ML20094G329

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Monthly Operating Repts for Jul 1984
ML20094G329
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 07/31/1984
From: Schroeder B, Scott D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
84-766, NUDOCS 8408130271
Download: ML20094G329 (20)
v • d • e


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' OPERATING DATA REPORT DOCKET NO. 050-237 DATE August 3.

1984 COMPLETED BY B. A. Schrceder TELEPHONE (815) 942-2920 OPERATING STATUS NOTES L 1.

Unit Name:

Dresden II 2.

Reporting Perlod:

anty_ i oat, 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 This Month Yr-to-Date Cumulative.

I l'.

Hours in'Rcporting Period 744 5111 124,631 12.

Number of Hours Reactor Was Critical 720.9 4923.3 97,147.8 13.

Reactor Reserve Shutdown Hours 0

0 0

14. ' Hours Generator On-Line 700.8 4821.3 95.727.3 15 Unit Reserve Shutdown Hours 0-0 0

16.

Gross Thermal Energy Generated (MWH) 1.454.064 11.312.560 188.007.196 17 Gross Electrical' Energy Generated-(MWH) 457.957 3.663.974 60,166,173 18.

Net Electrical Energy Generated.(MWH) 431.759 3.475.843 56,864,107

19. - Unit Service Factor 94.19 94.33 76.81 20.

Unit Availability Factor 94.19 94.33-76.81~

i l

21.. Unit Capacity Factor -(Using MDC Net) 75.17 88.09 59.10-l,
22. _ Unit Capacity. Factor (Using DER Net) 73.09 85.65 57.46 i
23.

Unit Forced Outage Rate 5.81-5.67 11.38 l.

24.

Shutdowns Scheduled ;0ver Next - 6 Month.s (Type, Date, and Duration of Each):

Sentember 3.

1983 for refuel; @ 12 weeks.

l-

.25.

'If Shut: Down At End 0f Report Period, Estimated Date of Startup:

N/A i

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8408130271 040731 PDR ADOCK 05000237.

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s-OPERATING DATA REPORT.

DOCKET NO.

050-249 DATE August 3, '1984 COMPLETED BY B. A.' Schroeder TELEPHONE

- gg7_797n g3m

' OPERATING STATUSl

- NOTES 1.

Unit':Name:

Dresden'III 2.,; Reporting-Period: Julv. 1984 3

Licensed Thermal Power (MWt):

2,527 4..

Nameplate Rating. (Gross MWe):

828 6..

HDesign Electrical Rating (Net MWe):' 794 5.

Maximum Dependable Capacity (Gross.MWe): 812 7

Maximum' Dependable Capacity (Net MWe):

773 8.

If Changes Occur in Capacity ' Ratings (ltems 3 Through 7) Since Last Report, Give heasons:

N/A

.9 Power Level to Which Restricted, If Any (Net MWe):

' N/A 10.

Reasons For Restrictions, if Any:

N/A L

This Month Yr-to-Date Cumul.a t ive.

11.

Hours in Reporting Period 7aa 5111' 114.216 12.

Number of Hours Reactor Was Critical 254.1 580.2 83.425.2 13.

Reactor Reserve Shutdown Hours 0~

0 0

14.

Hours Generator On-Line 186.2 186.2 80,047.4 15 Unit Reserve Shutdown Hours n

0

- 0 16~.- - Gross Thermal Energy Generated (MWH) 2an_s93 248.593 160,209,691-17.- Gross Electrical Energy Generated (MWH) 74.54 1 74.541 52,027,460 18.'

Net Electrical Energy Generated.(MWH) 64.412 34.559 49.265.143

'19.

Unit Service Factor 24.03 3.64 70.08

_., 2 0.

Unit Availability Factor 25.03 3.64 70.08 21.

Unit Capacity Factor (Using MDC Net) 11.20 0.87 55.80

-22.

Unit Capacity Factor -(Using DER Net) 10.90 0.85 54.32 23 Unit Forced Outage Rate 0.0 0.0 12.64 J24.

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

N/A 25.

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

N/A 1

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c DOCKET NO. 050-237 UNIT NAME Dre-d n II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE August 3, 1984 COMPLETED BY B. A. Schroeder TELEP110NE (815) 942-2920 REPORT MONTil JULY, 1984 MET 110D OF LICENSEE CAUSE & CORRECTIVE NO.

DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (110URS)

DOWN REACTOR 3 REPORT #

CODE 4 CODES PREVrF~ RECURRENCE 3

84-7-9 F

21.01 G

3 While performing surveillances the Instrument Mechanic improp-erly performed.the' required surveillance test.

Action discussed with mechanic.

4 84-7-22 F

19.28 G

3 Unit 3 RO requested that a recirculation valve on the EHC operator opened. The Operator opened the valve on Unit 2 by mistake. Action discussed with Operator.

1 2

3 4

F:

Forced Reason:

Method:

Exhibit G-Instructions for S:

Scheduled A-Equipment Failure (Explain) 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 4-Other (Explain)

(NUREG-0161)

E-Operator Training & License Examination F-Administrative g

G-Operational Error Il-Other (Explain) t

7 1

DOCKET NO. 050-249 UNIT NAME Drred*n III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE August 3, 1984 COMPLETED BY B. A. Schroeder TELEPHONE (815) 942-2920 1

REPORT MONTH JULY. 1984 METHOD OF LICENSEE CAUSE & CORRECTIVE NO.

DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS)

DOWN REACTOR 3 REPORT #

CODE 4 CODE 5 PREVENT RECURRENCE 8

83-9-30 S

557.2 C

1 Main Turbine repair.

1 2

3 4

F:

Forced Reason:

Method:

Exhibit G-Instructions for S: Scheduled A-Equipment Failure (Explain) 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 4-Other (Explain)

(NUREG-0161)

E-Operator Training & License Examination.

F-Administrative G-Operational Error O

H-Other (Explain)

9 AVERAGE DAILY UNIT POWER LEVEL g'-

v DOCKET NO. 050-237 UtilT II DATE August 3, 1984 COMPLETED BY B. A. Schroeder TELEPHONE 815/942-2020 HONTH JULY, 1984 DAY

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

(MWe-Net)

'l 293 17 762 2

624 18 729 3-747 19

,,8 4

751 20 760~

5 758 21 749

'6 766:

22 522

7

-769 23 79

8 704 24 330 287 9

25 328 10 273 26 453 11' 635 27 354-12 739 28 344 l'

.13'

-74 2 29 399 14 743 30 665 748

- 15 627 31

, 161 724' l p-O L

L%

"l-AVERAGE DAILY. UNIT POWER LEVEL

,y kJ DOCKET NO. 050-149 UlllT III

-DATE August 3, 1984 COMPLETED BY B. A. Schroeder TELEPHONE 815/942-2920 MONTH Jin,Y. 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net)

(MWe-Net) 1 0

17 0

2' O

18 0

F:

3 0

19 o

4 0

20 0

(_N_)

5 0

21 0

6 0-22 0

0 7

23 0

8 0

24 76 0

9 25 121 10 0

26 173 11 0

27 367 12 0

28 27) 13 0

29 589 14 0

30 599 15 0

31

-631 16 0

I

DRESDEN UNIT 2

i SAFETY RELATED MAINTENANCE - JULY, 1984' NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION l

?

D-2 Diesel Preventive W.R. #34501 N/A N/A Removed valve between air regulator and i

Gen:rstor, gauge.

EPN #2-6601 l

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  1. 2 Di e1 Preventive W.R. #34718 N/A N/A Performed quarterly inspection.

j Gen:rctor

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Accum. 54-23, Preventive W.R. #34478 N/A N/A Installed new ball and o-ring.

Inspected EPN #2-0305-internals.

138 j

CRC Accum.

Preventive W.R. #34558 N/A N/A Repacked val;e.

22-35 2B LPCI Heat Preventive W.R. #35615 N/A N/A Adjusted 3 nuts to a full nut adjustment.

Exchrnger LPRM 40-33, Preventive W.R. #34051 N/A N/A Ran detector plateau.

4B HPCI 5 Valve Preventive W.R. #33786 N/A N/A Installed missing cover bolts.

Precrure Preventive W.R. #34970 N/A N/A Prepared welds for ultrasonic examination Suppreesion by grinding (flap) weld crowns.

Piping LPRM 16-49A Preventive W.R. #32497 N/A N/A Investigated LPRM sporadic operation (2) problem. Found and repaired bad connection. I Snubbsrs Preventive W.R. #26071 N/A N/A Disassembled snubbers per work package PSA-10 to investigate cause of failure.

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DRESDEN' UNIT 3

l-4 SAFETY RELATED MAINTENANCE - JULY, 1983

};

NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECIIVE ACTION 7i Refu21 Preventive W.R. #34522 N/A N/A Installed ~new control switch..

