ML20137K353

Monthly Operating Repts for Dec 1985

ML20137K353
Person / Time
Site:	Dresden
Issue date:	12/31/1985
From:	Maxwell D, Scott D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8601240023
Download: ML20137K353 (13)

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OPERATING DATA REPORT DOCKET NO. 050-237 DATE January 1, 1986 COMPLETED BY D. C. Ma.xwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES

1. Un1t Name: Dresden II

2. Reporting Period: December, 1985 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

7. Maximum Dependable Capacity (Net MWe): 772

8. If Changes Occur in Capacity Ratings (items 3 Through 7) Since Last Report, Give Reasons:

N/A 9 Power Level to Which Restricted, if Any (Net MWe): N/A

10. Reasons For Restrictions, if Any: N/A 1

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 8,760 137,064

12. Number of Hours Reactor Was Critical 744.0 4,961.6 103,697.5 13 Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 744.0 4,680.2 98,984.6 15 Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1.833,306 10,295,591 201,633,639

17. Gross Electrical Energy Generated (MWH) 597,065 3,278,422 64,499,763

18. Net Electrical Energy Generated-(NWH) 571,098 3,087,488 60,936,114 19 Unit Service Factor 100.0 53.4 72.2

20. Unit Availability Factor 100.0 53.4 72.2

21. Unit Capacity Factor (Using MDC Net) 99.4 45.7 57.6

22. Unit Capacity Factor (Using DER Net) 96.7 44.4 56.0

23. Unit Forced Outage Rate 0 25.5 12.3

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

Mid-May, 1986 for a weekend snubber inspection.

25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/A 7

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OPERATING DATA REPORT DOCKET NO. 050-249 DATE January 1, 1986 COMPLETED BY D. C. Maxw11 TELEPHONE 815/942-2920 OPERATING STATUS NOTES

1. Unit Name: Dresden III

2. Reporting Period: December, 1985 3 Licensed Thermal Power (MWt): 2.527

4. Nameplate Rating (Gross MWe): R2R 5 Design Electrical Rating (Net MWe): 794

6. Maximum Dependable Capacity (Gross MWe): R12 7 Maximum Dependable Capacity (Net MWe): 773

8. If Changes occur in Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons:

N/A 9 Power Level to Which Restricted, If Any (Net MWe): N/A

10. Reasons For Restrictions, if Any: N/A a

i This Month Yr-to-Date Cumulative.

11. Hours in Reporting Period 744 8,760 126,649

12. Number of Hours Reactor Was Critical 0 6,718.8 96,596.7 13 Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 0 6,621.2 89,793.3 15 Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 14,715,613 181,772,636 17 Gross Electrical Energy Generated (MWH) 0 4,632,256 58,839,233

18. Net Electrical Energy Generated. (MWH) -5,225 4,390,064 55,726,294 19 Unit Service Factor 0 75.6 70.9

20. Unit Availability Factor 0 75.6 70.9

21. Unit Capacity Factor (Using MDC Net) 0 64.8 56.9

22. Unit Capacity Factor (Using DER Net) O 63.1 55.4

23. Unit Forced Outage Rate O 7.7 12.4

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

In 9th Refueling / Recirculation Pipe Replacement (RPR) outage.

25 If Shut Down At End Of Report Period, Estimated Date of Startup: July, 1986 j

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237 UtilT II DATEggnuary 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 Ext. 489 MONTH December, 1985 DAY

~ AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 757 17 719 2 776 18 780 3 781 19 777 4 787 20 785 5 786 21 777 6 725 22 730 7 765 769 23 8 765 24 778 9 759 25 781 10 792 26 776 11 767 27 787 12 791 28 782 13 776 751

• 29 14 789 769 30 15 732 779 31 16 786

AVERAGE DAILY UNIT POWER LEVEL T

DOCKET NO. 050-249 UNIT III DATE January 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 Ext. 489 MONTH December, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19

- 0 4 0 20 0 5 0 21 0 6 0 22 0

-7 0 0 23 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 i

! 12 0 28 0 t

13 0 0 l 29 14 0 0 30 15 0 0 l 31 16 0 l

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. COMMONWEALTH EDISON COMPANY i -

DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF DECEMBER, 1985 i

HOUR MAXIMUM DAILY LOAD DAY ENDING KW I 1 2200 806,800 2 2000 826,300

. 3 1000 828,000 4 2000 830,800 5 0100 826,700 i,

! 6 1600 829,000 7 1500 823,000 8 2000 808,900 9 2400 826,800 10 0400 830,200 11 2200 827,700 12 2200 831,100 i

13 0300 833,400 14 0300 829,800 i 15 0100 823,600 I

16 1400 833,000 r

17 0100 829,500 18 2300 828,600

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19 1600 831,100 20 2200 828,600 21 1300 829,100 22 2200 807,600 23 1900 831,500 24 1400 834,300 25 2200 826,900 26 1700 831,000 27 2400 830,000 I

28 1300 831,500 29 0100 830,200

! 30 0800 822,500

. 31 1800 830,600 i

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I DOCRET NO. 050-237 UNIT NAME II UNIT SHUTDOWHS AND POWER REDUCTIONS DATE January 1, 1986 .

l COMPLETED BY D. C. Maxwell j REPORT HONTH DECEMBER, 1985 TELEPHONE (815) 942-2920 i' I

HETHOD OF LICENSEE .

