ML20149G116

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Monthly Operating Repts for Jan 1988
ML20149G116
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/31/1988
From: Diederich G, Samolinski S
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0043R-0031R, 43R-31R, NUDOCS 8802180119
Download: ML20149G116 (32)
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V eN Commonwealth Edison

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LaSalle County Nuclear Station

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February 10, 1988 Director, office of Management Information and Program Control United States Nuclear Regulatory Comission 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 January 1, 1988 through January 31, 1988.

Very truly yours, 7),I

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G. J. Diederich

,f Station Manager LaSalle County Station GJD/SJS/sjc Enclosure xc:

.J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager J

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 Fuel Services Manager I

C. F. Dillon, Senior Financial Coordinator, LaSalle Dennis Carlson/ Tech Staff j

Terry Novotney/INPO Coordinator, Tech Staff Central File I

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.s LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JANUARY 1988 COMMONWEALTH EDISON COMPANY

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'g TABLE OF CONTENTS I.

INTRODUCTION II.

-MONTHLY REPORT FOR UNIT ONE A.

Summary of Operating Experience

  1. C 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.

C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and power Reductions e

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E.

UNIQUE REPORTING REQUIREMENTS 1.

Main Steam Relief Valve Operations 3

ECCS System Outages

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Off-Site Dona Calculation Manual Changes

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Major Changes to Radioactive Waste Treatment System

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Indlcatiens of Failed Fuel Elements s.

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INTRODUCTION

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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. 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 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, i

DOCUMENT ID 0043r/0031r

II.

MONTHLY REPORT FOR' UNIT ONE

  • A.

.SUtt4ARY OF OPERATIN9 EXPERIENCE FOR UNIT ONE January 1-31 January 1, 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Reactor critical, generator on-line at 960

MWe, January 8, 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> Load drop to 635 MWe for MSIV Surveillances and rod set.

January 9, 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> Commence ramping to 1090 MWe over a two day period.

January 16, 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> Load drop to 870 MWe e.t request of Load.

Dispatcher.

January 17, 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> Commence ramping to 1020 MWe.

January 29, 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> Load drop to 569 MWe for rod adjustments.

January 30, 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> Commence ramping to 842 MWe, January 31, 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> Ramping to 1030 MWe.

January 31, 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> Reactor critical, generator on-line at 980 MWe, continuing rsmp to 1030 MWe.

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

1.

Amendments to Facility License or Technical Specification.

t Amendment number: 52 The facility license was amended to allow transfer of Unit 1 and 2 fuel to either fuel pool.

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 this reporting period that are not described in the Safety Analysis Report.

4.

Corrective Mair,tenance 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.

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DOCUMENT ID 0043r/0031r i

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT UNIT #1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L75461 Supp. Pool Temp Bad card False upscale alarms Replaced card Recorder, ITR-CM037 L74698 "lD" APRM 1C51-R901D Bad wire APRM failed downscale Repaired wire L59799 250 VDC Charger Bad amp board Improper load supply Replaced amp board IDC-03E L74032 "lA" Diesel air Failed gasket Air leaking from compressor Replaced gasket compressor, IDG-08CB L73611 "lB" SBLC Pump, Sight Glass oil leak Oil leaking from crankcase Replaced sight glass IC41-C001B L75206 "1B" SBLC Relief Valve bellows failed Flange leaking Replaced bellows valve flange IC41-F029B L74855 S.P. Air temp / press.

Broken pin connector False alarm, would not reset.

Replaced pin connector Hi alarm L74891 Scram pilot solenoids Solenoids failed Control rod went full in during Replaced Solenoids 1C11-D001-118 1/2 scram testing ICll-D001.

L74893 Div. II SP/DW Temp.

Chart motor failed.

Chart not advancing.

Replaced slow speed Recorder ITR-CM038 chart motor.

L74919 "F" APRM 1C51-K605CS Dirty edge connector No downscale light.

Cleaned edge connector.

DOCUMENT ID 0043r/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.

7 UNIT ONE There were no safety related modificatons completed for Unit One during the reporting period, January 1, to January 31, 1988.

l DOCUMENT ID 0043r/0031r

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LICENSEE EVENT REPORTS i

6 The following is a tabular summary of.all licensee event reports for t

Lasalle Nuclear. Power Station, Unit One, logged during the reporting period, January 1, 1988 through January 31, 1988. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73, i

Licensee Event Report Number Date Title of Occurrence There were no Licensee Event Reports logged during the report period January 1, through January 31, 1988.

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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-i f

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1.

OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE February 10, 1988,

' COMPLETED BY S. J. Samolinski TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: January, 1988 GROSS HOURS IN REPORTING PERIOD:-744

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CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078 3.

