ML20137B056

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Monthly Operating Repts for Dec 1985
ML20137B056
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/31/1985
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
0043R-0005R, 43R-5R, NUDOCS 8601150034
Download: ML20137B056 (33)
v • d • e


Text

r-o LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFOIOUWCE REPORT DECEMBER, 1985 CONIONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. WPF-11 060115003 g5 373 PDR Am O PDR l

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I Document 0043r/0005r g{g

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o C I. INTitODUCTION The LaSalle County Maclear Power Station is a two-unit  !

facility owned by Comunonwealth Edison Company and  ;

located near Marseilles, Illinois.. Each unit is a i-Boiling Water Reactor with a designed not electrical i 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 l contractor was commonwealth Edision Company. ,

I Unit one was issued operating license number MPF-11 on  !

t April 17, 1982. Initial criticality was achieved on June 21, 1982 and cosmeercial power operation was commenced cn January 1, 1984. [

This report was complied by James P. Peters, telephone number (815)357-6761 extension 325. >

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-TABLE OF CONTENTS

~ 1 INTRODUCTION I.

II. MONTHLY REPORT FOR UNIT ONE A. Suunnary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE l.- Amendments to Facility License or Technical Specifications

2. Facility or Procedure Changes Requiring MRC Approval
3. Tests and Experiments Requiring MRC Approval
4. Corrective Maintenance of Safety Related Equipment 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 i
1. Main Steaua Relief Valve Operations
2. ECCS Systeen Outages
3. OfE-Site Dose calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment

. System 4

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II. MotlTHLY REPORT FOR Uti1T 095E '

' i R. SUIMARY OF'OPERATIllG EXPERIIDICE FOR UNIT ORIE l

December 1-31 j dec. 1, 0001 Hours. The Unit entered December,with ,

the reactor'subcritical and Unit-off line in cold shutdown for sfirst ryfuel outage.

-u e Dec. 30, 2400 Hours. Reactor in Ccid shutdown for

' ' First refueling outage.

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C;. " PLANT OR PROCEDUR3 CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

, MAINTENANCE.

1. Annendments to facility license or Technical Specification.

Amendsment 31- Removed RCCS/RCIC testable check air operated bypass valves.

2. Facility or procedure changes requiring NRC approval.

There were no Facility _or Procedure Changes Requiring NRC approval during this reporting period.

3. Tests and Experiments requiring NRC approval.

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) prerints a susanary of safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this suussary include: Work Request nusaber, Component Nasme, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED BQUIPfEDfT ,

WORK RBQUEST 00ff0NENT CAUEIE OF MALFUNCTION ,

RESULTS AND EFFECTS CORRECTIVE ACTION

-ON SAFE PLANT OPERATION ,

L35636 LPRM String 24-41A - Failed Detector, Pegged - LPRM Upscale LPRM Detector String to Upscale. be replaced. T

, L39494- LPRM String 24-25D Failed Detector, Pegged LPRM Upscale LPRM detector String to-upscale. be replaced..

l L44671 LPRM String 40-25A- Failed Detector, Pegged .LPRM Upscale- LPRM Detector String to ,

Upscale. .

be replaced.

L44768 DG Cooling Water Pump Inboard Pump Packing The Equipment Drain Being Unplugged equipment ODG0lP Leaks Excessively. plugged caused excessive drain and inspected water accumulation. pump.

L45391 LPRM String 32-41C Failed Detector, Pegged LPRM Upscale LPRM Detector String Upscale. to be Replaced.

L46931 LPCS Full Flow Test Bad Cap and Bushing on The Valve stem Cover vibrates. Remove old cap and .m lE12-F012. valve. loose when flow is through the bushing and replaced. ,

valve.

L48509 LPRM String 24-57B Failed Detector, Pegged LPRM Upscale LPEM Detector String to Upscale. be' Replaced. ,

'L51947 Stack WRGM OD18-R522 Bad Action Pak Relay. Loose Effluent Range Recordeder is New retaining clips x in its socket. sporadic and does not track were installed.,

the digital reading. ,

L52447 Div-I Supp. Pool Bad. Selector Seith and Recorder would intermittently Replaced selector Temperature Recorder Range Select cards, drive downscale. switch and Range Select ITR-CM037. cards.

