Text

Monthly Operating Repts for Mar 1988
	ML20148R380
Person / Time
Site:	LaSalle
Issue date:	03/31/1988
From:	Diederich G, Samolinski S; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	0043R-0031R, 43R-31R, NUDOCS 8804140330
	Download: ML20148R380 (36)
	v • d • e

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0 LASALLE NtJCLEAR POWER STATION UNIT 1 MONTHLY PERPORMANCE REPORT MARCH 1988 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPP-11 l

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8804140330 880331 PDR ADOCK 05000373 R DCD i f

DOCUnENT ID 0043r/0031r d(

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

1. Amendments to Pacility 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 REQUIREMENTS

1. Main Steam Reliof 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 Puel Elements j

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1. INTRODUCTION l

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

Ea:h 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 NPP-il 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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4 l ,, . II. MONTMLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE March 1-31 March 1, 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Unit one entered March with the Reactor critical and the generator on-line at 1080 MWe.

March 12, 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months Begin shutdown for second refuel outage.

March 13, 0150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months Generator taken off line at 130 MWe and Reactor manually scrammed.

March 13, 0155 hours0.00179 days 0.0431 hours 2.562831e-4 weeks 5.89775e-5 months LaSalle Unit One Refuel Outag; x) begins.

March 31, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Unit One in Second Refuel Outage.

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

1. Amendments to Facility License or Technical Specification.

Amendment number: 54 Amendment changes locations of breakers for RRR shutdown cooling isolation valve (lE12-F009). ,

Amendment number: 55 Jet pump operability surveillance. ,

Amendment number: 56 Administrative change to include Nuclear Safety Review of all reportable occurrences per GL 03-43. ,

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

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

3. Tests and Experiments not described in the Safety Analy' sis Repc 1.

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 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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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENf UNIT #1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L70398 Fuel pool leakage Metal chips in seat Valve not seating, allowing Replaced disc and lapped line isolation valve enough flow to pick up alarm seat L72772 Div. 11 swgr heat Bad love controller Improper indication Replaced controller removal temp controller ITIC-VX008 L74204 LPCS pump cooler Faulty 14 relay Relay not picking up Replaced relay v11ve IDG035 L74444 "0" D/G Freq. mett Meter out of calibration Indicating low frequency Recalibrated OSI-DG02BB L76208 Reactor vessel Lo Lo Faulty switch Improper indication during Replaced switch water level isolaticr. calibration switch IB21-N02.3B L76280 RCIC suction Indicator out of Improper indication Recalibrated pressure pressure indicator calibration indicator L76354 Temperature switch Switen out of calibration Spurious high Lemperature Recalibrated switch OTIC-VD005 alarms L76358 Blocking diode at Blocking diode shorted Improper operation Replaced diode panel ODG03J L76420 Control power Faulty Relay Contacts 61 and 62 not making Replaced Relay relay OVD01C when deenergized L76434 "B" D/G voltmeter Meter out of calibration Meter reading 80 - 100 volts Recalibrated too high DCCUMENT ID 0043r/0031r

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT UNIT #1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLAh'T OPERATION L76710~ B/C RHR CSCS area Contact linkage Cooler would not autostart Adjusted contact linkage cooler improperly adjusted L76819 "F" IRM Loose connection under Spurious half scrams Repaired connection vessel L78927 APRM "D" -20 VDC Teflon bushing dirty Power supply shorting out Cleaned bushing power supply L79036 Div. III Battery Bad circuit board Charger tripping off Replaced board Charger spuriously EDCUMENT 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.

UNIT ONE M-1-0-86-009: Modification of power supply circuitry to Technical Support Center doors in order to provide power from the same MCC and diesel generator backup.

M 1- 87-016 : Upgrade cable trali in Auxiliary Building for addition of ARI/MSIV.

M-1-1-87-083: Snubber reduction on subsystem IVG01 and IVG03 per 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, March 1, 1988 through March 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 88-001-00 2/22/88 RCIC High Reactor Water Level Switch Failure.

88-002-00 3/16/88 30 Day - Type B and C Tetal Leakage Exceeded 88-003-00 3/25/88 30 Day - 2 INOP 1RMs During Core Alterations 1

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D. DATA TABULATIONS .

