ML20082J071
| ML20082J071 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/31/1995 |
| From: | Kaplan R SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20082J068 | List: |
| References | |
| NUDOCS 9504180088 | |
| Download: ML20082J071 (12) | |
Text
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NRC MONTHLY OPERATING REPORT 2
SAN ONOFRE-NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO:- 50-361 UNIT NAME:
SONGS - 2 DATE: April 12. -1995 COMPLETED BY:
R. L. Kapl an
-TELEPHONE:
(714) 368-6834 OPERATING STATUS 1.
Unit Name: ' San Onofre Nuclear Generatina'St'ation. Unit 2 2.
Reporting Period:
Marc q 1995 3.
Licensed Thermal Power (MWt):
E90 4.
Nameplate Rating (Gross MWe):
..:.27 5.
Design Electrical Rating (Net MWe):
- .070 6.
Maximum Dependable Capacity (Gross MWe):
- .127 7.
Maximum Dependable Capacity (Net We):
- .070 l
8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
]
Since Last Report Give Reasons:.
%A 9.
Power' Level To Whlch Restricted, If Any (Net MWe):
%A
+
- 10. Reasons For Restrictions, If Any:
NA
'This Month Yr.-to-Date Cumulative' j
11.
Hours In Reporting Period.
744.00 2160.00 101.857.00
' 12.
Number Of Hours Reactor Was Critical 0.00 98d..!;5 77.758.94-13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.
Hours Generator On-Line -
0.00 98d.02 76.615.66 15.
Unit Reserve Shutdown Hours 0.00 0 00 0.00 16.
Gross Thermal Energy Generated (MWH) 0.00 B.09:. 91:
10 250.469.767.6d.
17.
Gross Electrical Energy Generated (MWH) 0.00 07:.360.00 8d.922. 359.50 18.
Net Electrical Energy Generated (MWH)
(3.440.57) 01D.562.0d.
80.577.G56.9:.
19.
Unit Service Factor.
0.00%
d 5.hT%
75.22%
20.
Unit Availability Factor 0.00%
d,5. '! 7%
-75.22%
21.
Unit Capacity Factor (Using MDC Net) 0.00%
di
! 5%
73.92.%
22.
Unit Capacity Factor (Using DER Net) 0.00%
4!
! 5% -
73.9!,%
23.
Unit Forced Outage Rate 0.00%
- 0. 0.QM 5.40%
i 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shutdown At End Of Report Period, Estimated Date of Startup: April 27. 1995 26.
Units In Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY
%A' NA l
INITIAL ELECTRICITY
%A NA COMERCIAL' OPERATION N.A NA 1
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9504180008 950412
~
PDR ADOCK 05000361 R
f i
AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE:- Aoril 12.1995 COMPLETED BY:
R. L. Kaolan TELEPHONE:
(714) 368-6834 i
MONTH:
March 1995
. DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0.00 16 0.00 2
0.00 17 0.00 3
0.00 18 0.00 4
0.00 19 0.00 5
0.00 20 0.00 6
0.00 21 0.00 7
0.00 22 0.00 8
0.00 23 0.00 9
0.00 24 0.00 10 0.00 25 0.00 11 0.00 26 0.00 12 0.00 27 0.00 13 0.00 28 0.00 14 0.00 29 0.00
(
15 0.00 30 0.00 31 0.00 l
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L UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 10-361 UNIT NAME: _ SONGS - 2 REPORT MONTH:
March 1995 DATE: April 12.1995 COMPLETED BY:
R. L. Kaplan TELEPHONE: (714) 368-6834 Method of Shutting Cause & Corrective Duration Down LER System Component Action to 5
No.
Date Type (Hours)
Reason
- Reactor' No.
Code' Code Prevent Recurrence l
4 88 950210 5
744 C
1 N/A N/A N/A N/A Note:
Refueling shutdown continued from previous month.
2F-Forced Reason:
' Method:
S-Scheduled A-Equipment Failure (Explain) 1-Manval B-Maintenance or Test 2-Mer al Scram.
'IEEE Std 803A-1983 C-Refueling 3-At >matic Scram.
D-Regulatory Restriction 4-Coutinuation from F-Operator Training & License Examination Previous Month F-Administrative 5-Reduction in the Average G-Operational Error (Explain)
Daily Power. Level of more H-Other (Explain) than 20% from the previous day 6-Other (Explain) i 3
9 SUPMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:
50-361 UNIT NAME: SONGS - 2 DATE: April 12.1995 COMPLETED BY:
R. L. Kaplan i
TELEPHONE:
(714) 368-6834 j
Dale Ilme Event March 01 0001 Unit is in Mode 6, shutdown cooling in service with RCS at 87 degrees, refueling cavity at 23'8", full core off load in progress.
1900 Core off-load complete, Unit entered defueled mode.
March 10 1327 Unit entered Mode 6, commenced core re-load.
March 15 0504 Completed reactor vessel fuel loading.