NO. DATE TYPEI DURATION REASON 2 CAUSE & CORRECTIVE SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS) DOWN REACTOR 3 REPORT # CODE 4 CODES PREVENT RECURRENCE {

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None i I

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F: Forced 3 4 1

'; Reason: ,

S: Scheduled Hethod: Exhibit G-Instructions for A-Equipment Failure (Explain) 1-Manual

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B-Haintenance or Test Preparation of Data  ;

b P.; fueling 2-Manual Scram Entry Sheets for Licensee D-Regulatory Restriction 3-Automatic Scram Event Report ( ) File E-Operator Training & License Examination 4-Other (Explain) (NUREG-0161)

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' F-Administrative l:

G-Operational Error H-Other (Explain) l' f jI

i DOCKET NO. 050-249

! UNIT NAMEIII 4

! UNIT SHUTDOWNS AND POWER REDUCTIONS DATE January 1, 1986 2i '

COMPLETED BY D. c. Maxwell REPORT N0HTH DECEMBER, 1985 TELEPHONE (815) 942-2920 HETHOD OF LICENSEE NO. DATE TYPEI DURATION CAUSE & CORRECTIVE '

REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS) DOWN REACTOR 3 REPORT # CODE 4 CODES PREVENT RECURRENCE l

85-10-28 744:00 6 S C 1 -- -- --

Off-line manually to 9th Refueling / Recirculation Pipe  !

Replacement Outage. '

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1 1 2 F: Forced 3 4 Reason: ,

i ll 8: Scheduled Hethod: Exhibit G-Instructions for A-Equipment Failure (Explain) 1-Manual 1

B-Maintenance or Test Preparation of Data  ;

C-Refueling 2-Manual Scram Entry Sheets for Licensee D-Regulatory Restriction 3- Automatic Scram Event Report ( ) File E-Operator Training & License Examination 4-Other (Explain) (NUREG-0161) i F-Administrative G-Operational Error

) .

H-Other (Explain)

F-

DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - DECEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Check Valve Preventive W.R. #34842 N/A --- ---

Inspected - found nothing wrong.

MO-2-1201-2 LPCI LPCI System HFA Preventive W.R. #36758 N/A --- ---

Replaced relay coil per procedure.

Relays Bus 110/111 Plus Preventive W.R. #40909 N/A --- ---

Disconnected, disassembled and shipped.

Trans 115 HPCI Pumps Preventive W.R. #41041 N/A --- ---

Aligned pumps, greased couplings, made new gaskets.

CRD Accumulator Corrective W.R. #41151 N/A --- ---

Installed new gaskets, replaced flanges.

SDV Piping U2 MOV-202-7A, Preventive W.R. #42122 N/A --- ---

Performed inspections - completed Westec 2-202-7A checklists.

MO-2-1501-27B Preventive W.R. #42937 N/A --- ---

Removed jumper, performed test proce-dures.

3/4" Globe Valve Corrective W.R. #43007 N/A --- ---

Changed out valve and pipe per request U2 Isolation and procedures.

Condenser 3/4" Vent Line CRD Drives (4) Corrective W.R. #43018 N/A --- ---

Retorqued drives F2, T2, H-13 and M-12.

202 MOV 1501-28B, Corrective W.R. #43607 N/A --- ---

Corrected deficiencies of Unit 2 MOV 2-1501-28B 1501-28B per M.M.P.

MOV 2301-5 Corrective W.R. #43610 N/A --- ---

Replaced grease, changed wires and spliced motor leads.

DRESDEN UNIT 2/3 -

SAFETY RELATED MAINTENANCE - DECEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE- NUMBER CAUSE RESULT CORRECTIVE ACTION MOV 7504B Corrective W.R. #43613 N/A Replaced grease in L.S., replaced internal wiring, and spliced meter lead connections.

MOV 7505B Corrective W.R. #43615 N/A --- ---

Replaced grease, internal wiring, and spliced meter lead connections.

MOV 7507B Corrective W.R. #43617 N/A --- ---

Replaced grease, internal wiring, and spliced meter lead connections.

Spare Accumu- Corrective W.R. #46710 N/A --- Rebuilt accumulator, lator

UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period of December, 1985 are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circum-stances resulting in its actuation.

Valves Description Unit Reporting Period Actuated Actuations Conditions of Events 2 12-01-85 to 12-31-85 None 3 12-01-85 to 12-31-85 None - 4 Safety / Relief valves were removed and will be tested during the month of January, 1986.

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SUM >tARY OF OPERATING EXPERIENCE UNIT TWO DECEMBER, 1985 12-01-85 to 12-31-85 Unit 2 operated continuously the entire month at maximum core flow (except for normal weekend surveillances), reaching a power level of 834 MWe with a capacity factor of 96.22% and an avail-ability of 100%.

SUMMARY

OF OPERATING EXPERIENCE UNIT THREE DECEMBER, 1985 12-01-85 to 12-31-85 Refueling outage activities continued throughout the entire period. The unit is presently scheduled to start up in late June, 1986. Major work includes:

- Normal pump (s) and valve (s) maintenance.

- Decontamination of the recirculation piping.

- Removal of the recirculation piping, a

l Dresden Nucbar Power Stition O Commonwer.Ith Edison RR #1 Morris, Illinois 60450 ,

Telephone 815/942-2920 l

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l January 1, 1986 DJS LTR: 86-6 Director, Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

Dear Sir:

Enclosed, please find Dresden Station's operating data for last month. This information is supplied to your office per the instruc-tions set forth in Regulatory Guide 1.16.

Sincerely, D J. Scott Station Manager Dresden Nuclear Power Station DJS: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 Nuclear Fuel Services Manager Nuc. Sta. Div. Vice Pres.

Manager, Tech. Nuc. Sta.

Tech. Staff A.E.

On-Site NRC Inspector Sta. Nuc. Eng. Dept.

Comptroller's Office PIP Coordinator INPO Records Center File /NRC Op. Data File / Numerical e?

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