POWER LEVEL TO VHICH RESTRICTED (IP ANY) (MWe-Net):

1025 4.

REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744,0 20788.5 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0

_1642.0 7.

HOURS GENERATOR ON LINE 744.0 744.0 20174.8 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 2233488 2233488 54067786 10.

GROSS ELEC. ENERGY GENERATED (MWH) 755786 755786 17723045 11.

NET ELEC. ENERGY GENERATED (MWH) 730250__

730250 16828891 12.

REACTOR SERVICE FACTOR 100.0%

100.0%

58.0%

13. REACTOR AVAILABILITY FACTOR 100.0%

100.0%

62.6%

14.

UNIT SERVICE FACTOR 100.0%

__100.0%

56.3%

15.

UNIT AVAILABILITY FACTOR 100.0%

_100.0%

56.3%

16.

UNIT CAPACITY FACTOR (USING MDC) 94.7%

94.7%

45.3%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 91.0%

91.0%

43.6 18.

UNIT FORCED OUTAGE RATE 0.0%

0.0%

13.8%

19.

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

The Unit One second refuel outage is scheduled to begin March 13, 1988 and will last 15 weeks.

20.

IF SHUT DOWN IS AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A DOCUMENT ID 0043r/0031r

'2.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: February 10, 1988 COMPLETED BY: S. J. Samolinski TELEPHONE: (815) 357-6761 MCWTH: JANUARY, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

913 17, 936 2.

907 18, 952 3

970 19, 1028 i

4.

1034 20, 1037 5.

1029 21.

1026 6.

1032 22.

1036 7.

1019 23.

1033 8.

973 24, 1032 9.

723 25, 1039 10.

826 26, 1041 11.

986 27, 1040 12, 1045 28, 1020 13.

1042 29.

1030 14.

1043 30.

726 15, 1039 31.

871 16, 1000 DOCUMENT ID 0043r/0031r

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UNIT SHUTDOWNS AND POWER. REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle Osw -

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REPORT MONTH JANUARY, 1988 COMPLETED BY S. Samolinski' TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE i

NO.

DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER ACTIONS /COfftENTS 1

1/8/88 S

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5 MSIV Surveillances and rod set.

2 1/30/88 S

0.0 B

5 Rod set.

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UNIQUE REPORTING REQUIREMENTS

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1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting period.

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ECCS SyOtens,Outtges.

.Th3 following outagas vare ttkin on ECCS Systems during the reporting period.

OUTAGE NO_._

EQUIPMFM PURPOSE OF OUTAGE l-2-88 MPCS CY Suction Valve Replace limiter plate and IE22-F001 leads 14 and 14c 1-5-88 Petter diesel air Prevent operation compressor 1822-C302a 1-10-88 LE51-C004 Inspect motor and brushes on pump 1-11-88 1E51-C005 Inspect motor and brushes on pump 1-18-88 1E12-F003A Surveillance LES-EQ-112 1-53-88 IB D/G Air Compressor Replace head gasket 0-2-68 0 D/G Repair air start solenoid 0-21-88 0 D/G Rebuild air start' solenoids 0-23-88 0 D/G BOP calibrations 1

DOCUMENT ID 0043r/0031r

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3.

Off-Site Dose Calculation Manual There were no changes to the ODCM during this reporting period.

4.

Radioactive Waste Treatment Systems.

A new contract was awarded to our present vendor.

The new contract will cover a two year period. More information will be provided in February's report.

5.

Indications of Failed Fuel Elements There were no indications of Failed Fuel Elements during tMM reporting period.

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

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TABLE OF CONTENTS 1.

INTRODUCTION II.

MONTHLY RttPORT FOR UNIT TWO A.

Sunsaary of Operating Experience B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANLE 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 E.

UNIQUE REPORTING REQUIRE 4ENTS 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 d

DOCUMENT ID 0036r/0031r

p I.

INTRODUCTION The 1.aSalle 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' construction contractor was Commonwealth Edison Company.

Unit two was issued operating license number NPF-18 on Decembsr 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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MONTHLY REPORT FOR UNIT TWO

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SUtMARY OF OPERATING EXPERIENCE FOR UNIT TWO JANUARY 1-31 January 1, 0001 hrs.

Reactor critical, generator on-line at 840 MWe.

January 3, 1750 hrs.

Load drop to 620 MWe to repair pipe on "B" TDRFP.

January 4, 0400 hrs.

Commence ramping to 915 MWe.

January 6, 0900 hrs.

Ramping to 1115 MWe, January 13, 1850 hrs.

Load drop to 830 MWe for heater bay work and valve surveillance.

January 14, 0500 hrs.

Commence ramping to 1110 MWe, January 16, 2300 hrs.

