ML20083G757

Monthly Operating Rept for Nov 1983

ML20083G757
Person / Time
Site:	LaSalle
Issue date:	11/30/1983
From:	Diederich G, Lin D COMMONWEALTH EDISON CO.
To:	NRC
References
NUDOCS 8401120215
Download: ML20083G757 (24)

Text

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LASALLE NUCLEAR POWER STATION UNIT I MONTHLY PERFORMANCE REPORT NOVEMBER 1983-i

_ COMMONWEALTH ED1 SON COMPANY

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NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 a

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TABLE OF CONTENTS

1.

' INTRODUCTION-II.

SUMMARY

OF'0PERATING EXPERIENCE FOR UNIT ONE

- 111. PLANT ~0R PROCEDURE CHANGES, TESTS, EXPERlHENTS, AND SAFETY RELATED MAINTENANCE A.

Amendments ' to: Facili ty License or Technical. Speci fications B.

Facility or Procedure Changes Requiring NRC Approval C.

LTests and Experiments Requiring NRC Approval D.

' Corrective Maintenance of Safety Related Equipment IV~

LICENSEE EVENT REPORTS V.

. DATA TABULATIONS Operating <0ata Report' u.-

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions

.VI.

UNIQUE REPORTING REQUIREMENTS A.

14ain ~ Steam Relief Valve Operations B.

ECCS System _0utages C.

Off-Site Dose Calculation Manual Changes D.'

Major Changes to Radioactive Waste Treatment System E.

Changes to the Process Control' Program i

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lNTRODUCTION The LaSalle Nuclear Power Station Unit One-is a Bolling Water Reactor with_aldesigned electrical output of 1078 MWe net, located in Marsellies,

. lllinois.

The Station is owned by Commonwealth Edison Company. - The Architect / Engineer was SarSent's Lundy, and the primary construction contractor was Commonwealth Edison Company.

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-The condenser cooling method is a closed cycle cooling pond.

The plant Is subject _t<o License Number NPF-11, issued on April 17, 1982. The.date of initial criticality was June 21, 1982.

The unit has.not commenced commercial generation of power.

This report was complied by Diane L. Lin, telephone-number (815)357-6761, extension 499 o

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SUMMARY

OF OPERATlNG EXPERIENCE FOR UNIT ONF

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November 1-30 The unit started the reporting period at approximate'y 99% power.

On November 2, 1983 at 1002 hours0.0116 days <br />0.278 hours <br />0.00166 weeks <br />3.81261e-4 months <br /> reactor power was reduced to 40%, when the 'B' Reactor Recirculation Pump tripped for STP-34, Vibration Measurements Test. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on November l

2 reactor power was 68%.

On November 3 at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> the reactor scrammed due to opening the oil circuit breakers 9-10 and 10-11 during STP-27, Turbine Stop Valve Trip and Generator Load Rejection Test.

The reactor was critical for 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> and 45 minutes.

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• Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications.

There were no amendments to the facility license or technical specifications during the reporting period.

B.

Facility or Procedure Changes Requiring NRC Approval.

There were no facility or procedure chariges requiring NRC approval during the reporting period.

C.

Tests and Experiments Requiring NRC Approval.

There were no tests or experiments requiring NRC approval during the reporting period.

D.

Corrective Maintenance of Safety Related Equipment.

The following tables present a summary of safety-related maintenance completed on Unit One during the reported period.

The headings in-dicated in this summary include: Work Request Numbers, LER Numbers,

Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.

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ATTACllflEHT 'A L i l'- 300- /

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CORRECTIVE ltAINTENANCE OF Harch 1, 1983 SAFETY RELATED EQUlPHENT 5

UOl!K l'.f. QUES'I

. LER C0!!P0lli.ill CAUSE OF llAl.fullCTI0ll RESULTS A!!D EFFECTS -

00ltRECTIVI. AC rl0!!

