ML20072S578

Monthly Operating Repts for Mar 1991 for LaSalle County Nuclear Power Station

ML20072S578
Person / Time
Site:	LaSalle
Issue date:	03/31/1991
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9104160356
Download: ML20072S578 (22)

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'N) LaSatie County Nuclear Station Rural Route #1, Box 220

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J Marseilles, Illinois 61341 j Telephone B15/357 6761 April 10, 1991 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-137 Hashington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for March, 1991.

Very truly yours, hb kN '

G. J. Diederich Station Manager LaSalle County Station GJD/MJC/dj f Enclosure l

xc: A. B. Davis, NRC, Region III T.' M. Tongue, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety J .B. Hickman, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE Resident l

T. J. Kovach, Manager of Nuclear Licensing H. F. Naughton, Nuclear Full Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor M. M. Servoss, QA/NS Off Site Review Station File l $< 9.lO4160356 910331 l . L '. PDR ADOCK 05000373 R PDR ZCADTS/5 ZE Q 4-

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LASALLE NUCLEAR POWER STATION UNIT 1 HONTHLY PERFORMANCE REPORT HARCH 1991 COMHONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE N0, NPF-ll ZCADTS/S

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n TABLE OF CONTENTS (UNIT 1)

I.. INTRODUCTION II. . REPORT

A.

SUMMARY

OF OPERATING EXPERIENCE B.: AMENOMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE.T0 SAFETY-RELATED EQUIPMENT-

9. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. ;0perating Data Report. i

2. -Average-Oaily Unit Power Level 3.- Unit Shutdowns and Power Reductions F. ' UNIQUE REPORTING REQUIREMENTS 1 .- Main Steam Relief Valve Operations

2. ECCS System Outages-

-3. Off-Site Oose Calculation Manual Changes

4. Major Changes to Radioactive Haste Treatment System

-5. Indications of Falled Fuel Elements.

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I, INTRODUCTION (Unit 1)

TheLaSalleCountylNuclearPowerStationisatwo-unitfacilityownedby Commonyealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Hater Reactor with a-designed net electrical output of 1078 Hegawatts. Haste 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-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 Michael J. Cialkowski, telephone number (815)357-6761,- extension 2427.

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', II. HONTHLY REPORT

! - ' A. SUMMAP.Y OF OPERATING EXPERIENCE (Unit 1)

DAX lin LYiat 1 0000 Reactor subcritical, generator off line, LIR04 in progress.

31 2400 Reactor subtritical, generator off line, L1R04 in progress.

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AMENDMENTS:TO THE FACILITY' LICENSE 0R-TECHNICAL SP L FICATION Technica1' Specification Amendment to Allow Continued Plant Operation

for an Extended Period of Time (4 to 12 Hour Period) with The Main Steam Tunnel High Ambient Temperature and High Ventilation System.

Differential . Temperature Trips Bypassed.

' C.

A JOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D. ~ LICENSEE EVENT REPORTS (Unit 1)

LER Number DjLtg Description 91-002-00* 03/19/91 Inadvertent deenergizing of Bus 143 during surveillance testing.

003J00 03/26/91 Inadvertent Group-IV_ Isolation during Jumper removal due to loss of continuity.

'LER #91-002-00, LLRT 0.6 LA leakage criteria was exceeded, as reported in the F %ruary 1991 report was, upon further investigation. deterr,cir9d-to-be a non-reportable item. LER number 91-002-00.was rete. sued and a summary is included in this report.

E. 1

-DATA-' TABULATIONS (Unit 1) i

1. Operating Dats Report (See-Table 2)-

.2. : Average Daily Unit Power Level;(See Table 3) 3.- Unit-Shutdowns and Significant Power Reductions-(See Table 4)

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C TABLE 1 (Unit 1)

MAJOR CORRECTIVE MAINTENANCE TO -

SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS HORK REQUEST CORRECTIVE ACTION-COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION NUM3ER Pump degraded. Replaced pump.

LO3661 OD00lP Diesel Fuel Pump bearing.

Oil Transfer Pump OVC019YB HVAC Control Damper actuator. Damper inoperable. Rebuilt actuator.

LO4412 Room Damper Degraded operation. Replaced relay.

LO5597 lHR179 Drywell Relay.

Cooling Isolation Valve Temperature switch. None. Replaced switcn.

