Text

Monthly Operating Repts for Aug 1987
	ML20238F416
Person / Time
Site:	LaSalle
Issue date:	08/31/1987
From:	Diedrich G, Kirchner G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	0043R-0005R, 43R-5R, NUDOCS 8709160143
	Download: ML20238F416 (34)
	v • d • e

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I LASALLE NUCLEAR POWER STATION UNIT 1

, MONTHLY PERFORMANCE REPORT AUGUST 1987 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 9709160143 870831 PDR ADOCK 05000373 R PDH DOCUMENT ID 0043r/0005r b WA s ,

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.O j TABLE OF CONTENTS

1. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE I

A. Summary ;>f Operating Experience B. PLANT OR PROCEDURE CHANG 3S, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to racility License or Technical Specifications

2. Facility or Procedure Changes Requiring NRC Approval i

3. Tests and Experiments Requiring NRC Approval

4. Corrective Maintenance of Safety Related Equipment

5. Completed Safety Related Modifications.

C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS

1. Main Steam Relief Valve Operations 1

2. ECCS System Outager

3. Off-site Dose Calculation Manual changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Failed Fuel Elements i

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J I. INTRODUCTION 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 Vater Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejec'.d to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineet was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit one was issued operating license number NPF-ll on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

This report was compiled by Gregory J. Kirchner, telephone number (815)357-6761, extension 704, 1

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.o .r II. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE l

JULY 1987 I- B-1-87 0000 Hours Unit is in Cold shutdown for major equipment repair. Generator is off-line.

8-31-87 2400 Hours Unit is in Cold shutdown. Generator is ,

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B. PLANT'OR PROCEDURE CHANGES, 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 this reporting' period.

2. Facility or Procedure changes requiring NRC' approval.

There were no Facility or Procedural changes requiring NRC approval

'during.this reporting period. !

3. Tests and Experiments requiring NRC approval.

l There were no tests or experiments requiring NRC approval during '

/ this' reporting period.

4. . Corrective Maintenance of Safety Related Equipment.

~ The ~ following table (Table 1) presents a Sununary of safety-related maintenance completed on Unit:One during the reporting period. . The headings. indicated in this summary include:

4, Work Request number, Component Name, Cause of Malfunction, Results ]r 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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> s TABLE 2 COMPLETED SAFETY CELATED MODIFICATIONS U-1 MODIFICATION NUMBER: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

M-1-1-87-001 This modification was for spring hanger design errors on

, subsystems 1RHC9, 2RHC9, and 2MS64F. These spring hangers I

are to be redesigned per the snubber reduction program.

There were no unreviewed safety questions.

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t C.: . LICENSEE EVENS REPORTS - '

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\The follitudng is a tabular suminary of all licensee evoat reports for

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l. 3 pe.riod,J.tu!;ust 7., (i.987 through August 31, 1987, inis information is 4

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prw tded pursuant to the report,,tt)(' occurrence reportitJ; requirements as '

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/ 87.d$ 00 ' 8/13fb7

'B' VC Ammonia Detector Trip

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87 929 00 8/29/87 RWCU 1G33-P004 Isolation 1

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D. DATA TABULATIONS

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[ .The following data tabulations are presented in this report: 1 1 '

1. Operating Data Report -

y a, 1,' i.V ', . 2. .%verage Daily Unit Power Level 1f f 3. Unit Shutdowns and Power Reductions 3, .

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1. OPERATING DATA REPORT DOCKET No, ' 050-173 UNIT LaSalle One DATE September 10, 1987-1 COMPLETED'BY G. J._Kirchne,r j TELtl? HONE (815)357-676},

1 OPERATING STATUS

,1. REPORTING PERIODr ,_ August GROSS HOUhS IN REPORTING. PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):).G_3.3 MAX Df: PEND CAPACITY (MWe-Net): 1036- DESIGN 3LECTRICAL RATING (!fWe-Net): 1078

3 POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): 1050 .

4. REASONS FOlt RESTRICTION.(IF WY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5- NUMBER OF HOURS REACTOR WAS CRITICnL 0 ,0 , 3143.6 12069.5 ,

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83 !