Oil SAFE OPERATI0li L16276 83-139/03L-0 Standby Gas Done per modification No effect Replaced valve with a 3/4" valve Treatment Vent Sample Conditioner L26968 Diesel

'0', '1A' Done per modif cation To prevent cl'sure of Installed o

L26969 and ' 1 B' the diesel breaker when synchrocheck relays L26970 Synchocheck the D/G is out-of phase Relays with the grid i

L27451 "0" Diesel Wattmeter was out-of-adj us t-Wattmeter cycles between Calibrated wattmeter 2100 and 2400 KW when Generator ment loaded to approximately 2400 KW L28333 83-122/03L-0 RCIC Steam Line Mircoswitch stuck Switch failed to reset Tapped switch and it rese t Di f fe ren ti al Pressure Switch L28543 Control Room Mechanical defect in index Won' t advance paper &

leplaced motor Radiation motor won't print Recorde r L28598 OPL58JA SBGT Bad vacuum pressure transducer Local audible alarm did Replaced var,uum Monitor not actuate when sample pressure transducer air flow is lost i

L28718 Damper OVC03YB Neutral to ground lead off Damper remained open Relanded lead neutral bus during surveillance i

L28848 "A" RHR Service Oiler incorrectly installed Bearing leaks oil Reset oil bubbler Wa te r Pump on outboard bearing L29057 83-135/03L-0 SBGT WRGM Bad fuse Los t al l con t rol powe r Replaced fuse

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ATTACittlElli A L il'- 300 - /

Revision 3 CORRECTIVE IMINTEllAllCE OF March 1, 1983 SAFETY RELAiED EQUIPHENT 5

UORl' l'I.qtJES~I 1.ER C0!!!'0!!!.fil CAUSE OF llAl.fUllCTI0li RESULTS All0 EFFECTS -

Collnr.CIlvi. ACI'l0!!

Oil SAFE OPERATIO!!

L29166

'83-127/03L-0 RBM ' A' Defective power supply ASC level detectors are Replaced power reading wher an edge rod supply is selec.ted L29381 Keylock swi tch Keylock switch is stripped Key turns f reely, 360 Replaced keylock for IE32-F008 s9 switch L29389 APRM Flow

'A' Flow meter stuck at 62%

'A' flow meter reads Repai red ' A' flow Compari tor Uni t higher than

'B',

'C', or meter

'D' L29427 Shutdown Cooling Operator needed rebuilding Handwheel shaft bent Rebuilt operator Inboard Isolatior Valve L29443 HPCS Relay KX22 Relay contacts bound Relay did not drop out Replaced relay during surveillance L29578 Mechanical Snubber locked Snubber is inoperable Replaced snubbers L29579 Soubbers L29580 Intermediate Faulty inop inhibit switch Caused 1/2 scrams during Replaced switch L29610 Range Monitor functional testin~g

'C' L29623 HPCS full flow Tripping at 114a Tripped when attempting Adjusted breal<er I

Test Valve to to open from panel to trip at 140'a 1H13-P601 CST Diesel Generator Annunciator module loose Failure-to-start alarm Installed module L29624

'O' up without starting D/G into socket tightly RR Sample Valve Air diaphram bad Valve leaks Replaced air L29741 diaphram l

L29803 Drywell Pressure Di rty slidewi re and servo-Indication bogus Cleaned slidewire Recorder amplifier pin connectors and servoampli fier pin connections

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IV.

LICENSEE EVENT REPORTS I

The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, November 1 through November 30, 1983 This In forma t ion is provided pursuant to the reportable occurrence reporting requirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specificaticns.

Licensee Event Report Number Date Title of Occurrence 83-122/03L-0 10/07/83 RCIC isolation 83-123/01T-0 10/24/83 Loss of Secondary Containment Integricy 83-124/01T-0 10/26/83 Loss of Unit 2 SAT 83-125/03L-0 10/21/83 "1A" Rod Block Monitor 83-126/03L-0 10/27/83 Uncoupled Control Rod 30-19 83-127/03L-0 10/31/83 Malfunction of ' A' Rod Block Monitor 83-128/03L-0 10/16/83 Fai lure to Tes t 1 A DG Operable 83-129/03L-0 l

10/18/83 Critical Date Exceeded LIS-RR-01 83-130/03L-0 10/21/83 Stack WRGM 83-131/03L-0 i

10/19/83 Jet Pump 14 s 15 and 18 c.