The following cata tabulations are presented in this report:

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions e

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DOCUMENT ID 0043r/0031r

', , l. OPER.ATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE April 10, 1988 COMPLETED BY S. J. Samolinski TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: March 1988 GRObS 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 VHICH RESTRICTED (IF ANY) (MWe-Net): 0

4. REASONS FOR RESTRICTION (IF ANY): Refuel Outage THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR VAS CRITICAL 289.8 _1729.8 21774.3

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.0

7. HOURS GENERATOR ON LINE 289.3 1729.8 21159.8

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MVH) 848976 5252088 57086386

10. GROSS ELEC. ENERGY GENERATED (MVH) 286164 2227148 19194407

11. NET ELEC. ENERGY GENERATED (MVH) 270406 2152430 18251071 ,

12. REACTOR SERVICE FACTOR 39.0% 79.2% 58.4%

13. REACTOR AVAILABILITY FACTOR 39,0% 79.2% 62.8%

14. UNIT SERVICE FACTOR 39.0% 79.2% 56.8%

15. UNIT AVAILABILITY FACTOR 39.0% 79.2% 56.8%

16. UNIT CAPACITY FACTOR (USING MDC) 35.1% 95.1% 47.3%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 33.7% 91.4% 45.4

18. UNIT FORCED OUTAGE RATE 0.0% ___0.3% ___13.2%

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

N/A

20. IF SHUT DOVN IS AT END OF REPORT PERIOD, USTIMATED DN*E OF STARTUP:

Unit One is prasently in its second refuel outage. Ettimated date of startup is June 26, 1988.

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' 2. AVERAGE DAILY UNIT POWFR LEVEL DOCKE' NO: 050-373 lJIT: LASALLE ONE DATE: April 10, 1988 COMPLETED BY: S. J. Samo11nski TELEPilONE: (815) 357-6761 MONTil: MARC 11, 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (t%-Ne t ) (MWe-Net)

1. 1043 17. - 18

2. 1038 18. - 19 3 1032 19. - 13 4, 1007 20. - 13

5. 994 21. - 12 6, 991 22. - 8 7, 985 23. - 7

8. 973 24. __- 9 9 . _._ 968 25. _ - 9

10. 959 26. - 9

11. 954 27. - 8

12. _ 535 28. - 8

13. - 3 29. - 5

14. - 20 30. - 9

15. - 20 31. - 4

16. - 19 i

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3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373

UNIT NAME LaSalle One DATE April 10, 1988 REPORT MONTil MARCif, 1988 COMPLETED BY S. Samolinski TELEPilONE (815)357-6761 METiiOD OF ,

TYPE SIIUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCllEDULED (IfOURS) REASON REDUCING POWER ACTIONS /COMMEITIS 4 3/13/88 S 454.2 C 1 second refuel outage DOCUMENT ID 0043r/0031r

E. UNIQUE REPORTING REQUIREMENTS

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 actuated during the reporting period March 1 through March 31. 1988.

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2. ECCS Systems Outtgss

- The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO, EQUIPMENT PURPOSE _0F OUTAGE 0-58-88 ODG0lP Lubricate coupling 0-59-88 ODG0lx Inspection, replacement, of oil cire, pump motor 0-60-88 ODG01K Surveillance LMS-DG-01 0-61-88 ACB 1413, 2413 Electrical Surveillance ODG0lK 0-63-88 ODG0lK BOP Calibrations 0-73-88 "0" D/G Fix oil leak 1-04-88 1E22-C302B Prevent operation Petter diesel A/C 1-131-88 1DG090A Leave power off air dryer 1-174-88 HPCS Installation of CY flushing spoolpiece 1-182-88 "lB" D/G Surveillance LES-DG-102 1 183-88 "1B" D/G Replace stator temperature indicator l l-184-88 "1B" D/G Repair 1D0014 l l

1-185-88 "lB" D/G Surveillance LMS-DG-01 l l

s6-88 "lB" D/G Clean coolant sightglass l l

1-187-88 "lB" D/G llydrolaze D/G cooler l

i 1-188-88 "1B" D/G Repack 1E22-F319 l-191-88 1D0060 for 1DG04T Prain HPCS day tank 1-209-88 1E12-F092B/C Temporary removal of conduit support 1-246-88 HPCS Relay logic test i

