ML20073C247
| ML20073C247 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/31/1994 |
| From: | Kaplan R, Marsh W SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9409230197 | |
| Download: ML20073C247 (14) | |
Text
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Southem Califomia Edison Company 23 PARKER STREET BRVINE. CALIFORNI A 92718 September 14, 1994 WALTER C, MARSH T ELE PHONE i
MANAGF R OF #4UCL E A$t REGULATOMY AFF AIRE (714)454-4403 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 August 1994 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 (0DCM); and any major changes to the radioactive waste treatment system.
All covered activities are reported monthly, except for ODCM changes, which are reported w; thin 90 days from the time the changes were made effective.
This letter transmits the August 1994 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, b
i 4
Enclosures i
cc:
L. J. Callan, Regional Administrator, NRC Region IV A. B. Beach, 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 1, 2 & 3 210031
-9409230197 940831 PDR ADOCK 05000361 gl R
(
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Document Control Desk NRC MONTHLY OPERATING REPORT DOCKET NO:
50-361 UNIT NAME: SONGS - 2 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 OPERATING STATUS P
1.
Unit Name: San Onofre Nuclear Generatina Station. Unit 2 2.
Reporting Period:
Auaust 1994 3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Ratir g (Gross MWe):
1127 5.
Design Electrical Rating (Net MWe):
1070 6.
MaximumDependableCapacity(GrossMWe):
1127 l
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 744.00 5.831.00 96.768.00 12.
Number Of Hours Reactor Was Critical 744.00 5.831.00 73.845.59 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 4
14.
Hours Generator On-Line 744.00 5.831.00 72.702.34 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal Energy Generated (MWH) 2.440.983.00 19.202.399.60 237.776.656.04 17.
Gross Electrical Energy Generated (MWH) 812.894.50 6.525.395.00 80.613.183.00 18.
Net Electrical Energy Generated (MWH) 774.791.00' 6.217.669.00 76.472.367.88 19.
Unit Service Factor 100.00%
100.00%
75.13%
+
20.
Unit Availability Factor 100.00%
100.00%
75.13%
21.
Unit Capacity Factor (Using MDC Net) 97.33%
99.66%
73.86%
22.
Unit Capacity Factor (Using DER Net) 97.33%
99.66%
73.86%
23.
Unit Forced Outage Rate 0.00%
0.00%
5.71%
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
'Refuelina Shutdown. February 11. 1994. Duration (65 days) 25.
If Shutdown At End Of Report Period, Estimated Date of Startup:.
NA r
26.
Units In Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 2
Document Control Desk AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 110 NTH:
August 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1055.29 16 1038.58 2
1065.71 17 1054.13 3
1065.17 18 1056.46 4
1065.08 19 1060.33 5
1066.79 20 1061.04 6
1059.38 21 1056.92 7
1054.54 22 1056.33 8
1055.54 23 1056.50 9
1058.08 24 1056.25 10 1062.29 25 1030.67 11 1064.63 26 1017.79 12 1063.71 27 1059.17 13 790.25 28 1058.42 14 926.13 29 1057.75 15 1005.83 30 1053.54 31 1050.67 3
Document Control Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0: 50-36)
UNIT NAME: SONGS - 2
~
REPORT MONTH:
August 1994 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Method of Shutting Cause & Corrective Duration Down LER System Component Action to l
2 3
s No.
Date Type (Hours)
Reason Reactor No.
Code' Code Prevent Recurrence 85 940813 S
0.0 B
5 NA KE COND Reduce reactor power to perform circulating water system heat treatment and water box cleaning.
I 2
3 F-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-1983 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) 4
i i
Document Control Desk SUFMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:
50-361 UNIT NAME: SONGS - 2 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Date Time Event August 01 0001 Unit is in Mode 1, 92.5% reactor power,1040 MWe, to repair heater drain pump 2P059.
0201 Commenced raising reactor power to 98% after
)
completion of heater drain pump 2P059 outage.