LO5752 ODG0lK Diesel Lube Oil Temperature Breaker spring charging None. Replaced charging motor.

LO5755 1E22-C001 HPCS Pump motor.

None. Replaced switch.

LO5887 1DG0lK Diesel Lube Temperature switch.

Oil Temperature Switch failed to close Replaced switch.

LO5889 IDG0lK Diesel High Temperature switch.

Water Temperature during calibration.

Temperature switch. Degraded heater cc? trol. Replaced switch.

LO5908 1DG01K Diesel Immersion Heater Temperature switch. Switch fa led to alarm during Replaced switch.

LO5999 1E22-5001 HPCS Diesel f

Engine Temperature calibration.

l Time delay reJay. Contacts failed to close in the Replaced relay.

LO6213 1E27 5001 HPCS Diesel required time limit.

Valve inoperable. Rebuilt gear box.

LO6362 lE12-F090A Residual Broken handwheel.

Heat Removal Valve (No SOR failures this month.)

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. TABLE 2-E.1 OPERATING DATA REPORT DOCKET NO. 050-373 U UNIT LAStiLE OtE DATE April 10, 1991 CONFtETED BY M.J. CIALK0WSKI TELEftelE (815)-357-6761

0FERATING STATUS ,

1. RifilTING fiRIOD: March 1991 GROSS HOURS IN REPORTING FERIOD' 744 2.' CURRENTLY AlJTFORIZED POWER LEVEL (HWt): 3,323 NAX t(PEND CAPACITY (K'e-Net): 1,034 ffSIGN ELECTRICAL RATING (MWe-Net): 1,078 .

b3.' POWER LEVEL TO WHICH RESTRICTED (If ANY) (HWe-Net): (NONE) 4.-- REASONS FOR PESTRICTlfW (IF ANY):

REPORTING FERIOD DATA

__ THIS MONTH YEAR-TO-DATE - CUHulATIVE

-51 REACTOR CRITICAL TIME (HOURS)- 0.0 1,108.8 41,718.2

- 6.__ REACTOR RESERVE SIUTDOWN TlHE 010URS) 0.0 .

0.0 1,641.2

7. GENERATOR OH-LINE TIME (HCORS) 0.0 - 1,107.9 40,854.7

8. WII RESERVE SHUTIOH TIME UCLRS) 0.0 0.0 1.0

9. THERh/L ENERGY GENERATED (HWHt) 0 3,565,872 117,769,473

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross)- 0 1,230.541 39,233,829

11. ELECTRICAL ENERGY GENERATED (HWHe44et) -8,196 1,i?9,790 37,549,872

12. REACTOR SF';VICE FACTOR (%) 0.0 - 51.3 65.6

13. REACTOR AVAILABILITY FACTOR (%) 0.0 51.3 68.2

14. UNIT SERVICE FACTOR (%) 0.0 51.3 64.3-

, 15i UNIT AVAILIBILITY FACTOR (%) 0.0 51.3 64.3

-16lUNITCAPACITYFACTOR(USINGMDC)-(%) -t.1 52.7 57.0

' 17. UN!'T CAPACITY FACTOR (USIf6 DESIGN hWe) (%) -1.0 _50.7 34.8 10c UNIT CORCED OUTAGE FACTOR (%) J.0 0.0 8.3

19. SHUTDOWHS SCHEDULED OVER THE NEXT 6 MONTHC (TYPE, DATE, AND DURATION OF EACH):

20. IF SHUIDOWN AT END OF REPORT FERIOD, ESTIMATED DATE OF STARTUP:

04/29/91

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DOCKET NO. 050-373 131LE 3 UNIT LAMLE ONE E.2 AVERAGE DAILY LHIT fMR LEVEL (MWe4pt) DATE Aptil 10, 1991 ClWtETED BY M.J. CIALK0R3KI TElif' HONE (B15)-357-6761 REMJR1 PiRIOD: March 1991 DA) FMR DM FMR 1 -12 17 -11 2 -11 18 -11 3 -11 19 -11 4 -11 20 -11 5 -11 21 -11 6 -11 22 -11 7 -11 23 -11 8 -11 24 -11 9 -11 25 -11 10 -11 26 -11 11 -11 27 -11 12 -11 20 -11 13 -11 29 -11 14 -il 30 -11 15 ' 11 31 -11 16 -11

TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 207.: -

(Unit 1) -

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOHN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATIOF THE REACTOR OR (LER/DVR # if

?'UMSER (YYMMDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 0? 910216 S 744.0 C Refueling outage LIR04.