Load drop to 850 MWe at request of Load Dispatcher.

January 17, 0600 hrs.

Commence ramping to 1030 MWe, January 19, 0000 hrs.

Load drop to 850 MWe at request of L.D.

January 19, 0600 hrs.

Commence ramping to 1116 MWe.

January 20, 0000 hrs.

Load drop to 850 MWe at request of L.D.

January 20, 0500 hrs.

Commence ramping to 1110 MWe.

January 22, 2200 hrs.

Load drop to 840 MWe for Surveillances and reheater work.

January 27, 2300 hrs.

Load drop to 850 MWe at request of L.D.

January 28, 0300 hrs.

Commence ramping to 1110 MWe January 30, 2300 hrs.

Load drop to 700 MWe for rod adjustments and scram times, January 31, 0700 hrs.

Commence ramping to 938 MWe.

January 31, 2300 hrs.

Load drop to 672 MWe for rod adjustment.

Jahuary 31, 2400 hrs.

Reactor Critical, Generator on-line and holding at 670 MWe, DOCUMENT ID 0036r/0031r

B.-

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED:

MAINTENANCE.

1.

Amendments to Facility license or Technical Specification.

Amendment Number: 34 The facility license was amended to allow transfer of Unit 1 and 2 fuel to either fuel pool.

2.

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

There were no changes to procedures which are desetibed in the Safety Analysis Report.

3.

Tests and Experiments not described in the Safety Analysis Report.

There were no Tests or Experiments conducted during this reporting period that 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 pericd.

Each entry will have a short synopsis explaining details involved with each modification.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 VORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L73645 RCIC steam line Failed diaphragm Improper switch operation Replaced switch pressure switch 2E31-N007AA L73669 RCIC Steam line Failed diaphragm Imrpoper switch operaton Replaced switch isolation switch 2E31-N007AB L72610 Battery cells Low specific gravity Low battery charge Battery cells put on 2E22-S001 individual change.

L75231 LPCS water leg pump Failed valve seat Improper valve seal Rebuilt valve with new disc check valve spring and gacket 2E21-F033 L74742 "A" RBM 2C51-K605GU Bad Relay Erroneous rod blocks Replaced Kil relay.

L74778 "A" RBM 2C51-K605GU Failed Relays Improper response Replaced relays.

L74739 LPCS pump cooler Inadequate lubrication Valve sticking Manually exercised valve upstream stop and lubed valve stem.

2DG035 L74696 "A" APRM flow bias Vorn wiper assembly Improper indication Replaced wiper assembly L73548 "B" APRM recorder Loose clutch Pen not advancing Tightened clutch 2C51-R603B L74253 "B" SBLC Pump motor Cracked overload device Exposed contacts Replaced overload device 2C41-C001B DOCUMENT ID 0036r/0031r 3

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L75303 RIIR Area high temp Failed module Improper area temp. Indication Replaced Riley module Riley module 2E31-N608C L71954 HPCS diesel air Improper seal Leak in air line Removed line, cleaned, receiver tank applied new sealant 2E22-T302 L74733 S/P Temp. recorder Bad pinion gear Improper recorder operation Replaced pinion gear 2TR-CM037 L75179 S/P Temp. recorder Bad sync cord and signal Recorder not advancing properly Replaced sync cord and 2TR-CM037 level cord cleaned signal cord L75458 A/C APRM recorder Loose clutch and bad Improper power indication Tightened clutch and 2C51-R603A wiper arm assembly replaced wiper assembly DOCUMENT ID 0036r/0031r

s 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 M-1-2-86-091:

Snubber reduction on subsystem 2HO70 per the snubber reduction program.

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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, January 1,'through January 31, 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 There were no Licensee Event Reports logged during the reporting period January 1 through January 31, 1988.

3 DOCUMENT ID 0036t/0031r

e 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

DOCUMENT ID 0036t/0031r e

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, la OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two

.s-DATE February 10, 1988 COMPLETED BY Steven J. Samolinski TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: January, 1988 GROSS HOURS IN RRPORTING 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 WHICM RESTRICTED (IF ANY) (MWe-Net):

None 4.

REASONS FOR RESTRICTION (IF ANY):.None THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 17528.8 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83 7.

HOURS GENERATOR ON LINE 744.0 744.00 17215.1 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 2247120 2247120 50042176 10.

GROSS ELEC. ENERGY GENERATED (MWH) 753086 753086 16561297_

11.

NET ELEC. ENERGY GENERATED (MWH) 727007 727007 15809620 12.

REACTOR SERVICE FACTOR 100.0%_

100.0%

60.8%

13.

REACTOR AVAILABILITY FACTOR 100.0%

100.0%

60.9%

14.

