ML20133J496

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Monthly Operating Rept for Sept 1985
ML20133J496
Person / Time
Site: Dresden Constellation icon.png
Issue date: 09/30/1985
From: Maxwell D, Scott D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-963, NUDOCS 8510180472
Download: ML20133J496 (20)
v • d • e


Text

_______ _________ __ _____________ _ ___ - ____________________

a OPERATING DATA REPORT e

DOCKET NO. 050-237 DATE October 1, 1985 COMPLETED BY D. C. Maxwell TELEPHONE 815/942 'X)20 OPERATING STATUS NOTES 1.

Unit Name:

Dresden II 2.

Reporting Period:

September, 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 l

7.

Maximum Dependable Capacity (Net MWe):

772

)

8.

If Changes Occur in Capacity Ratings (items 3 Through 7) Since Last Report, Give l

Reasons:

N /A 9

Power Level to Which Restricted, if Any (Net MWe): N/A 10.

Reasons For Restrictions, if Any:

N/A

)

This Month Yr-to-Date Cumulative 11.

Hours in Reporting Period 720.0 6,551.0 134,855.0 12.

Number of Hours Reactor Was Critical 695.9 3,578.2 102,314.0 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 693.4 3,336.8 100,646.6 15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1,532,098 7,208,282 198,545,340 17 Gross Electrical Energy Generated (MWH) 485,249 2,277,578 63,498,919 18.

Net Electrical Energy Generated-(MWH) 461,110 2,143,406 59,992,032 19 Unit Service Factor 96.3 50.9 74.6 20.

Unit Availability Factor 96.3 50.9 21.

Unit Capacity Factor (Using MDC Net) 83.0 42.4 74.6 57.6 22.

Unit Capacity Factor (Using DER Net) 80.7 41.2 56.0 23.

Unit Forced Outage Rate 3.7 18.1 11.5 24.

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

April, 1986 for Drywell Snubber Inspection.

25.

If Shut Down At End Of Report Period, Estimated Date of Startup: October 7, 1985 8510180472 850930 PDR ADOCK 05000237 R

PDR I

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s OPERATING DATA REPORT DOCKET NO. 050-249 DATE 0ctober 1,1985 COMPLETED BY D. C. Ma.well TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.

Unit Name: Dresden III 2.

Reporting Period:

September, 1985 3

Licensed Thermal Power (MWt):

2 527 4.

Nameplate Rating (Gross HWe):

ang 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 I

This Month Yr-to-Date Cumul.a t i ve.

11.

Hours in Reporting Period 720.0 6,551.0 124,444.0 12.

Number of Hours Reactor Was Critical 487.2 6,069 9 95,94//5 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 474.3 5,984.5 89.156.+

15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (HWH) 1.020.264 13,434,993 180,492,016 17 Gross Electrical Energy Generated (MWH) 316.406 4,232,642 58,439.619 18.

Net Electrical Energy Generated.(MWH) 2o7,731 4,024,152 55,360,382 19 Unit Service Factor 65.9 91.3 11.6 20.

Unit Availability Factor 65.9 91.3 71.6 21.

Unit Capacity Factor (Using HDC Net) 53.5 79.5 57.6 22.

Unit Capacity Factor (Using DER Net) 52.1 77.4 56.0 23.

Unit Forced Outage Rate 34.1 8.2 12.4 24.

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

Refueling and Recirculation Piping Replacement - Fall, 1985 for approximately 6 months.

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

N/A s

.4.

m_,,.

. - _. -. -. _ -, ~. -

-..,-.. ~,

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DOCKET NO. 050-237 l

UNIT NAME Dresden II UNIT SHUTDOWNS A.!D POWER REDUCTIONS DATE October 1, 1985

'l COMPLETED BY D. C. Maxwell

{

TELEPHONE (815) 942-2920 REPORT MONTH September, 1985 METHOD OF LICENSEE NO.

DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM CONPONENT ACTION TO CAUSE & CORRECTIVE (HOURS)

DOWN REACTOR 3 REPORT f CODE 4 CODES PREVENT RECURRENCE 8

85-09-29 S

26:36 H

3 85-035-0 Unit taken off-line manually (26.6) for snubber inspections and E.Q.

modifications (Rx serain 231 hours0.00267 days <br />0.0642 hours <br />3.819444e-4 weeks <br />8.78955e-5 months <br /> l

after off-line because of' low condenser vacuum).

