ML20078P411

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Monthly Operating Repts for Jan 1995 for San Onofre Nuclear Generating Station Units 2 & 3
ML20078P411
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 01/31/1995
From: Kaplan R, Marsh W
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9502170056
Download: ML20078P411 (13)
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Southem Califomia Edison Company 23 PARKEFI BTRE ET IRVINE, CALIFOF4NIA 92718 waaen e uxnss February 14, 1995 m-.

fAANAC4f R OF NUCL E Art ne r5ULA TORY AFP' AIRS (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 January 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 (0DCM); 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.

l This letter transmits the January 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 rattioactive waste treatment systems during the reporting period.

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

Sincerely,  !

M l

Enclosures 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 4

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9502170056 950131 PDR R ADOCK 05000361 PDR pl '8

1 NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: February 14. 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station. Unit 2
2. Reporting Period: January 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 744.00 744.00 100.441.00
12. Number Of Hours Reactor Was Critical 744.00 744.00 77.518.59
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 744.00 744.00 76.375.34
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.359.616.90 2.359.616.90 249.737.472.74
17. Gross Electrical Energy Generated (MWH) 816.118.00 __816.118.00 84.667.617.50
18. Net Electrical Energy Generated (MWH) 777.211.00 777.211.00 80.341.305.88
19. Unit Service Factor 100.00% 100.00% 76.04%
20. Unit Availability Factor 100.00% 100.00% 76.04%
21. Unit Capacity Factor (Using MDC Net) 97.63% 97.63% 74.76%
22. Unit Capacity Factor (Using DER Net) 97.63% 97.63% 74.76%
23. Unit Forced Outage Rate 0.00% 0.00% 5.45%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling Shutdown. February 11. 1995. 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

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. l AVERAGE DAILY UNIT POWER LEVEL

. DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: February 14. 1995 COMPLETED 8Y: R. L. KaDlan TELEPHONE: (714) 368-6223 MONTH: January 1995 DAY AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1074.79 16 1076.67 2 1074.33 17 1076.67 3 1073.75 18 1076.08 4 4 1073.21 19 1075.92 5 908.96 20 1075.58 6 822.67 21 1077.13 7 819.33 22 1077.04 8 818.50 23 1077.42 9 1060.92 24 1076.83 10 1076.71 25 1076.71  ;

11 1077.46 26 1074.75 12 1077.29 27 1072.96 13 1075.25 28 1074.25 14 1061.67 29 1075.67 l 15 1076.42 30 1075.21 l

31 1073.67 l

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET-NO: 50-361 UNIT NAME: SONGS - 2 -

REPORT MONTH: January 1995 DATE: February 14. 1995

  • COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type l (Hours) Reason 2 Reactor' No. Code' Code' Prevent Recurrence l

There were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% this reporting period.

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'F-Forced ' Reason: 3 Method: 'IEEE Std 805-1984 S-Scheduled A-Equipnent Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. S 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 dcy 6-Other (Explain)

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T

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH

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DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: February 14. 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223 Date Time Event January 01 0001 Unit is in Mode 1, 97.7% reactor power, 1123 MWe.

January 05 0100 Commenced reducing reactor power to 75% to bump all circulating water pumps due to rising waterbox delta P's.

0300 Unit at 74% reactor power to bump circulating water pumps.

0550 Commenced raising reactor power to full load after bumping circulating water pumps.

0845 Unit is at 93% reactor power.

1533 Commenced r;Jucing reactor power to 75% and remain at this level throughout the weekend at management discretion to facilitate waterbox cleaning and circulating water pump bumping.

1920 Unit at 75% reactor power, 853 MWe.

January 08 2255 Commenced raising reactor power to full load at completion of circulating water pump bumping.

January 09 0300 Unit at 98% reactor power, 1130 MWe.

January 31 2400 Unit is in Mode 1, 98% reactor power, 1120 MWe.

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. REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: February 14. 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223 MONTH: January 1995

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 has been requested to revise the allowed Linear Heat Transfer Rate from 13.9 to 13.0 kw/ft.

] C. A proposed change to the Technical Specifications, revising the automatic

reset of the low pressurizer pressure bypass, has been revised to 1

simplify the request.

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. REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: February 14. 1995 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6223

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

A. Refueling Cavity Water Level Revision submitted January 30, 1995

8. Linear Heat Rate Submitted September 16, 1994 C. Low Pressurizer Pressure Bypass Revision submitted September 6, 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.

A. In the core. 217 B. In the spent fuel storage pool. 770 Total Fuel Assemblies 592 Unit 2 Spent Fuel Assemblies 108 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 l

Intended change in spent fuel storage capacity. None  !