March 20 1955 Unit entered Mode 5, Reactor Vessel Head fully tensioned.
March 24 1830 Completed RCS fill and pressurization of RCS to 350 psia to support reactor coolant pump runs.
March 26 0545 Completed drain of pressurizer-to 38% level.
March 31 2400 Mode 5, RCS Tcold 105 degrees, pressurizer level 54.2%.
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REFUELING INFORMATION DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE:'
April 12.1995 -
COMPLETED BY:
R. L. Kaolan TELEPHONE:
(714) 368-6834 MONTH:
March 1995
- 1. Scheduled date for next refueling shutdown.
Cycle 8 refueling outage began February 11, 1995.
- 2. Scheduled date for restart following refueling.
-Restart from Cycle 8 refueling outage iseforecast 'for' April 27, 1995.
- 3. Will refueling or. resumption of operation thereafter require a Technicar l
Specification change or other license amendment?
f Yes-Wh'at will'these be?
A.
A proposed change to the Technical Specifications has been requested to revise the allowed Linear Heat Transfer Rate from 13.9 to 13.0 kw/ft.
A proposed change to the Technical' Specifications,been revised torevising the automatic
)
B.
reset.of the low pressurizer pressure bypass, has simplify' the request.-
-]
- 4. Scheduled date for submitting proposed' licensing action and supporting information.
A.
Linear Heat Rate Submitted September 16, 1994 B.
Low Pressurizer Pressure Bypass Revision, submitted September 6, 1994 l
S. 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.
I None.
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a REFUELING INFORMATION DOCKET NO:
_10_-361 UNIT NAME: _ SONGS - 2 DATE:
April 12.1995 COMPLETED BY: ER. L. Kaplan_
TELEPHONE:
(7141 368-6834
- 6. The number of fuel assemblies.
217 _
A.
In the core.
ZIO Total Fuel Ass _embliest 2 Soent Fuel As In the spent fuel storage pool.
1Q0 IJn-t 2 New Fuel Assemblies _
i B.
0 Jn-
[70 Jn'it 1 Soent Fuel Assemblies _
_ Zero Unit 2 New Fuel Assemblies In the New Fuel Storage Racks C.
- 7. Licensed spent fuel storage capacity.__1542 _
_None Intended change in spent fuel storage capacity.
l storage
- 8. Proj ected date of last refueling that can be discharged to spent fue pooi assuming present capacity.
Approximately 2005 (full off-load capability) 6
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- ~ ~ - - -.
J NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 DOCKET NO:
50-362
-UNIT NAME:
SONGS - 3 DATE: April 12.1995 COMPLETED BY:
R. L. Kaolan i
TELEPHONE:
(714) 368-6834 OPERATING STATUS 1.
Unit Name:
San Onofre Nuclear Generatina Station. Unit 3 2.
Reporting Period:
March 1995 3.
Licensed Thermal Power (MWt):
BB90
)
4.
Nameplate Rating (Gross MWe):
..:.27 5.
Design Electrical Rating (Net MWe):
- .080 l
l 6.
Maximum Dependable Capacity (Gross MWe):
- .127 l
7.
Maximum Dependable Capacity (Net MWe):
- .080 l
8.
If Changes Occur In Capacity Ratings (Items Number 3.Through 7) l Since Last Report Give Reasons:
%A i
9.
Power Level To Whlch Restricted, If Any (Net MWe):
%A l
10.
Reasons For Restrictions, If Any:
INA This Month
.Yr.-to-Date Cumulative 11.
Hours In Reporting Period 744.00 2.160.0Q
-96.408.00 l
12.
Number Of Hours Reactor Was Critical 744.00 2.160.00 76.846.45 l
13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 l
14.
Hours Generator On-Line 744.00 2.160.00 75.20B.49 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal Energy Generated (MWH) 2.440.821.97 6,997.022.97 242.145.060.97 t
l 17.
Gross Electrical Energy Generated (MWH) 823.B84. 50 - 2.394.450. 5Q 82.227.127.09 18.
Net Electrical Energy Generated (MWH) 779.:.58.00 2.268.062.00 77.708.972.94 19.
Unit Service Factor
- .00.00%
- L00.00%
7_fiQ1%
20.
Unit Availability Factor
- .00. 0D%
- t00.00%
70.01%'
l 21.
Unit Capacity Factor (Using MDC Net) 96.9Z%
97.22%
74.63%
1 22.
Unit Capacity Factor (Using DER Net) 96.97%
97.22%
74.63%
23.
Unit Forced Outage Rate 0.00%
0.00%
5.94%
I 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)
Refuelina Shutdown. Julv 8. 1995, Duration (71 days) 25.
If Shutdown 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 sA sA COMERCIAL OPERATION
%A NA i
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 i
DATE: April 12.1995 COMPLETED BY:
R. L. Kaolan i
1 TELEPHONE:
(714) 368-6834 MONTH:
March 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1053.75 16 1048.92 2
1054.92 17.