0436 Unit at 98%, 1113 MWe.
August 13 0100 Commenced lowering reactor power to 80% for circulating water system heat treatment, water box cleaning, and condensate pump maintenance.
0317 Unit at 80% reactor power, 908 MWe-
]
1207 Circulating water heat treatment complete, j
August 14 0001 Unit at 75% reactor power, 773 MWe for water box cleaning.
0355 Commenced raising reactor power to 90% after completion of circulating water system heat treatment and water box cleaning.-
0600 Unit at 90% reactor power, 1003 MWe.
j August 15 1145 Commenced raising reactor power to 98% after completion of condensate pump maintenance.
1505 Unit at 98% reactor power, 1100 MWe.
August 25 2140 Commenced lowering reactor power to 80% for circulating water pump bumping and water box cleaning.
2330 Unit at 80% reactor power, 908 MWe for circulating pump bumping.
5
Document Control Desk
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET I40:
50-361 UNIT NAME:
SONGS - 2 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Date Time Event August 26 0330 Commenced raising power to 98% after completion of circulating water pump bumping and water box cleaning.
0715 Unit at 98% power, 1115 MWe.
August 31 2400 Unit is in Mode 1, 98% reactor power, 1103 MWe, 6
Document Control Desk REFUELING INFORMATION DOCKET N0:
50-361 UNIT NAME:
SONGS - 2 DATE:
COMPLETED BY:
R. L. Kaplan' TELEPHONE:
(714) 368-6834 MONTH:
Auaust 1994
- 1. Scheduled date for next refueling shutdown.
Cycle 8 refueling outage is forecast for February 11, 1995.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 8 refueling outage is forecast for April 15, 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 which will revise the minimum water level in the refueling cavity with only one train of shutdown cooling operable.
B.
A proposed change to the Technical Specifications and an exemption from 10 CFR 50 Appendix J has been requested to permit deferring the Integrated Leakrate Testing.
C.
A proposed change to the Technical Specifications has been, requested to revise the allowed Linear Heat Rate from 13.9 to 13.0 kw/ft.
D.~
A proposed change to the Final Safety Analysis has been requested to remove the diversity requirement of the pressurizer pressure transmitters providing input to the shutdown cooling open permissive interlock.
i E..
Proposed change to the Technical Specifications (PCN 431), revising the
~3 automatic reset of the low pressurizer pressure bypass, has been revised to simplify the request.
F.
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.
t r
Document Control Desk REFUELING INFORMATION DOCKET N0:
50-361 UNIT NAME:
SONGS - 2
"~'
DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834
- 4. Scheduled date for submitting proposed licensing action and supporting information.
A.
Refueling Cavity Water Level Submitted July 28, 1994 8.
Integrated Leakrate Testing Submitted August 17, 1994 C.
Linear Heat Rate Submittal Forecast Sept. 15, 1994 D.
Pressure Instrument Diversity Submitted July 6, 1994 E.
Low Pressurizer Pressure Bypass Revision submitted Sept. 6, 1994 F.
Control Room Air Cleanup System Submitted Aug. 26, 1994
- 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.
- 6. The number of fuel assemblies.
P A.
In the core.
217 B.
In the spent fuel storage pool.
662 Total Fuel Assemblies 592 Unit 2 Spent Fuel Assemblies 0 Unit 2 New Fuel Assemblies 1
70 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.
i Approximately,2005 (full off-load capability) j 1
4
Document Control Desk NRC MONTHLY OPERATING REPORT DOCKET NO:
50-362 UNIT NAME: SONGS - 3 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 OPERATING STATUS 1.
Unit Name: San Onofre Nuclear Generatina Station. Unit 3 2.
Reporting Period:
Auaust 1994 3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Rating (Gross MWe):
1127 5.
Design Electrical Rating (Net MWe):
1080 6.
Maximum Dependable Capacity Gross MWe):
1127 7.
Maximum Dependable Capacity Net MWe):
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 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 91.319.00 12.
Number Of Hours Reactor Was Critical 744.00 5.831.00 71.757.45 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.
