ML20133A016

Monthly Operating Repts for Jul 1985

ML20133A016
Person / Time
Site:	San Onofre
Issue date:	07/31/1985
From:	Maisel R SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20133A013	List: ML20133A010 ML20133A016 ML20133A037
References
NUDOCS 8510020114
Download: ML20133A016 (10)

Text

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361

- - ~ ~

UNIT SONGS - 2 DATE August 15, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 56657 OPERATING STATUS 1.

Unit Name:

San Onofre Nuclear Generating Station, Unit 2 1

2.

Reporting Period:

July 1985 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 Restrictiuns, If Any:

NA This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744.00 5,087.00 17,136.00

12. Number Of Hours Reactor Was Critical 744.00 2,414.39 10,059.61 13.

Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744.00 2,377T9 9,870.46

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2,492,170.10 7,443,665.00 31,716,368.30

17. Gross Electrical Energy Generated (MWH) _ 831,258 ] _2,494,700.00 10,705,008.50

18. Net Electrical Energy Generated (MWH) 793,1M.00 2,333,712.00 10,098,660.00

19. Unit Service Factor 100.00 46T15 57Jo

20. Unit Availability Factor 100.00

46. 16 57.60

21. Unit Capacity Factor (Using MDC Net) 99.63 42.87 55.08

22. Unit Capacity Factor (Using DER Net) 99.63 42W 55.08 23.

Unit Forced Outage Rate 0.00 4.78 _

4.16 24.

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

N/A l

25.

If Shut Down At End Of Report Period, Estimated Date of Startup:

NA

26. Units In Test Status (Prior To Commercial Operatior):

Forecast Achieved l

lNITIAL CRITICALITY NA NA l

lNITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA l

l l

6814u 0510020114e5g085pyl i

DR ADOCK O

AVERAGE DAILY UNIT POWER LEVEL I

\\

t DOCKET NO.

50-361 I

i UNIT SONGS - 2 DATE August 15, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 56657 MONTH July 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1101.17 17 1070.96 2

1100.79 18 1070.63 3

1095.50 19 1054.92 4

1082.25 20 1071.83 5

1070.58 21 1073.00 6

1054.79 22 1071.38 i

7 1080.50 23 784.50 8

1083.88 24 1017.17 9

1083.79 25 1074.54 10 1075.79 26 1065.25 11 1077.79 27 1082.29 12 1068.21 28 1087.75 t

13 1074.13 29 1083.79 14 1074.67 30 1085.00 15 1074.38 31 1085.25 i

i j

16 1072.04 i

j 6814u

UNIT SHUTDOWNS AND POWER REDUCTIO'NS DOCKET NO. 50-361 UNIT NAME SONGS - 2 REPORT MONTH JULY 1985 DATE Anoust 15. 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 56657 Method of Shutting Du ra t ion Down LER System Component Cause & Corrective 1

2 3

4 4

Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence 15 850723 S

0 B

5 N/A TC PSF Power reduction to facilitate repair or steam leak on high pressure sealing steam line to high pressure turbine.

i o

1 2

3 4

F-Fo rced Reason:

Method:

IEEE Std 803-1983 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

F C-Rerueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation f rom E-Operator Training & License Examination Previous Month F-Admini st ra t ive 5-Reduction of 20%

G-Ope ra t iona l Error (Explain) or greater in the H-Othe r ( Expla in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other ( Explain) 6814u

I

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH r

DOCKET NO.

50-361 UNIT SONGS - 2 DATE August 15, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 56657 Date Time Event July 1 0001 Unit in Mode 1 at 100% reactor power.

Full power operations are planned.

July 5 1935 Commenced power reduction to 95% to facilitate turbine stop and governor valve testing and maintenance on high pressure governor valves UV2200 B, C and G.

July 6 0910 Unit returned to 100% reactor power.

July 12 0820 High pressure turbine governor valve UV2200G failed closed due to high oil temperature.

Unit power reduced to 97%.

1505 Unit returned to 100% reactor power.

July 23 0845 Commenced power reduction to 50% to allow repairs of steam leak on high pressure sealing steam line to high pressure turbine flange.

1523 Reactor power at 50%.

July 24 1230 Unit returned to 100% reactor power.

July 31 2359 Unit in Mode 1 at 100% reactor power.

l 6814u

REFUELING INFORMATION DOCKET N0.

50-361 UNIT SONGS - 2 DATE August 15, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 56657 1.

Scheduled date for next refueling shutdown.

April 1986 2.

Scheduled date for restart following refueling.

July 1986 3.

Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?

Not yet determined.

What will these be?

Not yet determined.

4.

