ML20071H505

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Monthly Operating Repts for June 1993 for San Onofre Nuclear Generating Station Units 2 & 3
ML20071H505
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/30/1994
From: Darling J
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20071H503 List:
References
NUDOCS 9407190265
Download: ML20071H505 (12)


Text

'

, Docu' ment Control Desk NRC MONTHLY OPERATING REPORT DOCKET N0:

50-361 UNIT NAME: SONGS - 2 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 OPERATING STATUS 1.

Unit Name:

San Onofre Nuclear Generating Station. Unit 2 2.

Reporting Period:

June 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 4.343.00 95.280.00 12.

Number Of Hours Reactor Was Critical 720.00 4.343.00 72.357.59 13.

Reactor Reserve Shutdown Hours 0.00 0.00 0.00-14.

Hours Generator On-Line 720.00 4.343.00 71.214.34 15.

Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.

Gross Thermal Energy Generated (MWH) 2.359.616.90 14.320.433.60 232.894.690.04 17.

Gross Electrical Energy Generated (MWH) 802.800.50 4.893.796.00 78.981.584.00 18.

Net Electrical Energy Generated (MWH) 764.966.00 4.663.292.00 74.917.990.88 19.

Unit Service Factor 100.00%

100.00%

74.74%

20.

Unit Availability Factor 100.00%

100.00%

74.74%

21.

Unit Capacity Factor (Using MDC Net) 99.29%

100.35%

73.49%

22.

Unit Capacity Factor (Using DER Net) 99.29%

100.35%

73.49%

23.

Unit Forced Outage Rate 0.00%

0.00%

5.82%

24.

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

None 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 i

2 9407190265 940714 i

PDR ADOCK 05000361 R

PDR

, Docu' ment Control Desk AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:

50-361 UNIT NAME:

SONGS - 2 DATE:

COMPLETED BY:

J. L. Darling

(

._ 714) 368-6223 TELEPHONE:

MONTH:

June 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1079.04 16 1063.71 2

1079.13 17 1060.54 3

1055.00 18 866.29 4

1074.13 19 1064.21 5

1072.58 20 1069.50 6

1070.88 21 1071.29 7

1069.79 22 1074.29 8

1069.33 23 1074.79 9

1068.50 24 1073.96 10 1066.79 25 1074.13 11 1067.33 26 1073.75 12 1069.42 27 1073.08 13 1068.08 28 1065.83 14 1064.29 29 1064.92 j

15 1063.79 30 1065.21 4

3

Document Control Desk UNIT SHUTDOWNS AND F0WER REDUCTIONS DOCKET N0:

50-361 UNIT NAME: SONGS - 2 REPORT MONTH:

June 1994 DATE:

COMPLETED BY:

J. L. Darling TELEPHONE:

(714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to l

2 3

s No.

Date Type (Hours)

Reason Reactor 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.

F-Forced

' Reason:

3Method:

'IEEE Std 805-1984 2

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) 4

~

, Document Control Desk

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-361 UNIT NAME: 50NGS - 2 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 Date Time Event June 01 0001 Unit is in Mode 1, 98% reactor power, 1130 MWe, June 18 0400 Commenced unit load reduction in preparation for circulating water system heat treat.

0630 Unit at 80% reactor power.

2201 Commenced unit load increase following completion of circulating water system heat treat.

June 19 0255 Unit at 98.1% reactor power, 1120 MWe.

June 30 2400 Unit is in Mode 1, 98% reactor power, 1115 MWe.

5

~

Document Control Desk REFUELING INFORMATION DOCKET N0:

50-361 UNIT NAME:

SONGS - 2 DATE:

COMPLETED BY:

J. L. Darling TELEPHONE:

(714) 368-6223 MONTH:

June 1994

1. Scheduled date for next refueling shutdown.

Cycle 8 refueling outage is forecast for January 15, 1995.

2. Scheduled date for restart following refueling.

Restart from Cycle 8 refueling outage is forecast for March 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 will be 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 exemption from 10 CFR 50 Appendix J will be requested to permit deferring the Integrated Leakrate Testing.

C.

A proposed change to the Technical Specifications will be requested to revise the allowed Linear Heat Rate frcm 13.9 to 13.0 kw/ft.

D.

A proposed change to the Final Safety Analysis has been requested to 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, will be revised to simplify the request.

6

~

Docu' ment Control Desk REFUELING INFORMATION.

)

DOCKET N0:

50-361 UNIT NAME:

SONGS - 2 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 F.

A proposed change to the Technical Specifications will be requested to allow a 3.0.4 exception for entering Modes 5 and 6 with the Control Room Emergency Air Cleanup System inoperable.

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

A.