I I

l i

I i

i I

l l

i l

1 2

3 F: Forced Reason:

4 Method:

i S: Scheduled A-Equipment Failure (Explain)

Exhibit G-Instructions for 1-Manual Preparation of Data j

B-Haintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3 -Automatic Scram Event Report (

) File D-Regulatory Restriction E-Operator Training & License Examination 4-Other (Explain)

(NUREG-0161) i 5

F-Administrative l

G-Operational Error H-Other (Explain) i f

.a

=

i DOCKET NO. 050-249 UNIT NAME Dresden Ill UNIT SHUTDOWNS AND POWER REDUCTIONS DATE October 1, 1983 COMPLETED BY D.C. Maxwell REPORT MONTH September, 1985 TELEPHONE (815) 942-2920 i

ll METHOD OF LICENSEE i

NO.

DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO CAUSE & CORRECTIVE l

(HOURS)

DOWN REACTOR 3 REPORT f CODE 4 CODES PREVENT RECURRENCE 4

85-09-19 F

245:40 c.

3 85-018-0 I.M. error-E.H.C. panel (245.67) recorder removed in Auxiliary Electric Room - computer sensed

)

Q signal being sent to maximum combined steam flow - turbine control valves closed and resul-i tant high flux caused reactor j

scram on APRM hi-hi.

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a l

I t

i<!i

)

1 2

1 3

F Forced Reason:

4 Method:

i S: Scheduled A-Equipment Failure (Explain)

Exhibit G-Instructions for 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (

) File D-Regulatory Restriction lI if E-Operator Training & License Examination 4-Other (Explain)

(NUREG-0161)

F-Administrative l'

G-Operational Error H-Other (Explain) a

~

AVERAGE DALLY UNIT POWER LEVEL DOCKET NO. 050-237 UtilT IT DATE October 1, 1985 COMPLETED BY n. c. Maxwell TELEPHONE 815/942-2920 MONTH September, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 726 17 678 2

758 18 681 3

758 19 746 4

763 20 770 5

769 21 693 6

762 22 751 7

761 23 771 8

719 24 771 9

735 25 770 10 388 26 778 11 343 27 779 12 341 28 772 13 430 29 467 14 618 30 0

15 482 31 16 564

f AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-249 UNIT III l

DATE October 1, 1985 l

COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 l

MONTH September, 1985

~

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

(MWe-Net)

(MWe-Net)

I 657 17 613 i

j 2

674 18 660 i

3 655 19 364 4

1 4

696 20 0

5 676 21 0

i 6

667 22 0

t 7

665 23 0

i 8

659 24 0

1 9

656 25 0

j 10 665 26 0

l 11 652 27 0

12 667 28 0

666 l

I3 29 17 i

i 14 617 30

+34 l

15 570 31 i

16 595 i

I

COMMONWEALTH EDISON COMPANY

~.

DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF September, 1985 HOUR MAXIMUM DAILY LOAD DAY ENDING KW 1

2100 1,503,900 2

1900 1,521,100 3

1400 1,528,100

)

4 1700 1,515,500 5

1000 1,520,700 6

1200 1,513,900 7

0700 1,510,900 8

2400 1,497,200 9

0300 1,499,300 10 0100 1,495,000 11 1300 1,168,200 12 2200 1,061,700 13 2400 1,290,100 14 2400 1,388,300 15 2000 1,115,900 16 2400 1,293,700 17 1700 1,419,300 18 0600 1,417,400 19 1300 1,467,800 20 1300 814,100 21 0100 776,600 22 1800 815,100 23 1100 816,800 24 1800 816,400 25 2300 816,400 26 1600 823,800 27 2300 824,200 28 0700 824,500 29 0100 808,700 30 2400 579,400 31

DRESDEN UNIT 2

SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION ATWS and Contain-Preventive W.R.

  1. 25235 N/A Replaced terminal blocks.

nr.nt Pressure to Torus Level Inboard A Feed-Corrective W.R.

  1. 25675 N/A Machined bushings, cut O' ring groove into water Check body of valve (rebuilt check valve).

Valve 2-22& '84 ATWS Relay ZsD Preventive W.R.

  1. 26819 N/A Cleaned relay contacts.

Turbine Stop Preventive W.R.

  1. 29646 N/A Checked stop valve limits per procedure.

Valves Everything tested ok.