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< TABLE 1 CORRECTIVE MAINTENANCE OF SAFSTY RELATED SQUIPfEDfT ,

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L53678 H2 Recombiner Inlet Bad Torque Switch. The Valve opened but would . Replaced torque switch Valve PV-1 not close.

L53820 H2 Recombiner to _ Metal Shavings Present Valve was Mechanically bound, Removed Metal Shavings

, Suppression Pool in Valve Housing and Stem would not operate, from Handwheel Components.

Stop Valve lHG003.-

L53847 "A" VC Ammonia Bad fiber optics board Spurious Anusonia Detector Trip. Replaced Fiber Optics Detector OXY-VCl25B. and Sample Pump. Board and Sample Pump.

L53959 SBGT Inlet Valve Misadjustment of contact Valve won't electrically open. Adjusted Torque switch IVG001. on Torque' Switch.

L54148. H2 Recombiner X-Tie Pinched wire under the Fuse for control breaker keeps Repaired wire.-

Valve lHG009. cover on limit switch. blowing when breaker energized.

L54209 VC Chlorine Detector Detector would not alarm. Failure of LIS-VC-01. Cleaned wick and ad .

OAE-VC090A. justed Drip Rate.

L54760 VC Damper OVC13YB. Misaligned Linkage. Damper does not close fully. Adjusted linkage on actuator to close damper.

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C. LICENSEE EVID'T REPORTS The following is a tabular sumanary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, December 1 through December 31, 1985. 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 85-066-00 11/06/85 Failed LLRT on feedwater check valve 1

85-067-00 11/20/85 Spurious chlorine detector actuation.

85-068-00 11/24/85 LE12-F009 valve isolation due to air bubble in sarole line.

85-069-00 11/30/85 Surveillance not completed in time.

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

1. Operating Data Report
2. Average Daily Unit Power Level i
3. Unit Shutdowns and Power Reductions l

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1+. OPERATING DATA REPORT DOCKET WO. 050-373 UNIT LaSalle One DATE January 10, 1986 COMPLETED BY Jasnes P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: December 1985 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIEED POWER LEVEL (M t):3323 MAX DEPEND CAPACITY j (We-Met): 1036 DESIGN ELECTRICAL RATING ( W e-Net): 1078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (We-Met): N/A
4. REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUELATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0:0 5757:5 12039:00
6. REACTOR RESERVE SHUTDOWN HOURS 0:0 476:2 1642:00
7. HOURS GENERATOR ON LINE 0:0 5585:35 11642:00
8. UNIT RESERVE SHUTDOWN HOURS 0:0 0:0 0:0
9. GROSS THERMAL ENERGY GENERATED (WH) 0.0 15390361 32213650
10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 5028751 10499394
11. NET ELEC. ENERGY GENERATED ( W H) -9098 4809395 10004457 l 12. REACTOR SERVICE FACTOR 0.0% 65.7% 68.5%
13. REACTOR AVAILABILITY FACTOR 0.0% 71.2% 77.9%
14. UNIT SERVICE FACTOR 0.0% 63.8% 66.3%
15. UNIT AVAILLDILITY FACTOR 0.0% 63.8% 66.3%
16. UNIT CAPACITY FACTOR (USING MDC) -1.18% 52.9% 54.9%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.13% 50.9% 52.8%
18. UNIT PORCED OUTAGE RATE 0.0% 17.4% 17.4%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

The First Refueling, Maintenance, Surveillance and Modification outage began October 18, 1985 and will last 30 weeks.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTur': May, 1986 l

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: January 10, 1986 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: DECEMBER 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met) (MWe-Net)
1. -15 17. -15
2. -15 ,_
18. -15 3 -15 19. -14
4. -13 20. -13
5. -14 21. -14
6. -14 22. -14
7. -15 23. -16
8. -15 24. -12
9. -14 25. -9
10. -14 26. -6
11. -14 27. -5
12. -14 28. -5
13. -14 29. -3
14. -15 30. -5
15. -14 31. -6
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ATTACHMENT E .,

' 3. UNIT SHUTDOWNS AN9 POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One

  • DATE JANUARY 10. 1985- .

