Text

Monthly Operating Repts for Aug 1988 for LaSalle Nuclear Power Station,Units 1 & 2
	ML20154C812
Person / Time
Site:	LaSalle
Issue date:	08/31/1988
From:	Diedrich G, Samonlinski S; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	0043R-0031R, 43R-31R, NUDOCS 8809150036
	Download: ML20154C812 (31)
	v • d • e

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1 LASALLE NUCLEAR POWER STAT 10tl !

UNIT 1 -

MollTHLY PERFORMANCE REPORT '

AUGUST 1988 P I

C009tONWEALTH EDISON COMPANY r

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LICENSE WO. WPF-11 [

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TABLE OF CONTENTS

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1. INTRODUCTION -

II. MONTHLY REPORT FOR UNIT ONE A. Sunesary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED l MAINTENANCE ,

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1. Amendments to Facility License or Technical Specifications l

2. Changeo to pre edures which are described in the Safety '

Analysis Re,3

3. Teste and E ,e;b not covered in the Safety Analysis Report [

4. Cor:.m.tive >$ -, of Safety Related Equipment [

5. Comt1,eted

Y- id Modifications. !

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D. DATA 't u'd # f

1. Operat port

7. Averac '" Unit Power Level [

3. Unit 8";. t.:wns and Power Reductions !

E. UNIQUR REPORTING REQUIREMENTS l t

1. Main Steam Relief Valve Operations ;

2. ECCS System Outajob l

3. OfE-Gite Dose Calculation Manual changes i

4. Major Changes to R6dioactive Waste Treatment System

5. Indications of Failed Fuel Elements e

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l I. INTR,ODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned I by Commonwealth Edison Company and located near Marseilles, Illinois. l j Bach unit is a Boiling Water Reactor with a designed net electrical !

j output of 1078 Megawatts. Waste heat is rejected to a man-made cooling ,

i pofF1 using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction ,

, contractor was Commonwealth Edison Company. I

l 1 Unit one was issued operating license number NPP-11 on April 17, 1982. f l Initial criticality was achieved on June 21, 1982 and commercial power '

operation was commenced on January 1, 1984.

i This report was compiled by Steven J. Samolinski, telephone number (815)357-6761, extension 705. <

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II.- MONTHLY REPORT FOR UNIT ONE A. SUW ARY OF OPERATING EXPERIENCE FOR UNIT ONE August 1-31 August 1, 0000 hours0 days 0 hours 0 weeks 0 months Unit one entered August with the Reactor critical and the Generator on-line at 900 We.

August 5, 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months Load drop to 638 We to collect RR data.

August 6, 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months Ramping to 943 We.

August 24, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months Load drop to 644 We for rod set.

August 25, 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months Ramping to 1096 We.

August 29, 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months Load drop to 803 We for heater drain problems.

August 31, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Unit one is on line and holding at 1100 We.

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PLANT OF, PROCEDURE CHANGES, TESTS, EXPEZIMENTS AND SAFETY RELATED Bo MAINTENANCE.

1. Amendments to Facility License or Technical Specification.

There were no amendments to the Facility License or Technical Specifications during the month of August. j

2. Changes to procedures which are described in the Safety Analysis l Report. i There were no changes to procedures which are described in the safety Analysis Report. ,

3. Tests and Experimente not described in the Safety Analysis Report. l There were no tests or experiments conducted during August which I are not described in the Safety Analysis Report. I i

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a Sumunary of safety-related I maintenance completed on Urd t one during the reporting period. The headings indicated in this zu.srtary include: Work Request number, component Name, cause of Malfunction, Kesults and Effects on Safe operation, and corrective Action. i f

5. Completed Safety Related Modifications. !

i The following Table (Table 2) presents a list of completed ;

Modifications during this reporting period. Rach cntry will have a !

short synopsis explaining details involved with each modification.

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l TABLE 1 CORRECTIVE :.Alh'ENANCE OF SAFETY RELNiG EQUIPMENT UNIT 81 -

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION R M LTS AND EFFECTS CORRECTIVE ACTION 4 ON SAFC PLANT OPERATION s

! L83334 ACB 1433 GE Magna- Breaker fali.ure due to breaker would not latch Repitcad breakn blast breaker wear and improper closed maintencnce 1

g L83216 IVROSYB Asco solenoid failure Damper would not clo:.;e Replaced solenoid

Isolation damper 1

) L75842 IVR04YA Asce solenoid failure Damper would not close Replaced solenoid Isolation damper a

L83168 ODGOIP Breaker failure resulted Unable to supply cooling Breaker and motor o D/G cooling in faulted motor windings water to OD/G, Div. I replaced

! water pung switchgear rooms, and LPCS pumps.

