ML20087K701

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Monthly Operating Repts for Jul 1995 for San Onofre Nuclear Generating Station Units 2 & 3
ML20087K701
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 07/31/1995
From: Kaplan R, Marsh W
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9508240106
Download: ML20087K701 (13)
v • d • e


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Southem Califomia Edison Company P. O. BOX 128 SAN CLEMCidTE, CALWORNIA02674 4128 witusc uAnsa August 15, 1995 m . ,,,m MANAGF,4 CW NUCt F AF1941 GULATOHf A,, AmS (714) 308 7%O1 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 July 1995 San Onofre Nuclear Generating Station, Units 2 and 3 Techr;ical 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 (ODCM); 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 July 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 radioactive waste treatment systems during the reporting period.

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

Sincerely, 0

Enclosures cc: L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, 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 2 & 3 e

c .es m n.tU3D 9508240106 950731 PDR / I R ADOCK 05000361  ! k PDR 1

  • ,z NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING f,TATION,' UNIT 2 _

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DOCKET NO: 50-361 -'-

UNIT NAME: SONGS' 2 DATE:- August 15, 1995 2

COMPLETED BY: 'R. L. Kaplan .

TELEPHONE: (714) 368-6834-y OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 2
2. Reporting Period: July 1995
3. Licensed Thermal Power (MWt): 3390
4. Nameplate Rating (Gross MWe): 1127
5. Design Electrical Rating (Net MWe): 1070 .. J
6. Maximum Dependable' Capacity (Gross MWe) : 1127 l
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 5,087.00 104,784.00
12. Number Of Hours Reactor Was Critical- 744.00 3,121.40 79,895.99 j
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 744.00 2,559.32 78,190.66
15. Unit Reserve Shutdown Hours 0.00 0.00- 0.00
16. Gross Thermal Energy. Generated (MWH) 2,497,939.27 8,087,790.34 255,465,646.19
17. Gross Electrical Energy Generated (MWH) 852,799.00 2,718,989.00 86,570,488.50
18. Net Electrical Energy Generated .(MWH) 813,752.00 2,542,855.04 82,106,949.91

' 19 . Unit Service Factor 100.00% 50.31% 74.62%

20. Unit Availability Factor 100.00% 50.31% 74.62%

j' 21. Unit Capacity Factor - (Using MDC. Net) 102.22% 46.72% 73.23%

73.23%

22. Unit Capacity Factor (Using DER Net) 102.22% 46.72%'
23. Unit Forced Outage Rate 0.00% 3.33%- <

5.43%

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

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COtedERCIAL OPERATION NA- NA-1

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AVERAGE DAILY UNIT POWER LEVEL l s DOCKET NO: 50-361 ,

UNIT NAME: SONGS - 2 i DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: July 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1138.54 16 1028.17 2 1096.08 17 1096.96 3 1098.00 18 1102.63 4 1098.29 19 1106.04 5 1101.38 20 1104.33 6 1102.71 21 1103.58 7 1101.08 22 1101.96 8 1102.75 23 1104.96 9 1102.63 24 1100.58 10 1103.21 25 1095.25 11 1105.25 26 1097.29 12 1104.71 27 1097.96 13 1101.29 28 1094.96 14 1098.13 29 1069.38 15 1005.92 30 1093.29 31 1049.04 2

UNIT CHUTDOWN3 AND POWER REDUCTION 3 DOCKET NO: 50'-361-  ;

UNIT NAME: SONGS - 2 REPORT MONTH: July 1995 DATE: August 15, 1995 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 8 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.

2 F-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 (Explain) 3 s

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH i DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 Date Time Event July 01 0001 Unit is in Mode 1, 99.8% reactor power, 1043 MWe.

0105 Commenced turbine load increase to full load after completing turbine valve testing.

July 15 1530 Commenced reducing reactor power to 80% for circulating water system heat treatment.

1830 Unit at 80% reactor power for circulating water system heat treatment.

July 16 0450 Circulating. Water System Heat Treatment complete. Commenced raising reactor power.

July 16 0850 Unit at full load, reactor power 99.3%, 1145 MWe.

July 31 2400 Unit is in Mode 1, reactor power 99.7%, 1146 MWe.

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'* REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: July 1995

1. Scheduled date for next refueling shutdown.

Cycle 9 refueling outage is forecast for November 1996.

2. Scheduled date for restart following refueling.

Restart from Cycle 9 refueling outage is forecast for January 1997.

3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Unknown at this time.

What will these be?

Unknown at this time.

4. Scheduled date for submitting proposed licensing action and cupporting 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 DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 t
6. The number of fuel assemblies.

