ML20117G200
ML20117G200 | |
Person / Time | |
---|---|
Site: | San Onofre |
Issue date: | 04/30/1996 |
From: | Williams C SOUTHERN CALIFORNIA EDISON CO. |
To: | |
Shared Package | |
ML20117G161 | List: |
References | |
NUDOCS 9605210042 | |
Download: ML20117G200 (14) | |
Text
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NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATIN3 STATION, UNIT 2 ,,
DOCKET NO: 50-361 UNIT NAME: SONGS -2 -
DATE: May 14. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 OPERATING STATUS
- 1. Unit Name: San Onofre Nuclear Generatina Station. Unit 2
- 2. Reporting Period: Acril 1996
- 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 2.903.00 111.360.00
- 12. Number Of Hours Reactor Was Critical 719.00 2.903.00 86.291.19
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 719.00 2.903.00 84.733.31
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 2.359.616.90 9.E01.199.80 277,239.214.55
- 17. Gross Electrical Energy Generated (MWH) 798.959.00 3.282.200.50 93.984.083.00
- 18. Net Electrical Energy Generated (MWH) 760.554.64 3.125.876.04 89.168.467.95
- 19. Unit Service Factor 100.00% 100.00% 76.09%
- 20. Unir Availability Factor 100.00% 100.00% 76.09%
- 21. Uni: Capacity Factor (Using MDC Net) 98 953, 100.63% 74.83%
- 22. Unit Capacity Factor (Using DER Net) 98.86% 100.63% 74.83%
- 23. Unit Forced Outage Rate 0.00% 0.00% 5.07%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None
- 25. If Shutdown At End Of Report Period, Estimated Date of Startup: N/A
- 26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 9605210042 960515 1 PDR ADOCK 05000361 R PDR
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: May 14, 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 MONTH: Aoril 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net) (MWe-Net) 1 1080.60 16 1097.23 2 1021,42 17 1092.31 3 1073.52 18 1997.28 4 1018.33 19 1095.19 5 934.39 20 1097.54 6 1071.74 21 1097.77 7 1132.91 22 1097.25 ,
8 1087.82 23 1098.23 9 1089.48 24 1098.30 10 '1088.54 25 1094.99 11' 1043.98 26 1092.66 12 980.82 27 1090.98 l
13 742.70 28 1090.84 l 14 849.52 29 1092.24 15 1084.77 30 1047.61 l
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UNIT CHUTDONN3 AND POWER REDUCTION 3 DCCKET NO: 50-361 UNIT NAME: SONGS - 2 ,
REPORT MONTH: March 1996 DATE: May 14. 1996 .
COMPLETED BY: C. E. Williams
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TELEPHONE: f714) 368-6707 ,
Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type 2 (Hours) Reason 2 ~ Reactor 3 No. Code
- Code' Prevent Recurrence 95 4/13/96 S NA B 5 NA KE COND Heat treatment of circulating water system 1F-Forced 2 Reason: ' Method: *IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual 5
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 1
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SUte4ARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-361 l UNIT NAME: SONGS - 2 l DATE: Mav 14. 1996 l COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 l
l Data Time Event April 01 0000 Mode 1, Reactor power at 98.7%, 1132 MWe.
April 04 0335 Commenced load reduction to 1100 MWe to lower ,
circulating water temperature difference.
( 0410 Completed load reduction, reactor power at 95%,
1100 MWe. !
1100 circulating water temperature difference data logger determined to be inoperable. Commenced l power increase for optimal generation.
(_ 1444 Reactor power at 98.7%, 1137 MWe. !
1915 Commenced power reduction to bump' circulating
- water pumps.
2145 Reactor power at 75%, 810 MWe. :
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April 05 0840 Commenced power increase after bumping circ j -
water pump. ;
1335 Reactor power at 100%, 1130 MWe.
! April 06 1028 High pressure turbine governor valve 22008 failed closed. Turbine load reduced to 1053 MWe. ;
1345 HP turbine governor valve 2200B returned to service. Commenced raising turbine load.
1540 Reactor power at 100%, 1135 MWe.
April 07 0200 All clocks adjusted one hour forward for Pacific daylight saving time.
t April 11 0630 Stopped third point heater drain pump, 2P058, j due to increasing bearing temperature. Reactor power at 99.8%, 1118 MWe.
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I 1132 Reduced power to 95%, 1070 MWe, for third point .