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TABLE 2

- t COMPLETED SAFETY RELATED MODIFICATIONS !

HODIFICATION NUMBER: A brief synopsis of incore 1 rated modificat. ion objectives ;

with final design resolution. Also, statu reviewed or (

unreviewed safety questions.

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UNIT ONE [

M-1-0-83-019 Installation and revision of floor drains and curbing in the f electrode boiler area. The new curbing will contain the t water which has collected on the floor in the boiler area. {;

M-1-1-85-018 Removal of the eF,isting dampers IVP02CA/B and their ;

associated operators and replace with standard galvanized, [

non safety-related dampers, j M-1-1-8'l-084 Snubber reduction on the Main Steam piping subuystem per l snubber reduction program.

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. C.- LICENSEE EVENT REPORTS I

The following is a tabular sunwnary of all licensee event reports for LaSalle Nuclear Power Station,ifpit One, logged during the reporting period August 1 through August 31, 1988. This information is provided I

pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 88-017-00 8/21/88 "B" vc Ammonia Detector I

Actuation.

88-018-00 8/22/88 0 D/G Cooling pump Motor Failure. l l

88-019-00 8/29/88 Failure of IB D/G Breaker to Auto close onto Bus within 13 i seconds.

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1 D. DATA TABULATIONS l l

The following data tabulations are presented in this report: l l

1. Operating Data Repcrt i

2. Average Daily Unit Power Level

3. Unit Shutdowns and Powcr Reductions 4

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1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE Sept. 10. 1988 COMPLETED BY S. J. Samolinski TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: _ August, 1988 GROSS HOURS IN REPORTING PERIOD 744 !

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net):_1036 DESIGN ELECT!!ICAL RATING (MWe-Net) .1078

3. POWER LEVEL TO VHICH RESTRICTED (IF ANY) (MWe-Net): None i

4. REASONS FOR RESTRICTION (IF ANY): None THIS MONTH YR TO DATE CUMULATIVE '

5 NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 ,,3_Q02.1 23046.6

6. REACTOR RESERVE SHUTDOWN HOURS 0,0 0.0 1642.0

7. HOURS GENERATOR OH LINE 744.0 2890.3 22320.3

8. UNIT RESERVE SitOTDCUN HOURS 0.0 0 . 0 ,_ 0.0

9. GROSS THEkMAL ENERGY GENERATED (MWH) 22cM968 8287560 60121858 1

10. GROSS ELEC. ENERGY GENERATED (MWH) 736521 2252901 19669677

11. NET ELEC. ENERGY GENERATED (MWH) 703253 3067338 19165979

12. REACTOR SERVICE FACTOR 100.0% 51.3% 56.3%

13. REACTOR AVAILABILITY FACTOR 100.0% 51.3% 60.3%

14. UNIT SERVICE FACTOR 100.0% 49.4% 54.5%

15. UNIT AVAILABILITY FACTOR 100.0% 49.4%__ 54.5%

16. UNIT CAPACITY FACTOR (USING MDC) 91.2% 50.6% 45.2%

< 17. UNIT CAPACITY FACTOR (USING DESIGN ,

MWe) 87.7% 48.64 43,4%

18. UNIT FORCED OUTAGE RATE 0.0%_ 4.8% 13.1%_,

19. SitUTDOWNS SCHEDULED OVER NCXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

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20. IF SHUT DOWN IS AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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2. AVERAGE DAILY UWIT POWER LEVEL ;

DOCKET WO: 050-373 L UNIT: LASALLE ONE '

DATE: Sept. 10, 1988 COMPLETED BY: S. J. Samolinski TELEPHONE: (815) 357-6761 MONTH: AUGUST, 1988 -

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVht (MWe-Net) (MWe-Wet) r

1. 950.6 17. 939.2

2. 974.0 18. 964.2 3 947.6 19. 989.8 i

4. 963.4 20. 910.1 I 5, 982.3 21. 898.8 :

6. 825.1 22, 952.5

7. 819.0 23, 926.7

8. 913.1 24. 1005.0

9. 1026.6 2 5 . ,__, 889.9

10. 990.0 26. 1039.2

11. 974.3 . , _ .

