ML20070J699

Monthly Operating Repts for Feb 1991 for LaSalle County Nuclear Power Station Unit 1 & 2

ML20070J699
Person / Time
Site:	LaSalle
Issue date:	02/28/1991
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9103180088
Download: ML20070J699 (24)

Text

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i i Ctmmtnwealth Edison -

..c%c () RufalRoute 81.Bo::220LaSalle County Nuclear Station P

v ~ - Marseillesilllinois 61341

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Telephone 815/357 6761--

March 10, 1991-I Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station P1-137 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 February,--1991. -

Very truly yours,

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p.J.Diederich fo/StationManager LaSalle County Station GJD/HJC/djf Enclosure xc: A. B. Davis, KRC.-Region III T. M. Tongue, NRC Resident Inspector LaSalle_

J. L. Roman. IL Dept. of Nuclear. Safety J.B.Hickman,NRRProjectManager D. P. Galle, CECO D. L. Farrar CECO

-INPO Records Center D. R. Eggett, NED- .. .

J. E. Kuskey, GE Resident .

T. J. Kovach, Manager of. Nuclear Licensing H. F. Naughton, Nuclear. Fuel- Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical-Staff Supervisor ig M. M. Servoss, QA/NS Off Site Review '

Station File .

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s LASALLE NUCLEAR POWER STATION

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UNIT 1

HONTHLY PERFORMANCE REPORT FEBRUARY 1991 4

COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 4

LICENSE NO, NPF-11 I

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'ZCADTS/5

TABLE OF. CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. AMEN" VENTS TO FACILITY LICENSE OR-TECHNICAL SPECIFICATIONS C. MAJ0n CORRECTIVE MAINTENANCE TO SAFETY-RELATED 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. Main Steam-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.Falled fuel Elements I

I.

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I. INTRODUCTION (Unit-1)

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 Boilir.] Hater Reactor. with a designed not 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-11 on April 17, 1982.

Initial- criticality was achieved on June 21,1982l 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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IL HONTHLY REPORT A.

SUMMARY

OFOPERATINGEXPERIENCE(Unit [1)

QLy M Event 1 0000 ' Reactor critical, generator _on-line at 1135 MHE. ,

i 2 2100 -Reduced power to 1070 MHE for system load.-

3 1000 Increased power to 1135 MHE.

5 0100 Reduced power to 950 MHE.for-rod set.

1500 Increased power to 1135 MHE.

10 2300 Reduced ' power to 880 MHE to perform.. weekly / monthly surveillances: and _for systen: loadi

, 11 1400 Increased power to 1135 MHE.

l 16 0355 Generator'off line, refueling outage (L1R04) began, 0445 Reactor-subcritical..

28 2400 Reactor .subcritical, generator off line, LlR04 in -

progress, i

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l B. AMENDMENTS-TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION l (None)

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including-

-SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1) i: LER Number - Q.ittg - Descriotion ..

91-002-00 02/19/91 LLRT 0.6LA leakage criteria was exceeded.

l E. DATA TABULATIONS (Unit 1) i 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) i ZCADTS/5

l C TABLE 1 (Unit 1) -

i MAJOR CORRECTIVE MAINTENANCE TO - i' SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS ,

NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION  ;

LO2438 IPL77J Post LOCA Hydrogen bottle regulator. None. Replaced Hydrogen bottle  ;

Panel regulator.  !

LO4837 OXY-VC165A Ammonia Horn cassette carrier None. Rebuilt unit.

Detector guide posts.

LO5080 Hydraulic Control Valve leakage. Degraded control rod operation. Replaced valve.

Unit 14-39 -

LO5331 Control Room HVAC Temperature controller. None. Replaced temperature controller.

'LO5419 Vent Stack Haste Pump diaphragm. Pump inoperable. Replaced pump. ,

Monitoring Low Range High Flow Pump

.LO5445. Reactor Retirc Flow Flow summation unit. Unit failed to give an upscale Replaced summation card. I LoopA' alarm during calibration. j LO5599 'RPS' Motor Generator Electrical protection None. Replaced circuit board.  !

Set assembly relay.

, LO5686 Intermediate Range Inop inhibit switch. None. Replaced switch.  !