19 Out of Spec on 24 Hour Surveillance 83-132/03L-0 10/20/83 HPCS Diesel Generator 83-133/03L-0 10/24/83 Loss of Primary Containment Integrity 83-134/03L-0 10/28/83 Blowdown Flow Recorder 83-135/03L-0 10/28/83 Failure of VG WRGM 83-136/03L-0 10/26/83 RWM Fai i ure 83-137/01T-0 11/13/83 Drywe l l Instrument N Outboard 7

Isolation Suction VaTve Blocked Open

t LICEf4SE EVE!4T REPORTS (Continued) 83-138/03L-0 11/01/83 2A D/G "A" Ai r Compressor 83-139/03L-0 11/02/83 Standby Cas Treatment Sample Line 83-140/03L-0 11/23/83 Jumpers on Wrong Unit Panel 83-141/03L-0 11/02/83 Failure of OG H Analyze r "A"

2 83-142/03L-0 11/04/83 Shutdown Cooling Suction inboard Isolation Valve Failure to Open

\\4 V.

DATA TABULATIONS The following data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions

1 LTP-300-7 Revision 3 ATTACH ~.ENT C M

March 1, 1983 7

OPERATING DATA REPORT 00CKET NO.

050-373 f

LaSalle One l

UNIT l

DATE nnconsor o 1993 T

Diane L.'Lin COMPT.ETED BY-u (815)357-6761 x49j TELEPHCNE l

B OPERATING STATUS r

l November 1983 GROSS. HOURS IN REPORTING PERIOD: 720,,

1. REPORTING PERIOD:

l 100%

MAX. D EPEND. CAPACITY (MWo Netn 0

2. CURRENTLY AUTHORIZED POWER LEVEL (MWti:

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DESIGN ELECTRICAL RATING iMWo. Net):

1078 I

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3. POWER LEVELTO WHICH RESTRICTED (IF ANY) (MWe Net):

4. REASONS FOR RESTRICTION (lF ANY):

THl$ MONTH YR TO DATE ' CUM'ULAT1v E L

5. NUMEER OF HOURS REACTOR WAS CRITICAL..............67.8 M17 L 6364.8 1

0 0

0

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ff S. R EACTO R R EMMV E SHUTDOWN H OU RS...................

3086.8 4945.38

7. HOURS GEN ER ATdON U N E.......................... 6 7. 8 0

0 0

E. UNIT RESERVE SHUTDOWN HOURS......................

187365 5864648 ' 8005227

9. GROSS THERMAL ENERGY GENER ATED (MWH1 to. GROSS ELECTRICAL. ENERCY GENERATED (MWHI............ 61072 1782781 2304080

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............. 50157 1639809 2100584 __

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11. NET ELECTRICAL ENERGY CENERATED (MWHI NA NA NA 1

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12. REACTOR SERVICE FACTOR...........................

NA NA NA i

13. R EACTOR AV All.ASILITY F ACTOR.......................

NA NA NA

14. UNIT SERVICE FACTOR..............................

NA NA NA h

15. UNIT AVAILABILITY F ACTOR..........................

NA NA NA l

16. UNIT CAP ACITY FACTOR iusing MDCI.....................

I NA NA NA i

17. UNIT CAPACITY F ACTOR (Usens Demon MWel.................

j NA NA NA

18. UNIT F O RCE D OUTAG E R ATE..........................

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19. SHUTDOWNS SCHEDULED OVER NEXT E MONTHS (TYPE. DATE. AND DURATION OF EACHl:

f I2/lb/83 1

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20. IF SHUT DOWN AT END OF REFORT PERIOD. ESTIMATED DATE OF STARTUP:

FORECAST ACHIEVED

21. UNITS IN TEST STATUS (PRICR TO COMMERCIAL OPERATION 1; 6/21/83 INITI AL CRITICALITY 9/04/82 j

dilTI At. ELECTRICITY 12/31/83 couMERCIAL OPERATION I

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r LTP-300-7 Ravision 3 ATTACHMENT B March 1, 1983 l,

