ML20076G423

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Monthly Operating Repts for Sept 1994 for SONGS
ML20076G423
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 09/30/1994
From: Kaplan R
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20076G421 List:
References
NUDOCS 9410190318
Download: ML20076G423 (12)


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. NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: October 14. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatino Station. Unit 2
2. Reporting Period: September 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 6.551.00 97.488.00
12. Number Of Hours Reactor Was Critical 720.00 6.551.00 74.565.59
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 720.00 6.551.00 73.422.34
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.278.250.80 21.480.650.40 240.054.906.84
17. Gross Electrical Energy Generated (MWH) 762.285.50 7.287.680.50 81.375.468.50
18. Net Electrical Energy Generated (MWH) 726.189.00 6.943.858.00 77.198.556.88
19. Unit Service Factor 100.00% 100.00% 75.31%
20. Unit Availability Factor 100.00% 100.00% 75.31%
21. Unit Capacity Factor (Using MDC Net) 94.26% 99.06% 74.01%
22. Unit Capacity Factor (Using DER Net) 94.26% 99.06% 74.01% ,
23. Unit Forced Outage Rate 0.00% 0.00% 5.66%  !
24. Shutdowns Scheduled Over Next 6 Months (Type,-Date, and Duration of Each):

Refuelino Shutdown. February 11. 1994. 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  !

9410190318 DR 943o34 ADOCK 05000361 PDR

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, AVERAGE DAILY UNIT POWER LEVEL DOCKET N0: 50-361 UNIT NAME: SONGS - 2 I DATE: October 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834 MONTH: SeDtember 1994 DAY AVERAGE DAILY POWER LEVEL DAY : AVERAGE DAILY POWER LEVEL (MWe-Net). (MWe-Net) 1 1 1048.46 16 '777.75 ,

2 1012.08 17 798.50  !

3 732.71~ 18 1062.46 _

4 735.33 19 1068.92 5 772.17 20 1071.08 6 932.67 21 1071.38 7 1063.08 22 1072.96 8 1067.17 23 1060.21 e 9 1069.13' 24 1052.96 10 1064.67 25 1061.83 11 1067.54 26 1061.54 l 12 1066.29 27 1071.00 13 1067.04 28 1080.38 l l

14 1069.63 29 1075.42 1 15 1030.25 30 1073.29 l

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-361

' UNIT NAME: SONGS - 2

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REPORT MONTH: September 1994 DATE: October- 14. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 ,

Method of Shutting Cause & Corrective Duration Down LER System Component Action to 5

No. Date Type l (Hours) Reason 2 Reactor3 No. Code' Code Prevent Recurrence i

86 940902 S 0.0 B 5 NA KE COND Reduce reactor power to perform circulating water pump repair and water box cleaning.

87 940915 S 0.0 B 5 NA KE COND Reduce reactor power to perform:

circulating water pump repair.

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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) s

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-SUMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: October 14. 1994

-COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 Date Time Event September 01 0001 Unit is in Mode 1, 98% reactor power,1103 MWe.-

2055- Reduced turbine load by 30 Mwe due to circulating water Delta T limits.

September 02 0001 Unit at 94.7 reactor power, 1071 Mwe.

0446 Returned Unit to full load, 1096 Mwe.

i 2103 Commenced lowering reactor power to 75% for water box cleaning, and circulating pump maintenance.

September 03 0001 Unit at 74% reactor power, 770 MWe September 06 0935 Commenced raising reactor power to 98%

1645 Unit at 98% reactor power, 110E MWe.

September 15 2045 Commenced lowering reactor power to 75% for circulating pump maintenance.

2300 Unit at 75% reactor power, 837 MWe. ,

September 17 1420 Commenced raising reactor power to 80% for circulating water system heat treatment i

2300 Commenced raising reactor power to 98% after completion of circulating water system heat l treatment.

September 18 0240 Unit at 98% power, 1112 MWe.

September 30 2400 Unit is in Mode 1, 98% reactor power,_1121 MWe.

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, REFUELING INFORMATION l DOCKET NO: 50-361 UNIT NAME: SONGS - 2 1 DATE: October 14. 1994 ,l COMPLETED BY: R. L. KaDlan l TELEPHONE: (714) 368-6834 _

MONTH: September 1994 i

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.

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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 and an exem) tion from  !

10 CFR 50 Appendix J has been requested to permit deferring tie '

Integrated Leakrate Testing.

C. 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. ,

i D. A proposed change to the Final Safety Analysis has been requested to i remove the diversity requirement of the pressurizer pressure transmitters providing input to the shutdown cooling open permissive interlock. ,

E. Proposed change to the Technical Specifications (PCN 431), revising the -

automatic reset of the low pressurizer pressure bypass, has been revised i to simplify the request.

F. 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 j DOCKET N0: 50-361 +

UNIT NAME: SONGS - 2 -

DATE: October 14. 1994 j COMPLETED BY: R. L. Kaplan  :

TELEPHONE: (714) 368-6834  !

4. Scheduled'date for submitting proposed licensing action and supporting [

information..

