ML20154F665

Monthly Operating Repts for Apr 1988

ML20154F665
Person / Time
Site:	LaSalle
Issue date:	04/30/1988
From:	Diederich G, Samolinski S COMMONWEALTH EDISON CO.
To:	NRC
References
0043R-0031R, 43R-31R, NUDOCS 8805240019
Download: ML20154F665 (32)

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.1 i-LASALLE NUCLEAR POWER STATION UNIT 1 M0ttMLY PERPORMANCE REPORT APRIL 1988 COtttONWEALTH EDISON COMPANY i

NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll i

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DOCUMENT ID 0043r/0031r 8805240019 880430 gDR ADOCK0500g3

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-4 TABLE OF CONTENTS

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INTRODUCTION 11.

IONTHLY REPORT POR UNIT ONE A.

Summary of Operating Experience B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED 191NTENANCE 1.

Amendments to Facility License or Technical Specifications 2.

Changes to procedures which 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 Modifications.

C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions 1

E.

UNIQUE REPORTIN7 REQUIREMENTS 1.

Main Steam Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System 5.

Indicatlens of Failed Fuel Elements i

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DOCUMENT ID 0043r/0031r

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INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Gdison 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 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 Steven J. Samolinski, telephone number (815)357-6761, extension 705.

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MONTHLY REPORT FOR UNIT ONE A.

SUN %RY OF OPERATING EXPERIENCE FOR UNIT ONE s

April 1-30 l

April 1, 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Unit One entered April with the Reactor suberitical and the generator off line.

Unit One is in second refuel outage.

April 30, 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> Unit & e in second refuel outage. Reactor vessel is defueled.

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'B PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

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Noendments to Facility License or Technical Specification.

There were no amendments to the Facility License or Technical i

specifications during this reporting period.

2.

Changes to procedures which are described in the Safety Analysis

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Report.

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There were no changes made to procedures which are described in the Safety Analysis Report during this reporting period.

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Tests and Experiments not described in the Safety Analysis Report.

There were no tests or experiments conducted which are not described in the Safety Analysis Report during this reporting period.

4.

Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a Summary of safety-related maintenance completed on Unit one 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.

DOCUMENT ID 0043r/0031r

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TABLE 1 CORRECTIVE MAINTENANCE OF

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SAFETY RELATED EQUIPMENT UNIT #1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L72508 LPCI water leg pump Corrosion of orifice Low pressure in B/C RHR loop Replaced orifice min. flow orifice 1E12-D002 L72931 Rx pressure vessel Malfunction of fitting Sensing line leaking Replaced fitting and safety relief valve on sensing line performed leak test L75866 HPCS cooling water Packing malfunction Valve leaking Repacked valve strainer IE22-F319 L766".2 Valve IE32-F00lJ Packing malfunction Valve leaking Replaced packing L76833 Rx low level relay Contacts not properly Contacts not making Adjusted, cleaned and lE22A-K7 adjusted connection tested contacts L79142 IB D/G overcurrent Weak tension in contact Prevents overcurrent alarm Readjusted contact arms relay lE22B-K7 arm for contacts 7 & 8 from being received L79403 1A D/G IDG0lK Malfunctioning fuel Low exhaust temp. on Replaced fuel injectors injectors 2 cylinders on cylinder 20 and cylinder 10 L79728 APRM Channel "A"

Shorted output circuits ESF actuation Replaced card IC51-K605GM on Quad trip card L79755 Under voltage relays Faulty operation of Improper load shedding for Cleaned under voltage 1327-AP108A/B undervoltage relays bus 136Y relays DOCUM"NT ID 0043r/0031r

TABLE 2 COMPLETED SAPBTY RELATED MODIP1 CATIONS MODIPICATION NUMBER: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

UNIT ONE M-1-0-85-013:

Installation of a third radio frequency. The new frequency will allow the security force a second usable frequency and another frequency for the new clip on pager system.

M-1-1-82-160:

Revise the refrigerated air dryer control for D/G 0, lA, 1B, and 2A to allow continuous operation of the dryers.

H-1-1-84-116:

Installation of potter & Brumfield 5138 relays in the 1A D/G control circuitry. These relays replace the K6 and K36 relays.

M-1-1-87-022:

Remove two existing pipe supports and a section of line IVQO2AB to improve Drywell Cooling system ventilation.

M-1-1-87-063:

Snubber reduction on the primary containment combustible gas control system (in) per the snubber reduction program.

M-1-1-87-071:

Snubber reduction on the Diesel Generator piping subsystem per the cnubber reduction program.

