ML20076G423
ML20076G423 | |
Person / Time | |
---|---|
Site: | San Onofre |
Issue date: | 09/30/1994 |
From: | Kaplan R SOUTHERN CALIFORNIA EDISON CO. |
To: | |
Shared Package | |
ML20076G421 | List: |
References | |
NUDOCS 9410190318 | |
Download: ML20076G423 (12) | |
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. NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: October 14. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 OPERATING STATUS
- 1. Unit Name: San Onofre Nuclear Generatino Station. Unit 2
- 2. Reporting Period: September 1994
- 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 6.551.00 97.488.00
- 12. Number Of Hours Reactor Was Critical 720.00 6.551.00 74.565.59
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 720.00 6.551.00 73.422.34
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 2.278.250.80 21.480.650.40 240.054.906.84
- 17. Gross Electrical Energy Generated (MWH) 762.285.50 7.287.680.50 81.375.468.50
- 18. Net Electrical Energy Generated (MWH) 726.189.00 6.943.858.00 77.198.556.88
- 19. Unit Service Factor 100.00% 100.00% 75.31%
- 20. Unit Availability Factor 100.00% 100.00% 75.31%
- 21. Unit Capacity Factor (Using MDC Net) 94.26% 99.06% 74.01%
- 22. Unit Capacity Factor (Using DER Net) 94.26% 99.06% 74.01% ,
- 23. Unit Forced Outage Rate 0.00% 0.00% 5.66% !
- 24. Shutdowns Scheduled Over Next 6 Months (Type,-Date, and Duration of Each):
Refuelino Shutdown. February 11. 1994. Duration (64 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 COMMERCIAL OPERATION NA NA 1 !
9410190318 DR 943o34 ADOCK 05000361 PDR
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, AVERAGE DAILY UNIT POWER LEVEL DOCKET N0: 50-361 UNIT NAME: SONGS - 2 I DATE: October 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834 MONTH: SeDtember 1994 DAY AVERAGE DAILY POWER LEVEL DAY : AVERAGE DAILY POWER LEVEL (MWe-Net). (MWe-Net) 1 1 1048.46 16 '777.75 ,
2 1012.08 17 798.50 !
3 732.71~ 18 1062.46 _
4 735.33 19 1068.92 5 772.17 20 1071.08 6 932.67 21 1071.38 7 1063.08 22 1072.96 8 1067.17 23 1060.21 e 9 1069.13' 24 1052.96 10 1064.67 25 1061.83 11 1067.54 26 1061.54 l 12 1066.29 27 1071.00 13 1067.04 28 1080.38 l l
14 1069.63 29 1075.42 1 15 1030.25 30 1073.29 l
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-361
' UNIT NAME: SONGS - 2
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REPORT MONTH: September 1994 DATE: October- 14. 1994 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 l (Hours) Reason 2 Reactor3 No. Code' Code Prevent Recurrence i
86 940902 S 0.0 B 5 NA KE COND Reduce reactor power to perform circulating water pump repair and water box cleaning.
87 940915 S 0.0 B 5 NA KE COND Reduce reactor power to perform:
circulating water pump repair.
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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) s
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-SUMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: October 14. 1994
-COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 Date Time Event September 01 0001 Unit is in Mode 1, 98% reactor power,1103 MWe.-
2055- Reduced turbine load by 30 Mwe due to circulating water Delta T limits.
September 02 0001 Unit at 94.7 reactor power, 1071 Mwe.
0446 Returned Unit to full load, 1096 Mwe.
i 2103 Commenced lowering reactor power to 75% for water box cleaning, and circulating pump maintenance.
September 03 0001 Unit at 74% reactor power, 770 MWe September 06 0935 Commenced raising reactor power to 98%
1645 Unit at 98% reactor power, 110E MWe.
September 15 2045 Commenced lowering reactor power to 75% for circulating pump maintenance.
2300 Unit at 75% reactor power, 837 MWe. ,
September 17 1420 Commenced raising reactor power to 80% for circulating water system heat treatment i
2300 Commenced raising reactor power to 98% after completion of circulating water system heat l treatment.
September 18 0240 Unit at 98% power, 1112 MWe.
September 30 2400 Unit is in Mode 1, 98% reactor power,_1121 MWe.
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, REFUELING INFORMATION l DOCKET NO: 50-361 UNIT NAME: SONGS - 2 1 DATE: October 14. 1994 ,l COMPLETED BY: R. L. KaDlan l TELEPHONE: (714) 368-6834 _
MONTH: September 1994 i
- 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.
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- 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 exem) tion from !
10 CFR 50 Appendix J has been requested to permit deferring tie '
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. ,
i D. A proposed change to the Final Safety Analysis has been requested to i remove the diversity requirement of the pressurizer pressure transmitters providing input to the shutdown cooling open permissive interlock. ,
E. Proposed change to the Technical Specifications (PCN 431), revising the -
automatic reset of the low pressurizer pressure bypass, has been revised i 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. ;
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REFUELING'INFORMATION j DOCKET N0: 50-361 +
UNIT NAME: SONGS - 2 -
DATE: October 14. 1994 j 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 .