REPORT MONTH DECEMBER 1985 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED ~ (HOURS) REASON REDUCING

  • POWER ACTIONS /COf9fENTS No Unit Shutdowns or Power Reductions During This Reporting Period.

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E. UbIIQUE REPORTIWJ REQUIRFJUDrrS

1. Safety / Relief valve operations for Unit One.

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

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.- .2.. ECCS Sy2tems Outiges

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

OUTAGE NO. ROUIPMENT PURPOSE OF OUTAGR 1-1288-85 IE22-F354 Remove Equipment 1-1296-85 IB DG Repair 1DOO14 1-1302-85 LPCS System Remove IE21-F333 1-1303-85. RI'(F354) Remove 1851-F354/355 1-1322-85 "A" RHR loop Fill Stop xfer water to supp. Pool.

1-1341-85 HPCS Inj. Test Stop Drain Line 1-1370-85 A RHR Hx Ws Side Hydrolaze HK.

1-1371-85 RCIC Pump IE51-C001 Install New Seal 1-1372-85 1821-F005 LES-BO-112 1-1374-85 1851-F069 LES-BO-112 1-1375-85 1851-F064 LES-BO-112 1-1376-85 1851-F076 LES-BO-112 1-1377-85 IE51-F063 LES-BO-112 1-1378-85 1851-F008 LES-BO-112 1- 1379-85 1851-F080 LES-BO-112 1-1380-85 1851-F086 LES-BO-112 1-1381-85 IE51-F068 LES-BO-112 1-1382-85 1E22-F023 LES-EO-112 1-1383-85 1E22-F012 ~LES-BO-112 1-1384 1E22-F010 LES-BO-112 1-1385-85 LE21-F011 LES-BO-112' 1-1386-85 1E21-F012 LES-EO-112 1-1387-85 1DG035 LES-BO-112 1-1390-85 1E22-F354 Disconnect W'res 1-1391-85 IE22--F004 LES-BO-112 1-1397-85 "1B" DG Remove IE22-F381B for use

, on 1R DG.

1-1401-85 "0" DG Instrument Recalibration 1-1402-85 "U" DG Prelube Mod.

1-1403-85 OD0006 Repeck Valve 1-1404-85 "0" DG Calibrate Protective Relaying 1-1405-85 "0" DG Feed 141Y ~ Replace sulfer piston

'1-1406-85 "1C" RHR Pump LES-BO-112 1-1407-85 LPCS Pump LES-BO-112 1-1408-85 HT3 Pum.p LES-BO-112 1-1409-85 "1B" DG Oil and filter change 1-1410-85 HPCS DG For Mod Package review 1-1413-85 "A" RHR LES-BO-112 1-1414-85 1812-F042A Inspect work gear i

1-1415-85 1E12-F004C LES-BO-112 l 1-1416-85 1812-F011A LES-BO-112 l

1-1417-85 1812-F011B LES-BO-112-1-1418-85 1812-F017A LES-Bo-112 1-1419-85 1E12-F026A LES-BO-112 1-1420-85 1E12-F026B LES-BO-112  ;

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  • ~ BOUIPMENT PURPOSE OF OUTAGE OUTAGE NO.
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4 1-1421-85 1812-F042A LES-BO-112 1-1422-85 LE12-F049A LES-BO-112 1-1423-85 IE12-F049B LES-BO-112 1-1424-85 1812-F052A LES-80-112 1-1425-85 1812-F052B LES-BO-112 1-1426-85 1E12-F064C LES-BO-112 1-1428-85 1812-F068A LES-BO-112 1-1429-83 1E12-F063B LES-BO-112 1-1430-85 1E12-F068B Motor change Out 1-1431-85 1E12-F073A LES-EO-112 1-1432-85 LE12-F073B LES-BO-112 1-1433-85 LE12-F074B LES-BO-112 1-1434-85 1812-F074B LES-BO-112 1-1435-85 1E12-F037A LES-BO-112 1-1436-85 IE12-F087B LES-BO-112 1-1437-85 1E12-F093 LES-BO-112 1-1438-85 IE12-F03A/47A LES-BO-112 1-1444-85 "C" RHR Ws Pp Throttle Disch.