Monitor 'C' i (No SOR failures this month.)

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'ZCADTS/5+ .

1 AM E 2 -

E.1 OPERATIK DATA REPORT LOCKETN0.-056-373 1 UNIT LASALLE ONE DATE Merch it, 1991 COV LETED PY M.J. CIAL W iK!

TELEFh0NCt815)-357-6761 c OffRAf!W,SikiUS

t. REPORT 1% PERIOD Februry 1991 GROSS HOURS IN REf0 Rile PERIOD: 672

2. CtniNTLY AUTHMIZil' POWEE LDEL (itWt): 3,323' MAX DEFEND C@ACITY (HWe-het)i 1,034 -

DESIGN ELEE1Rittd. Rail % (MW NetP 1,070

3. F0 DER LEVEL TO WHICH RESTRICTED (If ANY)-(HWe het): (Nane) 4 REASONS FOR RESTRICT!04 (If ANY):

REPORTIE PERIOD DATA THIS MONTH YEAF-TO-DATE CUMULATIVE

5. REAC10R CR111 CAL TIME (HOURS) 364.8 - t,108.8 41,718.2-

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6. FEACICR RESERVE SHUTDOWN f!ME HIOURS) 0.0 0.0 1,641.2

7. EENERAIDA Od-LINE TIMF f HOURS) 343.9 1,107.9 40,854.7 i

S. UN!i RESlPVE SHUIDOWN ilhE (HOURS) '0.0' O.0 1.0

9 TriERME ENERD GENERATED (MWHt) 1,i61,384 3,56$,872 . 117,769,473

10. ELECTRICAL ENEET G UfRATED (MWHe Gross) 401,616 1,230,54t 39,233,829

' ti. ELECTRICAL ENERGY GENERATED (PWHe-Net) 385,351- 1,187,984 37,558,068

12. REACT 0A EERVICE FACTER (%) 54.3 78.3 66.4

13. FEACTOR AVAILAMLITY FACT 08 (I) 54.3 70.3 69.9 l

14.-UNIT SERVICE FACT 0E m 54.2 78.2 65.1

15. lmli AVAILIMLITT FACIOR (%i ' 54.2 ?8.2 65.1 16, UNIT CAPACITY FACTOR (USING MZ ) (I) 55.4 Bt.0 - 57.7

17. UNIT CAFACITY FACTOR (L"ilNG DF. SIGN PWe) (%) 53.2 '77 8. 55.5

10. Uh!T FORCED OUTAGE FACTOR (%) 0.0 0.0 0.3

-19. SHUTDOWN 3 SCHEDULED DVER TFE NEXT-6 MONTHS-(TiFE, DATE, AND DURATION OF EACH):

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20. IF-SHUTDOWN AT E N OF P EDR1 PERIOD, ESTIMATED OF STARTUP:

04/28/?!

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~ DOCKET NO. 950-311 TAPLE 3 UNii LASALLE ONE -

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E.2 AVERA:t DA!LY LW11 POWER LEVEL (Ne-het) LATE Nrch 16,1991.

COMPLETED BY h.J. CIALX0WSKI TELLPHONE (01D -357-6741 e

FEP081 FfRIOD: February 1971 i NY 00kE9 DM POWER 3-i i,112 17 -12 2 1,104 18 -12 3 t,092 19 -12 4 1,107 26 -12 5 1,067 21 -11 6 1,105 22- -12 7 1,t05 23 -12 6 1,167 24 -11 9 1,197 25- -12 i

13 1,032 26 -12 '

ii 1,044 27 -12 i 12 1,107 28 -12 _

13 1,104 29 4

t L I4 1,100 30 f

u e4e - 3e 16 14 --

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_ . . .. - .. _,--_ - ,,,,, -,_.. . _. ,, _. . . . . - . _ __ _ ,. . , _ _ . , _ . _ . _ _ ____ ____._.m.__...

W . . . . - - - . . . . . . . . . _ . . .

TABLE 4 E.3 UNIT SHUTD0HNS AND POWER REDUCTIONS > 201 .

-(Unit 1)

METHOD OF CORRECTIVE YEARLY . .