'7. HOURS GTNERATOR ON LINE 0.0 3028.9 11830.84

8. UNIT kESERVB SHUTDOWN HOURS 0.0 0.0 , 0.0

9. CROSS THERMAL ENERGY GENERATED'(MWH)' 0.0 6356588 33635128

10. .OROSS ELEC. ENERGY GENERATED (MWH) __,0.0~ 2046424 11100804

~11. NET ELEC. ENERGY GENERATED (MWH) -30865 1935377 10504502

12. REACTOR SERVIC8 FACTOR 0.0% 53.9% 37.5%

13. .REACTOP AVAILABILITY FACTOR 0.0% 53.9% 37,6%

14. UNIT SERVICE FACTOR 0.0% 51.9% 36.9% ,

Ib. - UNIT AVAILABILITY FACTOR 0.0% 51.9% 36.9%

16. UNIT CAPACITY FACTOR (USING MDC) N/A_ 32% '31.5%

.17e UNIT CAPACITY FACTOR (USING DESIGN MWe) N/A 30.8% 30.3% __

18. UNIT FORCED OUTAGE RATE 0% _24.4% 20.6%

19. SHUTOOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH) ]

N/A - Unit.is shutdown during this reporting period.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 9/14/87 i

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UNIT: MSALLE ONE'-

'DATE: September 10, 1987-

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4 COMPLETED BY:' Gregory Kirchner TELEPHONE: (815) 357-6761 4

MONTH: AUGUST, 1987 e

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

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2. -14 18.- ' -14

'3 -14 19. -14=

4. -14 20. -14 ._

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6. -13 _ 22. -15 j

'1 - -13 23. -15

~8. -13 _,

24. -15

.9. -13 25. -15

10. -14 26. -15_

.11. -14 ,

27. -15 l

12. -14 28. -16

13. -14 29. -16

14. -14 30. --15 i

15. -14 31. -15 ,

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,1. Safety /Nelief valve operations'for Unit'One.,

VALVES hO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT _;_

'ilhere were no Safety Relief Valves Operatea for Unit One during this reporting period.

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, ," 2. ECCS Systems Outag:s The following outages were teken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPMENT ' PURPOSE OF OUTAGE U-l 1-743-87 MSIV-Line D Fix/ Replace valve 1-754-87 1E31-F005Gl. Replace Valve 1-755-87 IB21-F001,2,5 Limitorque inspection 1-770-87 1E51-F031 Replace control relay 1-771-67 lE51-F022 Troubleshoot and repair 1-772-87 lE51-F086 Replace thermal L.L.

1-800-87 RCIC-008 Repair declutch lever 1-J07-87 RCIC Ind. valves Prevent vessel drain 1-808-87 IB21-F005 Prevent vessel drain 1-815-87 lE12-F053A Repair leaks 1-823-87 RCIC Repair leak on 1RIllA

'l-827-87 RCIC Lube coupling 1-828-87 RCIC heplace pump seal 1-830-87 MSIV's Inspect wiring 1-847-87 1E12-F090A Replace flex 1-848-87 lE12-F041A Replace damsged lugs 1-850-87 lE51-F086 Replace covers on limitorque 1-853-87 LPCS Install EQ motor term kit 1-855-87 lE12-F009 Open for testing 1-876-87 lE21-C001 Install termination kits 1-880-87 Turbine Oil Res. Install drain stool piece 1-881-87 IB21-F002, F005 Hydro head vents 1-893-87 'C' RHR Pump Install EQ motor term kit 1-894-87 ID RHR SW-Pump Remove motor mount dowel pin 1-905-87 IB21-F019 MSL drain adjust declutch 1-906-87 IB21-V019 Verify limitswitch 1-907-87 lE212-C002B Install kerite term.

1-910-87 MSL flow inst. Replace IE21-F323D valve 1-914-87 IB21-F020 set trip fingers 1-920-87' 'A' LPCI HP Vent Install new sightglass 1-922-81 1A RHR Replace 4A spring pak f

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3. Off-Sito Dose calculation Manual There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Trentment Systams.

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

5. Indications of Failed Fuel Elements I There were no indications of Failed Fuel Elements during this ,

reporting period.

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LASALLE NUCLEAR POWER STATION i

UNIT 2 i

MONTHLY PERFORMANCE REPORT Al.1 GUST , 1987 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 i.

DOCUMENT ID 0036r/0005r L_____

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TABLE OF CONTENTS

1. INTRODUCTION

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

1. Amendments to Facility License or Technical Specifications

2. Facility or Procedure Changes Requiring NRC Approval

3. Tests and Experiments Requiring NRC Approval

4. Corrective Maintenance of Safety Related Equipaent

5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Failed Fuel Elements l

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f,; ,( 3 7I; INTRODUCTION

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The LaSallu County Nuclear' Power Station is a two-unit facility owned l

by Commorreealth~ Edison Company and located near. Marseilles, Illinois.

J Each unit'is a Boiling Water Reactor with a designed net. electrical' ;

' output of,1078 Megawatts. Waste 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 construction- !

' contractor was Commonwealth Edison Company.

Unit two was issued operating license number NPF-10 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, Gregory J. Kirchner, telephone number (815)357-6761 extension'70d.

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. . II. MONTHLY REPORT FOR UNIT TWO A.

