ML20080C974

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Monthly Operating Repts for Nov 1994 for SONGS Units 2 & 3
ML20080C974
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 11/30/1994
From: Kaplan R, Marsh W
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9412220117
Download: ML20080C974 (13)
v • d • e


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. /S5 Southem Califomia Edison Company 23 PARKER STREET IRVtNE. CALIFORNIA 92718 WALTER C. MARSH TELE PHONE MQfeAGER OF PeuCLE AR REOULATORY AFFAIRS (714) 484-4403 U. S. Nuclear Regulatory Comission Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 Monthly Operating Reports for November 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 within 90 days from the time the changes are effective.

This letter transmits the November 1994 Monthly Operating Reports for Units 2 l and 3, respectively. There were no challenges to safety valves, and no major j 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, MO I

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 H. B. Fields, NRC Project Manager, Units 2 and 3 J. A. Sloan, Senior NRC Resident Inspector, San Onofre Units 1, 2 & 3 1

f 9412220117 941130 h '*

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NRC MONTNLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2

! DOCKET N0: 50-361 l UNIT NAME: SONGS - 2 l DATE: December 14. 1994 l COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 2
2. Reporting Period: November 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 8.016.00 98.953.00
12. Number Of Hours Reactor Was Critical 720.00 8.016.00 76.030.5_2

! 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00 l 14. Hours Generator On-Line 720.00 8.016.00 74.887.34

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.359.616.90 26.281.250.30 244.855.506.74
17. Gross Electrical Energy Generated (MWH) 810.086.50 8.928.641.50 83.016.429.50
18. Net Electrical Energy Generated (MWH) 774.265.00 8.511.659.00 78.766.357.88
19. Unit Service Factor 100.00% 100.00% 75.68%
20. Unit Availability Factor 100.00% 100.00% 75.68%
21. Unit Capacity Factor (Using MDC Net) 100.50% 99.24% 74.39% i
22. Unit Capacity Factor (Using DER Net) 100.50% 99.24% 74.39%
23. Unit Forced Outage Rate 0.00% 0.00% 5.55% l
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

l Refuelina 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 COMERCIAL OPERATION NA NA

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AVERAGE DAILY UNIT POWER LEVEL DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: December 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834 MONTH: November 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1074.33 16 1075.71 2 1071.67 17 1078.42 3 1072.17 18 1068.96 4 1072.75 19 1080.42 5 1065.29 20 1079.13 6 1074.08 21 1077.46 7 1073.13 22 1075.96 8 1073.83 23 1078.04 i

9 1074.88 24 1077.29 10 1075.63 25 1075.92 11 1075.58 26 1075.96 12 1075.96 27 1077.33 l 13 1075.54 28 1077.25 l

14 1075.13 29 1078.46 l 15 1075.75 30 1079.04 l

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

REPORT MONTH: November 1994 DATE: December 14. 1994 -

COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 .

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

, 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: ' 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

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-361

UNIT NAME
SONGS - 2 l

, DATE: December 14. 1994 l COMPLETFD BY: R. L. Kaplan TELEPHONE: (714) 368-6834 i

Date Time Event j November 01 0001 Unit is in Mode 1, 98% reactor power,1121 MWe.

November 30 2400 Unit is in Mode 1, 98% reactor power, 1123 MWe.

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REFUELING INFORMATION i DOCKET NO: 50-361 l UNIT NAME: SONGS - 2 l DATE: December 14. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: November 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?

l 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 Rate from 13.9 to 13.0 kw/ft.

C. A proposed change to the Final Safety Analysis has been requested to remove the diversity requirement of the pressurizer pressure tran.mitters providing input to the shutdown cooling open permissive interlock. l D. Proposed change to the Technical Specifications (PCN 431), revising the automatic reset of the low pressurizer pressure bypass, has been revised

! to simplify the request.