Scheduled date for submitting proposed licensing action and supporting information.

Not yet determined.

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.

Not yet determined.

6.

The number of fuel assemblies.

a)

In the core.

217 b)

In the spent fuel storage pool.

72 7.

Licensed spent fuel storage capacity.

800 Intended change in spent fuel storage capacity.

NA 8.

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

Approximately 1997.

6814u

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE August 15, 1985 COMPLETED BY R. J. Maisel l

TELEPHONE (714) 492-7700 Ext. 56657 OPERATING STATUS 1.

Unit Name:

San Onofre Nuclear Generating Station, Unit 3 2.

Reporting Period:

July 1985 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 1

This Month Yr.-to-Date Cumulative 11.

Hours In Reporting Period 744.00 5,087.00 11,687.00 12.

Number Of Hours Reactor Was Critical 744.00 3,713.84 8,134.01 13.

Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744.00 3,633.50 7,739.45 15.

Unit Reserve Shatdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1,416,332.70 9,996,999.40 23,058,587.84

17. Gross Electrical Energy Generated (MWH) 429,410.00__ 3,364,617.00 7,731,448.50

18. Net Electrical Energy Generated (MWH) 392,279.00 3,146,812.00 7,247,182.00

19. Unit Service Factor 100.00 71.43 66.22

20. Unit Availability Factor 100.00 ~

71.43 66.22

21. Unit Capacity Factor (Using MDC Net) 48.82 57.28 57.42

22. Unit Capacity Factor (Using DER Net) 48.82 57.28 57.42 23.~ Unit Forced Outage Rate 0

27.32 15.77 24.

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

Refueling, September 1985, 110 days duration 25.

If Shut Down 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 6814u

~ AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-362 UNIT SONGS - 3 DATE August 15, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714)492-7700 Ext. 56657 MONTH July 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 6 1

526.75 17 519.54 2

527.33 18 519.00 3

526.63 19 519.75 4

516.63 20 522.08 5

512.33 21 520.13 6

511.25 22 517.29 7

515.92 23 515.25 8

517.96 24 515.25 9

518.29 25 513.29 10 516.63 26 515.04 11 517.75 27 521.96 12 728.71 28 523.79

-13 567.71 29 515.04 14 519.67 30 513.71 15 520.33 31 514.25 16 519.88 6814u

I

{

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-362

(

U:3t T NAME SONGS - 3 REPORT MONTH JULY 1985 DATE AUGUST 1 c.

1985 COMPLETED BY R.

J.

Maiset TELEPHONE f7141 492_Z7 2 _ _

Ext. 56657 Method of l

Shutting l

Du ra t ion Down LER System Component Cause & Corrective 1

2 3

4 4

Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence 21 850713 S

0 F

5 N/A N/A N/A Power reduction to 55% to prolong unit's initial core and defer commencement of Cycle 1 refueling outage until September 1985.

1 2

3 4

F-Fo rced Reason:

Method:

IEEE Std 803-1983 S-Scheduled A-Equipment failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation f rom E-operator Training & License Examination Previous Month F-Adm i n i st ra t i ve 5-Reduction of 20%

G-Ope ra t iona l Error (Explain) or greater in the H-Other ( Expla in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other (Explain) 6814u

t o

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

50-362 UNIT SONGS - 3 DATE August 15, 1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 492-7700 Ext. 56657 Date Time Event July 1 0001 Unit in Mode 1 at 54.5% reactor power.

Unit will remain at reduced reactor power to conserve megawatt days for use during summer peak demand period.

July 12 0200 Commenced power increase to 80% to heat treat intake structure.

July 13 0630 Ur.it returned to 55% reactor power.

July 31 2359 Unit in Mode 1 at 55% reactor power.

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o REFUELING INFORMATION DOCKET NO.

50-362 UNIT SONGS - 3 DATE August 15, 1985 COMPLETED BY R. J. Maisel l

TELEPHONE (714) 492-7700 Ext. 56657 1.

Scheduled date for next refueling shutdown.

September 1985 2.

Scheduled date for restart following refueling.

January 1986 3.

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

Yes What will these be?

Not yet determined.

4.

Scheduled date for submitting proposed licensing action and supporting information.

Proposed Technical Specification change regarding required boric acid volume and concentration (PCN Number 163) was submitted March 9, 1985.

l S.

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.

Reload analysis is the same as Unit 2.

6.

The number of fuel assemblies, a)

In the core.

217 t

l b)

In the spent fuel storage pool.

O l

7.

Licensed spent fuel storage capacity.

800_.

Intended change in spent fuel storage capacity.

NA 1

(

8.

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

I N/A 6814u

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