Grapple 1

(

Refuel Preventive W.R. #33522 N/A N/A Adjusted track limit switch for proper I

Grapple operation.

D-3 125V Preventive W.R. #34261 N/A N/A Adjusted equalizer voltage and recali-Bsttery brated panel meter with certified fluke.

I Charger 3A

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Relay AQ590-Preventive W.R. #33451-N/A N/A Repaired wire.and tested.

104A j

3-1501-27A Preventive W.R. #34785 N/A N/A Verified and adjusted proper torque settings.

D3 "A" LPCI Preventive W.R. #35610 N/A N/A Adjusted nut on stud for full thread Heat Exchan-engagement on nut.

ger, EPN

  1. 3-A-1503 Condenser Preventive W.R. #35245 N/A N/A Installed and removed jumper blocks.

Low Vacuum and MSIV Closure Bypass Relays SRM In/Out Preventive W.R. #34440 N/A N/A Investigated the SRM position indication Lights malfunction. Recently installed modifica -

tion of new relays and wiring was removed to permit proper operation of position L

indication lights.

'?

l DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - JULY, 1984 F

NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION l

5 D-3 V:cuum Prevcntive W.R. #33604 N/A N/A Inspected valve internals and repacked l

Brerk:rs, all (12) vacuum breakers, j

EPN #3-1601-l 32A thru F R fu:1 Preventive W.R. #34524 N/A N/A Adjusted track switch for proper operation.

Grepple Replic: ment Preventive W.R. #29712 N/A N/A Performed LPRM - insulation resistance LPRMs and breakdown checks.

LPRMs Preventive W.R. #31178 N/A N/A Removed 10 LPRMs and installed 10 new LPRMs.

Reactor Preventive W.R. #34698 N/A N/A Replaced 120 and 122 solenoid.

M nual Con-trol Timer Sy: tem Steamline Preventive W.R. #34776 N/A N/A Replaced auxiliary contact on right side.

Drcin Isola-tion Valve Pre:sure Preventive W.R. #30665 N/A N/A Adjusted pressure switch for proper Suppression operation.

AO Velve 3-1601-22 LPRM Ccrd Preventive W.R. #34872 N/A N/A Replaced components required and completed checkout of LPRM card;.

R:rctor Bldg. Preventive W.R. #31093 N/A N/A Replaced solenoid valve.

Supply Valve l

l

DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - JULY, 1984 NATURE OF LER OR OUTACE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Air Inlet Preventive W.R. #29898 N/A N/A Replaced tubing to E/P 3-2540-17B leak.

Flow Conver-Checked ok, tar-Air Supply for ACAD E/P 3-2541-17B 3E Electro-Preventive W.R. #27901 N/A N/A Replaced electromatic pilot valve.

matic, EPN

  1. 3-203E ADS "AS" Preventive W.R. #34452 N/A N/A Replaced relay.

Rr;1ry 287-IISC M03-1501-38A Preventive W.R. #34995 N/A N/A Replaced bad light socket.

l 3C Electro-Preventive W.R. #34327 N/A N/A Removed operator.

matic Relief Velvu "on-trol l

i Torus to Preventive W.R. #35274 N/A N/A Repaired relay.

Drywmil Vicuua Brc k r M03-2301-6 Preventive W.R. #34984 N/A N/A Cleaned and tightened connections on light Local socket.

Switching Stction f

i HPCI Motor Preventive W.R. #34312 N/A N/A Repaired limit switch, i

Spe d Chrnger x

DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - JULY, 1984 NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION U-3 "E" Preventive W.R. #34022 N/A N/A Replaced sealtite on "E" safety valve.

Srfety Valve, EPN #203-3E RBCCW Supply Preventive W.R. #33347 N/A N/A Installed and tightened bolts.

Valv2 to Drywell D-3 24/48 Preventive W.R. #33574 N/A N/A Adjusted to 27 volts.

VDC Bottom "B" Chrrger SRM Diecri-Preventive W.R. #30722 N/A N/A Perfarmed SRM discriminator curves and cinstor adjusted DC voltage as needed.

Curves, EPN l

  1. 0700 l

HPCI System Preventive W.R. #34647 N/A N/A Adjusted limit switch lir.kage to correct i

reset problem.

i 3-1001-2A Preventive W.R. #33305 N/A N/A Corrected the open/close torque setting to i

3A SDC Pump permit proper valve operation.

Suction j

Velva Rx Bldg.