M-1-1-87-075:

Snubber reduction on the MSIV leakage control system piping subsystem per the snubber reduction program.

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C.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, April 1, 1988 through April 30, 1988. 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 88-004-00 4/22/88 Loss of RPS Bus A while Replacing Relay.

88-005-00 4/22/88 1A Diesel Generator Failure tc Meet Load t.cceptance.

j 88-006-00 4/17/88 Inoperative conductivity monitor due to Reactor Vessel drain down for chemical cleaning.

(voluntary)

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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 T

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DOCUMENT ID 0043r/0031r

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OPERATING DATA REPORT DOCKET NO. 050-373

-UNIT LaSalle One DATE May 10. 1988 COMPLETED BY p. J. Samolinski TELEPHONE (815)357-6761 OPERATING STATUS 14 REPORTING PERIOD:

_ April. 1988 GROSS HOURS IN REPORTING PERIOD: 719 2.

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

3.

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

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REASONS FOR RESTRICTION (IF ANY):_ Refuel Outage THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 1729,8 21774.3 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0

_._1642.0 7.

HOURS GENERATOR ON LINE 0.0

_1729,8 21159.8__

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UNIT RESERVE SHUTDOWN HOURS 0.0

0. 0 _ _

0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 0.0 22J2 M _

57086386

10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 2227148 _

19194407 11.

NET ELEC. ENERGY GENERATED (MWH)

-2920 2149510 18248151_

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REACTOR SERVICE FACTOR 0.0% -

59.6%___

57.3%

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REACTOR AVAILABILITY FACTOR 0. 0%___

59.6%

61.6%

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UNIT S3RVICE FACTOR 0.04_

59.6%_

55. ~1%

15. UNIT AVAILABILITY FACTOR 0.0%

J 9.6%_

55.7%

16.

UNIT CAPACITY FACTOR (USING MDC)

-0. 4%,

~11.5%

46.4%

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UNIT CAPACITY FACTOR (USING DESIGN MWe)

-0.4%_

68.7%

44.6%

18.

UNIT FORCED OUTAGE RATE 0.0%

0.0%

13,2%

19.

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

None 20.

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

Unit One is in the second refuel outage and is scheduled to startup July 3, 1988.

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AVERAGE DAILY UNIT POWER LEVEL

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j DOCKET NO: 050-373 j

UNIT: LASALLE ONE DATE: MeV 10, 1988 COMPLETED BY: S. J. Samolinski TELEPHONE: (815) 357-6761 l

MONTH: BE.RIL, 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Wet) i i

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1 17.

4 1

18.

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1 19.

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20.

1 4.

1 21.

1 5.

6.

- 11 22.

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- 13 23.

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- 12 24.

9.

- 13 25.

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26. -

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- 13 27.

12.

- 13 28.

1 5

1 13.

- 5 29.

4 2

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3 30.

15.

6

31...

1 16.

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UNIT SliUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One DATE May 10, 1988 REPORT MONTil APRIL, 1088 COMPLETED BY S. Samolinski TELEPliONE (815)357-6761 METiiOD OF TYPE SIIUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCllEDULED (HOURS)

REASON REDUCING POWER ACTIONS / COMMENTS 4

4/1/88 S

719.0 C

4 Continuing Unit one second refuel outage l

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DOCUMENT XD 0043r/0031r

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UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations Fe-U;til On6.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT There were no Safety Relief Valves actuated for Unit One during the reporting period April 1 through April 30, 1988.

I DOCUMENT ID 0043r/0L/31r

2.

ECCS Systems Outcges The following outcgsc wero tckea on ECCS Systems during the reporting period.

QUTAGE NO, NOUIPMENT PURPOSE OF OUTAGE 0-86-88 0 D/G Cooling Water Pump Breaker inspection 0-87-88 0 D/G Cooling Water Pump LMS-DG-01 surveillance, replace oil filter 0-89-88 0 D/G Rebuild stab solenoids.