Primary Contain-Preventive W.R. #35662 N/A All 34 relay coil assemblies replaced ment Isolation (Slave 1-34) per proced2re.

System Logic, U-2 Diesel Corrective W.R.

  1. 36728 N/A Replaced STR (HFA) relay - performed Generator adjustments per procedure.

Isolation Con-Preventive W.R.

  1. 37456 N/A Replaced relay coils and adjusted relays denser Control per procedure.

Circuit Valve #MO-2-1301-Preventive W.R.

  1. 38495 N/A Replaced open resistor. Open circuit is 10 Local MO Valve good.

Station APRM Channel 1 Preventive W.R.

  1. 39435 N/A Performed procedure and replaced potentiometer.

MO-202-5A Preventive W.R.

  1. 39857 N/A During decon installed and removed Discharge Valve jumper.

R l

DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION D-2 Diesel WM Preventive W.R. #39868 N/A Replaced watthour meter per work 2-6641-1 instructions.

U-2 HFA Relays Preventive W.R.

  1. 40270 N/A Replaced relays per marking and prints 595-ll5A and (panel).

595-ll6A U-2 Relay Corrective W.R.

  1. 40559 N/A Tested and replaced relay.

590-107C Rafuel Grapple Preventive W.R.

  1. 40877 N/A Adjusted slack cable alarm.

j 125VDC Battery Preventive W.R.

  1. 41047 N/A Cleaned coated with NO-0X and tightened link.

}

1 l MO-2-1301-4 Corrective W.R. #41092 N/A Performed procedure and readjusted contact.

CRD 10-23 117 Corrective W.R.

  1. 41215 N/A Tightened fitting - stopped air leak, I

and 118 Valves CRD 14-19 117 Corrective W.R. #41216 N/A Tightened fitting - stopped air leak, and 118 Valves CRD 26-47 117 Corrective W.R.

  1. 41218 N/A Tightened fitting - stopped air leak.

and 118 Valves Refuel Grapple Preventive W.R.

  1. 41990 N/A Adjusted load cell according to work instructions.

U-2 MOV 2301-5 Preventive W.R. #42087 N/A Performed E.Q. inspection.

U-2 MOV 1501-28A Preventive W.R.

  1. 42094 N/A Performed E.Q. inspection.

U-2 MOV 2301-8 Preventive W.R.

  1. 42110 N/A Performed E.Q. inspection.

DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION U-2 Preventive W.R.

  1. 42192 N/A Performed procedure - placed in operating Diesel Generator service.

Refuel Grapple Corrective W.R.

  1. 42311 N/A Adjusted load cell.

Accumulator Preventive W.R. #42324 N/A Tightened fitting so water would not leak.

  1. 06-31 Accumulator Preventive W.R. #42325 N/A Tightened fitting to repair water leak.
  1. 06-31 Accumulator Preventive W.R.
  1. 42326 N/A Tightened fitting.
  1. 42-07 CRD Hydraulic Preventive W.R. #42591 N/A Tightened fitting.

Control Unit FCV2-305-120 MOV 1402-25A Preventive W.R. #43593 N/A Replaced grease and wiring and made splices per E.Q. instructions.

ESS UPS Corrective W.R.

  1. 43779 N/A Replaced 3 blown SCR's and blown fuse.

Drywell Eq. Dr.

Corrective W.R.

  1. 23782 N/A Set switch limits for correct valve Isolation operational indication lights.

V-2001-5

'C' CCSW PP Corrective W.R.

  1. 43844 N/A Straightened valve stem - tightened packing.

APRM Channel 4 Preventive W.R.

  1. 43893 N/A Performed procedure and replaced power supply.

A02-203-1D Main Preventive W.R. #43894 N/A Tightened all screw connections inside Steam Isolation terminal box.

Valve

r DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985

~~

LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT ~~

CORRECTIVE ACTION ERV 202-3C Preventive W.R. f44214 N/A Replaced indicating light socket.

l Sockst Analog Panel Preventive W.R. f44230 N/A Adjusted the gross failure alarm.

2202-73B LPRM 40-09-C Preventive W.R.

  1. 44474 N/A Replaced LPRM amp. card.

'A' Off-Gas MON Preventive W.R. f45533 N/A Calibrated per procedure.

SDV Hi-Level FCI Preventive W.R. f45622 N/A Checked alarms per procedure.