Preventive W.R. #33991 N/A N/A Investigated and corrected valve closing Vrcuum Brea-problem.

kar, EPN

  1. 3-1601-20B "A" ATWS Preventive W.R. #34796 N/A N/A Investigated high temperature problem.

I Invarter Found wrong fan installed. Will be replaced.

3

DRESDEN UNIT 3

SAFETY RELATED MAINTENANCE - JULY, 1984 I

NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION IRM Chrnnel Preventive W.R. #34752 N/A N/A Investigated IRM Channel A alarm problem -

High High No problem found.

or Inoper-eble Alarm MO 3-2301-3 Preventive W.R. #33061 N/A N/A Repaired broken sealtite by installing new j

fittings.

R rctor Preventive W.R. #31091 N/A N/A Replaced solenoid.

Bldg. Return Volva, EPN

  1. 3B-5742 R actor Preventive W.R. #31092 N/A N/A Replaced solenoid.

Bldg. Return

}

Velva, EPN

  1. 3A-5742 HFA Relays Preventive W.R. #30709 N/A N/A Replaced cracked relay covers with new ones, j Prnnels Preventive W.R. #30924 N/A N/A Replaced cracked covers on relays with new l

903-15 and

ones, r

903-17 RPS i

HFA Relays l

3B LPCI Heat Preventive W.R. #34926 N/A N/A Removed heads - found no leaks and installed Exchanger new heads.

D-3 CRDs Preventive W.R. #27876 N/A N/A Leak tested CRDs per procedure DMP 300-11.

,f "A" R:circu-Preventive W.R. #34442 N/A N/A Repaired and tested switch.

I 1rtion Pump Switch, EPN

  1. 3-261-35C j

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DRESDEN UNIT 3

SAFETY RELATED MAINTENANCE - JULY, 1984 NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Hi Up;cale Preventive W.R. #34536 N/A N/A Adjusted LPRM.

GRI LPRM 40-09D LPRM 08-25B Preventive W.R. #34388 N/A N/A Replaced Q8 and G4 on LPRM card, f

LPCI System Preventive W.R. #33694 N/A N/A Investigated and repaired faulty connectors Flow Indica-on flow instrumentation.

7 tir, EPN

  1. 3-1540-I I A "D" MSL Rad.

Preventive W.R. #34262 N/A N/A Replaced rad. monitor with spare monitor.

Monitor, EPN Tested for proper operation.

  1. 3-1705-2D Powar Supply Preventive W.R. #34284 N/A N/A Replaced defective diodes and adjusted i'

APRM "B" voltage. Checked for proper operation of Flow Con-flow converter.

i l

varter LPRM 48-33C Preventive W.R. #34563 N/A N/A Readjusted gain and LPRM per work package.

Bid LPRM Preventive W.R. #34428 N/A N/A Reset downscale trip set points.

l Down Scale S:t Points U-3 Accumu-Preventive W.R. #34603 N/A N/A Cleaned and reinstalled alarm.

lcter Hi i

Wattr Alarm f

(18-11)

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+

DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE - JULY, 1984 J

Il NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER.

CAUSE RESULT CORRECTIVE ACTION Rx Bldg.

Preventive W.R. #30193 N/A N/A Adjusted upper limit.

i Crant Spara Diesel Preventive W.R. #27268 N/;A N/A' Repaired 7 spare rectifier assemblies.

Gen 2rator Surge Sup-pressors IRM Monitor Preventive W.R. #33207 N/A N/A Repaired and calibrated spare IRM monitor.

TN-9 Spent Preventive W.R. #34862 N/A N/A Inspected, repaired and replaced parts of.

Fuel Cesk the TN-9 cask.

f, Spnre IRM Preventive W.R. #31816 N/A N/A Removed kinks from two snare IRM detectors.

Detectors 2/3 SBGT Preventive W.R. #34242 N/A N/A Removed and replaced restraint.

I R2streint 2/3 SBGT Preventive W.R. #35073 N/A N/A Removed and replaced pipe restraint.

Restraint (Qurd Cities Preventive W.R. #33766 N/A N/A Disassemblad, lapped and tested valve.

Sptre) Rx Safety Valve S/N Breaker 6249 Storeroom Preventive W.R. #34527 N/A N/A Calibrated / tested spare switch and returned Spare Diesel to Stores.