0-90-88 0 D/G check Cyl temp. indication and speed indication 0-91-88 0 D/G Space Heater Replace control and 74 relays 1-617-88 1A D/G LMS-DG-01

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0-618-88 1A D/G Lubrication 1-619-88 1A D/G LES-GM-129 1-620-88 1A D/G BOP Calibrations 1-621-88 1A D/G 1DG034 Cooler relief 1-622-88 1A D/G LES-DG-101, LES-GM-109 1-627-88 Bus 143, 1B D/G Feed Modification M-1-1-84-019 1-628-88 1B D/G Lubrication 1-652-88 1B D/G Replace relay 1-712-88 1A D/G Replace governor 1-713-88 1A D/G Replace pyrometer probes 1-714-88 1B D/G Repair relay terminations 1-719-88 1A D/G valve adjustments 1-740-88 1A D/G Heat exchanger Clean heat exchanger 1-743-88 1A D/G Fuel transfer pump Remove manway 1-744-88 1DOOO4 Upgrade valve internals 1-746-88 1A D/G Replace 1DG-K39 relay I

DOCUMENT ID 0043r/0031r

OUTAGE NO.

EOUTPMENT PURPOSE OF OUTAGE

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1 *I47-88 1A D/G Rolcy modificction 1-762-88 IB D/G Repnit oil leaks 1-890-88 1A D/G Chaage air intake filters 1-893-88 1A D/G Repair governor 1-913-88 1DG035 Repack valve 1-986-88 IB D/G Prevent autostart DOCUMENT ID 0043r/0031r

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3.

Off-Site Do30 Calculction Manual i

There were no changes to the off-Site Dose calculation Manual during this reporting period.

4.

Radioactive Waste Treatment Systems, r

There were no changes to Radioactive Waste treatment systems during this reporting period.

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Indications of Failed Fuel Elements There were no indications of failed fuel elements during this 1

reporting period. The reactor is defueled.

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT APRIL, 1988 COMMONVEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO, NPP-18 DOCUMENT ID 0036r/0031r

TABLE OF CONTENTS 1

1.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TWO A.

Susumary 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 which 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 Modifications f

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.

Rafety/ 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 DOCUMENT ID 0036r/0031r

• ..o 1.

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 Bofling Water Reactor with a designed net electrical output of 1078 Megawatts. Vaste !. eat 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 numbet NPF-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.

DOCUMENT ID 0036r/0031r

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MONTHLY REPOttT FOR UNIT 'TWO b

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SUlttARY OF OPERATING EXPERIENCE FOR UNIT TWO APRIL 1-30'

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April 1. 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Unit Two entered April with the Reactor

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critical and the generator on-line at 1075 MWe.

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April 6. 0130. hours Load drop to 615 MWe for maintenance on A TDRFP.

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April 12, 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> Begin ramping to 1067 MWe.

i April 15. 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Load drop to 627 MWe for control rod adjustment.

April 15, 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> Ramping to 1085 MWe.

April 30, 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> Begin load drop to 632 MWe for control rod adjustment.

April 30, 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> Unit Two completed April with the Reactor Critical and the Generator on line at 774 MWe, Continuing load drop to 632 MWe.

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PLANT OR PROCEDURE CHANGES, TESTS. EXPERIMENTS AND SAFETY RELATED

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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.

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

There were no changes to procedures described in the Safety Analysis Report during this reporting period.

3.

Tests and Experiments not described in the Safety Analysis Report.

There were no Tests or Experiments conducted which are not described in the Safety Analysis Report.

4.

Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a sumnary of Safety-Related Maintenance completed on Unit Two during the reporting period. The headings indicated in this sumatry include:

W.- 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.

J DOCUMENT ID 0036r/0031r

..'. 'o TABLE A CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 VO3K REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION l

ON SAFE PLANT OPERATION L79120 LPCS pump cooler Faulty packing Valve would not move Repacked valve upstream stop valve j

2DG035 j

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t.79397 IRM "G" Faulty connection and No noise reading on Cleaned contacts and l

2CSI-K60lG dirty range switch channel I replaced range switch l

contacts l

l L70434 "C" MSL outboard Actuating bar out of Limit switch would not close Adjusted actuating bars j

isolation 2B21-F028C adjustment on limit and replaced cover gaskets l

switches l

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DOCUMENT ID 0036r/0031r

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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 questions.

UNIT TWO There were no safety related modifications completed on Unit Two during the reporting period of April 1 through April 30, 1988.

DOCUMENT ID 0036r/0031r

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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, April 1, through April 30, 1988. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.~13.

Licensee Event Report Number Date Title of occurrence 88-005-00 4/12/88 HPCS Minimum Flow Bypass Pressure Switch out of Tolerance.

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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 DOCUMENT ID 0036r/0031r i

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1.. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE May 10, 1988 i

COMPLETED BY Steven J. Samolinski TELEPHONE (815)357-6761 i

OPERATING STATUS 1.

REF0RTING PERIOD:

April, 1988 GROSS HOURS IN REPORTING PERIOD: 719 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 (IF ANY)-(MWe-Net):

None 4.