6 AVERAGE dilly UNIT POWER LEVEL p.

DOCKET NO. ncn_272 LaSalle One UNIT DATE December 9,1983 COMPLETED BY Diane L. Lin TELEPHONE (815)357-6761 X499 p

L MONTH November 1983 L

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

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1052 37 1

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These figures will be used to p'ut s paph for each repor:ing mon:h. Nute that when rn d h

wed :er the itet c:ee: ieai rar:ng of the urat. the:e may be oce:stens when the d::ly sver:Se

'l in caeh 4::>es. ihe a* crap da.h emt powe: ou:put sheet should be s0 See f or r.t :o::.::d pese lesci !ine) twinerej eex;..:::: L::

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ITP-300-7

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ATTACIIHENT '..E UNIT SiluTDOWNS AND POWER REDtt0TIONS DOCKET Slo. __959-373 UNIT NAHE LaSalle One REPORT HONill November 1983 DATE December 9,83 00HPLETED BY Diane L. Lin TELEPl10llE (815)357-6761 M3V llElll0D OF TYPE Sil0TTING DOWN F: FORCED DURATION Tile REACTOR OR NO.

DATE S: SCllEDULED (Il00RS)

REASON (1)

REDUCING POWER (2)

' CORRECTIVE ACT10NS/C0titlEN15' 41 11/2/83 S

0.0 B

5 Tripped the 'B', Pea g 34 Recarc Pump durivig 42 11/3/83 S

652:15 B

3 Opened oil circuit breakers 9-10 and 10-11 for STP-27 I

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VI.

UNIQUE REPORTING RE0UIREMENTS A.

Main Steam Relief Valve Operations for Unit 1 Relief valve operations during the reporting period are summarized in the following Table.

The table included information as to which relief valve was actuated, how it was activated and the circumstances resulting in its actuation.

Valves No & Type Plant Description Date Actuated Actuations Conditions of Events 11/3/83 1821-F013S 1 Automatic 1070 psig STP-27 11/3/83 1821-F013V 1 Automatic 1070 psig STP-27 11/3/83 1821-F013E 1 Automatic 1070 psig STP-27 B.

ECCS Systems Outages There were no ECCS System Outages during this reporting period.

C.

Off-Site Dose Calculation Manual The following changes were made to the Off-Site Dose Calculation Manual effective September 1983 1.

Page 8.4-2, Table 8.4-1, item 2 The number of "other sites" is 24, not 40.

There are 8 inner ring TLD locations and 16 outer ring TLD locations.

2.

Page 8.4-2, Table 8.4-1 This program is a 2 year program which began with September 1982, and will terminate in September 1984.

3 Page 8.4-5, Table 8.4-2 Subsequent program will commence in 1985 Refer to item 2 above.

4.

Page 8.4-6, Table 8.4-2, i tem 2b Refer to i tem 1 above.

1. ^-

- The changes incorporated into pages 8.4-2, 8.4-5, and 8.4-6 and shown as Revision 10, September 1983 are changes in the administration of the program.

The accuracy or reliability of dose calculatI6ns and setpoints are not reduced. The subject changes were reviewed and found acceptable by the Onsite Review and investigative Function.

Attached are copies of the revised pages to the'0DCM and Onsite' Review, OSR 83-33, dated August 30, 1983 D.

Radioactive Waste Treatment System

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There were no changes to the Radioactive Waste Treatment System during this reporting period.

E.

Process Control Program There were no changes to the Process Control Program during this reporting period.

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TABLE 8.4-1 RAD 10 LOGICAL MONITORING PP0 GRAM (1982 - 1984)

TYPE AND FREQUENCY FREQUENCY NONR00 TINE SAMPLE MEDItM OF ANALYSIS

• COLLECTION SITES OF COLLECTING REPORTING LEVELS 1.

Airborne 3

a.

Particulate Gross beta - W.

Seneca, Marseilles, Continuous Cs-134, 10 pCi/m 3

Filter Sr 89, 90 - Q. comp.