SUMMARY

OC CPERATION:

The unit entered a scheduled refueling outage on 02/16/91.

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F. UNIQUE REPORTING REQUIREMENTS (Unit 1)

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DAIX ACTUATED ACTUATION _ CONDITION QF EVENT (None)

2. ECCS System Outages (See Table 5)

3. Changes to the Off-Site Dose Calculation Manual (None)

4. Major changes to Radioactive Haste Treatment Systems.

(None)

5. Indications of Failed fuel Elements.

(None) l l

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. (Unit 1)

Table 5 F.2 ECCS System Outages Note: Th's year and t nit data has been removed from the outage number.

DUTAGE NQt [0VIPMENT PURPOSE 611 1[G01K Maintenance.

615 614 1DG01K Ground cluster Installation.

616 10G01K Inspection 617 10G01K Installation of auto close inhibit modi fication.

721 10G0lK Replaced air compressor.

744 849 10G01K Logic test.

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LASALLE NUCLEAR POWER STATION UNIT 2 HONTHLY PERFORMANCE REPORT HARCH 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET N0. 050-374 ,

LICENSE NO. NPF-18 ZCADTS/7

TABLE OF CONTENTS (Unit 2)

, .I . INTRODijCTION , , ,.

II. REPORT A. SUHHARY OF OPERATING EXPERIENCE B. AMENDsEafS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELt'ED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

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

1. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Haste Treatment System

5. Indications of failed Fuel Elements I

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I. INTRODUCTION (Unit 2)

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

, unit is a Boiling Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste heat is rejected t0 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 operatic .ias commenced on June 19, 1984.

Thit report was compiled by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.

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, ! II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day lime Event 1 0000 Reactor critical, generator on line at 750 MHE for rod set and sc :m timing of rod 26-19.

1400 Incron ed power to 1124 MHE. .. ,

6 0300 Reduced power to 1067 MHE for weekly surveillances.

1100 Increased power to 1135 MHE.

13 0030 Reduced power to 1060 MHE for weekly surveillances.

0600 Increased power to 1135 ME.

20 0100 Reduced power to 975 MHE for monthly surveillances.

1400 Increased power to 1132 MWE.

24 2330 Reduced power to 1075 MWE for condensate booster pump transfer.

25 0700 Incteased power to 1134 MHC.

27 0030 Reduced power to 1075 WE for weekly surveillances.

0600 Increased power to 1134 MHE.

31 2400 Reacto critical, generator on line at 1134 MHE.

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, B. AMENDHENTS TO THE FACfLfTY LICENSE OR TECHNICAL $PECIFICATION Technical Specification Amendment to Allow Continued Plant Operation for an Extended Period of Time (4 to 12 Hour Period) with The Main Steam Tunnet High Ambient Temperature and High Ventilation System Differential Hmperature Trips Bypassed.

C. MAJOR CORRECTIVE MAINTENANCE TI).SVETY RELATED EQUIPMENT (including SOR different,.L1 pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 2)

LER Number QLt1 DescriotioD 91-002-00 03/18/91 Division 1 Group 4 Reactor Building Ventilation Isolation occurred during Instrument Surveillance, 91-003-00 03/28/91 Reactor Building Ventilation Isolation due to misplaced jumper.

E. DATA TABULATIONS (Unit 2)

1. Operating Data Report.

(See Table 2)

2. Average Daily Unit Power Level.

(See Table 3)

3. Unit Shutdowns and Significant Power Reductions.

(See Table 4) l l

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C TABLE Y (Unit 2)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-FELATED EQUIPMENT i

HORK REQUdST RESULTS AND EFFECTS .

NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LO5793 Hydraulic Control Valve actuator diaphragm. Degraded control rad operation. Replaced valve diaphragm. i Unit 26-19 ,

LO6187 20 Main Steam Line Radiation monitor. Radiation monitor inoperable. Replaced radiation monit'sr.