1-1445-85 "C" RHR Ws Pp ~ Repair Motor 1-1452-85 1851-F064 LES-BO-112 I

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3. Off-Sit @ Dose Calcult. tion Manual l

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

4. Radioactive Waste Treatsment Systems.

There w3re no significant changes to the radioactive waste treatment ,

system during this reporting period. [

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT DECEMBER 1985 COtttONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO NPP 18 l

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I. InmtODUCTION l l

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'The 1.aSalle County Nuclear Power Station is a two-unit l facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical l 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-18 on December 16, 1983. Initial criticality was achieved on March 10,-1984 and commercial power operation was cosmaenced on June 19, 1984.

This report was compiled by James P. Peters, telephone number (815)357-6761 extension 325.

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TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Summary of Operating Experience B. - PLANT OE. PROCEC'JRE CHANGES, TESTS, EXPERIMENTS, AND SAFET'I RELATED MAINTENANCE l '. Amendm xts to Fecility License or Technical Specificatiort s

2. Facility or Ptw edure Changes Requiring NRC Approva?
3. Teets and Pwperiments Requiring NRC Approval
4. Correceive Maintenance of Safety Related Equipment C. LICENSEE EVENT REPORTS D. -DATA TABULATIONS
l. Operating Data S port
2. Average Daily iJnit Power Level
3. Unit Shutdowns and Pcwer noductions 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 s

DOCUMENT ID 0036r/0005r-

II. ' M0hTHLYREPORTFORUNITTWO A. SUIMARY OF OPERATING EXPERIENCE FOR UNIT TWO ,

'Movember 1-30 Dec. 1,'_0001. Hours. The Jnit entered December with the

g. reactor.subcritical and Unit-off Line in a cold. shutdown.

Dec. 22, 2110 Hours. Reactor Sustained Criticality Dec. 23, 2215 Hours. Generator Synchronized to Grid, 18% (130 MWe) ,

Dec. 24, 2300 Hours. Reactor Power Increased to 50%

(444 MWe)

Dec. 25, 0000 Hours. Entered 8 Hour Time-Clock Due to containment.02 concentration.

. Dec. 25, 0045 Hours. . Unusual Event declared, commenced '

Reactor shutdown.

Dec. 25, 0745 Hours. ' Reactor' Power at 15% (108 We), t Main turbine taken off line due to high vibrations.

Dec. 25, 1025 Hours. Generator Synchronized Back onto the Grid

  • Dec. 25, 1500 Hours. Reactor Power Increased to 29%

(272 MWe)-

Dec. 25, 2300 Hours. . Reactor Power at 45% (455 MWe)  ;

! Limited by feedwater control problems.  :

Dec. 26, 2300 Hours. Reactor Power at 69% (125 MWe)

Dec. 27, 1500 Hours. Reactor Power at 81% (905 MWe) i Dec. 27, 2000 Hours. Reactor Power Reduced to Manipulate the control' Rods. .  !

Dec. 27, 2300 Hours. Reactor Power Restored to 59% (625 MWe).

Dec. 29, 1500 Hours. Reactor Power Increased to 99%

l (1105 MWe) i Dec. 30, 2000 Hours. . Commenced Power Reduction to 78% i (850 MWe) Due to Leak in 25A Heater.

. Dec. 31, 0020 Hours. 25 A Heater Isolated and Power is .

increased to 82% (900 MWe) r l Dec. 31, 2400 Hours. Reactor Power at'88% (886 MWe). [

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. B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMIDITS AND SAFETY RELATED l

MAINTENANCE.

1. Amendments to facility license or Technical Specification.

No Amendments Changes Reported during this period.

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure change requiring NRC

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3. Tests and experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during the reporting period.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of.

I 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 a.alfunction, results and effects on safe operation, and corrective action.

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TABLE 1 -

CORRECTIVE MAINTENANCE OF .

SAFETY RELATED EQUIPMENT ,

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L44242 LPRM String 56-41D Bad connection under vessel LPRM Pegged. Upscale. Replaced connection on on cable. cables under vessel. ,

L51318 LPRM, APRM B 2C51- LPRM Card 40-17-6'B Had a LPRM Downscale Alarm will Replaced zener diode.