Refueling Cavity Water Level Submittal Forecast July 31, 1994 B.

Integrated Leakrate Testing Submittal Forecast July 31, 1994 1

C.

Linear Heat Rate Submittal Forecast Aug. 31, 1994 D.

Pressure Instrument Diversity Submitted July 7, 1994 E.

Low Pressurizer Pressure Bypass Revision Forecast Aug. 31, 1994 F.

Control Room Air Cleanup System Submittal Forecast Aug. 31, 1994

5. Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perforraance 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 Spent Fuel Assemblies 0 Unit 2 New Fuel Assemblies 70 Unit 1 Spent Fuel Assemblies

7. Licensed spent fuel storage capacity.

1542 i

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.

r Approximately 2005 (full off-load capability) i i

7 i

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Docu' ment Control Desk NRC MONTHLY OPERATING REPORT DOCKET NO:

50-362 UNIT NAME: SONGS - 3 DATE:

COMPLETED BY:

J. L. Darling TELEPHONE:

(714) 368-6223 OPERATING STATUS 1.

Unit Name:

San Onofre Nuclear Generating Station. Unit 3 2.

Reporting Period:

June 1994 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 720.00 4.343.00 89.831.00 12.

Number Of Hours Reactor Was Critical 720.00 4.343.00 70.269.45 13.

Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.

Hours Generator On-Line 720.00 4.329.60 68.626.49 15.

Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.

Gross Thermal Energy Generated (MWH) 2.359.461.23 13.994.045.95 220.665.835.66 17.

Gross Electrical Energy Generated (MWH) 805.717.50 4.788.962.50 74.932.369.50 18.

Net Electrical Energy Generated (MWH) 762.809.00 4.535.149.00 70.798.187.94 19.

Unit Service Factor 100.00%

99.69%

76.40%

20.

Unit Availability Factor 100.00%

99.69%

76.40%

21.

Unit Capacity Factor (Using MDC Net) 98.10%

96.69%

72.97%

22.

Unit Capacity Factor (Using DER Net) 98.10%

96.69%

72.97%

23.

Unit Forced Outage Rate 0.00%

0.00%

6.48%

24.

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

None 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 8

Docdment Control Desk AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:

50-362 UNIT NAME: SONGS - 3 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 MONTH:

June 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1069.96 16 1060.42 2

1068.29 17 1057.17 3

1066.79 18 1057.00 4

1064.33 19 1057.38 5

1063.92 20 1061.54 6

1063.79 21 1063.83 7

1064.83 22 1065.00 8

1065.63 23 1065.25 9

1065.63 24 1058.88 i

10 1052.83 25 1053.88 11 1020.42 26 1056.46 12 1064.54 27 1054.50 13 1065.71 28 1049.17 14 1062.54 29 1050.67 15 1062.04 30 1051.33 9

' Document Control-Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-362.

UNIT NAME: SONGS - 3 REPORT MONTH:

June 1994 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 I

Method of Shutting Cause & Corrective Duration Down LER System Component Action to No.

Date Type (Hours)

Reason Reactor No.

Code' Code' Prevent Recurrence t

t 2

3 t

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

F-Forced

' Reason:

3Method:

"IEEE Std 805-1984 2

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) t' 10

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, Docdment Control Desk

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0:

50-362 UNIT NAME: SONGS - 3 DATE:

COMPLETED BY:

J. L. Darlino TELEPHONE:

(714) 368-6223 Date Time Event June 01 0001 Unit is in Mode 1, 97% reactor power, 1122 MWe.

June 25 2110 Commenced unit load reduction to allow main turbine valve testing.

2149 Unit at 90% reactor Power, 1010 MWe.

2245 Commenced unit load increase following completion of main turbine valve testing.

2347 Unit is at 97%, 1115 MWe June 30 2400 Unit is in Mode 1, 97% reactor power, 1101 MWe.

f 11

Document Control Desk REFUELING INFORMATION DOCKET NO:

50-362 UNIT NAME:

SONGS - 3 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 MONTH:

June 1994

1. Scheduled date for next refueling shutdown.

Cycle 8 refueling outage is forecast for June 9,1995.

2. Scheduled date for restart following refueling.

Restart from Cycle 8 refueling outage is forecast for August 18, 1995.

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

NA l

l 1

12

4 Document Control Desk REFUELING INFORMATION l

DOCKET N0:

50-362 UNIT NAME:

SONGS - 3 DATE:

COMPLETED BY:

J. L. Darlina i

TELEPHONE:

(714) 368-6223 i

MONTH:

June 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.

710 Total Fuel Assemblies 592 Unit 3 Spent Fuel Assemblies 0 Unit 3 New Fuel Assemblies 118 Unit 1 Spent 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).

13