ML20086L429

Monthly Operating Repts for June 1995 for Songs,Units 2 & 3

ML20086L429
Person / Time
Site:	San Onofre
Issue date:	06/30/1995
From:	Darling J, Marsh W SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9507210192
Download: ML20086L429 (14)

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l Southem Califomia Edison Company P O. BOX 128 SAN CLEMENTE, CALIFOHNIA92674-0128

. l WALTER C. MARSH July 14, 1995 ,m _  !

1 MANAO,H OF faJrXF AM RPOULATOHY AFF AIMS (714)366-7601 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 June 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, +

requirer 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 (00CM); 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 June 1995 Monthly Operating Reports for Units 2 and i 3, respectively. -There were no challenges to safety val es, and no major  ;

, changes to the Units 2 and 3 radioactive waste treatment systems during the i reporting period.

If you require any additional information, please let me know.

Sincerely, l

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l Enclostres cc: L. J. Callan, Regional Administrator, NRC Region IV  !

J. E. Dyer, Director, Division of Reactor Projects, NRC' Region IV i 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  !

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NRC NONTHLY OPERATING REPORT SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET N0: 50-361 .

UNIT NAME: SONGS - 2 l DATE: July 14. 1995 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6834 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 2

2. Reporting Period: June 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 l

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720.00 4.343.00 104.040.00

12. Number Of Hours Reactor Was Critical 720.00 2.377.40 79.151.99

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 631.72 1.815.32 77.446.sh

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00  ;

16. Gross Thermal Energy Generated (MWH) 2.013.810.98 5.589.851.07 252.967.706.92 j

17. Gross Electrical Energy Generated (MWH) 679.188.50 1.866.190.00 85.717.689.50 j

18. Net Electrical Energy Generated (MWH) 643.083.00 1.729.103.04 81.293.197.91 '

19. Unit Service Factor 87.74% 41.80% 74.44%

20. Unit Availability Factor 87.74% 41.80% 74.44%

21. Unit Capacity Factor (Using MDC Net) 83.47% 37.21% 73.02%

22. Unit Capacity Factor (Using DER Net) 83.47% 37.21% 73.02%

23. Unit Forced Outage Rate 12.26% 4.64% 5.48%

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:

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 1

i AVERAGE DAILY UNIT POWER LEVEL DOCKET N0: 50-361 i UNIT NAME: SONGS - 2 DATE: July 14.1995 COMPLETED BY: J. L. Darlina .

TELEPHONE: (714) 368-6223 i MONTH: June 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL -

(MWe-Net) (MWe-Net)

-1 1141.92 16 1096.00 ,

2 1026.00 17 1097.21 3 673.83 18 1100.58 4 662.67 19 1102.21 5 933.29 20 1099.42 ,

6 1094.25 21 1099.42 7 1094.25 22 1097.88 8 1093.54 23 1097.29 9 1041.33 24 1098.63 10 0.00 .25 1098.13 ,

11 0.00 26 1097.33 ,

12 0.00 27 1095.25 13 0.00 28 1097.92  ;

14 666.50 29 1099.00

'15 1088.88 30 1040.54 ,

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-361 UNIT NAME: SONGS - 2 REPORT MONTH: June 1995 DATE: July 14. 1995 - .

COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223

• Method of Shutting Cause & Corrective Duration Down LER System Component Action to s

No. Date Type (Hours) Reason

• Reactor 3 No. Code' Code Prevent Recurrence 89 950603 S 0.0 H 5 NA NA NA Unit load was reduced at the request of Edison Energy Control Center to support distribution system load requirements 90 950610 F 88.28 B 5 NA TC PSF Turbine generator was removed from service to repair a crack in a gland steam pipe flange.

The reactor was maintained critical during this turbine generator outage.

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'F-Forced ' Reason: Method: *IEEE Std 805-1984 4 S-Scheduled A-Equipment Failure (Explain) 1-Manual 2 B-Maintenance or Test 2-Manual Scram. S IEEE Std 803A-1983 j C-Refueling 3-Automatic Scram. c D-Regulatory Restriction 4-Continuation from  ?

E-Operator Training & License Examination Previous Month a 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 a 6-Other (Explain) d5

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: _Aq1v 14, 1995 COMPLETED BY: J. L. Darlinu TELEPHONE: (714) 368-6223 Dat_e Time Event June 01 0001 Unit is in Mode 1, 99% power 1144 MWe.

June 02 1940 Commenced power reduction to 65% to support Edison system load requirements.

2255 Completed power reduction to 65%.

June 05 0300 Commenced raising reactor power to meet system load demands.

1634 Unit returned to full load 98.6%, 1142 MWe.

June 09 2045 Commenced reactor power reduction to remove turbine from service to repair a non-isolable steam leak on the high pressure turbine gland steam supply system.

June 10 0223 Main turbine manually tripped at 22% reactor power per procedure.

0314 Entered Mode 2.

June 13 1215 Commenced reactor power increase.

1304 Entered Mode 1.

1530 Reactor power at 16.5%

1840 Unit Synchronized to grid at 60 MWe, after completion of repairs to gland steam supply system.

June 14 0200 Commenced raising reactor power to full power.

2040 ' Reactor increase stopped at 93% to perform excore instrumentation calibration.

2355 Commenced Reactor power increase to full power after completions of excore instrumentation calibration.

June 15 0300 Reactor power at 98.5%, 1140 MWe.

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH-DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: July 14.1995 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 Qitt_q Time Event June 30 2048 Turbine load reduced to 1035 MWe to support main turbine stop and governor valve testing.

June 30 2400 Unit is in Mode 1, 99.8% reactor power, 1043 MWe.

