ML20138R718
| ML20138R718 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 08/31/1985 |
| From: | Maisel R SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20138R711 | List: |
| References | |
| NUDOCS 8511180799 | |
| Download: ML20138R718 (11) | |
Text
!
1 NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE September 16, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 86657 OPERATING STATUS 1.
Unit Name: San Onofre Nuclear Generating Station, Unit 2 2.
Reporting Period:
August 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 Nurrber 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 744.00 5,831.00 17,880.00
- 12. Number Of Hours Reactor Was Critical 701.20 3,115.69 10,760.91 13.
Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 687.67 3,065.06 10,558.13
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2,284,374.50 9,728,039.50 34,000,742.80
- 17. Gross Electrical Energy Generated (MWH) 751,359.50 3,246,059.50 11,456,368.00 18.
Net Electrical Energy Generated (MWH) 714,167.00 3,047,879.00 10,812,827.00
- 19. Unit Service Factor 92.43%
52.56%
59.05%
- 20. Unit A.ailability Factor 92.43%
52.56%
59.05%
21.
Unit C&pacity Factor (Using MDC Net) 69.71%
48.85%
56.52%
- 22. Unit Capacity Factor (Using DER Net) 89.71%
48.85%
56.52%
- 23. Unit Forced Outage Rate 7.57%
5.42%
4.39%
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
N/A 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 s
6814u 8511180799 850916 PDR ADOCK 05000361 R
I AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO.
50-361 UNIT SONGS - 2 i
DATE September 16, 1985 j
COMPLETED BY R. J. Maisel l
TELEPHONE (714) 492-7700 Ext. 86657 i
MONTH August 1985 i
i j
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
(MWe-Net)
(MWe-Net) i 1
685.25 17 1059.79 2
0.00 18 1075.92 1
l 3
719.25 19 1087.42 i
4 1086.96 20 620.04 l
5 1040.58 21 173.50 6
1007.25 22 1058.63 7
1003.50 23 1080.79 i
j 8
993.38 24 1084.63 9
1006.13 25 1087.92 I
10 1024.21 26 1088.92 i
11 1021.42 27 1088.58 12 1061.67 28 1091.29 13 1080.00 29 1091.75 14 1062.08 30 1074.71 i
15 1085.96 31 1089.13 16 1071.71 3
i j
6814u t
~.,
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. $Q-361 UNIT NAME SONGS - 2 REPORT MONTH AUGUST 1985 DATE September 16. 1985 COMPLETED BY R. J _ Maisel TELEPHONE (114) 82 M LOO 1Ext. 866S7 Method of Shutting Du ra t ion Down LER System Component Cause & Corrective 1
2 3
4 4
Action to No.
Date Type (Hours)
Reason Reactor No.
Code Code Prevent Recurrence l
16 850801 F
32.68 A
3 2-85-041 EE INVT A voltage transient of unknown origin occurred on Phase
'A' of the non-lE uninterruptable power supply which de-energized two Control Element Drive Mechanism (CEDM) auxilia ry relays associated with the turbine trip logic, which tripped the turbine and the reactor. As corrective action, a design change has been implemented which re-a rranged the auxi l ia ry relays, so that a single phase voltage transient will not cause a turbine trip.
17 850820 F
23.65 G
3 2-85-018 JC CPU Reactor and turbine trip due to spurious penalty factor generated by Control Element Assembly Calculator (CEAC) i number 1 during surveillance testing. As corrective action.
to prevent recurrence changes will be made in the surveillance p rocedu re, j
1 2
3 4
F-Fo rced Reason:
Method:
IEEE Std 803-1983 S-Scheduled A-Equipment fa i lure ( Expla in) 1-Manual B-Ha intenance or Test 2-Manual Sc ra m.
C-Refueling 3-Automat ic Scram.
