ML20083N228
| ML20083N228 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/30/1995 |
| From: | Kaplan R, Marsh W SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505220300 | |
| Download: ML20083N228 (13) | |
Text
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. Southem Califomia Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 May 12, 1995
,m,,_
WALTER C. MARSH McNunt M OP #AJCLE A t ettGUL ATORY AFF AIMS (714) 4&t-4403 U.
S.
Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Monthly Operating Reports for April 1995 San Onofre Nuclear Generating Station, Units 2 and 3 Technical Specification 6.9.1.10 of Facility Operating Licenses NPF-10 and NPF-15 for the San Onofre Nuclear Generating Station, Units 2 and 3, respectively, requires Edison to provide a Monthly Operating Report for each Unit, which includes: routine operating statistics and shutdown experience; all challenges to safety valves; any changes to the Offsite Dose Calculation Manual (ODCM); and any major changes to the radioactive waste treatment system.
All covered activities are reported monthly, except for ODCM changes, which are reported within 90 days from the time the changes are effective.
This letter transmits the April 1995 Monthly Operating Reports for Units 2 and 3, respectively.
There were no challenges to safety valves, and no major changes to the Units 2 and 3 radioactive waste treatment systems during the reporting period.
If you require any additional information, please let me know.
Sincerely, NAd Enclosures cc:
L.
J.
Callan, Regional Administrator, NRC Region IV J.
Dyer, Director, Division of Reactor Projects, NRC Region IV K.
E.
Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV M. B. Fields, NRC Project Manager, Units 2 and 3 J. A. Sloan, Senior NRC Resident Inspector, San Onofre Units 2 &3 200011
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NRC NONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE: May 12. 1995 COMPLETED BY:
R. L. Kaplan TELEPHONE:
(7141 368-6834 OPERATING STATUS 1.
Unit Name: _ San Onofre Nuclear Generatina Station. Unit 2 2.
Reporting Period:
Aoril 1995 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 719.00 2.879.00 102.576.00 12.
Number Of Hours Reactor Was Critical 54.30 1.038.65 77.813.24 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.
Hours Generator On-Line 0.00 984.32 76.615.66 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal Energy Generated (MWH) 0.00 3.091.911.80 250.469.767.64 17.
Gross Electrical Energy Generated (MWH) 0.00 1.071.360.00 84.922.859.50 18.
Net Electrical Energy Generated (MWH)
(14.101.00) 999.461.04 80.563.555.91 19.
Unit Service factor 0.00%
34.19%
74.69%
20.
Unit Availability Factor 0.00%
34.19%
74.69%
21.
Unit Capacity Factor (Using MDC Net) 0.00%
32.44%
73.40%
22.
Unit Capacity Factor (Using DER Net) 0.00%
32.44%
73.40%
23.
Unit Forced Outage Rate 0.00%
0.00%
5.43%
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: May 16. 1995 26.
Units In Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA CONNERCIAL OPERATION NA NA 1
L AVERAGE DAILY UNIT POWER LEVEL DOCKET'NO:
50-361 UNIT NAME:
SONGS - 2 DATE: May 12. 1995 COMPLETED BY:
R. L. Kaolan TELEPHONE:
(714) 368-6834 MONTH:
April 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 t
8 0.00 23 0.00 9
0.00 24 0.00' 10 0.00 25 0.00 11 0.00 26 0.00 f
'12 0.00 27 0.00 13 0.00 28 0.00
{
14 0.00 29 0.00 15 0.00 30 0.00 e
C
(
2
UNIT SHUTDOWNS afb POWER REDUCTIONS DOCKET-NO: 50-361 UNIT NAME:--SONGS - 2 REPORT MONTH:
April 1995 DATE:- May 12. 1995-COMPLETED BY:
R. L.-Kaplan TELEPHONE:
(714) 368-6834 l
1 Method of Shutting cause & Corrective Duration Down LER System Component Action to l
2 No.
Date
-Type (Hours)
Reason Reactor No.
Code' Code' Prevent Recurrence 88 950210 S
719 C
1 N/A N/A N/A N/A Note:
Refueling shutdown continued from previous month.