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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)  !

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NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 DOCKET NO: 50-362 l UNIT NAME: SONGS - 3 l DATE: February 14. 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223 OPERATING STATUS l

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3 l
2. Reporting Period: January 1995 '
3. Licensed Thermal Power (MWt): 3390  ;
4. Nameplate Rating (Gross MWe): 1127  ;
5. Design Electrical Rating (Net MWe): 1080 l
6. Maximum Dependable Capacity (Gross MWe): 1127 1
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 >

Yr.-to-Date This Month Cumulative

11. Hours In Reporting Period 744.00 744.00 94.992.00 l
12. Number Of Hours Reactor Was Critical 744.00 744.00 75.430.45 '
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00  !
14. Hours Generator On-Line 744.00 744.00 73.787.49
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 ,
16. Gross Thermal Energy Generated (MWH) 2.359.461.24 2.359.461.24 237.507.507.24
17. Gross Electrical Energy Generated (MWH) 820.203.50 820,203.50 80.652.880.00 '
18. Net Electrical Energy Generated (MWH) 777.878.00 777.878.00 76.218.788.94
19. Unit Service Factor 100.00% 100.00% 77.68% l
20. Unit Availability Factor 100.00% 100.00% 77.68% l
21. Lait Capacity Factor (Using MDC Net) 96.81% 96.81% 74.29% i
22. Unit Capacity Factor (Using DER Net) 96.81% 96.81% 74.29% l
23. Unit Forced Outage Rate 0.00% 0.00% 6.05% l
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuelina Shutdown. July 8. 1995. Duration (66 days) 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 COMERCIAL OPERATION NA NA I

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. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: February 14. 1995 COMPLETED BY: R. L. KaDlan l TELEPHONE: (714) 368-6223 I

MONTH: January 1995  !

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL '

(MWe-Net) (MWe-Net) ,

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1 812.08 16 1062.13 i 2 1041.58 17 1062.54  !

3 1065.67 18 1063.33 4 1066.17 19 1063.58 l

5 1066.13 20 1063.83 6 1066.21 21 1053.54 I 7 1066.04 22 1063.33 l 8 1066.29 23 1062.71 j 9 1065.79 24 1062.79 10 1065.00 25 1062.04 I

11 1063.58 26 1061.04

.l 12 __ 1064.04 27 1050.42 13 1064.88 28 813.88 ___

14 1064.38 29 1037.13 __ l 15 1062.29 30 1064.42 l 31 1064.75 t

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: January 1995 DATE: February 14. 1995 .

COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type l (Hours) Reason 2 Reactor 3 No. Code' Code 5

Prevent Recurrence 84 950101 S 0.0 B 5 NA KE COND Reduce reactor power to perform condenser waterbox cleaning.

85 950128 S 0.0 B 5 NA KE COND Reduced reactor power for t circulating water pump maintenance.

3 2

F-Forced ' Reason: Method: "IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. S 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

)

o

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-362 ,

UNIT NAME: SONGS - 3 )

DATE: February 14. 1995 1 COMPLETED BY: R. L. Kaplan  !

TELEPHONE: (714) 368-6223 i Date Time Event January 01 0001 Unit is.in Mode 1, 97% reactor power, 1110 Mwe.

0039 Commenced reducing reactor power to perform Isothermal Temperature Coefficient test. l 0110 Commenced reducing reactor power from 92.3% at I completion of the Isothermal Temperature

  • Coefficient test to 80% for circulating water i system heat treatment.

0235 Unit at 80% reactor power, 905 MWe.

1445 Reactor power reduced to 75% power to perform condenser waterbox cleaning.

January 02 0105 Commenced raising reactor power to full load at i completion of waterbox cleaning and circulating water system heat treatment.  !

0410 Unit at 97.2% reactor power, 1116 MWe.  :

January 27 2137 Commenced reducing reactor power to 80% for i circulating water system heat treatment.

2330 Unit at 80% reactor power.

)

January 28 1320 Commenced reducing reactor power to 75% to bump I circulating water pump. l January 29 0115 Commenced raising reactor power to 97% after completion of circulating water system heat treatment and circulating water pump maintenance.

0445 Unit at 97% reactor power, 1108 MWe.

January 31 2400 Unit is in Mode 1, 96.8% reactor power, 1111 MWe.

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. REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: February 14. 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223 MONTH: January 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 11, 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.

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

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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.. REFUELING INFORMATION DOCKET N0: 50-362  !

UNIT NAME: SONGS - 3 DATE: February 14. 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6223

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 -

Zero Unit 3 New Fuel Assemblies l 118 Unit 1 Spent Fuel Assemblies j

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).

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