27. 991.4

, 12. 949.4 28. 886.1 13.__ 977.5 29. 895.3 l 14. 936.0 30. 908.7

15. 999.5 31. 939.5 i 16, 951.3 l

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3. UNIT SIIUTDOWNS AND POWE REDUCTIONS -

DOCKET NO. 050-373-UNIT NAMP 12Sa1Ie One '.

DATE September 10, 1988 REPORT MONT11 AtrAFST, 1988 _

COMPLETED BY S. Saanolinski TELEPilONE (815)357-6761 METilOD OF TYPE SIIUTTING DOWN F: IORCED DURATION TIIE REACTOR OP. CORRECTIVE NO. DATE S: SCllEDULED (HOURS) REASON REDUCING POWER ACTIONS / COMMENTS 7 8/5/88 S 0.0 B 5 Load drop to gather RR data 8 8/24/88 s 0.0 11 5 Load drop to 644 MWe for control rod set l

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I E. UNIQUE REPORTING REQUIREMENTS

1. safety / Relief val"r operations for Unit One.

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VALVES NO #< TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT ;

There were no Safety Relief Valves actuations for Unit One during the '

reporting period August I through August 31, 1988.

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2. ECCS Sy0tems Outcge3

, , . Th3 following outtg o wero ttkcn on ECCS Systcms during the reporting period.

OUTAGE WO z HOUIPMENT PURPOSE OF OUTAGB 0-208-88 0 D/G cooling water pump Replace motor 0 DG01P 0-210-88 0 DG01P Repack coupling 0-211-88 0 D/G Lubrication 1-1634-88 1A D/G Repair air pilot valve 1-1635-88 1A RitR heat exchanger flydrolaze Service water side.

1-1683-88 LPCS pump Change oil l

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3. Off-Sito Do;o Calculation Manus 1 Review of past Monthly Operating Reports submitted to the NRC identified that changes to the Offsite Dose Calculation Manual (ODCM) were incompletely reported. Technical specifications require a determination that changes made will not reduce the accuracy or reliability of dose calculations or setpoint determinations. This information was not included in the submittal of revisions 11A, 12 and 12A to the ODCM.

Technical evaluation of revisions 11A, 12 and 12A to the ODCM has determined that the changes do not reduce the accuracy or reliability of the dose calculations and setpoint determinations have not beea affected.

4. Radioactive Waste Treatment Systems.

No changes to Radioactive Waste Treatment systems during the reporting period.

5. Indicat)ons of Failed Fuel E) *ments No indications of Failed Fuel Eleinents on Unit One during this reporting period.

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT AUGUST. 1988 COMMONWEALTH EDISON COMPANY NRC DOCKET No. 050-374 LICENSE NO. NPF-18 DOCUMENT ID 0036r/0031r

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, , , , TABLE OF CONTENTS I

1. INTRODUCTION

11. MONTHLY REPORT FOR UNIT TWO A. Suer.ary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

) 1. Amendments to Facility License or Technical Specifications

2. Changes to procedures w'ich are described in the Safety Analysis Report.

3. Tests and Experiments not covered in the safety Analysis Report.

4. Corrective Maintenance of Safety Related Equipment

5. Completed Safety Related Modific.?tions C. LICENSEE EVENT REPORTS 3

l D. DATA TABULATIONS j 1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions ti, . UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose calculation Manus 1 Changes 1 4. Major Changes to Radioactive Waste Treatment Cystem

5. Indications of Failed Fuel Elements d

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1. INTRODUCTION I

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. '

Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Vaste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary consttuction contractor was commonwealth Edison Company.

Unit two was issued operating license number NPP-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.

This report was compiled by Steven J. Samolinski, telephone number (815)357-6761 extension 705.

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II. MONTHLY REPORT FOR UNIT TWO A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO August 1-31 August 1, 0000 hours0 days 0 hours 0 weeks 0 months Unit Two entered August with the reactor critical and the generator on-line at 750 MWe.

August 6, 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months Load drop to 446 MWe to maintain condenser backpressure.

August 10, 0000 nours Load drop to 440 MWe per L.D.

August 10, 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months Ramping to 857 MWo.

August 19, 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months Generator off line to repair steam leaks.