I E. 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 l l

DOCKET N0: 50-361 l UNIT NAME: SONGS - 2 l DATE: December 14. 1994 i l COMPLETED BY: R. L. KaDlan j l

TELEPHONE: (714) 368-6834 j

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

i A. Refueling Cavity Water Level Submitted July 28, 1994 l

! B. Linear Heat Rate Submitted September 16, 1994 l l C. Pressure Instrument Diversity Submitted July 6, 1994 1 l D. Low Pressurizer Pressure Bypt.n Revision submitted September 6, 1994 l

E. Control Room Air Cleanup System Submitted August 26, 1994 l

5. Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfonnance 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. 662 Total Fuel Assemblies 592 Unit 2 SDent Fuel Assemblies 0 Unit 2 New Fuel Assemblies 70 Unit 1 SDent Fuel Assemblies C. In the New Fuel Storage Racks 48 Unit 2 New Fuel Assemblies

7. Licensed spent fuel storage capacity. 1542 l

Intended change in spent fuel storage capacity. None j

8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

Approximately 2005 (full off-load capability) 1 1

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l NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 DOCKET N0: 50-362 UNIT NAME: SONGS - 3 DATE: December 14. 1994 COMPLETED BY: R. L. Kaplan l TELEPHONE: (714) 368-6834 i

OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatino Station. Unit 3
2. Reporting Period: November 1994
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
7. Maximum Dependable Capacity (Net HWe): 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 l

i This Month Yr.-to-Date Cumulative 1

11. Hours In Reporting Period 720.00 8.016.00 93.504.00
12. Number Of Hours Reactor Was Critical 720.00 8.016.00 73.942.45
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 720.00 8.002.60 72.299.49 l 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 1
16. Gross Therml Energy Generated (MWH) 2.359.461.23 26.035.434.32 232.707.224.03
17. Gross E' '1 Energy Generated (MWH) 799.606.00 8.856.330.00 78.999.737.00
18. Net Ele il Lnergy Generated (MWH) 759.214.00 8.388.235.00 74.651.273.94
19. Unit S(,, ne Factor 100.00% 99.83% 77.32%
20. Unit Availability Factor 100.00% 99.83% 77.32%
21. UnitCapacityFactor(UsingMDCNet) 97.64% 96.89% 73.92%
22. Unit Capacity Factor (Using DER Net) 97.64% 96.89% 73.92%
23. Unit Forced Outage Rate 0.00% 0.00% 6.17%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

l None l 25. If Shutdown At End Of Report Period, Estimated Date of Startup: NA Units In Test Status (Prior To Commercial Operation): Forecast

26. Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA C0044ERCIAL OPERATION NA NA l

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AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: December 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834 MONTH: November 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I (MWe-Net) (MWe-Net) 1 l

1 1060.00 16 1064.00 2 1058.38 17 1065.17 3 1058.25 18 1064.08 4 1057.88 19 1064.42 5 828.54 20 1065.29 6 1056.21 21 1065.75 7 1061.67 22 1065.71 8 1062.83 23 1065.25 9 1065.00 24 1064.75 l

10 1064.38 25 1061.33 l 11 1057.33 26 1046.29 12 1063.79 27 1064.67 l

l 13 1063.21 28 1064.96 14 1063.42 29 1C53.63 15 1063.67 30 1064.08 l

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-362

  • UNIT NAME: SONGS - 3 REPORT MONTH: November 1994 DATE: December 14. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 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 83 941105 s 0.0 B 5 N/A KE COND Reduce reactor power to perform circulating water system heat treatment and circulating pump maintenance.

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'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) 3

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1 SUMARY OF OPERATING EXPERIENCE FOR THE MONTH l

DOCKET N0: 50-362 UNIT NAME: SONGS - 3 DATE: December 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834 Date Time Event November 01 0001 Unit is in Mode 1, 97% reactor power, 1107 Mwe.

November 05 0130 Commenced reducing reactor power to 80% for circulating water system heat treatment.

l 0317 Unit at 80% reactor power, 850 MW for circulating water system heat treatment.

! 1131 Commenced reducing reactor power to 75% for circulating water system pump maintenance.

l 1230 Unit at 75% reactor power, 814 MW for circulating water system pump maintenance.

2111 Commenced increasing power to 97% from 75% after completion of circulating water system heat treatment and circulating pump maintenance.

November 6 0200 Unit at 97% reactor power, 1108 MW.

November 30 2400 Unit is in Mode 1, 97% reactor power,1110 MWe.

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REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: December 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834 HONTH: November 1994 l

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.

l 3. Will refueling or resumption of operation thereafter require a Technical l

Specification change or other license amendment?

Unknown at this time for Cycle 8 refueling.

What will these be?

NA

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

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l REFUELING INFORMATION l DOCKET N0: 50-362 UNIT NAME: SONGS - 3 DATE: December 14. 1994 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 SDent 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 l

pool assuming present capacity.

I Approximately 2003 (full off-load capability).

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