Hours Generator On-Line 744.00 5.817.60 70.114.49 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal Energy Generated (MWH) 2.440.821.97 18.875.689.88.225.547.479.60 17.
Gross Electrical Energy Generated (MWH) 818.628.00 6.433.020.50 76.576.427.50 18.
Net Electrical Energy Generated (MWH) 774.245.00 6.090.930.00 72.353.968.94 19.
Unit Service Factor 100.00%
99.77%
76.78%
20.
Unit Availability Factor 100.00%
99.77%
76.78%
[
21.
Unit Capacity Factor Using MDC Net 96.36%
96.72%
73.36%
e 22.
Unit Capacity Factor Using DER Net 96.36%
96.72%
73.36%
23.
Unit Forced Outage Rate 0.00%
0.00%
6.35%-
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None i
. 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
[
COMMERCIAL OPERATION NA NA 4
l 5
9 r
Document Control Desk AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:
50-362 UNIT NAME: SONGS - 3 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 MONTH:
August 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1050.88 16 1038.96 2
1053.96 17 1038.96 3
1052.88 18 1041.38 4
1053.83 19 1040.58 5
1056.63 20 1047.38 6
1044.42 21 1044.79 7
1047.21 22 1044.54 8
1034.63 23 1045.13 9
1049.42 24 1047.33 10 1027.42 25 1049.08 11 1052.42 26 1049.79 12 1051.00 27 860.54 13 1047.33 28 1046.58 14 1045.33 29 1053.00 15 1042.46 30 1050.63 31 1051.75 10
Docunent Control Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH:
Auaust 1994 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Method of Shutting Cause & Corrective Duration Down LER System Component Action to l
2 3
5
.No.
Date
. Type (Hours)
Reason Reactor No.
Code' Code
' Prevent Recurrence There were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% -this reporting period.
l 1
F-Forced
' Reason:'
3 2
Method:
'S-Scheduled A-Equipment Failure (Explain) 1-Manual S
B-Maintenance or Test 2-Manual Scram.
.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) 11
. - -. - -...... a..- -.--
Document Control Desk SUlMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0:
50-362 UNIT NAME:
SONGS - 3 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Date Time Event August 01 0001 Unit is in Mode 1, 97% reactor power, 1110 MWe.
August 08 1055 Commenced load reduction from 1098 MWe to 1025 MWe using the steam bypass control valves to repair high pressure governor valve.
1405 Returned to full load 1096 MWe.
August 10 1016 Commenced lowering reactor power to <90% to repair Core Protection Calculator (CPC) C and Control Element Assembly Calculator (CEAC) 1.
1120 Unit at 87% reactor power, 987 MWe.
1430 Commenced raising reactor power to 97% after repair of CPC C and CEAC 1.
1630 Unit at 97% reactor power,1096 MWe.
August 27 0300 Commenced lowering reactor power to 80% for circulating water system heat treatment.
0500 Unit at 80% reactor power, 908 MWe.
2330 Commenced raising reactor power after completion of circulating water system heat treatment.
28 0250 Unit at 97% reactor power, turbine valves wide j
open, 1104 MWe.
August 31 2400 Unit is in Mode 1, 97% reactor power, 1101 MWe.
12
utr -
Docu'ent Control Desk m
REFUELING INFORMATION DOCKET N0:
50-362 UNIT NAME:
SONGS - 3 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 MONTH:
August 1994
- 1. Scheduled date for next refueling shutdown.
Cycle 8 refueling outage is foiecast for June 4, 1995.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 8 refueling outage is forecast for August 6, 1995.
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Unknown at this time for Cycle 8 refueling.
What will thase be?
NA
- 4. Scheduled date for submitting proposed licensing action and supporting information.
NA
- 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.
13
i Document Control Desk REFUELING INFORMATION DOCKET N0:
50-362 UNIT NAME:
SONGS - 3 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834
- 6. The number of fuel assemblies.
A.
In the core.
217 B.
In the spent fuel storage pool.
710 Total Fuel Assemblies 592 Unit 3 Spent Fuel Assemblies 0 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).
i l
l a
14