SUMMARY

OF OPERRTING EXPERIEWCE FOR UMIT TWO 8/01/87 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Ex at 700 MWe, Generator on line.

1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months ramp at 10MWe/hr to 1100 MWe.

8/06/87 0300 hourt Drop 50 MWe for CRD exercising.

0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months ramp at 10 MWe/hr. to 1097 MWe.

8/14/87 0000 hours0 days 0 hours 0 weeks 0 months Drop Rx power to 966 MWe for C.V. testing.

0300 hourcs Ramp up to 1103 MWe at 10 MWe/hr.

0/19/87 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months Drop 100 MWe for load dispatcher. Rx at 1000 MWe.

0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months Ramp up to 1109 MWe at 10MWe/hr.

8/21/87 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months Drop 50 MWe for CRD exercising. Rx at 1044 MWe.

0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months Ramp up to 1105 MWe at 10 MWe/hr.

8/23/87 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months Drop 130 MWe for load dispatcher. Rx at 962 MWe.

8/24/81 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months Ramp up to 1105 MWe at 10MWe/hr.

8/28/87 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months drop Rx power to 1043 MWe for CRD exercising.

0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months Ramp up to 1115 MWe at 10MWe/hr.

8/29/87 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months Drop Rx power to 1014 MWe for MDRFP test. Rx at 1014 MWe.

1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months Ramp up to 1115 MWe at 10 MWe/hr.

8/31/87 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Rx holding steady at 1115 MWo. Generator on-line.

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DOCUMENT'1D 0036r/0005r

II. MONTHLY REPORT FOR UNIT TWO l

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SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO 8/01/87 0000 hours0 days 0 hours 0 weeks 0 months Rx at 700 MWe, Generator on line.

1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months ramp at 10MWe/hr to 1100 MWe.

8/06/87 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months Drop 50 MWe for CRD exercising. )

D400 hours ramp at 10 MWe/hr. to 1097 MWe.

8/14/87 0000 hours0 days 0 hours 0 weeks 0 months Drop Rx power to 966 MWe for C.V. te: sting. I 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months Hamp up to 1103 MWe at 10 MWe/hr. ]

8/19/87 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months Drop 100 MWe for load dispatcher. Rx at 1000 MWe.

0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months Ramp up to 1109 MWe at 10MWe/hr.

8/21/87 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months Drop 50 MWe for CRD exercising. Rx at 1044 MWe.

0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months Ramp up to 1105 MWe at 10 MWe/hr.

8/23/87 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months Drop 130 MWe for load dispatcher. Rx at 962 MWe. l 6/24/87 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months Ramp up to 1105 MWe at 10MWe/hr.

8/28/87 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months drop Rx power to 1043 MWe for CRD exercising, j 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months Ramp up to 1115 MWe at 10MWe/hr. ;

I 8/29/87 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months Drop Rx power to 1014 MWe for MDRFP test. Rx l at 1014 MWe. l 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months Ramp up to 1115 MWe at 10 MWe/hr. l l

8/31/87 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Rx holding steady at 1115 MWe. Generator on-line.

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DOCUMENT'ID 0036r/0005r

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'A B. PLANT OR PROCEDURE CHANGES, 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 this reporting period.

2. Facility or Procedure changes requiring NRC approval.

There were no Facility or Procedure changes requiring NRC approval during the reporting period.

3. Tests and Experiments requiring NRC approval.

There were no Tests or Experiments requiring NRC approval during tha reporting period.

4. Corrective Maintenance of Safety Rein'.ed Equipment, The following table (Table 1) presents a summary of f 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 j Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification. f 1

4 i

I DOCUMENT ID 0036r/0005r

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-TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questior.s.

UNIT TWO M-1-2-84-094 This modification installed branch connection fittings on the control rod drive scran discharge volume headers. This will allow the system to be occasionally hydrolazed to- -

prevent radiation build-up. There were no unreviewed safety questions.

M-1-2-84-099 This mod was to add additional piping supports to the low pressure heater. Vent lines Nos. 2DV15AA, 2DV15AB,'2DV15AC, -

.and also one new rigid support guide on drain line 2HD15c.

There were no unreviewed safety questions.

M-1-2-84-166. This mod called for the installation of an additional generator _ load rejection unit tripping scheme, there were ;

no unreviewed safety questions.

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l DOCUMENT ID 0036r/0005r l I

., se .

C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, August 1, through August 31, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 87-027 8/31/87 Drywell Temperature exceeded limit.

i DOCUMENT ID 0036r/0005r l

- _ _ _ _ _ _ _ - _ _ - - _ _ - _ _ _ _ _ _ _ _ - - _ _ _ _ _ .h

o .. ,

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

1. Operating Data Report ,

2. Average Daily Unit Power Level

3. Unit Shutdowns and power Reductions i

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l DOCUMENT ID 0036r/0005r

= - - _ _ - _ .