1034.38 3
1049.75 18 1034.79 I
1 4
1023.17 19 977.58 i
j 5
1054.17 20 1035.50 t-l 6
1054.25 21 1036.96 7
1052.67 22-1054.83 8
1053.71 23 1052.50 9
1052.83 24 1052.46 10 1050.96 25 1054.63 j
11 1050.54 26 1054.33 I
12 1052.38 27 1055.08 1
13 1051.67 28 1054.13 14 1051.83 29 1054.00 15 1051.50 30 1052.96 i
31 1053.79-l I
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UNIT SHUTDOWNS APS POWER REDUCTIONS DOCKET NO:
50-362 UNIT NAME: SONGS - 3 REPORT MONTH:
March 1995 DATE: April 12.1995 COMPLETED BY:
R. L. Kapl an TELEPHONE:
(714) 368-6834 Method of Shutting Cause & Corrective-Duration Down LER System Component Action to 1
2 5
No.
Date Type (Hours) Reason Reactor' No.
Code' Code Prevent Recurrence Th:re were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% this reporting period.
F-Forced rReason:
' Method:
- IEEE Std 805-1984 2
5-Scheduled A-Equipment Failure (Explain) 1-Manual S
B-Maintenance or Test 2-Manual Scram.
IEEE Std 803A-1983 C-Refueling 3-Automatic-Scram.
D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previcus Month F-Administrative
~5-Reduction in the Average G-Operational Error (Explain)
Daily-Power Level of more H-Other (Explain) than 20% from the previous day 6-Other (Explain) 3'
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SupW4ARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: _30-362 UNIT NAME:
SONGS - 3 DATE: April 12.1995 COMPLETED BY:
R. L. Kaolan TELEPHONE:
(714) 368-6834 i
Qalg Time Event March 01 0001 Unit is in Mode 1, 96.5% reactor power, 1104 Mwe.
March 03 2254 Main turbine governor valve 30V-2200F failed j
closed. Unit load decreased to 980 MWe as a result 1
of closed valve.
Reactor power was maintained at full power by the steam bypass control system valves.
March 04 0330 Reactor power' reduced to 91% power, 1040 MWe for j
l closure of steam bypass control system valves.
i 0907 Reactor power increased to 96.5% power,1105 MWe.
i March 19 0358 Commenced lowering reactor power to 82%l 910 MWe to bump circulating water pumps and water box delta pressure. reduction.
Raisedreactorkowerto 96.6%, 1088 MWe after 1835 completion of c rculating water pump bumping.
l March 31 2400 Unit is in Mode 1, 96.5% reactor power, 1104 MWe.
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I-o REFUELING INFORMATION DOCKET NO:
50-362 4
-UNIT NAME:
SONGS - 3 1
DATE:
April 12. 1995
}
COMPLETED BY:
_S.
L. Kaplan i.
TELEPHONE: - (714) 368-6834 MONTH:
March 1995 l
- 1. Scheduled date for next refueling shutdown.
Cycle 8 refueling outage is forecast for July 8,1995.
j-
- 2. Scheduled date for-restart following refueling.
Restart from Cycle 8 refueling. outage isl forecast for September' 16, 1995.
1
~ 3. Will refueling or resumption of operation thereafter require a Technical j
Specification change or other license amendment?
i Yes 4
What will these be?
A.'
- A proposed change to the Technical Specifications 'has been requested to i
allow a 3.0.4. exception for entering Modes 5 'and 6 with the Control Room Emergency Air Cleanup System inoperable.
B.
A proposed change to the Technical Specifications has been requested to update the Unit 3 pressure-temperature curves and the low temperature j
overpressure protection enable temperature.
- 4. Scheduled date for submitting proposed licensing action and supporting information.
A.
Control Room Air Cleanup System Submitted August 26, 1994 B.
Pressure-Temperature Curves Revision submitted July 6,1994
- 5. Important licensing considerations associated with refueling, e.g. new or l
different fuel design or supplier unreviewed design or performance analysis methods, significant changes in-f el design, new operating procedures, j
- None, i
b
}
e l
1 1
i 1
i i
5
o REFUELING INFORMATION DOCKET NO:
__50-362 UNIT NAME:
SONGS - 3 DATE:
April 12.1995 COMPLETED BY:
R. L. Kaolan TELEPHONE:
(714) 368-6834 a
- 6. The number of fuel assemblies.
A.
In the core.
217 B.
In the spent fuel storage pool.
710 To1:al' Fuel Assemblies 112 Unnt 3 Soent
- ue' Assemb' es l
Zero Unit 3 New
- ue' Assem)'
' es 118 Unit 1 Spent
- ue' Assem)'
- es
- 7. Licensed spent fuel storage capacity.1542 t
l Intended change in spent fuel storage capacity.
None L
- 8. Pro; ected date of last refueling that can be discharged to spent fuel storage poo assuming present capacity.
j I
Approximately 2003 (full off-load capability).
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