ML20237H278

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Monthly Operating Repts for Jul 1987
ML20237H278
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 07/31/1987
From: Eenigenburg E, Maxwell D
COMMONWEALTH EDISON CO.
To:
NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
87-509, NUDOCS 8708170128
Download: ML20237H278 (17)
v • d • e


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4 OPERATING DATA REPORT DOCKET NO. 050-237 i

DATE August 5, 1987 COMPLETED DY D. C. Maxwell TELEPHONE,815/942-2920 l

l OPERATING STATUS

! NOTES i 1. Unit Name: Dresden II

( 2. Reporting Period: July, 1987 3 Licensed Thermal Power (MWt): 2.527

4. Nameplate Rating (Gross MWe): 828 5 Design Electrical Rating (Net MWe): 794
6. Maximum Dependable Capacity (Gross MWe): 812 i 7 Maximum Dependable Capacity (Net MWe): 772
8. If Changes Occur in Capacity Ratings (ltems 3 Through 7) Since Last Report, Give Reasons:

N/A 9 Power Level to Which Restricted, If Any (Net MWe): N/A l 10. Reasons For Restrictions, if Any: N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 s.og7 1so.911
12. Number of Hours Reactor Was Critical 691.6 2,340.1 113,147.7 13 Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 674.9 2,007.5 107.755.4 15 Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 1,295,749 3,862,624 220,734,706 17 Gross Electrical Energy Generated (MWH) 411,520 1,217,593 70,602,694
18. Net Electrical Energy Generated.(MWH) 387,743 1,128.358 66.711,001 19 Unit Service Factor 90.7 39.5 71.4
20. Unit Availability Factor 90.7 39.5 71.4
21. Unit Capacity Factor (Using MDC Net) 67.5 28.7 57.3
22. Unit Capacity Factor (Using DER Net) 65.6 27.9 55.7 23 Unit Forced Outage Rate 9.3 7.4 12.0 ~
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A 25 If Shut Down At End Of Report Period, Estimated Date of Startup: N/A D b i

OPERATING DATA REPORT DOCKET NO. 050-249 DATE August 5, 1987 l COMPLETED BY D. C. Maxwell l TELEPHONE 815/942-2920 l OPERATING STATUS NOTES

1. Unit Name: Dresden III
2. Reporting Period: July, 1987 3 Licensed Thermal Power (MWt): 2_527
4. Nameplate Rating (Gross MWe): sps 5 Design Electrical Rating (Net MWe): 794
6. Maximum Dependable Capacity (Gross MWe): 81 2 7 Maximum Dependable Capacity (Net MWe): 773
8. If Changes Occur in Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons: i N/A 9 Power Level to Which Restricted, if Any (Net MWe): N/A l l 10. Reasons For Restrictions, if Any: N/A l

! l l l l

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period .

744 5,087 140,496  !

12. Number of Hours Reactor Was Critical 665.3 4,509.6 103,863.1 l 13 Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 595.7 --

4,073.7 96,324.2 15 Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,175,857 9,169,065 195,980,162

, 17 Gross Electrical Energy Generated (MWH) 359,920 2,891,510 63,296,029

18. Net Electrical Energy Generated-(MWH) 339,029 2,748,882 59.932.200 19 Unit Service Factor 80.1 80.1 68.6
20. Unit Availability Factor 80.1 80.1 68.6
21. Unit Capacity Factor (Using MDC Net) __

59.0 69.9 55.2

22. Unit Capacity Factor (Using DER Net) 57.4 68.1 53.7 1 23 Unit Forced Outage Rate 19.9 ~

19.2 12.8 j

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

January, 1988 refueling outage - approximately 15 weeks.

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1 25 If Shut Down At End Of Report Period, Estimated Date of Startup: N/A l I

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l l COMMONWEALTH EDISON COMPANY DRESDEN STATION l l

MAXIMUM DAILY LOAD MONTH OF JULY, 1987 HOUR MAXIMUM DAILY LOAD l

l DAY ENDING KW i

( 1 2200 1,607,100 2 2400 1,560,000

, ___ 3 0600 1,567,600 l 4 1300 1,556,200 5 2300 1,549,400 i 6 2200 1,558,300 7 0100 1,537,700 8 0900 1,432,800 9 1400 1,451,200 10 1300 1,439,400 11 0100 1,067,900 12 0100 677,400 13 2300 703,700 14 0200 701,800 15 2400 729,600 ,