UNIT SERVICE FACTOR 100.0%

100.0%

59.7%

15. UNIT AVAILABILITY FACTOR 100.0%

100.0%

59.7%

16.

UNIT CAPACITY FACTOR (USING MDC) 90.7%

94.31 52.9%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 90.7%

90,7%

50.%

18.

UNIT FORCED OUTAGE RATE 0.0%

0.0 19.9%

19.

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

No shutdowns are scheduled durin9 the next six months.

20.

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

DOCUMENT ID 0036r/0031r

2. AVERAGE DAILY UNIT POWER LEVEL 9

DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: February 10, 1988 COMPLETED BY: Steven J. Samolinski TELEPHONE: (815) 357-6761 MONTH: DECEMBRR 1987 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net)

(MWe-Net) 4 1.

809 17.

940 2.

816 18.

1023 3

782 19.

986' 4.

804 20.

996 5,

877 21.

1051 6.

942 22.

1015 7.

1067 23.

872 8.

1068 24.

942 9.

1066 25.

1011 10.

1068 26.

1046 11.

1035 27, 1063 12.

1034 28, 985 13, 1011 29.

1036 l

14.

985 30.

1053 15, 1040 31.

801 l

16.

1068

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UNIT SHUTDOd*3 AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle itso DATE February 10, 1988' REPORT.TA mi January, 1988 COMPLETED BY S. Samolinski-TRLEPHONE (815)357-6761 METHOD GF TYPE SHUTTING DOWN F: FORCED sDURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCllEDULED (HOURS)

REASON REDUCING POWER ACTIONS /COFNDITS 1

1/31/88 S

0.0 B

5' toad drop for rod adjustments.

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UNIQUE REPORTING. REQUIRBMENTS -

_ Safety / Relief Valve-Operations for Unit Two. %:.4 1.

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%j'iDESCRIPTION

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f DATE VALVES NO & TYPE-PLANT CONDITION - A. 'h- -'Q.'OF EVENT

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, ACTUATED ACTUATIONS d'

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4g There were.n< Safety / Relief Valve operated for Unit ff di./

"a 1 ring this reporting'

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period.

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DOCUMENT ID 0036r/0031r

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2.,

ECCS Systems Outq;es

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7 ollowino.cutages were taken on ECCS Systems during f

Th therepcytingperiod.

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1 OUTAGE DO.ic

~ EOUIPMENT

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PURPOSE OF OUTAGE i

2-1-88 y

2B D/G Strai!

Bqukwagh During backwash valve goes f

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full open 2822-P319

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sf 2B D/G CoolillytWateX litraineq Reddr backwash viv. limits 2-7-88 b

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Mis $ D/G work 2-8-88 HPC3 D/G N

76. -

g4908-A IIPCS D/G Calibrate VAR meter 7

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h 2-y bq HPCS D/G Lubtication i

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HPCS Water leg pump Lubrication a

2;-j?;f.8-HPCS Pump Change oil

't 2-19-d8 LPCS motor cooling valve Troubleshooting 2-21-88

. C UHW Service Water pump

-Lubrication

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2-22-88 D RHR Styl, ice Wat r pump 1,.ubric at ion 2-23p8, B/CRHRMaterk,egPump Lubrication r

,1 2B-RilR Pump

'Qiangeoil 2-21-88'g(

2-25-88 2C RllR Pump

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C RFIR Hir/1 point vent"

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Repair sightglass leak 2-26-88 j

2E31-D3ih!.

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l 2-28-88 C/D RllR pudtp Strair;er

  • Change oil 2-37-88 RilR Servl.ce Water pum'ps A/B Change oil 7,

2-38-88 2A'Sy vice Water Strainer Change oil r

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<p 2-39-88 2A RHR Lubrication I,

LPCS Lubrication 2-40-88 W

2-41-68 Rhd 2A; service water pump Lubrication 2-42-88

  • lHR 2B serrice water pump Lubrication 2-43-88 Division i LDCS/RilR water leg L' Abrication pump 2-3-88 LPCS water leg pump 2821-C002 Cleaning 2-54-88 RilR shutdown cooling valves Repair 2E31-N068C DOCUMENT ID 0036r/0031r

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3.

Off-sits Doss Calculation Manual There were no changes to the ODCM during this reporting period.

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Radioactive Waste Treatment Systems.

A new contract was awarded to our present vendor. The new contract will cover a two year period. More.information will be provided in -

February's report.

5.

Indications of Failed Puel E1.ements.

Off Gas Levels indicate one pinhole fuel element failure in the reactor.

This does not represent a change from the previous reporting period.

There were no indications of Failed Puel Elements during this reporting period.

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DOCUMENT ID 0036r/0031r i

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