2 3
2F-Forced Reason:
Method:
"IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual S
B-Maintenance or Test 2-Manual Scram.
IEEE Std 803A-19831 C-Refueling 3-Automatic Scram.
D-Regulatory Restriction 4-Continuation from E-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) 3
e
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH r
DOCKET N0:
50-361 UNIT NAME:
SONGS - 2 DATE:
May 12. 1995 COMPLETED BY:
R. L. Kaolan TELEPHONE:
(714) 368-6834 t
D_alg li.mg Event April 01 0001 Unit is in Mode 5, shutdown cooling'in service with RCS at 105 degrees.
April 02 0100 All clocks adjusted ahead one hour to conform to Pacific Daylight Saving Time.
April 06 0050 Unit entered Mode 4, RCS at 200 degrees.
April 07 0346 Commenced cooldown to Mode 5 to investigate cause of RCS inventory loss to Refueling Water Storage Tank.
0609 Unit entered Mode 5.
April 08 1809 Unit entered Mode 4.
April 14 1122 Unit entered Mode 3.
i April 17 1755 Unit entered Mode 2.
1842 Reactor is critical.
April 20 0100 Reactor is manually tripped from.1% power, unit is in Mode 3.
l 1010 Commenced cooldown to Mode 5 to repair leaks in steam generator 2-ME-088 and heat exchanger on reactor coolant pump 2-MP-003.
1545 Unit entered Mode 4.
April 21 1015 Unit entered Mode 5.
April 23 0410 Unit entered a reduced inventory condition.
April 28 1850 Unit exited reduced inventory condition April 30 2400 Mode 5, RCS Tcold 180 degrees, Train B shutdown cooling in service, reactor coolant pumps 2-MP-002 and 3 in service.
4
c 4
REFUELING INFORNATION DOCKET NO:
50-361 L
UNIT NAME:
SONGS - 2 DATE:
May 12. 1995 COMPLETED BY:
R. L. Kaplan TELEPHONE:
(7141 368-6834 i
MONTH:
April 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 is forecast for May 16,.1995.
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No What will these be?
N/A
- 4. Scheduled date for submitting proposed licensing action and supporting information.
N/A
- 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.
None.
1 5
r-n REFUELING INFORNATION DOCKET N0:
50-361 UNIT NAME:
SONGS - 2 DATE:
May 12. 1995 COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 i
- 6. The number of fuel assemblies.
A.
In the core.
217 B.
In the spent fuel storage pool.
770 Total Fuel Assemblies-700 Unit 2 Snent Fuel Assemblies 0 Unit 2 New Fuel Assemblies 70 Unit 1 SDent Fuel Assemblies C.
In the New Fuel Storage Racks Zero Unit 2 New Fuel Assemblies
- 7. Licensed spent fuel storage capacity.
1542 r
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 2005 (full off-load capability) t t
I k
i I
i 6
e NRC NONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 I
DOCKET N0:
50-362 UNIT NAME:
SONGS - 3 DATE: May 12. 1995 COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 OPERATING STATUS 1.
Unit Name:
San Onofre Nuclear Generatina Station. Unit 3 2.
Reporting Period:
April 1995 3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Rating (Gross MWe): __
1080 1127 5.
Design Electrical Rating (Net MWe):
6.
Maximum Dependable Capacity (Gross MWe):
1127 7.
Maximum Dependable Capacity (Net NWe):
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 HWe):
NA 10.
Reasons For Restrictions, If Any:
NA This Month Yr.-to-Date Cumulative 11.
Hours In Reporting Period
-719.00 2.879.00 97.127.00 12.
Number Of Hours Reactor Was Critical 719.00 2.879.00 77.565.45 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.
Hours Generator On-Line 719.00 2.879.00 75.922.49 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal Energy Generated (MWH) 2.359.461.23 9.356.484.21 244.504.530 20 17.
Gross Electrical Energy Generated (MWH) 794.774.50 3.189.225.00 _83.021.901.50 18.
Net Electrical Energy Generated (MWH) 754.614.00 3.022.676.00 78.463.586.94 19.
Unit Service Factor 100.00%
100.00%
78.17%
20.