August 20, 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months Generator on line and ramping to 178 MWo.

August 22, 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months Ramping to 665 MWe.

August 31, 2323 hours0.0269 days 0.645 hours 0.00384 weeks 8.839015e-4 months Generator taken off line. Reactor in process of being shutdown for Technical Specification compliance.

August 31, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Generator off line, reactor shutdown proceeding.

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B. PLANT OR PROCEDURE CitANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

. MAINTENANCE. '

1. Amendments to Facility license or Technical Specification.

There were no amendments to the Facility License or Technical Specifications during the month of August,

2. Changes to procedures which are described in the Safety Analysis Report.

There were no changes to procedures which are described in the safety Analysis Report.

3. Tests and Experiments not described in the Safety Analysis Report.

There were no tests or experiments conducted during the month of August which are not described in the Safety Analysis Report.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of Safety-Related Maintenance completed on Unit Two during the reporting period. The headings indicated in this summary include: Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

5. Completed Safety Related Modifications.

The following table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.

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TABLE 1 O

CORRECTIVE MAINTENANCE OF '

SAFETY RELATED EWIIM unit s2 WCHK REQUEST COPG'ONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L83041 PDS-2E31-N007BB Ruptured diaphra<pa Division II isolation and RCIC *htitch replaced Pressure Differential trip unavailable Switch DCIUMENT ID 0036r/0031r

TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIPICETION NUMBERJ F. Drief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unroviewed safety questions.

UNIT TWO There were no Safety-Related Modifications completed on Unit Two during the month of August.

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C. LICEN5EE EVENT REPORTS I The following is a tabular summary of all licensee event reports for Lasalle Nuclear Power Station, Un'.t Two, logged during the reporting period, July 1, through July 31, 1988. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73. l l

1icensee Event Report Number

. Egit Title of occurrence I 44-009-00 8/1*l/88 RCIC IWoe Due to Failed SOR Switch. }

l 88-010-00 8/31/88 Failure of ADS Backup Nitrogen l Bottle Pressure Regulator.

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P D. DATA TABULATIONS The following data tabulations are presented in this

port:

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions t

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. 1. OPRRATING DATA REPORT !

DOCKET Wo. 050-374 f UNIT baSalle Two i

DATE Sept. 10. 1988 COMPLETED BY Steven J. Samolinski TELEPHONE (615)357-6761 OPERATING STATUS

1. REPORTING PERIOD _ August. 1988 GROSS HOURS IN REPORTING PERIOD:_744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Wet): 1036 DESIGN ELECTRICAL RATING (MWe-Wet): 1074

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Wet): 725

4. REASONS FOR RESTRICTIOU (IF ANY): Fuel Deoletion. Administrative TH'.S MONTH YR '!O DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 744.0__ .5635.5 22438.3

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.8

7. HOURS GENERATOR ON LINE 118.8 _5611.7 R2002.8

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) }700136- 15973752_ 63764804

10. GROSS ELEC ENERGY GENERATED (MWH) _509725_ _5224376 21032587

11. NET ELEC. ENERGY GENERATED (MvH) ,489642_ _5021821_ 20104434

12. REACTOR SERVICE FACTOR _100.0% 96.6% 66.1%__

13. REACTOR AVAILABILITY FACTOR 100.0% 96.6% 66.2%

14. UNIT SERVICE FACTOR 96.6% _ 95.8%_ 65.1%

15. UNIT AVAILABILITY FACTOR 96.6% 95.8%_ 65.1%_

16. UNIT CAPACITY FACTOR (USING MDC) 63.5% 82.8% 57.2%_

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 61.1% 79.6%_ , 55.0%

18. UNIT FORCED OUTAGE RATE _.

0.1% 4.0% 17.0%

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF RACH):

Unit 2 is scheduled for Second Refuel Outage on October 15. 1988. The outage is scheduled to last 15 weeks.

20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATA DATE OF STARTUP: 9/3/88 DOCUMENT ID 0036t/0031r

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2. AVERAGE DAILY UNIT POWER LEVEL

.. DOCKET WO 050-374 j UNIT: LASALL W y DATE: Sept. 10. 1944 i COMPLETED BY: Steven .1 Samolinskt i TELEPHONEt (415) 357-6761 l MONTH: AUGUST. 1944 !

r DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Wet ) (MWe-Wet) l i

1. 792.4 17, 744.2

2. 403.9 18. 736.5 f I

3. 749.8 19. 17.5 i

4. 773.5 20. 105.0 l S. 749.5 __

21. 162.0 ;

6. 696.4 %2. 465.4 l

7. 540.3 23. 745.0 l l

8. 607.4 24, 747.7 j

9. 578.7 25. 117.8 !