1-266-88 1DOO2T Prevent draining or filling of tank 1-267-88 lE12-F063B Fill reactor vessel l

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OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE

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1-273-88 lE51-F064 Detereinste Steam to RHR 1-284-88 "lB" D/o Surveillance LES-cM-129 l-285-88 lE51-F064 Repair valves 1-287-88 LPCS CY spool piece Install spool piece 1-291-88 RCIC drain pot Repair 1E51- F053 i 1-292-88 lE22-F023 Rework valve 1-293-88 lE22-F023 Surveillance LES-EQ-ll2 1-294-88 HPCS pump Disassemble motor for t inspection and maintenance ,

1-295-88 HPCS pump Motor inspection 1-296-88 HPCS Water leg pump Replace min. flow orifice Repair discharge check valve 1-297-88 lE22-F010 Inspect anti-rotation setscrew 1-298-88 HPCS D/G storage tank Remove manway 1-307-88 RCIC Change out water leg pump orifice plate and relief valves 1E51-F017/18 1-335-88 "1B" D/G Replace lug on engine control power 1-346-88 lE22-F011 HPCS to CY test, inspect rotation 1-347-88 HPCS Uncouple motor / pump and drain system 1-355-88 HPCS pump Surveillance LES-GM-106 1-367-88 B/C RHR Surveillance LES-RH-101 1-371-88 lE12-F0908/92B Locked valve administrative control l

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,' OUTAG8 NO. EQUIPMENT PURPOGC OF OUTAGE l-384-88 IVYO2A Hydrolczs cros coolst 1-386-88 ACB 1433 Surveillance LES-GM-106 1-388-88 lE21-F016B/17B Surveillance LIS-RH-ll4 1E51-F086 1-469-88 1812-F017B Surveillance LES-EQ-112 1-476-88 B/C RRR Isolate and drain 1-477-88 B/C RHR Isolate and drain 1-478-88 B/C RRR Isolate and drain 1-485-88 lE12-F050B Repair Sealtite 1-486-88 B/C RHR water leg pump Replace MCC contactor 1812-C003 1-487-88 !E12-F0998 Repair Sealtite 1-490-88 1E12-F003B Determinate 1-491-88 1E12-F074B LES-EQ-ll2 1-492-88 1E12-F024B Determinate 1-520-88 1E22-F023 LES-GM-108 inspection 1-521-88 1E22-F010 LES-GM-108 inspection 1-522-88 lE22-F0ll LES-GM-108 inspection 1-523-88 1E22-P012 LES-GM-108 inspection 1-524-88 lE22-F015 LES-GM-108 inspection 1-525-88 1822-F001 LES-GM-108 inspection 1-526-88 1E22-F004 LES-GM-108 inspection 1-527-88 1822-F003 LES-GM-108 inspection 1-528-88 "1B" D/G Petter Diesel LES-GM-108 inspection A/C 1-529-88 HPCS Spool piece from CY Connect temporary flush DOCUMENT ID 0043r/0031r I

- OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE

' 1-532-88 "B" RHR pump Chemically clotn cac1

- 1812-C002B coolst 1-550-88 1E12-F003B Remove and inspect limitorque motor 1-551-88 1812-F024B "1B" RHR pump 1-552-88 1E12-C002C "C" RHR pump seal cooler 1-553-88 1E12-F048B "B" RHR Hx 48B repair 1-554-88 1812-F021 "C" MUt FFT repair 1-555-88 "B" RR pump drains Install coupling 1-567 88 1E22-F023 Administrative control 1-570-88 1E51-F068 RCIC Turbine Administrative control-isolation Floodup 1-575-88 1E12-F008 LES-EQ-112 1-593-88 1E12-F053A Decon flush of 1RR0744 1E12-F090A LLP-88-023 LKXNMENT ID 0043r/0031r

3. Off-Site Ooss Calculation Manust There were no changes to the OSDC 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 Puel Elements There were no indications of failed fuel elements during this reporting period.