Unit Availability Factor 100.00%
100.00%
78.17%
21.
Unit Capacity Factor (Using MDC Net) 97.18%
97.21%
74.80%
22.
Unit Capacity Factor (Using DER Net) 97.18%
97.21%
74.80%
23.
Unit Forced Outage Rate 0.00%
0.00%
5.89%
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 NA NA CONNERCIAL OPERATION NA NA 1
- t..
1 AVERAGE DAILY UNIT POWER LEVEL 8
DOCKET NO:
50-362 UNIT NAME: _. SONGS - 3 DATE:
May 12. 1995 COMPLETED BY:
R. L. Kaplan TELEPHONE:
(7141 368-6834-c MONTH:
April 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-(MWe-Net)
(MWe-Net) 1 1053.75 16 1054.25 2
949.39 17 1055.75 3
1044.13 18 1056.08 I
4 1054.38 19 1055.71 5
1053.96 20 1056.04 6
1054.17 21 1054.83 7
1055.67 22 1056.75 8
1056.33 23 1055.96 9
1056.46 24 1057.08 10 1057.67 25 1055.29 11 1058.08 26 1052.46 12 1057.58 27 1052.04 i
13 1057.13 28 1051.33 t'
14 1052.38 29 1051.92 15 1048.29 30 1006.96 l
2
UNIT SHUTDOWNS Afm POWER REDUCTIONS DOCKET NO:- 50-362
-r-UNIT NAME: ' SONGS - 3 REPORT MONTH:
April 1995 DATE: May 12. 1995.
I COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 i
Method of Shutting Cause & Corrective Duration Down LER _
System Component Action to No.
Date Type (Hours) Reason Reactor No.
Code' Code' Prevent Recurrence l
3 There were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% this reporting period.
i
'F-Forced
' Reason:
Method:
t I
S-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 t
E-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) l 1
j 3
c i
'l SUNNARY 0F OPERATING EXPERIENCE FOR THE MONTH DOCKET N0:
50-362 UNIT NAME:
SONGS - 3 DATE: May 12. 1995-COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Qalg Time Event April 01 0001 Unit is in Mode 1, 96.5% reactor power, 1104 Mwe.
April 02 0100 All clocks adjusted ahead one hour to conform'to Pacific Daylight Saving Time.
1000 Commenced power reduction to 80% for circulating water system heat treatment 1151 Reactor power at 80% for heat treatment April 03 0020 Commenced raising reactor power to 97% at completion of circulating water system heat treatment.
April 30 2400 Unit is in Mode 1, 96.5% reactor power, 1100 MWe.
t 9
6 e
4 9
2 4
i
?
,.~
o F
REFUELING INFORMATION DOCKET N0:
50-362 UNIT NAME:
SONGS - 3 DATE:
May 12. 1995 COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 l
. MONTH:
April 1995
- 1. Scheduled date for next refueling shutdown.
Cycle 8 refueling outage is forecast for July 8,1995.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 8 refueling outage is forecast for September 16, 1995.
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes What will these be?
A.
A proposed change to the Technical Specifications has been requested to 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 overpressure protection enable temperature.
C.
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.
D.
A proposed change to the Technical Specifications, revising the automatic reset of the low pressurizer pressure bypass, has been revised to simplify the request.
- 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 C.
Linear Heat Rate Submitted September 16, 1994 D.
Low Pressurizer Pressure Bypass Revision submitted September 6, 1994
- 5. Important licensing considerations associated with refueling, e.g. new or i
~
different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None.
5
1 4.
a REFUELING INFORNATION DOCKET N0:
50-362' UNIT NAME:
SONGS - 3 DATE:
May 12. 1995 COMPLETED BY:
R. L. Kaolan TELEPHONE:
(714) 368 5834
- 6. The number of fuel assemblies.
A.
In the core.
217 8.
In the spent fuel storage pool.
710 Total Fuel Assemblies c,
592 Unit 3 Spent Fuel Assemblies Zero Unit 3 New Fuel Assemblies 118 Unit 1 Spent Fuel Assemblies
- 7. Licensed spent fuel storage capacity. 1542 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 2003 (full off-load capability).
4 P
6
-