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

4 B. Integrated Leakrate Testing Submitted August 17, 1994 i C. Linear Heat Rate Submitted September 16, 1994  !

D. Pressure Instrument Diversity Submitted July 6, 1994  !

E. Low Pressurizer Pressure Bypass Revision submitted September 6, 1994  :

F. - Control Room Air Cleanup System Submitted August 26, 1994 -

5. Important licensing considerations associated with refueling, e.g. new or i different fuel design or supplier, unreviewed design or performance analysis ,

methods, significant-changes in fuel design, new operating procedures. i None.

6. The number of fuel assemblies. l A. In the core. 217 i i

B. In the spent fuel storage pool. 662 Total Fuel Assemblies i 592 Unit 2 Spent Fuel Assemblies  !

0 Unit 2 New Fuel Assemblies 70 Unit 1 SDent Fuel Assemblies

7. Licensed spent fuel storage capacity. 1542 l r

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 2005 (full off-load capability) ,

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NRC MONTHLY OPERATING REPORT j SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 3 1

DOCKET NO: 50-362 I UNIT NAME: SONGS - 3 l DATE: October 14. 1994 ,

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

i OPERATING STATUS I

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3 '
2. Reporting Period: SeDtember 1994
3. Licensed Thermal Power (MWt): 3390 3
4. Nameplate Rating (Gross MWe): 1127  !
5. Design Electrical Rating (Net MWe): 1080  :
6. Maximum Dependable Capacity (Gross MWe): 1127 f
7. Maximum Dependable Capacity (Net MWe): 1080 -l '
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 6.551.00 92.039.00 '
12. Number Of Hours Reactor Was Critical 720.00 6.551.00 72.477.45
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00- i
14. Hours Generator On-Line 720.00 6.537.60 70.834.49  !
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 ,
16. Gross Thermal Energy Generated (MWH) 2.359.461.23 21.235.151.12 227.906.940.83
17. Gross Electrical Energy Generated (MWH) 801.305.00 7.234.325.50 77.377.732.50
18. Net Electrical Energy Generated (MWH) 758.440.00 6.849.370.00 73.112.408.94  !
19. Unit Service Factor 100.00% 99.80% 76.96%  ;
20. Unit Availability Factor 100.00% 99.80% 76.96%
21. UnitCapacityFactor(UsingMDCNet) 97.54% 96.81%. 73.55% i
22. Unit Capacity Factor (Using DER Net) 97.54% 96.81% 73.55% l
23. Unit forced Outage Rate 0.00% 0.00% 6.29%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):  ;

None j

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 l INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA l

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: October 14. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: September 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1050.92 16 1051.92 2 1047.21 17 1043.08 3 1034.63 18 1050.71 4 1051.33 19 1051.08 5 1051.50 ,_

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1053.38 6 1053.25 21 1053.63 7 1053.96 22 1055.29 8 1056.25 23 1057.04 9 1057.17 24 1057.96 10 1055.79 25 1058.04 11 1054.75 26 1059.21 12 1054.08 27 1060.58 13 1053.58 28 1061.54 14 1055.46 29 1061.67 15 1056.92 30 1039.75 i

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UNIT SHUTDOWNS AND POWER REDUCTIONS  ; DOCKET NO: 50-362 ~ 4 UNIT NAME: SONGS - 3 REPORT MONTH: September 1994 DATE: October 14. 1994' ~

COMPLETED BY: R. L. KaDlan TELEPHONE: _J714) 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 There were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% this reporting period.

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2 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) i j

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH  :

DOCKET NO: 50-362-UNIT NAME: SONGS - 3 l DATE: October 14. 1994 COMPLETED BY: R. L. KaDlan TELEPHONE: (714) 368-6834  ;

Date Time Event l i

September 01 0001 Unit is in Mode 1, 97% reactor power, 1103MWe. l September 30 2100 Commenced lowering reactor power to 75% for  !

circulating water system heat treatment and waterbox cleaning.

2340 Unit at 75% reactor power, 830 Mwe.  ;

September 30 2400 Unit is in Mode 1, 75% reactor power, 830 MWe, i

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REFUELING INFORMATION i

DOCKET N0: 50-362 ,

UNIT NAME: SONGS - 3 DATE: October 14.-1994  :

COMPLETED BY: R. L. KaDlan

-TELEPHONE: (714) 368-6834 a i

MONTH: September 1994

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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 i Specification change or other license amendment? i t

Unknown at this time for Cycle 8 refueling.

What will these be?

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4. Scheduled date for submitting proposed licensing action and supporting information. j NA l
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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j REFUELING INFORMATION DOCKET N0: 50-362 5' UNIT NAME: SONGS - 3 DATE: October 14. 1994  ;

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

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6. The number of fuel assemblies.

A. In the core. 217  !

8.- In the spent fuel storage pool. 710 Total- Fuel Assemblies 'I 592 Unit 3 SDent Fuel Assemblies >

0 Unit 3 New Fuel Assemblies i 118 Unit 1 SDent Fuel Assemblies j

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

Intended change in spent fuel storage capacity. None [

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

Approximately 2003 (full off-load capability).  ;

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