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4 LASALLE NUCLEAR POWER STATION <

UNIT 2 MONTHLY PERFORMANCE REPORT MARCH, 1988 COMMOWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 4

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TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT 'WO A. Summary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility 1.icense or Technical Sper ifications

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 RFSORTS 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 DOCUMEl;T ID 0036r/003Ar

I. INTRODUCTION f 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 l 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.

l Unit two was issued operating license number NPF-18 on December 16 E 1983. Initial criticality was achieved on March 10, 1984 and i commercial power operation was commenced on June 19, 1984. l This report was compiled by Steven J. Samolinski, telephone number (

(815)357-6761 extension 705.

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II.

MONTHLY R2 PORT FOR UNIT TWO e_

A. SUf9mRY OF OPERATING EXPERIENCE FOR UNIT 'NO MARCH 1-31 i March 1, 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Unit Two entered March with the Reactor l critical and the generator on-line at 1085 We. ;

March 7, 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months Load drop to 725 MWe to perform Heater Bay Surveillances and work. I March 8. 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months Begin ramping to 930 MWe. !

March 9. 1739 hours0.0201 days 0.483 hours 0.00288 weeks 6.616895e-4 months Reactor scram on APRM Hi-Hi.

March 18, 0307 hours0.00355 days 0.0853 hours 5.076058e-4 weeks 1.168135e-4 months Reactor critical.

March 18. 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months Main Generator synchronized on to grid. Begin I ramping to 440 MWe. ;

March 21. 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months Ramping to 1030 MWe.

March 30, 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Load drop to 611 MWe for rod pattern adjustment.

March 30, 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months Begin ramping up to 1074 MWe. i March 31, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Reactor critical, generator on line and holding l at 1074 MWe, DOCUMENT 3D 0036r/0031r

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

,,' MAINTENANCE.

Amendments to Facility license or Technical Specification.

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l Amendment Numbet: 36 Jet Pump Operability Surveillance.

Amendment Number: 37 Administrative Change to Include Nuclear Safety Review of all ,

Reportable Occurrences, i

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

Report.

i There were no changes made 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 which are not described in the Safety Analysis Report.

4. Corrective Maintenance of Safety Related Equipment. )

The following table (Table 1) presents a sumenary of ;

Safety-Related Maintenance completed on Unit Two during the i reporting period. The headings indicated in this sunsaary I include: Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and .

corrective action.

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5. Completed Safaty Related Modifications. !

The following table (Table 2) presents a list of completed i Modifications during this reporting period. Each entry will have ;

a short synopsis explaining details involved with each '

modification.

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l CORRECTIVE r1AINTENANCE OF SA7ETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION i L54478 FMCRD Faulty position Improper position indication Replaced probe indicating probe L73912 "C" outboard Faulty limit switch Prevented pickup of the Replaced limit switch MSIV limit switch K3F relay I

L75974 LPRM 40-17D Bad LPRM card LPRM Failed downscale Replaced card I

L76185 "B" RR inbd. Bad shell assembly coil Valve closing spuriously Replaced coil and isolation valve and loose terminal tightened terminal 2B33-F344B connection connection l L76353 125 VDC DIV. I Faulty inverter Inconsistant charging amps Repaired inverter battery charger L764C2 DIV. I Post LOCA O2 monitor out of Monitor reauing high Recalibrated Monitor 2PL76J calibration L76438 Alarm unit Broken lead lug Improper connection Replaced lead lug PS-2E32-N651E L76459 PCIS test switch Bad contact block and Improper IN isoletion Replaced contact block and faulty relay repaired faulty relay L76528 liCU 46-19 Bad scram pilot valves Improper IICU isolation Replaced scram pilot valves L76604 IRM "C" 2C51-K601C Bad MAV connection at IRM spiking causing spurious Replaced connector De'tector OXY-VC165A IRM drawer half scrams L76605 IRM "D" 2C51-K601D Faulty inhibit switch Spurious half scrams Replaced switch DOCUMENT IL 3036r/0031r

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CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 VORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L76659 "B" RR HPU Inbd. Damaged lug inside valcour Valves failed closed Replaced lugs Isolation Valves valve 2B33-F342B L76667 "A" FW testable check Seals failed on air Compromised valve operation Replaced actuator air valve cylinders cylinder.