Radiation Monitoring l

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(No SOR failures this month) I t

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1 A!LE 2 l

l E.1 0F ERAllNG I41A FFORT MK1ET NO. 0$0-374 Di41i LALALLE im I ATE 4 t il 10,1994 CCrPL(TED EY M.J. CIAlf EKI TELU10E (815)-357-6761 (FIF Ai!4 f. Tails , ,, , ,

i. RD%Il% PERIOD, March 1991 GROSS HOUF$ IN RLF% TIE ItRIOD- 744

2. CURRENTLY rsJ11MI?ED FWER LEVEL (MWt): 3,323 7%\ DEPEND CtPACITY (Ne-Hei). 1.036 IU121 ELECTRICli RATIE 01.Je-Neth 1,078

3. WWER LEVEL 10 vi10' RESTRICTED (IF t#f) (hWe-Net): 00E) 4 REASOfC FOR RESTRICTION (II ANY):

RU W TIE Fik!OD DATA THIS MONTH YE W TO-DATE tuttJLAllVE

5. RE/CTOR CRITICAL TIME (HOURS) 744.0 2,160.0 38,650.2

6. REACTOR RESERVE SfJTDOW 11ME (HOURS) 0.0 0.0 1,716.9

7. LENERATOR OMINE 11ME 40URS) 744.0 2,160.0 38,007.2

6. UtJIT RESERVE 9fJTKWN TIME 00.RS) 0.0 0.0 0.0

9. IRRML ENLRGY GLtERATED (Mit) 2,452,744 7,117,272 112,556,447 10 rLECTRICtl ENERGY GENrJtATED (M6e-Grow D33,749 2,418,413 37,302,245

11. ELECTRICAL ENERGY GENDlAIED (Mie-Net) 811.436 2,346,654 35,765,744

12. RE/C10R SERVICE FILTOR (%) 100.0 100.0 68.4

13. FEActuR AVAIL /41LITY FACifE (%) 100.0 100.0 71.4

14. UNIT SERVICE ftCTOR (%) 100.0 if$,0 67.2

15. UNIi AVAILIMLITY FACTOR (%) 100.0 10') .0 67.2

16. UNIT CAPACITY FACTOR (U3ING MDC) (%) 105.3 104.9 61.1

17. LNIT CriACliY F ACIGR (USING IESIGN hW) (%) 101.2 100.8 58.7

10. 'AIIT FORCED OUTALC FACTOR (%) 0.0 0.0 14.2 19, 9fJTDOW.; KdDULED DVER THE NEXT 6 MONTHS (TYft, DATE, AND DURATION OF EACH):

(TOE)

20. IF 9fJT[GN A1 END OF REPORT FERIOD, E511MTED DATE OF STARitP:

DOCKET NO. 050-374 TAl4.E 3 LNIT LAS/tLE TWO

, E.2 MERMC DAILY LNIT FMR LEVEL (MWe-Net) DATE 4til 10,1991 004tETED M N.J. CIALKDEKI TELDt[NE (B151-357-6761 n

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RfMR1 Fikl0D

March 1991 DAY FMR DM FMR ,,

t 970 17 1,099 2 1,007 10 _

1,070 3 1,094 19 1,077 4 1,095 20 1,049 5 1,6 21 1,098 6 1.087 22 1,099  !

? 1,096 23 1,100 8 -1,096 24 1,099  ;

9 1,097 25 1,091 3 i

I 10 1,09? 26 1,101 11- i ~,090 . 71 1,092 i i2 i,099 28 i,097 13 1,089 29 1,099 14 1,096 30 1,099 15 1,097 31 1,090 16 1,100 a~e--- <_- . emv, -am.. .- am sv ,,z-

TABLE 4 E3 UNIT SHUTDOWNS AND POWER REDUCTIONS >207.

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOHN ACTIONS /COMMENIS SE00ENTIAL DATE F: FORCED DURATION TtlE REACTOR OR (LER/DVR # if NUMBER (YYMMDD) S: SCIEDULED (HOURS) REASON REDUCING POWER applicable)

(None) 4

SUMMARY

OF OPERATION:

The unit remained on line at high power throughout the month. Several cainor power reductions were required for routine surveillances.

ZCADTS/7

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F. UNIQUE REPORTING REQUIREMENTS (Unit 2)

1. Safety / Relief Valve Operations VALVES NO & TiPE PLANT DESCRIPTION QAll ACTUATED ACTUATION; CONDITION OF EVENT ,

(None)

2. ECCS System Outages (None)

3. Changes to the Off-Site Dose Calculation Manual.

(None)

4. Major changes to Radioactive Haste Treatment Systems.

(None)

5. Indications of failed fuel Elemer'.s (None) ll l -

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