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13. 743.5 29, 130.1

14. 703.3 30. 123.7

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8. UNIQU8 REPORTING REQUIREMENTS

1. Safety / Relief valve Operations for Unit 'No, pag vat.VES NO & TYPE PLANT DESCRIPTION !

ACTUATRD ACTUATIONS CONDITION OF RVRNT There were no Safety Relief Valve actuations during the reporting period August 1 through August 31, 1988 for Unit 'No.

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3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 -

UNIT NAME LaSalle ha:t '.

DATE September 10, 198E REPORT MONTH AUGUST, 1988 COMPLETFD BY S. Samolinski TELEPHONE (815)357-6F61 METHOD OF TYPE SHUTTING DOWN

F: FORCED DURATION T1lE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /CDf9ENTS 11 8/6/88 F 0.0 B 5 Load drop to 446 MWe to maintain Condenser Backpressure.

12 8/19/88 S 24.5 B 5 Off-line to repair steam leaks.

13 8/31/88 F 0.62 A 5 Shutdown for Technical Spec 1ficatico compliance. Div I and II inoperative due to instrument nitro <]en problems.

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2. BCCS Systems outcges j

, . . . r The following outages were taken on RCCS Systems during j the reporting period. ;

i 00TME No. RQVIPMENT WRPO6E OF_ OUTAGE !

T 2-424-84 2ES L- F063 Technical Specification i 2251-F076 3.3.2 Bad son. !

I 2-452-44 2E12-F047A 39 MOV inspection. f i

2-453-84 2R12-F040A 90 MOV inspection. !

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3. Off-Sito Do2O Calculction Manus 1 Review of past Monthly Operating Reports submitted to the NRC identifico that changes to the offsite Dose Calculation Manual (ODCM) were incompletely reported. Technical Specifications require a determination that changes made will not reduce the accuracy or reliability of dose calculations or setpoint determinations. This information was not included in the submittal of revisions 11A, 12 and 12A to the ODCM.

Technical evaluation of revisions 11A, 12 and 12A to the ODCM has determined that the changes do not reduce the accuracy or reliability of the dose calculations and setpoint determinations have not been affected.

4. Radioactive Waste Traatment Gystems.

No changes to Radioactive waste treatment systems during this reporting period.

S. Indications of Failed ruel Elements.

Off Oas levels indicate that there is one pinhole Fuel Element failure in the reactor vessel. This does not represent a change frem the previous reporting period.

There were no further inoications of failed fuel elements during this reporting period.

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') Commonwealth LaSet) County Nuc!:at Station RuralRoute #1, Scx 220 ECaen

'# '-' MarseWes. llicois 61341 .

( . Telephone 615/357 6761 l September 10. 1944 .

t Director of Nuclear Reactor Regulation '

United States Nuclear Regulatory commisston Mail station F1-137 Washington. D.C. 20555 ATDit Document Control Desk Gentlesen Enclosed for your information is the monthly performance report covering LaSalle County Wuclear Power Station for the pertod August 1. 1944 through August 31, 1944.

very truly yours.

,h E.' U f 0, J. Diederich f/[f Station Manager LaSalle County Station !

WD/SJS/jdp ,

i Enclosure i act A. B. Davis, WRC. Region 111 NFC Resident Inspector LaSalle .

Gary Wright. 111. Dept. of Wuclear Safety l P. Shonenski WRR Project Manager i D. P. Galle. CSCO ,

D. t.. Farrar. Ceco !

IWro Recorda conter L. J. Anastasia. AIP Coordinator Nuclear Services ,

M. A. ortin, os Resident l

H. E. Bliss. Manager of Wuclear Licensing

W. F. Naughton, Nuclear Fuel Services Manager C. F. Dillon. Senior Financial Coordinator. LaSalle f Dennis Carlson/ Tech Staff ,

Terry Novotney/IWPo Coordinator. Tech Staff i Central File l l

, 1 DOCUMENT ID 0043r/0031r (

I

ML20154C812

Text

SUMMARY

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