Ottawa, Grand Ridge operation of a Cs-137, 20 pCi/m Gama Spec. - Q. comp. xceator, Ransom, sampler for a Route 6 at Gonnam Road, week Kernan, and six stations near the site (see Figure 8.4-1)

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3 b.

Charcoal I-131 Same as for la Continuous 0.9 pCi/m m

L Cartridge operation of a m

A3 sampler for 2 weeks 2.

TLD Gama Same as for la, plus 24 Quarterly None Radiation other sites distributed near the site boundary and at 5 miles (see Figures 8.4-1 and 8.4-2)

Minimum of 2 TLD's per packet g

M m u,$

3.

Surface Water Sr-89, 90 - Q. comp.

Illinois River at intake Weekly Gama Spec. - M. comp. of Illinois Nitrogen Corp.

w Gross beta - W.

Illinois River at Marseilles 4

Tritium - Q. comp.

Illinois River at Ottawa Illinois River at Seneca South Kickapoo Creek Cooling lake near recreation area a

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TABLE 8.4-2 RADIOLOGICAL MONITORING PROGRAM (1985 and Later)

NONR00flNE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **

1.

Air a.

Onsite and near field

• a.

Filter -

a.

Continuous Cs-134, 10; 3

Monitoring gross beta ***

operation of a Cs-137, 20 i,Ci/m 1.

Nearsite Station 1 sampler for a 2.

Onsite Station 2 week 3.

Onsite Station 3 3

4.

Nearsite Station 4 b.

Charcoal -

b.

Continuous 0.9 pCi/m 5.

Onsite Station 5 1-131 operation of a 6.

Nearsite Station 6 sampler for r-2" 2 weeks P'

c.

Sampling c.

Weekly Not Applicable

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Train -

Test and Maintenance b.

Far Field

• 7.

Seneca a.

Filter a.

Continuous Cs-134, 10; 3

8.

Marseilles Exchange operation of a Cs-137, 20 pCi/m 9.

Grand Ridge sampler for a when analyses

10. Streator week are made ElY

11. Ransom 3

12. Kernan b.

Charcoal b.

Continuous 0.9 pCi/m 21 :5

13. Route 6 at Exchange operation of a when analyses E!$

Gonnam Road sampler for are made 81 5!

14. Ottawa 2 weeks 00' c.

Sampling c.

Weekly Not Applicable Ej Train -

Test and Maintenance

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TABLE 8.4-2 (Cont'd)

NONR00 TINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **

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TLD a.

Same as item 1, Air Gama Quarterly None Monitoring Sites

• Radiation b.

Plus 24 other sites l

distributed about the site boundary and at 5 miles * (minimum of 2 TLD's per packet) 3.

Fish a.

Marseilles Pool of Gama Semi-annual pCi/kg wit weight j

Illinois River Isotopic 4

Ma-54 3 x 10 r

4 Co-58 3 x 104 co Zn-65 2 x 10 II b

3 F

Cs-137 2 x 10 A

4 Fe-59 1 x 104 Co-50 L x 10 3 Cs-134 1 x 10 4.

Milk a.

Three nearby dairies I-131 a.

Weekly pCi/l or private animals during I 131 3

including the nearest, grazing Cs-134' 70 if possible season, May Cs-137 60 to October Ba-La-140, 300 b.

Monthly, Same as above mg November o<

to April S$E

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,i il TABLE 8.4-1 RA0lGLOGICAL MONITORING PROGRAM (1982 -

ln'tH TYPE AND FREQUENCY FREQUENCY NONR00 TINE SAMPLE MEDIUM OF ANALYSIS

• COLLECTION SITES OF COLLECTING REPORTING LEVELS _

1.

Al.rborne 3

a.

Particulate Gross beta - W.

Seneca, Marsefiles, Continuous Cs-134, 10'p01/m F il ter Sr 89, 90 - Q. comp.

Ottawa, Grand Ridge operation of a Cs-137:, 20 pCl/m Gama Spec. - Q. comp.

Streator, Ransom, sampler for a Route 6 at Gonnam Road, week Kernan, and six stations near the site (see I

r-Figure 8.4-1) j g

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4 b.