4 B. Integrated Leakrate Testing Submitted August 17, 1994 i C. Linear Heat Rate Submitted September 16, 1994 !
D. Pressure Instrument Diversity Submitted July 6, 1994 !
E. Low Pressurizer Pressure Bypass Revision submitted September 6, 1994 :
F. - Control Room Air Cleanup System Submitted August 26, 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. i None.
- 6. The number of fuel assemblies. l A. In the core. 217 i i
B. In the spent fuel storage pool. 662 Total Fuel Assemblies i 592 Unit 2 Spent Fuel Assemblies !
0 Unit 2 New Fuel Assemblies 70 Unit 1 SDent Fuel Assemblies
- 7. Licensed spent fuel storage capacity. 1542 l r
Intended change in spent fuel storage capacity. None l
- 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Approximately 2005 (full off-load capability) ,
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NRC MONTHLY OPERATING REPORT j SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 3 1
DOCKET NO: 50-362 I UNIT NAME: SONGS - 3 l DATE: October 14. 1994 ,
COMPLETED BY: R. L. Kaplan i TELEPHONE: (714) 368-6834 ,
i OPERATING STATUS I
- 1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3 '
- 2. Reporting Period: SeDtember 1994
- 3. Licensed Thermal Power (MWt): 3390 3
- 4. Nameplate Rating (Gross MWe): 1127 !
- 5. Design Electrical Rating (Net MWe): 1080 :
- 6. Maximum Dependable Capacity (Gross MWe): 1127 f
- 7. Maximum Dependable Capacity (Net MWe): 1080 -l '
- 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 6.551.00 92.039.00 '
- 12. Number Of Hours Reactor Was Critical 720.00 6.551.00 72.477.45
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00- i
- 14. Hours Generator On-Line 720.00 6.537.60 70.834.49 !
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 ,
- 16. Gross Thermal Energy Generated (MWH) 2.359.461.23 21.235.151.12 227.906.940.83
- 17. Gross Electrical Energy Generated (MWH) 801.305.00 7.234.325.50 77.377.732.50
- 18. Net Electrical Energy Generated (MWH) 758.440.00 6.849.370.00 73.112.408.94 !
- 19. Unit Service Factor 100.00% 99.80% 76.96% ;
- 20. Unit Availability Factor 100.00% 99.80% 76.96%
- 21. UnitCapacityFactor(UsingMDCNet) 97.54% 96.81%. 73.55% i
- 22. Unit Capacity Factor (Using DER Net) 97.54% 96.81% 73.55% l
- 23. Unit forced Outage Rate 0.00% 0.00% 6.29%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): ;
None j
- 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 l INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA l
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: October 14. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: September 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1050.92 16 1051.92 2 1047.21 17 1043.08 3 1034.63 18 1050.71 4 1051.33 19 1051.08 5 1051.50 ,_
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1053.38 6 1053.25 21 1053.63 7 1053.96 22 1055.29 8 1056.25 23 1057.04 9 1057.17 24 1057.96 10 1055.79 25 1058.04 11 1054.75 26 1059.21 12 1054.08 27 1060.58 13 1053.58 28 1061.54 14 1055.46 29 1061.67 15 1056.92 30 1039.75 i
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UNIT SHUTDOWNS AND POWER REDUCTIONS ; DOCKET NO: 50-362 ~ 4 UNIT NAME: SONGS - 3 REPORT MONTH: September 1994 DATE: October 14. 1994' ~
COMPLETED BY: R. L. KaDlan TELEPHONE: _J714) 368-6834 ,
Method of -
Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type l (Hours) Reason 2 Reactor3 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.
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2 F-Forced Reason: ' Method: "IEEE Std~805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual
. 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) i j
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SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH :
DOCKET NO: 50-362-UNIT NAME: SONGS - 3 l DATE: October 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834 ;
Date Time Event l i
September 01 0001 Unit is in Mode 1, 97% reactor power, 1103MWe. l September 30 2100 Commenced lowering reactor power to 75% for !
circulating water system heat treatment and waterbox cleaning.
2340 Unit at 75% reactor power, 830 Mwe. ;
September 30 2400 Unit is in Mode 1, 75% reactor power, 830 MWe, i
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REFUELING INFORMATION i
DOCKET N0: 50-362 ,
UNIT NAME: SONGS - 3 DATE: October 14.-1994 :
COMPLETED BY: R. L. KaDlan
-TELEPHONE: (714) 368-6834 a i
MONTH: September 1994
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- 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 11, 1995. ,
- 3. Will refueling or resumption of operation thereafter require a Technical i Specification change or other license amendment? i t
Unknown at this time for Cycle 8 refueling.
What will these be?
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- 4. Scheduled date for submitting proposed licensing action and supporting information. j NA l
- 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.
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j REFUELING INFORMATION DOCKET N0: 50-362 5' UNIT NAME: SONGS - 3 DATE: October 14. 1994 ;
COMPLETED BY: R. L. Kaolan TELEPHONE: (714) 368-6834 !
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- 6. The number of fuel assemblies.
A. In the core. 217 !
8.- In the spent fuel storage pool. 710 Total- Fuel Assemblies 'I 592 Unit 3 SDent Fuel Assemblies >
0 Unit 3 New Fuel Assemblies i 118 Unit 1 SDent Fuel Assemblies j
- 7. Licensed spent fuel storage capacity. 1542- l t
Intended change in spent fuel storage capacity. None [
- 8. Projected date of last refueling that can be discharged to spent fuel storage r pool assuming present capacity. !
Approximately 2003 (full off-load capability). ;
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