I heater drain pump 2P058 outage. )
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SUbt4ARY OF OPERATING EXPERIENCE FOR THE MONTH (Continued)
DOCKET NO: 50-361 UNIT NAME: SONGS - 2 i
DATE: Mav 14. 1996 I COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 l
l Date ling Event April 12 2005 Commenced power reduction to 75% to clean l
condenser water boxes and perform heat treat of l
circulating water system intake. ,
l 2359 Reactor power at 76%, 780 MWe.
Aoril 14 2015 Commenced reactor power increase to full power i l following circulating water system heat treat, i and high pressure turbine stop'and governor valve testing.
April 15 0220 Reactor power at 98.2%, 1134 MWe. I l
April 30 2400 Mode 1, Reactor power at 99.7%, 1141 MWe.
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REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: May 14. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 MONTH: Acril 1996
- 1. Scheduled date for next refueling shutdown:
Cycle 9 refueling outage is forecast for November 30, 1996.
- 2. Scheduled date for restart following refueling:
Restart from Cycle 9 refueling outage is forecast for February 3, 1997.
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes.
I What will these be?
, 1. Increase in Diesel Generator allowed outage time (AOT) ,
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- 2. Increase in Low Pressure Safety Injection AOT
- 3. Increase in fuel enrichment to 4.8%.
- 4. Revision to test interval of load sequencing relays.
- 5. Implementation of barrier control program.
- 6. Revision to Containment Isolation Valve action statement.
- 7. Appendix J Option B Technical Specification.
- 8. Increase in Safety Injection Tank boron concentration.
4, Scheduled date for submitting proposed licensing action and supporting information.
- 3. PCN 449 Enrichment Increase Submitted 12/6/95
- 4. PCN 454 Load Sequencing Relays Forecast 5/24/96
- 5. PCN 467 Barrier Control Program Submitted 5/09/96
- 6. PCN 460 Containment Isolation Valves Submitted 4/11/96 Supplement Forecast 5/30/96
- 7. PCN 361 Appendix J Option B Forecast 6/15/95
- 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.
Increase in fuel enrichment.
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REPUELING INEVRNATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: Mav 14. 1996 I COMPLETED BY: C. E. Williams l TELEPHONE: (714) 368-6707 i
- 6. The number of fuel assemblies.
A. In the core. 217 B. In the spent fuel storage pool. 770 Total Puel Assemblies 700 Unit 2 Soent Fuel Assemblies I O Unit 2 New Puel Assemblies l 70 Unit 1 Scent Fuel Assemblies C. In the New Puel Storage Racks Zero Unit 2 New Fuel Assembligg
- 7. Licensed spent fuel storage capacity. 1542 l Intended change in spent fuel storage capacity. None l
l 8. Projected date of last refueling that can be discharged to spent fuel
! storage pool assuming present capacity.
April 2005, assuming current fuel loading for all future cycles, and Unit 1 fuel remains at current location.
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REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: Mav 14. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707
- 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 Scent Fuel Assemblies 0 Unit 2 New Fuel Assemblies 70 Unit 1 Soent Fuel Assemblies C. In the New Fuel Storage Racks Zero Unit 2 New 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.
April 2005, assuming current fuel loading for all future cycles, and' Unit 1 fuel remains at current location. 1 l
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NRC MONTHLY OPERATING REPORT- .
SAN ONOFRE NUCLEAR GENERATING STATION,. UNIT 3 N NAME S NG - 3 -
l DATE: May 14. 1996 .
COMPLETED BY: - C. E. William = i
' TELEPHONE: f714)'368-6707 r OPERATING STATUS l 1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3'
- 2. Reporting Period: Aoril 1996 ;
Licensed Thermal Power (MWt) :
7
- 3. 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 i
- 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) .i Since Last Report, Give Reasons: NA !
- 5. 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 2.903.00 105.911.00
, 12. Number Of Hours Reactor Was Critical 719.00 2.903.00 84.839.70 :
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00 :*
- 14. Hours Generatot On-Line 719.00 2.903.00 83.122.64 ;
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 2.359.616.90 9.682.565.90 268.'182.065.30
- 17. Gross Electrical Energy Generated (:MWH) 795.852.50 3.292.404.50 91.051.874.50 i
- 18. Net Electrical Energy Generated (MWH) 754.495.64 3.127.080.04 86.066.443.60 i
- 19. Unit Service Factor 100.00% 100.00% 78.48% -[
- 20. Unit Availability Factor 100.00% 100.00% 78.48%
- 21. Unit Capacity Factor (Using MDC Net) 97.16% 99.74%. 75.24% j
- 22. Unit Capacity Factor (Using DER Net) 97.16% 99.74% 75.24%
- 23. Unit Forced Outage Rate 0.00% 0.00% 5.41%
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- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): 'I None
- 25. If Shutdown At E :d Of Report Bgriod, Estimated Date of Startup: . NA
- 26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved- j i INITIAL CRITICALITY NA NA .!
INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA ;
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AVERAGE DAILY UNIT POWER LEVEL
. , DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Mav 14. 1996 COMPLETED BY: C. E. Williamn TELEPHONE: (714) 368-6707 MONTH: Aoril 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net) (Mwe-Net)
I 1 1077.27 16 1081.15 l 2 1075.55 17 1082.43 3 1072.86 18 1079.28 l l
4 1072.92 19 1082.82 5 1023.23 20 1083.08 6 725.28 21 1080.90 7 808.35 22 1081.42 8 908.82 23 1083.06 9 1081.73 24 1078.55 10 1085.21 25 1080.15 11 1084.48 26 1073.62 ;
12 1083.99 27 1071.40 13 1082.11 28 ,
1069.76 14 1081.35 29 1071.62 15 1080.81 30 1027.82__
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9 UNIT CHUTDOWNS AND~ POWER REDUCTION.3 DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: Anril 1996 DATE: May 14. 1996 .
COMPLETED BY: C. E. William =
2 TELEPHONE: -f714) 368-6707
- Method of Shutting Cause & Corrective.
Duration Down LER System Component Action to No. Date Type l (Hours) Reason 2 Reactor 3 No. Code' Code' Prevent Recurrence 90 4/6/96 S NA B 5 NA KE COND Heat treatment of circulating water system 2
P-Forced 2 Reason: 3 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 - (Explai n) 3
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SIDE 4ARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: May 14. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 :
Date Time Event April 01 0000 Mode 1, reactor power at 99.2%, 1127 MWe.
April 05 1906 Commenced power reduction to 75% for !
circulating water system condenser water box cleaning and intake heat treat. !
I 2145 Reactor at 75%, 792 MWe.
April 07 0200 All clocks adjusted one he'2r forward for Pacific daylight saving time 1730 Commenced power increase to 80% in preparation for heat treatment of circulating water system intake. l 1
1930 Unit at 80% reactor power, 906 MWe. l April 08 0104 Lowered reactor power to 78% and commenced 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> heat treat at 96 "F due to condenser vacuum limits.
1115 Commenced power increase to full load following completion of heat treatment.
1645 Reactor at 99.2%, 1117 MWe.
! April 29 2400 Mode 1, Reactor at 99.2%, 1117 MWe.
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REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Mav 14, 1996 COMPLETED BY: C. E. Williams TELEPHONE: f714) 368-6707 1
MONTH: Acril 1996
- 1. Scheduled date for next refueling shutdown.
Cycle 9 refueling outage is forecast for April 5, 1997.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 9 refueling outage is-forecast for June 9, 1997.
- 3. Will refueling or resumption of operation thereafter require a l Technical Specification change or other license amendment?
Unknown at this time.
l What will these be?
Unknown at this time.
- 4. Scheduled date for submitting proposed licensing action and supporting information.
Unknown at this time.
- 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.
Unknown at this time.
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REFUELING INFORMATION I DOCKET NO: 50-362 UNIT NAME: SONGS - 3 :
DATE: Mav 14. 1996 COMPLETED BY: C. E. Williamm TELEPHONE: (714) 368-6707
- 6. The number of fuel assemblies.
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A. In the core. 217 B. In the spent fuel storage pool. 818 Total Fuel Assemblies 700 Unit 3 Soent Fuel Assemblies O Unit 3 New Puel Assemblies !
118 Unit 1 Scent Fuel Assemblies C. In the New Puel Storage Racks Zero Unit 3 New Fuel Assemblies
- 7. Licensed spent fuel storage capacity. 1142 Intended change in spent fuel storage capacity. 'None, !
- 8. Projected date of last' refueling that can be discharged to spent fuel l storage pool assuming present capacity.
November 2003 (full off-load capability assuming current fuel loading for all future cycles, and unit 1 fuel remains where it is currently-located).
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