LS-2-302-82G, 80A, 82J and 82H HPCl System HFA Preventive W.R.

  1. 36743 N/A Adjusted relay and replaced core Relays (Slaves 1-38) assembly according to procedure.

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l DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Strndby Cas Preventive W.R.

  1. 34742 N/A Terminal blocks installed.

l Trretment P;nal 2223-28A HFA R21ay Preventive W.R.

  1. 39589 N/A Calibrated and replaced coil.

l Electric Heater Preventive W.R.

  1. 42174 N/A Performed E.Q. inspection.

7503A 1

l Spare Electro-Corrective W.R.

  1. 42472 N/A Rebuilt spare electromatic relief valve.

matic Valve l Log Rad Monitor Preventive W.R.

  1. 44349 N/A Troubleshot and replaced tube V3 and cleaned and calibrated monitor.

Control Room Preventive W.R.

  1. 45623 N/A All relay and contacts checked - everything i

HVAC System ok.

2/3 Rx Crane Preventive W.R. #45726 N/A Adjusted relay main hook limit switch.

Control Room Preventive W.R.

  1. 45744 N/A Checked system and charged both units l Back-up Vent with freon - all looks ok.

C/R and Office Preventive W.R.

  1. 45765 N/A Meggered all phases - replaced bad

! Exhaust Fan CR-120 relay.

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DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION LPRM 48-41A Preventive W.R.

  1. 37430 N/A Performed procedures.

LPRM will be (APRM 4) 3-705-replaced on future W.R.

  1. 45749.

002 D-3 LPRM 08-25-B Preventive W.R. #37495 N/A LPRM will be replaced on W.R. #45749.

Group 1 3-705-002 U-3 250 Charger Preventive W.R.

  1. 37496 N/A Replaced meter and adjusted volts for 262.

3 Channels A and B Preventive W.R.

  1. 37678 N/A Replaced alarm card.

I Condenser Low I Vacuum Alarm I (A-ll)

LPRM 24-41 A Preventive W.R. #37774 N/A Detector will be replaced on W.R. #45749.

Channel 3-705-l 002 Suppression Pool Corrective W.R.

  1. 38306 N/A Installed new doors, handles and removed bar on the recorders.

l Terperature l R: cord rsLPRM 48-17D Corrective W.R. #38820 N/A Replaced defected plant side cable (Channel 1) connector.

3-705-002 24-49C LPRM Preventive W.R. #38835 N/A Changed plant side connector.

3-705-002 LPRM 24-41D Preventive W.R. #39560 N/A Tested and will replace LPRM on W.R.

3-705-002

  1. 45749.

.o DRESDEN UNIT 3

SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION LPRM 24-175C Preventive W.R.

139597 N/A Changed plant side connector. Will 3-705-002 replace detector on W.R.

  1. 45749.LPRM 48-49D Preventive W.R.
  1. 39739 N/A Detector shorted. Will replace on (APRM) 3-705-W.R.
  1. 45749.

002 LPRM IC-32 Preventive W.R.

  1. 41304 N/A LPRM will be changed on W.R. #45749.

3-705-002 CRD C-7 Scram Corrective W.R.

  1. 41528 N/A Installed 2 new Asco valves and coil Prot. Solenoid assemblies.

305-117 10-27 MO-3-1001-5A Preventive W.R.

  1. 41543 N/A Replaced transfer and light socket.

Local Position Indicator HPCI Room Cooler Preventive W.R. #42162 N/A Replaced belts and adjusted for proper tension.

Drywell and Preventive W.R. #42421 N/A Replaced bad cell and press. control Torus CAM H valve.

2 Sensor 3-HM-2402-A and B MO-3-1501-13A Preventive W.R.

  1. 42655 N/A Replaced broken light bulbs.

MO-1501-50 Valve Preventive W.R.

  1. 42815 N/A Adjusted open limit stack.LPRM 24-490 Preventive W.R. #43114 N/A Shorted LPRM - will replace on W.R.

(Channel 4)

  1. 45749.

3-705-002 LPRM D 40-41D Preventive W.R. #43115 N/A Will replace LPRM on W.R.

  1. 45749 (Group 1) 3-705-002

1 DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION LPRM 48-41D Preventive W.R. #43116 N/A Shorted LPRM will be replaced on (Group 2)

W.R.

  1. 45749.

3-705-002 SRM/IRM Drive Preventive W.R.