16 1300 772,700 l 17 2000 1,253,800 l 18 2400 659,500 19 ];';C0 760,900 20 . g. 2400 891,900 21 1300 1,231,900 22 1100 1,107,700 23 0400 912,900 24 0400 918,800 25 0600 911,600 26 0900 909,700 27 0600 911,800 28 1000 1,112,100 29 1800 914,500 30 0100 908.100 31 1300 013,200 ,

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e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237 l UNIT II DATE August 5, 1987 ,

COMPLETED BY D. C. Maxwell _

815/942-2920 TELEPHONE I

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l HONTH JULY l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) l 1 766 17 714 l 2 740 18 0 3 756 19 0 4 727 20 7 5 698 21 438 6 761 22 450 7

725 415 23 8 608 24 449 9 645 427 25 10 621 436 26 11 683 27 444 12 446 28 498 13 565 395 29 14 682 427 30 666 15 3; 3g3 16 741

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AVERAGE DAILY UNIT POWER. LEVEL i DOCKET NO. '050-249 ~

UNIT III

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DATE August-5, 1987 COMPLETED BY- D. C. Maxwell

.l TELEPHONE 815/942-2920

.l MONTH JULY, 1987 l

DAY ' AVERAGE DAILY POWER LEVEL DAY -AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

! '1 768 279 17 2 607 18 513 l l 3 762 19 701 4 713 20 705 5 697 21 620 6 777 22 465 1 7 722 419 23

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)

UNIQUE REPORTING REQUIREMENTS j 1

MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period July, 1987 are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its

. actuation.

l 1

Valves Description Unit Reporting Period Actuated Actuations Conditions of Events 2 07/01/87 to 07/31/87 None 3 07/01/87 to 07/31/87 None I

1 1

l

.{

SUMMARY

OF OPERATING EXPERIENCE UNIT TWO JULY, 1987 07/01/87 to 07/20/87 Unit 2 entered the month on-line and operating at a power level of 798 MWe. The unit operated until l 2328 hours0.0269 days <br />0.647 hours <br />0.00385 weeks <br />8.85804e-4 months <br /> of July 17th when a reactor scram occurred because of a failure of the 2B feedwater regulating valve. After investigation of the problem and repairs were completed, the reactor was brought critical on l July 20th at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> and the generator was snychro-I nized to the grid at 2032 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.73176e-4 months <br /> of the same day.

07/21/87 to 07/31/87 The unit operated the remainder of the month at reduced load because of high circulating water inlet tempera-tures with a capacity factor of 66.32% and an availa-bility of 90.72%. ' Unit load was limited by Illinois Environmental Protection Agency (EPA) river discharge temperature requirements.

4 4

l

_ _ _ _ _ _ _ _ _ _ _ _ - _ - _ i

a +

SUMMARY

OF OPERATING EXPERIENCE UNIT THREE JULY, 1987 07/01/87 to 07/17/87 Unit 3 entered the month on-line and operating at a power level of 795 MWe. The unit operated until -

July lith, 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> when a turbine trip and reactor i scram occurred because of a failure of the 3A feed-water regulating valve. The unit was brought on-line July 17th at 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br />.

07/18/87 to 07/31/87 The unit operated the remainder of the month at reduced load because of high circulating water inlet temperatures with a capacity factor of 58.14% and an l

availability of 80.07%. Unit load was limited by EPA l

river discharge temperature requirements.

l

Comm:nwerith Edistn )

DrIsdIn NuclJar Pow 3r Station I R.R. #1 i Morris, tilinois 60450 I Telephone 815/942-2920 August 5, 1987 EDE LTR: 87-509 l

Director, Office of Inspection and Enforcement United States Nuclear Regulatory Commission i

Washington, DC 20555 l 1

l l l

! Attention: Document Control Desk l I

Dear Sir:

{

Enclosed, please find Dresden Station's operating data for the month of July, 1987. This information is supplied to your office per the i instructions set forth in Regulatory Guide 1.16.

i i

l Sincerely,

~

E. D. Eenige1 t g Station Managaf Dresden Nuclear Power Station EDE:DCM:hjb Enclosure cc: Region III, Regulatory Operations, U.S. NRC Chief, Division Nuclear Safety, State of IL U.S. NRC, Document Management Branch Nuclear Licensing Administrator Nuc. Sta. Div. Vice Pres.

Manager, Tech. Serv. Nuc. Sta.

Tech Staff A.E. (2)

On-Site NRC Inspector Site Q.A.

Sta. Nuc. Eng. Dept.

Comptro11er's Office PIP Coordinator INPO Records Center File /NRC Op. Data File / Numerical 6.h

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