D-Regulatory Restriction 4-Cont inua tion f rom i
E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20%
G-Ope ra t iona l Error (Explain) or greater in the 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 /> 6-Other ( Expla in) l 6814u t
b
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-361 UNIT SONGS - 2 DATE September 16, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 86657 Date Time Event August 1 0001 Unit in Mode 1 at 100% reactor power.
Full power operations are planned.
August 1 1532 Turbine / reactor trip occurred due to a transient low voltage condition on a single phase of Non-1E uninterruptable power supply bus.
August 2 1355 Entered Mode 2.
August 2 1410 Reactor critical.
August 2 2023 Entered Mode 1.
August 3 0013 Unit synchronized to grid.
August 4 0001 Unit returned to 100% reactor power.
August 8 1955 Initiated power reduction to PS% to bump main saltwater circulating pumps to lower differential pressure across condenser water boxes.
August 9 0430 Unit returned to 100% reactor power.
August 14 1905 Initiated power reduction to 85% to bump main saltwater circulating pumps.
August 15 0115 Unit returned to 100% reactor power.
August 17 1115 Initiated power reduction to 95% for corrective maintenance on high pressure turbine governor valve 2VV22008.
August 18 0540 Unit returned to 100% reactor power.
August 20 1405 Reactor and turbine trips occurred due to spurious penalty factors generated while performing CEAC No. 1 31-day surveillance and associated troubleshooting activities.
6814u
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH (Continued)
DOCKET NO.
50-361 UNIT SONGS - 2 DATE September 16, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 86657 Date Time Event August 21 0958 Entered Mode 2.
August 21 1015 Reactor critical.
August 21 1136 Entered Mode 1.
August 21 1344 Unit synchronized to grid.
August 22 0640 Unit returned tc 100% reactor power.
August 31 2359 Unit in Mode 1 at 100% reactor power.
Full power operations are planned.
6814u
REFUELING INFORMATION DOCKET NO.
50-361 UNIT SONGS - 2 DATE September 16, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 86657 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 thereaf ter 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.
1 Not yet determined.
5.
Important Licensing considerations associated with eefueling, 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.
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 capacity.
Approximately 1997.
6814u
-~ - - - - _ - - -.... - - -
NRC MONTHLY OPERATING REPORT I
DOCKET NO. 50-362 UNIT NAME !f0NGS - 3 DATE September 16, 1985 i
COMPLETED BY R. J. Maisel j
TELEPHONE (714) 492-7700 Ext. 86657_
i OPERATING STATUS i
1.
Unit Name: San Onofre Nuclear Generating Station, Unit 3 l
2.
Reporting Period:
August 1985 j
3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Rating (Gross MWe):
1127 i
5.
Design Electrical Rating (Net Rde):
1080 j
6.
Maximum Dependable Capacity (Gross Kde):
1127 i
7.
Maximum Dependable Capacity (Net MWe):
1080 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7) j j
Since Last Report, Give Reasons:
NA i
4' I
9.
power Level To Which Restricted, If Any (Net MWe):
NA l
10.
Reasons For Restrictions, If Any:
NA i
3 This Month Yr.-to-Date Cumulative j
- 11. Hours In Reporting Period 744.00 5,831.00 12,431.00 s 12.
Number Of Hours Reactor Was Critical 13.
Reactor Reserve Shutdown Hours 744.00 4,457.84 8,878T 0
0 0
,l 14.
Hours Generator On-Line 744.00 4,377.50 8,483.45 t
15.
Unit Reserve Shutdown Hours 0
0 0
i j
- 16. Gross Thermal Energy Generated (MWH) 1,379,092.40 11 376 091.80 24,437,6804 1
1
- 17. Gross Electrical Energy Generated (KAH) 420,218.50_ __3,784,835.50 8 151,6 D.00 1
18.
Net Electrical Energy Generated (KdH) 382,636.00 __3,529,488.00 7,629,818.0D f
l 19.
Unit Service Factor 100.00%
75.07%
68.24%
- 20. Unit Availability Factor 100.00*.~
75.07%
68.24%
- 21. Unit Capacity Factor (Using MDC Net) 47.62*.