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REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: July 14. 1995 COMPLETED BY: J. 1. Darlina

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TELEPHONE: (714) 368-6223 l

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6. The number of fuel assemblies.

A. In the core. 217 B. In the spent fuel storage pool. 818 Total Fuel Assemblies 592 Unit 3 Spent Fuel Assemblies 108 Unit 3 New Fuel Assemblies 118 Unit 1 Spent Fuel Assemblies C. In the New Fuel Storage Racks Unit 3 New Fuel Assemblies 1

7. Licensed spent fuel storage capacity. 1542 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 2003 (full off-load capability). )

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REFUELING INFORMATION DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: July 14. 1995 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 ,

6. The number of fuel assemblies.

A. In the core. 217

8. In the spent fuel storage pool. 770 Total fuel Assemblies 10_0 linit 2 Spent Fuel Assemblies 0 Unit 2 New Fuel Assemblies 70 Unit 1 Spent 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 S. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

Approximately 2005 (full off-load capability) i i

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NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 DOCKET N0: 50-362 UNIT NAME: SONGS - 3 DATE: July 14. 1995 COMPLETED BY: J. L. Darlina i TELEPHONE: (714) 368-6223 i

OPERATING STATUS I

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3

2. Reporting Period: June 1995

3. Licensed Thermal Power (MWt): 3390

4. Nameplate Rating (Gross MWe): 1127  ;

5. Design Electrical Rating (Net MWe): 1080 4

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 720.00 4.343.00 98.591.00

12. Number Of Hours Reactor Was Critical 720.00 4.343.00 79.029.45.

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 720.00 4.343.00 77.386.49

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 2.278.250.80 14.075.718.01 249.223.764,00

17. Gross Electrical Energy Generated (MWH) 761.621.00 4.770.091.50 84,602.768.00

18. Net Electrical Energy Generated (MWH) 722.041.00 4.522.043.00 79.962.953.94

19. Unit Service factor 100.00% 100.00% 78.49%

20. Unit Availability Factor 100.00% 100.00% 78.49%

21. Unit Capacity Factor (Using MDC Net) 92.86% 96.41% 75.10%

22. Unit Capacity Factor (Using DER Net) 92.86% 96.41% 75.10%

23. Unit Forced Outage Rate 0.00% 0.00% 5.79%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of- Each):

Refuelina Shutdown. July 22, 1995. Duration (76 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

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: July 14. 1995 COMPLETED BY: J. L. Darlina TELEPHONE: (7141 368-6223 MONTH: June 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1080.63 16 1043.29 2 1035.46 17 815.42 3 1034.08 18 756.13 4 1036.96 19 830.17 5 1036.96 20 1055.75 6 1047.79 21 1058.96 7 1049.58 22 1058.04_

8 1048.96 23 1057.58 9 1052.42 24 1058.08 10 1054.08 25 1054.75 11 1053.13 26 1040.08 12 1049.33 27 761.71 13 1048.13 28 757.08 14 1047.08 29 995.96 15 1047.63 30 1019,83 2

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: June 1995 DATE: July 14. 1995 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to 2 s No. Date Type 2 (Hours) Reason Reactor 3 No. Code' Code Prevent Recurrence 86 950617 S 0.0 8 5 NA KE COND Circulating water system heat treat.

87 950627 5 0.0 B 5 NA KE COND Condenser water box cleaning 2 3 1

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) 3 L

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-362 UNIT NAME: SONGS - 3 t

DATE: July 14. 1995 l COMPLETED BY: J. L. Darlina l TELEPHONE: (714) 368-6223 Date Time Event June 01 0001 Unit is in Mode 1, 96.3% reactor power, 1091 MWe, June 16 2200 Connenced reactor power reduction in preparation for circulating water system heat treat.

June 17 0135 Unit at 80% reactor power, for heat treat.

2112 Commenced reactor power reduction to 75% to perform cleaning condenser waterboxes.

2200 Reactor power at 75.5% reactor power, 830 MWe.

June 19 1605 Commenced reactor power increase to full power following completion of waterbox cleaning.

June 20 2400 Reactor power at 98% reactor power, 1110 MWe.

June 26 2100 Commenced reactor power decrease to 75% reactor power to perform condenser waterbox cleaning.

June 27 0450 Reactor power at 75% reactor power, 780 MWe.

29 0340 Commenced raising reactor power to full power following completion of waterbox cleaning.

1040 Unit at full load 97.7% reactor power,1110 MWe.

June 30 2400 Unit is in Mode 1, 98.1% reactor power, 1091 MWe.

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j REFUELING INFORMATION  ;

DOCKET N0: 50-362 UNIT NAME: SONGS - 3 DATE: July 14. 1995 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 MONTH: June 1995

1. Scheduled date for next refueling shutdown.

Cycle 8 refueling outage is forecast for July 22, 1995.

2. Scheduled date for restart following refueling.

Restart from Cycle 8 refueling outage is forecast for October 5, 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.

4. Scheduled date for submitting proposed licensing action and supporting information.

i 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 ,

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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.l REFUELING INFORMATION .

DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: July 14. 1995

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COMPLETED BY: J. L. Darlino TELEPHONE: (714) 368-6223 j i

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6. The number of fuel assemblies.

. A. In the core. 217

. B. In the spent fuel storage pool. 818 Total Fuel Assemblies  !

592 Unit 3 Spent Fuel Assemblies 108 Unit 3 New Fuel Assemblies 118 Unit 1 Spent Fuel Assemblies l

C. In the New Fuel Storage Racks Zero Unit 3 New Fuel Assemblies 4

7. Licensed spent fuel storage capacity. 1542 ,

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.  ;

Approximately 2003 (full off-load capability).

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