K605 Cu. Bad zener diode. not reset.

L51601 RBM A 2C51-K605GU Bad Transistor on Second With Rod Group 2-2 Selected the Replaced Transister.

Level Multiplexer Card. APRM A Reads upscale.

L52460 LPRM String 48-09C. Bad Transistor on circuit Core Display on 2H13-P603 shows Replaced Transistor.

Card, downscale.

I ~L53067 Post Loca Monitor Misadjusted Flow Control Room indication does not Readjusted tiow .

2 AIR-CM048. Regulators, match survey. regulators.

L53135- FW Testable Check The Valve Actuators were Valve actuation is stuck in Replace Air Actuators.

2B21-F032A. blown. Mid-Position.

L53162 "B" LPCI Inj. Line Bad Air Cylinders and Valve would not cycle then no Replaced Air cylinder-Testable Check Misaligned open/ closed control room indication, and reset limit switches.

l 2E12-F041B Limit Switches.

L53398 RWCU Isolation Timer M-1-2-85-065 Prevents the LD Rileys Trips Installed RC Network

2E31-R621A/B. when RWCU isolates. across isolation timer-motor.

L53451 MSIV Leakage Control Loose Contacts and Lead Valve would not go full closed. Tightened and cleaned contacts and wires.

Valve 2E22-F00lJ. Wires on Torque Switch.

. L53503 2A RHR Pump Bad Relay that feeds the Pump Auto Trip Light will not Replaced Relay.

2E12-C002A. the Alarm. Reset, i

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1 TABLE 1 CORRECTIVE MAINTENANCE OF-

  • SAFETY RELATED. EQUIPMENT ,

WORK REQURCT. COff0NENT CAUSE OF MALPUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION. -

ON SAFE PLANT OPERATION L53514 H2 Recombiner TSC and TSO Setting Two LLRT, LTS-100-23 Required- Reset TSC and TSO

  • i Outboard Valve High, to 1.

< 2HG0018-L5351~1 RWCU Outboard Iso- TSC setting to High. LLRT, LTS-100-19 Required.- Reset TSC to 1 1/2.

lation valve 2G33-

")04.

b3659 MSIV Leakage control Misadjusted Open contacts Valve would not go full open, Cleaned and adjusted Valve 2E22-F003J. on Limit and Torque Switch. intermediate only. .open Torque and Limit Switch.

L53712 RHR Cont.. Spray Small Packing Leak. LLRT, LTS-100-27 Required Repacked Valve.

2E12-F016A.

L53906 RCIC Vacuum Isolation Internal Mechanical Valve Movement in any direction, Repacked Valve. '

Valve 2E51-F086. Binding. Torque Switch goes open.

L54058 RCIC Discharge Valve Bad Limitorque Valve. Removed From U1 to Put in U2. Replaced Valve.

2851-F013.

L54084 VQ Vent and Purge Limitorque not positioned Valve is leaking past the seat. Rotated Limitorque Inlet. valve 2VQO29. correctly. LLRT, LTS-100-5 Required. 45' counterclockwise, and cleaned-seats.

L54315 2851-F069 Breaker. Shorted Torque Switch. 250 VDC Ground when breaker.is Replaced Torque Switch.

closed.

L54402- VQ Vent and Purge TSC and TSO set Two High. LLRT, LTS-100-5 Required. Reset TSC and TSO to Inlet Valve 2VQO30. I 1/4.

L54404 H2 Recombiner Valve Internal Mechanical Valve will not go full closed. Repacked Valve.

2HG002A. Binding. LLRT, LTS-100-23 Required.

Bad Suction Gage L54411 "A" RHR Pump Suction Gage Reads too high. Replaced and Recalibrated 2E12-F002A. Gage.

DOCUMENT 0044r/0005r

~ TABLE 1 .

CORRECTIVE MAINTENANCE OF ,

SAFETY RELATED EQUIPMENT ,

i WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L54473 RHR a Full Flow Test Excessive Flow Through. The Min. Flow Valve will not Set Gehred Limit Switches '

-Valve 2B12-F024A. 2E12-F024A Valve. open. on valve to bypass Torque Switch. -

L54528 HPCS DG Cooling Water Breaker Trips. Requested by NRC For Test Tested Breaker.