REASONS FOR RESTRICTION (IP ANY): None THIS MONTil YR TO DATE CUMULATIVE 5

NUMBLR OF HOURS REACTOR WAS CRITICAL 719.0

__2701.5 19486.3 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83 7.

HOURS GENERATOR ON LINE 719.0 2684.9 19156.0 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.-

GROSS TilERMAL ENERGY GENERATED (MWH) 2373168 7913808 55708864 r

10.

GROSS ELEC. ENERGY GENERATED (MWH) 694986 2648921 18457132

11. NET ELEC. ENT.RGY GENERATED (MWH)

_668945

_2552307 17634920 l

12.

REACTOR SERVICE FACTOR 100.0%

93.1%

62.9%

13.

REACTOR AVAILABILITY FACTOR 100.0%

93.1%

63.0%

14.

UNIT SERVICE FACTOR 100.0%

92.5%

61.8%

15.

UNIT AVAILABILITY FACTOR 100.0%

9 2. 53,_

61.8%

d 16.

UNIT CAPACITY FACTOR (USING MDC) 89_.8%

84.9%

54. 9,J_

a 17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 86.3%

_ 81.6%_

52.8%

18.

UNIT FORCED OUTAGE RATE 0.0%

7.5%

19.0%

19.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DhTE, AND DURATION OF RACil):

Unit Two is scheduled to shutdown for second refuel outage October 12, t

1988.

20.

IF SHUT DOWN AT END OF REPORT PERIOD, RSTIMATED DATE OF STARfUP. N/A i

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,2. AVERAGE DAILY UNIT POWER LEVEL e

DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: May 10, 1988 t

COMPLETED BY: Steven J. Samolinski TELEPHONE: (015) 357-6761 MONTH:

APRIL, 1988

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

(MWe-Net) 4 1.

1048 17.

1066 2.

1042 18.

1057 3.

977 19.

1050 4.

1016 20.

1047 5.

1014 21.

1045 6._

634 22.

1041 r

7.

581 23.

1036

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577 24.

1030 9. _.

667 25, 1021 10.

693 26, 1024 11.

715 27.

1022 i

12.

570 28.

1017 i

13, 925 29.

1013 s

14.

993 30, 998

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15, 891 31.

I 16, 1053 4

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UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Ywo DATE May 10, 1988 REPORT MONTH APRIL, 1988 COMPLETED BY S. Samolinski TELEPHONE (815)357-6761 METilOD OF TYPF SHUTTING DCM4 F: FORCED DURATION TIIE REACTOR OR CORRECTIVE CD.

DATE S: SC11EDULED (llOURS)

REASON REDUCING POWER ACTIONS / COMMENTS 8

4/6/88 S

0.0 H

5 "A" TDRFP was brought off line to replace coupling and correct aligruw nt.

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UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF_ EVENT There were no Safety Relief Valves actuated on Unit Two during the reporting period April 1 through April 30. 1988.

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ECCS Syctems Outsges The following outages were taken on ECCS Systems during l

the reporting period.

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 2-261-88 2E22-F012 Administrative control; SOR t

removal.-

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2-273-88 2A D/G Alignment check of AC citc.

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oil pump.

i 2-277-88 2DG035 Inspect torque switch.

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DOCUMENT ID 0036r/0031r

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3.

Off-Sito Dosa Calcul: tion Manual p

There were no changes to the off site Dose calculation manual during this reporting period.

4.

Radioactive Waste Treatment Systems.

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

5.

Indications of Failed Fuel Elements.

Off Gas levels indicate that there is one pinhole fuel element failure in the reactor core. This does not represent a change from the previous reporting period.

There w<>re no further indications of failed fuel elements during this reporting period.

DOCUMENT ID 0036r/0031r

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Commonwealth Edison

(

LaSille County Nuctrar Station Rural Route #1, Box 220 L

Marsei!!es. Illinois 61341 Telephone 815/357-6761 May 10, 1988 Director, Office of Management Information and Program Control Unit ed States Nuclear Regulatory Consnission Washington, D.C.

20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period April 1, 1988 through April 30, 1988.

Very truly yours, O

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J. Diederich hf Station 'ianager LaSalle County Station GJD/SJS/jdp Enclosure Mc:

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, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED M. A. Ortin, GE Resident H. E. Bliss, Nuclear Puel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle L

Dennis Carlson/ Tech Staff q

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Terry Novotney/INPO Coordinator, Tech Staff

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Cent.ral File

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i DOCUMENT ID 0043r/0031r