Gsnerator Crenk Case Pressure Switch l-t

DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE - JULY, 1984 NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION U-2/3 Safety Preventive W.R. #35049 N/A N/A Checked relays for deterioration per RJ1rtid HFA I.E.Bulletin 84-02.

Wrote additional Ralcy Work Requests for defective relays (2).

IRMs Preventive W.R. #33407 N/A N/A Checked all IRMs for proper fuse amperage.

Replaced two improperly sized fuses.

Errton 368 Preventive W.R. #29693 N/A N/A Rebuilt and tested spare transmitter.

Tre:nraitter Amplifier t

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. i

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SUMMARY

OF OPERATING EXPERIENCE UNIT ONE JULY, 1984' The status of Unit I remains shutdown with all fuel removed. The environ-ment and equipment continues to be maintained as needed.

Last month it was reported that-the activities for chemical cleaning have increased.- The defective discharge outlet on the concentration recircula-tion pump _has been repaired and is operational again.

During the last.few days of the period a " Mock Run" was performed. This included pressurizing and heating of the Unit I reactor and piping. The

-purpose of the test was to determine the integrity of all involved systems and operator competence.

JL small number of flange leaks were noted during the test which will necessi-

. tate a delay'in the actual chemical cleaning. It is expected that by early August the long awaited ' chemical cleanir.g project will be in operation.

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SUMMARY

OF OPERATING EXPERIENCE UNIT TWO

f.

JULY, 1984 07-01 to 07-09 Unit 2 was in the process of being put on-line at the -

end of the last reporting period. At 0246 hours0.00285 days <br />0.0683 hours <br />4.06746e-4 weeks <br />9.3603e-5 months <br /> (7-1-84)
Unit 2 was again on-line. Normal ramp rates and procedures were followed and by the 3rd of July the power output was over 800 MWe.

On the 9th during normal operation, while performing surveillance tests, an Instrument Mechanic improperly per-formed the steam line high rad.iation monitor test which caused.the plant to scram. All safety systems performed as designed. A startup was then initiated to recover the Unit.

07-10 to 07 The unit operated continuously during this period (with normal power reductions on weekends for surveillances) until the 22nd of July. The~ Unit 3 RO requested that a recirculation valve on the EHC system be opened. The' operator opened the valve on Unit 2 by mistake which resulted in a Unit 2-scram. All systems performed as designed.

07-23 to.07 A startup was initiate'd'to again recover the' unit, however, problems developed with the reactor feed pumps (RFP)'. The seal on one punip developed a leak while' the other received '

damage due'to.a leaking discharge check' valve (pump turning backwards)..-This left only one operational RFP and restricted the power level to about 350 MWe.

By the 29th a second RFP became available and unit power.

level was: increased (at designed ramp rates) until at the close;of this period the unit was once again above 800 MWe.

The unit achieved a capacity factor of 73.81% and an avail-

-aaility of 94.18%.

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SUMMARY

OF OPERATING EXPERIENCE

. UNIT THREE JUbY, ~1984-07-01 to 07.-24

-Th'e': final work on the' main' turbine was completed during

~

.this' period. luue long awaited startup was commenced with.

. criticality being achieved by the 21st. However,Lon the

-22nd the reactor scrammed due to MSIV closure with greater

'than 600-pounds reactor pressure. After the scram was reset, the unit was again prepared for startup and by the afternoon the unit was critical.

Unit heat-up continued along with turbine < warm-up. -After initial turbine rolls and instrument checks, the turbine was synchronized to-the grid. A loud " hurrah" wasithen heard in the Control Room which meant.the official end to a long outage that began September 30, 1983. The turbine.

performed as expected.

07-25 to 07-31

.A 150 MWe level was established on the unit by adjusting control rods. This~ allowed for tests, i.e. scram testing to be performed which is required at the end of each refueling outage. By months end the unit was operating at'680 MWe but was limited due to condensate demineralizer

~

differential pressure.

The unit achieved a. capacity factor of 12.04% and an availability of 25.03%

.}

UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period 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.actua-tion.

Valves Description Unit

.Date Actuated Actuations Conditions of Events 1

07-01-84 to 07-31-84 None 2

None 3

None

m Commonwealth Edison Dresden Nucle:r Power SLtion R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 August 3, 1984 DJS LTR: 84-766 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.

Sincere y, D.

. Scott Station Superintendent Dresden Nuclear Power Station DJS: BAS: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. Nue. Sta.

Tech. Staf f EA On-Site NRC Inspector Sta. Nuc. Eng. Dept.

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

.r&2.y y,

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