Pump 2822-C002. Results.

L54549 2VQO36 Purge Valve Pinched Wire on Motor. Breaker Trips on Magnetics. Repaired Bad Wire Leads.

," . Breaker.

L54551 H2 Recombiner Inlet Misadjusted. Limited Switch Valve will only Partially Open. Reset applicable Valve 2HG0028. Limit Switch. .

L54557. -vg Outlet Purge. Misadjusted Limit Switch. Dual Indication when valve was Reset Closed Limit Isoltion Valve. full closed. Switch.- ,

2VQO29.

4 L54562 H2 Recombiner Bad Torque Switch Lugs and valve will not open or close.- Replaced Torque Switch 2HG002A. misadjusted Torque Switch. Lugs and set limits.

L54570 SDV Vent Valve Loose packing at steam. Valve Leaks are excessively. Tightened Packing.

2Cll-F380.

L54816 2DC06E MCC 221Y compt. Thermal Overload Elements. Circuit Breaker would not Reinstalled thermal 3B,3C,58 and 7A. upside down. -operate on overload trip. overload elements right side up.

L54827 "B" DG AIR Start Bad Valve internais. When diesel Returned to service Replaced internals.

Motor 2DG061B. air start valve failed to fully in valve, close.

L54858 .RCIC HI STM Flow Improper backfill of HI RCIC HI Steam flow Isolation Backfilled the HI and i.ow Isolation 2E31-N007B. and Low sensing lines. During Start-up. sensing lines.

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! DOCUMENT 0044r/0005r

- - .~. _ . .

    • LICENSEE EVENT REPORTS The following is a tabular suweary of all licensee event reports for i

i LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, December 1 through Decer.ber 31, 1985. This information is provided pursuant to the reportas,le occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Numble . 'Date Title of Occurrence 85-047-00 11/15/85 Missed Technical Specification sample on "B" RHR Service Water PRM.

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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 4
3. Unit shutdowns and Power Reductions i

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DOCUMENT ID 0036r/0005r

, 1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE January 10, 1985 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: December 1985 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MJt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Met):1078
3. POWER LEVEL TO WHICH RESTRICTED (IF AM) (MWe-Met): N/A
4. REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUIRJLATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 218:8 3777:6 5389:4
6. REACTOR RESERVE SHUTDOWN HOURS 525:2 1561:8 1687.1
7. HOURS GENERATOR ON LINE 191:1 3698:91 5236:31
8. UNIT RESERVE SHUTDOWN HOURS 0:0 0:0 0:0
9. GROSS THERMAL ENERGY GENERATED (MWH) 433833.6 11000 % 0 15508552
10. GROSS ELEC. ENERGY GENERATED (MWH) 13 % 34 3625083 5110069
11. NET ELEC. ENERGY GENERATED (MWH) 128462 3430898 4823215
12. REACTOR SERVICE FACTOR 29.4% 43.1% 51%
13. REACTOR AVAILABILITY FACTOR 100% 60.9% 6%
14. UNIT SERVICE FACTOR 25.% 42.2% 49.6%
15. UNIT AVAILABILITY FACTOR 25.% 42.2% 49.6%
16. UNIT CAPACITY FACTOR (USING MDC) 16.% - 37.8% 26.5%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 16.1% 36.% 25.5%
18. UNIT PORCED OUTAGE RATE 74.% 30.2% 26.8%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF BACH):

None

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

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DOCUMENT ID 0036r/0005r

2. AVERMit DAILY UNIT POWER LEVEL

.' DOCKET NO: 050-374_

  • UNIT: LASALLE TWO DATE: January 10, 1985 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: December DAY AVERME DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met) (MWe-Met)
1. -14 17. -15
2. -14 18. -15 3 -15 19. -13
4. -13 '20. -12
5. -13 21. -13
6. -13 22. -14
7. -14 23. -5
8. -15 24, 308
9. -14 25. 237
10. -14 26. 468
11. -13 27. 805 i
12. -14 28, 891
13. -14 29. 1062
14. -14 30. 1025
15. -14 31. 863
16. -14 DOCUMENT ID 0036r/0005r

ATTAC"9 MENT E ,

, 3. UNIT SHUTDOWNS AND POWER REDUCTIONS ~'

DOCKET NO.' 050-374

, UNIT NAME LaSalle Ttso DATE January 10, 1986 .

