONGS - 3
[
{
DATE 01/n/ss j
COMPLETED BY M. c. Farrell j
TELEPHONE DT4DifF7760 i
j Ext. 569D7 i
i OPERATING STATUS i
j 1.
Unit Name: San Onofre Nuclear Generating Station, Unit 3 l
1 2.
Reporting Period: _ June 1985 j
3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Rating (Gross MWe):
If27 h
j 5.
Design Electrical Rating (Net MWe):
10110 i
1 6.
MaximumDependableCapacity(GrossMWe):
1127 l
7.
Maximum Dependable Capacity (Net MWe):
1680 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
{
Since Last Report, Give Reasons:
i NA 9.
Power Level To Which Restricted, If Any (Net MWe):
NA 10.
Reasons For Restrictions, If Any:
NA l
t This Month Yr.-to-Date Cumulative i
- 11. Hours In Reporting Period 720.00 4,343.00 10 943.00 1
l
- 12. Number Of Hours Reactor Was Critical Mo DD 2,96 Q 4 7,30070]
13.
Reactor Reserve Shutdown Hours 0
0 0
[
14 Hours Generator On-Line 7FC60 2.883.58 6.99573
- 15. Unit Reserve Shutdown Hours D-0~
~~6~
{
i'
- 16. Gross Thermal Energy Generated (MWH)
TJTBG2E5D-666.75F116421255.14 i
j 17.
Gross Electrical Energy Generated (MWH) 36d91E00 2i 6Dl 836 SD 'f.
20TTid ~7.362f03830 l
D 18.
Net Electrical Energy Generated (MWH)
,513T00 6,834,7>0 E00 j
- 19. Unit Service Factor f0E0D -~-
66 !f3 6E93 l
- 20. Unit Availability Factor 166~00 6E53 6E93
- 21. Unit Capacity Factor (Using MOC Net) 72 78
!i875 500d
- 22. Unit Capacity Factor (Using DER Net) 727 8 -
5~875 SC0D L
- 23. Unit Forced Outage Rate 0
JE69
[Ef6 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration ofTach):
j Refueling, September, 1985, 110 days duration.
i 1
l 25.
If Shut Down At End Of Report Period Estimated Date of Startup:
NA j
- 26. Units In Test Status (Prior To Commercial Operation):
Forecast Achieved i
INITIAL CRITICALITY NA NA i
INITIAL ELECTRICITY NA N'A j
COMMERCIAL OPERATION NA-NA~
4 I
)
l 2941u
~
i
)
)
r AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-362 UNIT SONGS - 3 OATE 07/t5/85 COMPLETED BY M. J. Farr_ ell TELEPHONE (714)~492-7700 Gt~S6901 MONTH June _1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (P4e-Net)
(Kde-Net) 1 1065.83 17 __
_607.25 2
1065.54 18 606.88 3
1062.21 19 596.58 4
1042.54 20 582.88 5
_1041.21 21 583.04 6
1038.21 22 578.92 7
1030._0.4 23 575.54 8
1030.83 24 538.3_9_
9 1036.38 25
_50fdl 10 1_052.54 26 499.96 11 l_034.33 27 __
49_8.25_
12 1047.08 28 497.17 13 1059.54 29
,4 91 A4,. __
14 10_40.21 30 __
4 89. 50.__ _
15 681.59 31 NA 16 600.04 2941u
I U4li SHUTDokiss AseO POWER REDUCTICats DOCKET 800. K -362 UNIT DiAME SO4GS - 3 REPORT MONTH JuhE 1985 OATE QZfj M 55 COMPLETED BY M _J.
f a rgel l 2
TELEPHOhE 17Wl 8 22-1100 tEst. % 907 Method of Shutting Duration Down LER System Component Cause & Corrective 1
2 3
4 4
Action to 20.
Date Type (Mours)
Reason Reactor 2o.
Code Code Prevent Recurrence 15 850615 5
0 F
5 mA u
4A Fwer reduction to 60% to prolong unit's initial core and defer commencement of Cycle 1 refueling outage until Sep tembe r, 1985, i
l l
l l
1 2
3 4
F-forced season:
Method:
(
5-Scheduled A-Eguspoent Failure (Explain) 1-m tma l i
a-sem entenance or Test 2-meme s scran.
C-Reruesing 3-Automatic Scraa.
l D-Regulatory Restriction 4-Ccatir.uation f ros l
E-Cperator Tra sning k License Examination Previous stanth F-Aasini st ra t ive 5-Reduction of 20%
l C-Ope ra t iona l Error (Explain) or greater in the l
H-Othe r ( Expla in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> j
9-other (Explain) 2941u l
l l
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-362 UNIT SONGS - 3 DATE 07/15/85 COMPLETED _BY M. J. Farrell TELEPHONE (714)~492-7700 EstT53967 Date Time Event June 1 0001 Unit in Mode 1 at 100% reactor power.
Turbine load is 1106 MWe, June 7 2100 Commenced power reduction to 90% for turbine stop and governor valve testing.
June 8 0300 Reactor power at 100%.
June 11 2000 Commenced power reduction to 85% to " bump" all four circulating water pumps to reduce high dif ferential seawater pressure across main condenser.
June 12 0305 Reactor power returned to 100%.
June 14 2000 Commenced power reduction to 60% to prolong unit's initial core and defer commencement of Cycle 1 refueling outage untti September 1985.
June 15 1640 Reactor power at 60%.
June 24 0905 Reactor power reduced further to 55%.
June 30 2359 Unit in Mode 1 at 55% reactor power. Unit will remain at reduced reactor power until commencement of refueling outage.
2941u
r REFUELING INFORMATION DOCKET NO.
50-362_
UNIT SONGS - 3 DATE 07/15/85 COMPLETED BY M. J. Farrell TELEPHONE
[~714)~492-7700
.GtTEM. M.
1.
Scheduled date for next refueling shutdown.
September 1985 2.
Scheduled date for restart following refueling.
January 1986 3.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes What will these be?
Not yet determined.
4.
Scheduled date for submitting proposed licensing action and supporting information.
Proposed Technical Specification change regarding required boric acid volume and concentration (PCN Number 163) was submitted March 9, 1935.
5.
Important Licensing considerations associated with refueling, e.g. new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Ncne.
Reload analysis is the same as Unit 2.
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.
NA 2941u
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