A. In the core. 217 I

B. In the spent fuel storage pool. 770 Total Fuel Assemblies 700 Unit 2 Spent Fuel Assemblies j 0 Unit 2 New Fuel Assemblies {

__ 70 Unit 1 Spent Fuel Assemblies j I

C. In the New Fuel Storage Racks Zero Unit 2 New Fuel Assemblies l

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l l 7. Licensed spent fuel storage capacity. 1542 l

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. I Approximately 2005 (full off-load capability) 1 1

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NRC MONTHLT OPERATING REPORT.' ,

SAN ONOFRE NUCLEAR GENERATING ~OTATION,. UNIT 3 -

DOCKET NO: 50-352 .

UNIT NAME: SONGS - 3 .

DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 T OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3
2. Reporting Period: July 1995
3. Licensed Thermal Power (MWt) : '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
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 5,087.00- 99,335.00
12. Number Of Hours Reactor Was' Critical 504.57 4,847.57 79,534.02
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 504.45 4,847.45 77,890.94
15. Unit Reserve Shutdown Hours" 0.00 0.00 0.00
16. Gross Thermal Energy.. Generated (MWH) 1,627,322.00 15,703,040.01 250,851,086.00
17. Gross Electrical Energy Generated (MWH) 553,826.50 5,323,918.00 85,156,594.50 _
18. Net Electrical Energy Generated (MWH) 523,515.30 5,045,558.30 80,486,469.24
19. Unit Service Factor 67.80% 95.29% 78.41%'
20. Unit Availability..-Factor 67.80%. 95.29% 78.41%
21. Unit Capacity Factor .(Using MDC Net) 65.15% 91.84%- 75.02%
22. Unit Capacity Factor (Using DER Net) 65.15% 91.84% 75.02%
23. Unit Forced Outage Rate 0.00% -0.00% 5.75%.
24. Shutdowns Scheduled'Over Next 6 Months (Type, Date, and Duration of Each):

Refueling 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 CODGERCIAL OPERATION NA -NA-1

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: July 1995 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL '

(MWe-Net) (MWe-Net)

1. 1108.79 16 1044.33 2 1062.38 17 1040.92 3 1059.71 18 1043.33 4 1058.04 19 1045.08 5 1061.71 20 1025.92 6 1065.25 21 734.92 7 1064.29 22 0.00 8 1063.38 23 0.00 9 1063.38 24 0.00 10 1065.46 25 0.00 11 1066.83 26 0.00 12 1066.17 27 0.00 13 1065.21 28 0.00 14 1059.63 29 0.00 15 1056.29 30 0.00 31 0.00 2

UNIT tHUTDOWN3 AND POWER REDUCTION 3- DOCh1!:T NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: July 1995 DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan

  • TELEPHONE: (714) 36826834 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 88 950721 S 139.55 C 1 N/A N/A N/A N/A Note Power reduction for unit shutdown began on July 21, at 2132. The unit was taken off line on July 22 at 0027, which is the time used to calculate shutdown duration.

2F-Forced 2 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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.SUttdARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET No: 50-362 .!

UNIT NAME: SONGS DATE: August 15, 1995 l

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

.1 Date' Time ~ Eveny  ;

July 01 0001 Unit is in Mode 1,' reactor power 98.1%, 1115 )

MWe j 20 1655 Commenced reducing reactor power to 79%:forz

-July-

. circulating water., system' heat treatment and tol reset Hi Linear Power' Trip setpoints.for Main.  ;

Steam Safety Valve Testing. .

i July 21 0408 Unit at 79% reactor power for. circulating ~ water' -

system heat treatment. -:

1555 Commenced reducing reactor power to 75%-power' '

for circulating water pump maintenance.

1800 Unit at 75% reactor power, 834lMWe.

2132 Commenced-reducing reactor' power for Cycle 8 Refueling Outage.

July 22 0027 Main Turbine removed-from service, commenced Unit 3 Cycle 8 refueling outage.

0034 Unit 3 Reactor Trip Breakers open at.17% power in accordance with procedure, entering Mode.3.

July '23 0315 Unit entere'd Mode 4.

July 24 0405 Unit entered Mode 5, Tcold less than 200--

degrees.

2130 All reactor coolant pumps stopped.

July 29 1153 Unit entered Mode 6, one reactor vessel head stud detensioned.

July 31 2400 Unit is in Mode.6, Cycle 8. Refueling Outage in progress.

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i-REFUELING INFORMATION DOCKET NO: 50-362 l UNIT NAME: SONGS - 3 DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: July 1995

1. Scheduled date for next refueling shutdown.

Cycle 8 refueling outage began 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 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.

A. 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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  • i REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: August 15, 1995 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 s
6. The number of fuel assemblies. r 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 Zero Unit 3 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.

Approximately 2003 (full off-load capability).

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