REPORT MONTH DECEMBER 1985 COMPLETED BY Jesnes P. Peters TELEPHONE (815)357-6761 i

METHOD OF TYPE SHUTTING DOWN

'F: FORCED DURATION- THE REACTOR OR CORRECTIVE NO. DATE S:' SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COfMENTS

12. 12/25/85 P 2.7 HI Turbine 5 Inerted drywell and-Vibration Increased Power Level.-

.(15% causes excessive

-vibration).

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, DOCUMENT 0044r/0005r i

E. UtlIQUE REPORTING REQUIREMENTS i

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CODIDITION OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period.

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DOCUMENT ID 0036r/0005r

, 2. ECCS Systems Outs.gaa o'

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

OUTAGE MO. BOUIPMENT PURPOSE OF OUTAGE 2-1591-85 2E51-F068 Replace Limitorque Motor 2-1599-65 2E12-F027A Rotate Motor Mounting 2-1603-85 2E51-F068 Replace Motor 2-1610-85 2851-F080 Replace Jumper 2-1611-85 2A RHR Pp Motor Change Oil 2-1626-85 2E51-P069 Troubleshoot Ground 2-1627-85 2E12-F027A Prevent Inadvertent Draining of Reactor 2-1633-85 2E12-F336A Replace Contactor ,

2-1635-85 2E12-F024A Inspection 2-1643-85 2E12-F004B Inspection 2-1644-85 2E12-F042B Inspection 2-1645-85 2E12-F004C Inspection 2-1646-85 2E12-F016B Inspection 2-1647-85 2812-F049B Inspection 2-1648-85 2E12-F042C Inspection 2-1649-85 2E12-F064C Inspection.

2-1652-85 2E12-C002C Inspection 2-1653-85 2812-C002B Inspection 2-1672-85 2E51-F091 Inspect MCC Wiring 2-1673-85 2E12-F023 Inspect MCC Wiring

, 2-1675-85 2E51-F086 Inspection 2-1679-85 2B RHR Pp Inspection

2-1680-85 2C RHR Pp Inspection 2-1686-85 "B" DG Clg Wtr. Pp Test Circuit Breaker 1

2-1687-85 HPCS Change Oil, Meggar l 2-1689-85 2E51-F019 Repack

2-1690-85 2E51-F069 Repack l

2-1691-85 2E51-F045 Repack 2-1695-85 2E51-F045 Troubleshoot and Set Limits 2-1696-85 2E51-F069 Lube and Cycle.

2-1697-85 LPCS Meggar i

2-1700-85 2A RHR Meggar l 2-1711-85 2A DG Repair Air Line 2-1717-85 2A DG Repair 2DG061B 2-1719-85 2B DG C1g Water Pp. Repair Motor controller 2-1723-85 RCIC Water Leg Pp Inspection i

2-1725-85 RCIC Prevent Auto Initiation l 2-1729-85 2E51-F066 Prevent Scram

! 2-1730-85 2CB05AA Repair Weld t

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DOCUMENT ID 0036c/0005r

,C 3. OfE-sita Dose calculttion Manual.

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

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4. Radioactive Waste Treatiment Systems.

l There were no changes to the radioactive waste treatment system during this reporting period. l l

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DOCUMENT ID 0036r/0005r l

  • / x: Commonwealth Edison m LaSalle County Nuclear Station

..[ G) Rural Route #1, Box 220

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Marseilles, Illinois 61341 Telephone 815/357-6761 l

l January 9, 1986 Director, Office of Management Information and Program Control United States Muclear 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 December 1, 1985 through December 31, 1985.

Very truly yours, G J. Diederich tation Manager LaSalle County Station l GJD/RJR/cth i

! Enclosure xc: J G. Keppler, NRC, Region III MRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CBCo IMPO Records Center l

L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident l J. M. Nowicki, Asst. Comptroller H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle 1 /

3 Document 0043r/0005r

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