56.055 56.83i j
- 22. Unit Capacity Factor (Using DER Net) 4 7. 62*.' _
56.05%
!I67 83%
[
23.
Unit Forced Outage Rate 0*.
23.78%
1479%
[
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, September 1985, 95 M ys duration i
I l
25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
NA l
26.
Units In Test Status (Prior To Commercial Operation):
Forecast Achieved i
INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA ~
COMMERCIAL OPERATION NA NA I
l 6814u l
w
m i
AVERAGE DAILY UNIT POWER LEVEL i
I I
DOCKET NO.
50-362 UNIT SONGS - 3 DATE September 16, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 86657 MONTH August 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
{
(MWe-Net)
(MWe-Net) 1 513.17 17 517.17 2
591.38 18 518.71 1
3 514.58 19 515.42 4
514.63 20 512.42 5
518.58 21 509.75 6
522.42 22 513.29 7
513.71 23 513.83 8
520.29 24 525.08 9
516.33 25 511.96 10 512.92 26 510.17 l
11 508.46 27 508.79 12 508.67 28 511.54 J
13 514.42 29 514.00 14 518.92 30 513.04 15 518.83 31 506.50 16
'517.54 i
l 6814u k
i
5 8
9 7
1 5
06 06 6l18 1
e7 s
3 ri2 t
e a9 x
- bM4E 2
m e e 6S e
.)
1C tJ4 iv cn N p 1
t e
0O e
.7 c r 1SSR(
eor rtu 3
.EEYE r c 8
OMTBN one 9
NAA O CoR 1
NDDH i
T EP
&tt 3
KI EL eAe 8
D M
a r t
O C P S
C E
E E
I 4
tn m
e e4
.o
%h n e mr 0t
)
o d afh2 n
p o
.r t
nsi m C mcnnfir a o
aSooo ul C
r iM rop cct nehx S
Siasot E
N tuuia4(
O m4 ll anote2 I
e e
- aamiicr r
T t
d duuotvugte C
s o onntned sh U 5 y C haauorer at D
8 S
e E
9 l
tMMACPRopO e-R 1
b M1234 5
6 a
R T
c E
S i
3 W
U O C R
l P
U E
o.
p p
n A
L N
A o
D i
N H
t t
A T
o a
N N
n S O f
N M
og 3 i
m W
n r
a O T din o
x D R otw t
E T
O hto c
t P
tuD a u
)
e
)
i E eh e
n s n S R MS R
i n i a
e T
l c
la I
2 p
ni p
N n
x oL x U
o E
it&
E s
(t
(
a s c e
oe ig r
R rT rn o u
ti r) l r snern o
eivEi i
n
)
a Rai a
o s fe rtll i r c
yT a a p t
u tngr rnx a o nanortoE r H enitosi(
u
(
mel atit D
- ptel anar ninuurire o uif ge m eh s q a e e pd p t 1
aEMRROAOO e
e-p RABCDEFGH y
T 2
d e
e t
l a
du D
ed ce rh oc fS u
FS 4
o 1
N 1
8 6
4
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-362 UNIT SONGS - 3 DATE September 16, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 86657 Date Time Event August 1 0001 Unit in Mode 1 at 55*. reactor power.
August 31 2359 Unit in Mode I at 55% reactor power. Commencement of refueling outage planned for September 20, 1985.
6814u
REFUELING INFORMATION DOCKET NO.
50-362 UNIT SONGS - 3 DATE September 16, 1985_
COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 86657 1.
Scheduled date for next refueling shutdown.
September 1985 2.
Scheduled date for restart following refueling.
December 1985 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 change regarding required boric acid volume and concentration (PCN 163) 4.
Scheduled date for submitting proposed licensing action and supporting information.
Proposed Technical Specification change regarding required boric acid volume and concentration (PCN 163) was submitted March 9, 1985.
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. 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.
N/A 6814u 1
}
L_