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1. OPERATING DATA REPORT DOCKET 100, 050-374 UNIT LaSalle Two DATE September 10. 1987 OOMPLETED BY Gregory Kirchner TELEPilONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: August GROSS HOURS IN REPORTING PERIOD: 744 .

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078

3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): 1050

4. REASONS FOR RESTRICTION (IF ANY): Administrative !

TIIIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 744 1852.34 13855.79

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83

' 7. HOURS GENERATOR ON LINE 744 1770.91 13542.13

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2408472_ 5199576 38713840

10. GROSS ELEC. ENERGY GENERATED (MWH) 800098 1701759 12763331

11. NET ELEC. ENERGY GENERATED (MWH) 776414 1600558 12140787

12. REACTOR SERVICE FACTOR 100% 31.8% 55.1%

13. REACTOR AVAILABILITY FACTOR 100% 31.8% 55.2%

14. UNIT SERVICE FACTOR 100% 30.4% 53.8%

15. UNIT AVAILABILITY FACTOR 100% 30.4% 53.8%

16. UNIT CAPACITY FACTOR (USING MDC) 99.2% 26.5% 46.6%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 96.8% 25.5% 44.8% l 1 18 . UNIT FORCED OUTAGE RATE N/A 3.1% 23.9%

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

N/A

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A i

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J DOCUMENT ID 0036r/0005r

2. AVERAGE DAILY UNIT POWER LEVEL

.s, ,

DOCKET NO: 05")-374 UNIT: LASALLE TWO DATE: Sept. ember 10, 1987 COMPl.ETED BY: Gregory Kirchner TELEPHONE: 1815) 357-6761 MONTH: ..AUGIIST 1987 DAY T.VERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 756 17, 1070

2. 916 18. 1066 3 1025 19. 1050 l

l 4. 1039 20, 1065 ,

5. 1060 21. 1064 6, 1059 22, 1069

7. 1057 23. 952

8. 1060 24.__ 1036

9. 1058 25. . . _

1073

10. 1063 26, 1077

11. 1062 27. 1077

12. 1065 28. 1062

13. 1066 29. _.

1069

14. 1039 30, 1075

15. 1065 31. 1075

16. 1067 DOCLIMENT ID 0036r/0005r

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6 4* m 2. ECCS Systems Outtges I The following outages were taken on ECCS Systems during the reporting period.

UNIT 2 l

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-1621-87 RCIC Calibrate and Repair 2E51-N010D 2-1629-87 HPCS Pump Mtr. 2E22-C001 Megger Motor 2-1639-87 LPCS Pump 2E21-C001 Megger Motor 2-1645-87 RCIC Pump Lube Coupling 2-1646-87 RCIC Pump Lube l

DOCUMENT ID 0036r/0005r

3. Off-sito Do2s C01culction Manual (U-2)

There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Treatment Systcms.

There were no changes to the Radwaste Treatment Systems for this reporting period.

5. Indications of Failed Fuel Elements.

There were no indications of fa$ led fuel elements during this reporting period.

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scw3 E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DhTE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF INENT There were no Safety / Relief Valve actuations during this reporting period, t

)

DOCUMENT ID 0036r/0005r

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4 Commonw alth Edison

+- . LaSalto County Nucirar Station . .<

, Rural Route #1, Box 220 i(

- Marseilles, Illinois 61341 % .

Telephone B15/357-6731 i

T l' h,

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, r' s September 10, 1987

' l4.l j

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Director, Office of Management Information

.and Program Control

' United Statya Nuclear Regulatory Commission Washington,' D.C. ;20555 ATTN: Document Control Desk ..u

, , Gentlemen:

y Enclosed for your information is the monthly performance report covering LaSalle' County' Nuclear Power Station for the' period August 1, 1987 through August 31, 1987. .

7

'Very truly yours, AV b.J.Diederich Station Manager LaSalle County Station y

GJD/GJK/msh Enclosure rj xc: J. G. Keppler, NRC, Region III NRC Resident Inspector'LaSalle ,

Gary Wright, Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager

(.

D. P. Galle, CECO D. L. Farrar, CBCo

V(

INPO Records Center J. Anastasia, PIP Coordinator SNED '

j ME

/M

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M. A. Ortin, GE Resident 1 i

.) P H.'E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Finincial Coordinator, LaSalle f 4

Denth Carlson/ Tech Staff Terry Novotney/ Training "contral File

% Ml s;t' ll o

DOCUMENT IW OO43r/0005r s

_____- cn. - _ . . _ _ _____________-___________-_-_____-__-_--___L

ML20238F416

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