L76668 "C" Inbd. MSIV Inoperable Norgren valve M31V not closing properly Replaced valve 2B21-F022C when slow closing L75720 "C" Inbd. MSIV Improperly adjusted limit K3F relay would not reset Readjusted limit switch 2B21-F022c switch L28936 LPRM 32-57A Improperly connected fuse No input to process Resoldered fuse to trace computer on LPRM card.

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CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 E K REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L54478 FMCRD Faulty position Improper position indication Replaced probe indicating prooe L75912 "C" outboard Faulty limit switch Prevented pickup of the Replaced limit switch MSIV limit switch K3F relay L75974 LPRM 40-17D Bad LPEM card LPRM Failed downscale Replaced card L761d5 *B" RR inbd. Bad sitell assembly coil Valve closing spuriously Replaced coil and isolatiori valve and loose terminal tightened terminal 2833-F344B connection connection L76353 125 VDC DIV. I Faulty inverter Inconsistant charging amps Repaired inverter battery charger L76402 DIV. I Post LOCA O2 monitor out of Monitor reading high Recalibrated Monitor 2PL76J calibration L76438 Alarm unit Broken lead lug Improper connection Replaced lead lug PS-2E32-N651E L76459 PCIS test switch Bad contact block and Improper IN isolation Replaced contact block and faulty relay repaired faulty relay L76528 HCU 46-19 Bad scram pilot valves Improper HCU isolatior Renlaced scram pilot valves L76604 IRM "C" 2C51-K601C Bad MAV connection at IRM spiking causing spurious Replaced connector Detector OXY-VC165A IRM drawer half scrams L76605 IRM "D" 2C51-K601D Faulty inhibit switch Spurious half scrams Replaced switch 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 desiga resolution. Also, state reviewed or unreviewed safety questions.

UNIT TWO There were no safety related modifications completed on Unit 'No during the reporting p2riod of March i through March 31, 1988, i

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r C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Uttit Two, logged during the reporting period, February 1, through February 29, 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 88-001-00 3/2/88 2B D/G Circulating Water Pump Failure to Auto Start.

88-002-00 3/3/88 30 Day - Group 10 Div. II Isolation.

88-003-00 3/9/88 Scram 1 - Reactor Scram on High APRM Flux.

88-004-00 3/21/88 30 Day - Missed Surveillance on LOS-MS-M1.

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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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" 1. OPERATING DATA REPORT DOCKET NO. 050-374 l

.- UNIT LaSalle Two l

DATE April 10, 1988 1 COMPLUTED BY Steven J. Saseolinski s TELEPHONE (815)357-6761 i

! OPBRATING STATUS 1

i 1. REPORTING PERIOD: March. 1988 GROSS HOURS IN REPORTING PERIOD: 744 ,

I' 2. CURRENTLY AUTHORIZED POWER LEVEL (Wt):3323 MAX DEPEND CAPACITY $

(We+et ) : 1036 DESIGN ELECTRICAL RATING (MWe-Net):_1078 i

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

4. RFJtSONS FOR RESTRICTION (IF ANY): None <

THIS MONTH YR TO DATE CUMULATIVE l 5 NUMBER OF HOURS REACTOR WAS CRITICAL 542.5 1982.5 18767.3 ;

6. REACIOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83 i

7. HOURS GENERATOR ON LINE 525.9 1965.9 18437.0 ,

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 1419096 5840640 53635696

10. G. TOSS ELEC. ENERGY GENERATED (MWH) 470842_ 1953935 17762146

11. NET ELEC. ENERGY GENERATED (MWH) 450050 .1883362 16965975 !

12. REACTOR SERVICE FACTOR 72.9% 90.8% 62.0%

13. REACTOR AVAILABILITY FACTOR 72.9% 40.8% (,2.1%

14. UNIT SERVICE FACTOR 70.7% 90.0% 60.9% I

15. UNIT AVAILABILITY FACTOR __,70.7% 90 % 60.9% !

16. UNIT CAPACITY FACTOR (USING MDC) 58.4% 83. 2% _ 54.1%

17. UNIT CAPACITY FACTOR (USING DESIGN l MWe) 56.1% 80.0% 52.0%

18. UNIT FORCED OUTAGE RATE 29.3% 10,0% 19.6%

19. SHUTDOVNS Scr4EDULTD OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

N/A

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

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DOCUMENT ID 0036r/0031r ,

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' AVERAGE DAILY UNIT POWER LEVEL ,

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i DOCKET NO: 050-374

!* UNIT: LASALLE TWO DATE: April 10. 1988 )

! OOMPLETED BY: Steven J. Samolinski i i

TELEPHONE: (815) 357-6761 l l MONTH: MARCH. 1988_, i i i i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL !

(MWe-Net) (MWe-Wet)

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! i j 1. 1049 17. -

18 l

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2.. 1043 18. 13

! 3. 1044 19. 385 l

j 4. 1045 20, 398

) 5. 1040 21, 475 ;

6.__ 1037 22. 904 ,

7. 988 _

23, 932 ;

8. 810 24. 922 i

9. 637 25, 897 i ,

.\

10. -

7 26. 864 '

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11. - 7 27, 884

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J j 12. - 14 _ 28. 874

13. - 18 29, 921 _ f r ,

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14. - 19 30. 773

) i j 15. - 19 31. 939 [

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16. - 18 !

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COCUMENT ID 0036r/0031r

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3. UNIT SHUTDOWN 3 AND POWER REDUCTIONS I '

DOCKET NO. 050-374 '

UNIT NAME LaSalle Two

DATE April 10, 1988 REPORT MONTH MARCH, 1988 COMPLETED BY S. Samolinski TELEPHONE (815)357-6761 METHOD OF T~ti 3 SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORREC TIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTION 3/ COMMENTS 5 3/7/88 S 0.0 B 5 Heater i3ay work and surveillances.

6 3/9/88 F 218.10 A 3 Reactor scrammed on APRM Hi-Hi and loss of both RR pumps.

7 3/30/88 s 0.0 B 5 Rod pattern adjustat.nt.

DOCUMENT ID 0036r/0031r

l E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUPTIONS CONDITION _OF EVENT There were no Safety Relief Valves actuated during the reporting period of March 1 through March 31, 1988.

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d' 2. ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period.

I OUTAGE NO. EOUIPMENT PURPOSE OF OUTAE 2-131-88 "2B" D/G Clean Kl8 rela:' contacts 2-145-88 2DG08CA Head relief lifts "2A" D/G "A" A/C 2-171-88 "B,'C" RHR Water leg pump Replace EQ contactor 2-176-88 "C" RHR pump Motor EQ terminations 2-196-88 RCIC Barometric condensor Inspect r.otor vacuum pump 2-209-88 RCIC Lubrication 2-230-88 2E12-P004B Repair valve actuator 2-237-88 "2A" D/G Lubricatloa 2-242-88 "2B" D/G air compressor Change high pressure valve assembly 2-249-88 2E12-F049A/B Prevent use 2-250-88 2E12-D313 Replace Sightglass 2-252-88 2E12-P049A/B Repair 2812-D313

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I 4* 3. Off-Site Dose Calculation Manual There were no changes to the OSDC 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. This does not represent a change from the previous reporting period.

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

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Ccmmsnw:alth Edisen

. LaSalle County Nuclear Station

@ RuralRoute #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357-6761 April 10, 1988 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period March 1, 1988 through March 31, 1988.

Very truly yours, s odi A G J. Diederich Station Manager LaSalle County Station GJD/EJS/jdp Enclosure xc: J. G. Keppler, NT.C, Region III l Gary Wright, Ill. Dept. of Nuclear Sat'ety l P. Shemanski, NRR Project Manager INPO Records Center L. J. Anastasia, PIP Coordinator SNED D. P. Galle, CECO D. L. Farrar, CECO H. E. Bliss, Nuclear Fuel Services Manager NRC Resident Inspector LaSalle M. A. Ortin, GE Resident C. F. Dillon, Senior Financial Laordinator, LaSalle Dennis Carlson/ Tech Staff ,

Terry Novotney/INPO Coordinator, Tech Staff Central File I\

LA.A.6 ID 0043r/0031r

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ML20148R380

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SUMMARY

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