Charcoal I-131 Same as for la Continuous 0.'9'pCl/m p

n Cartridge operation of a sampler for 2 weeks 1

aq 2.

TLD Gama Same as for la, plus %

Quarterly None i

Radiation other sites distrituted near.the site boundary *:

and at 5 miles (see 3,,

Figures 8.4-1 and 8.4-2)

Minimum of 2 TLD's per j;'a QG packet

._, i:'i op 3.

Surface Water Sr-89, 90 - Q. comp.

Illinois River at intake Weekly Gama Spec. - H. comp.

of Illinois Nitrogen Corp.

Gross beta - W.

Illinois River at Marseilles Tritium - Q. comp.

Illinois River at Ottawa Illinois River at Seneca South Kickapoo Creek Cooling take near recreation area

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TABLE 8.4-2 d

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R D10 LOGICAL MONITORING PROGRAM h and later)

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l@f NONROUTINE SAMPLE MEDIA

_ COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **

1.

Air a.

Onsite and near field

• a.

Filter -

a.

Continuous Os-134, 10; 3

Moaltoring gross beta ***

operation of a Cs-137, 20 pCI/m 1.

Nearsite Station 1 sampler for a 2.

Onsite Station 2 week 3.

Onsite Statien 3

,3 4.

Nearsite Station 4 b.

Charcoal -

b.

Continuous 0.9 pCl/pi 5.

Onsite Station 5 I-131 operation of a 6.

Nearsite Station 6 sampler for 2 weeks j

2-m c.

Sampilng c.

Weekly Not App 1,1 table p

Train -

Test and i

Maintenance i

3 b.

Far Fleid*

7.

Seneca a.

Filter a.

Centinuous Cs-134,'10; 3

11.

Marsellics Exchange operation of a Cs-137, 2D pCl/m

~

9.

Grand Ridge sampler for a when analyses 10.

Streator week are matie' j,,

,, m 11.

Ransom 3

n 12.

Kernan b.

Charcoal b.

Continuous,U "0.'9 pCf/m 2,7 13.

Route 6 at Exchange operation of a when analyses

,_. g Gonnam Road sampler for are made gx 14.

Ottawa 2 weeks c.

Sampling c.

Weekly Not Applicable Train -

~

Test and Maintenance m

)

,I ll TABLE 8.4-2 (Cont'd)

NONROUTINE SAMPLE MEDIA COLLECTION SITE - t-TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **

2.

TLD a.

Same as item 1, Air Gama Quarterly None Monitoring Sites *

' Radiation A']

b.

Plus M other sites distributed about the

~

site boundary antj at 5 mites *1 (minimun of 2 TLD's per packet)

I 3.

Fish a.

Marsellies Pool of Gama Semi-annual pCl/kg wet weight Illinoit River Isotopic Mn-54 l 3.x10l Co-58 l.

3 x 10 4

,m Zn-65 2 x 10 p

3 p

Cs-137,1 2 x 10 p

4 m

Fe-59 I,.

I x 10 m

4 Co-60 j 1 x 103 Cs-134 >-

1 x 10 a.

Weekly pC1/1 4.

Milk a.

Three nearby dalries 1-131 "

or private animals during g,g 3 g 'i, 3

~

grazing Cs-134 70 including the nearest, if possible season, May Cs-137 {'

60 to October g,,g,,40, 300

.?, y,

.o b.

Monthly,',i

" fame as above 25 November

9 to April g.

.i

7 N Commonw: Ith Edison

/

')

LaSalle County Nuclear Station

(

Rural Route #1, Box 220 C-7 Marseilles, Illinois 61341 1

\\

\\

j Telephone 815/357-6761 December 9, 1983 Di rector, Of fice of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station, Unit One, for the period covering November 1 through November 30, 1983 Very truly yours, G

J. Diederich Station Superintendent LaSalle County Station GJD/DLL/bej Enclosure xc:

J. G. Keppler NRC, Region lli NRC Resident inspector LaSalle Gary Wright 111. Dept. of Nuclear Safety D. P. Galle CECO D. L. Farrar CECO INP0 Records Center Ron A. Johnsor., P/P Coordinator SNED 9 k

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