  1. 43514 N/A Changed SRM/IRM alternate action select Control switch.

IRM 17 Drive Preventive W.R. #43575 N/A Changed IRM selector switch.

Control MCC-39-3 Preventive W.R.

  1. 43742 N/A Disconnected leads and retired cable.

LPRM 3-705-002 Preventive W.R. #44221 N/A Performed procedure and completed plateaus for all LPRM's.

LPRM 4D 40-33 Preventive W.R. #44294 N/A Performed procedure for LPRM.

SRM-21 RI3-750-Preventive W.R.

  1. 44593 N/A Calibrated and repaired meter.

3A Rod Block Moni-Preventive W.R.

  1. 44774 N/A Performed procedure and replaced power tor Channel 7 pot.

LPCI Ex Discharge Preventive W.R.

  1. 45025 N/A Investigated problem and found no apparent Valve 3-1501-3B malfunction of the valve at this time.

Reactor Building Preventive W.R.

  1. 45074 N/A Calibrated the recorder by comparing Exhaust Monitor reading and penetration - all ok.

Recorder 3-1705-21 APRM's Channels Preventive W.R. #45437 N/A Replaced relay for 5 APRM's.

1,2,3,5 and 6

DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - SEPTEMBER, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 24/48 Battery Preventive W.R. f45691 N/A Replaced timer motor.

Charger 3A Drywell Pressure Preventive W.R. #44831 N/A Replaced switch and performed procedure.

Switch (ECCS)

P.S. 1628B RBM 7 and 8 Preventive W.R. #45871 N/A Performed procedure.

Drive Flow Converters HPCI 3-2301-10 Preventive W.R. f45926 N/A Cleaned brush holders - connected leads.

Valve CAM Monitor Preventive W.R. f43677 N/A Temperature elements at both locations Systen TE3-2401, found to be connected.

001,002,003 and 004 LPRM 16-33B Preventive W.R. #44598 N/A Adjusted and calibrated LPRM 16-33B (Chtnnel 1) readings.

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SUMMARY

OF OPERATING EXPERIENCE l

UNIT TWO SEPTEMBER, 1985 09-01-85 to 09-28-85 Unit 2 entered the month operating at a level of 785 MWe and operated steadily l

through September 28, 1985.

l l

09-29-85 to 09-30-85 On September 29, 1985 at 2124 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.08182e-4 months <br />, I

the unit was manually taken off-line for the planned snubber inspection and environmentally qualified work in the drywell. At 2355, a reactor scram occurred because of low condenser vac-uum.

The unit remained off-line the remainder of the month. Capacity fac-tor is 80.81% and availability is 96.

31% for the month.

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SUMMARY

OF OPERATING EXPERIENCE UNIT THREE SEPTEMBER, 1985 09-01-85 to 09-18-85 Unit 3 entered the month operating, per Load Dispatcher's instructions, at a power level of 676 MWe and operated con-tinuously through September 18, 1985.

09-19-85 to 09-30-85 On September 19, 1985, at 1333 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.072065e-4 months <br />, a reactor scram and turbine trip occurred.

This was the result of a Maint. Dept.

error. An EHC recorder had been removed in the Auxiliary Electric room and the unit computer sensed a zero signal being sent to the maximum combined steam flow and the turbine control valves closed.

l The resultant high flux caused a reactor i

scram on APRM Hi-Hi.

The reactor was made critical September 29, 1985, at 0622 hours0.0072 days <br />0.173 hours <br />0.00103 weeks <br />2.36671e-4 months <br />, and the unit was brought on line at 1913 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.278965e-4 months <br />.

The unit operated the remainder of the month, stead-11y increasing load, reaching a power level of 525 MWe with an availability of 65.88%

and a capacity factor of 52.827.

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

Valves Descript.

Unit Reporting Period Actuated Actuations Conditions oi' Events 2

09-01-85 to 09 None 85 3

09-01-85 to 09 None 85

P

/

'x Commonwe:lth Edison

[

) Dr;sdin Nuclair Power Station

- - _ -- :7 FtR. #1

(

,/

Morris, Illinois 60450 N _s

Telephone 615/942 2920 October 1, 1985 DJS LTR: #85-963 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 in-structions set forth in Regulatory Guide 1.16.

Sincerely,

/W D. J. Scott Station Manager Dresden Nuclear Power Station DJS:DCM:rme 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 4

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