TYPE SHUTTING DONN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCEC DURATION THE. REACTOR OR (LER/DVR # if NUMBER (YYMMDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable).

01 910216 S 308.1 C 1 Refueling outage L1R04.

SUMMARY

OF OPERATION:

LThe~ Unit remained ~on line at high power from 02/01/91 to 02/15/911- Several minor. power reductions were required due to low grid demand.and routine survelliances. The unit entered'a' scheduled refueling outage on'02/16/91.

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,.. ._.:.-.m.m - _. _ _ _ _ _ - - -

4 F. ' UNIQUE REPORTING REQUIREMENTS (Unit-1) 4

1. Safety / Relief valve operations VALVCS NO & TYPE PLANT DESCRIPTION =

QAII ACTUATED ACTUATION CONDITION OF EVENT (None)

. ECCS System Outages (See Table 5) >

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

4. Hajor changes to Radioactive Haste Treatment Systems.

(None)

5. Indications of Failed fuel Elements.

(Nont) i ZCADTS/5

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(Unit,1)- '

Table 5 F.2 ECCS System Outages >

Note: The year and unit data has been removed from the outage number.

DUTAGE NO. EOUIPMENT- PURPOSE

-(U-0) 53 00G0lK Replace air start solenoid.

55 00G01K- Lubrication.

-56 ODG08CA Breaker inspection.

58 59 ODG08CA Inspection.- -

60 68 -0DG08CB Repair relief valve.

79 ODG0lK Inspection / maintenance.

80 00G0lK Replace watt' transducer.

81 ODG0lK Calibrations.

83 84 - 0DG0lK = Repair fuel oil solenoid valve.-

85 ODG0lK _ Repair leaking manway cover.

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. - # - . ,,,.,m y- , . - - - , -. - . _ , . . . .

(Unit 1)

Table 5 F.2 ECCS System Outages Note: The year and unit' data has been removed from the outage number.

OUTAGE NO. EOUIPMENT PURPOSE

. (U-1) 131 lE12-C300A Coupling lubrication.

1E12-C300B 132 lE12-C002A Change motor oil.

134 1E12-C002A Relay calibration.

152 1E51-C002 Change motor oil.

168 IE12-F024A- - Performance of LOP-RH-07.

IE12-F027A 279 1E22-C001 Relay inspection.

335 IE22-S001. Administrative control.

345 1E22-F015 EQ inspection.

347 IE22-F012 Valve spring pack replacement.--

367 1E12-C002A Relay inspection.

368 lE214F051 Performance of LES-LP-101.

3 .lE21-F034 369 1E21-C001 Relay inspection.-

370 lE21-F001 EQ inspection.-

371 1E21-F005 EQ: inspection, j -372 lE21-F011- EQ-inspection.

"f21-F012- EQ inspection.

373 i i 374 lE21.F005- Replace valve packing.

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'i LASALLE NUCLEAR POWER STATION UNIT 2 HONTHLY PERf0RMANCE REPORT TEDRUARY 1991 COMMONHEALTH EDISON CCHPANY NRC DOCKET NO. 950-374 L! CENSE NO. NPF-18 l

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! TABLE OF CONTENTS (Unit 2)  !

T I. INTRODUCTION i .

i

, II. REPORT i A.

SUMMARY

OF OPERATING EXPERIENCE ,

i- 8. -AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJCR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT q D. LICENSEE EVENT REPORTS E. DATA TABULATIONS  !

1. Operating Data Report

2. Average Daily Unit Power Level.

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

l. Safety / Relief Valve Operations

._ 2. ECCS System Outages l 3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Haste Treatment System j 5. Indications of Failed fuel Elements.

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ZCADTS/7-

l . I 4 I. INTRODUCTION (Unit 2) I

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I i The laSalle County Nuclear Power Station is a two-unit facility owned by i Commonwealth Edison Company and located near Marsellies, Illinois. .

Each unit 1s a Boiling Water. Reactor with a designed net electrical output of ,

i 1078 Megawatts. 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 Two was issued operatibg license number NPF-18 on December 16, ,

j 1983. Initial criticality was achieved on March 10, 1984 and commercial l .

power operation was commenced on June 19, 1984. .

This r6 port was compiled by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.

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i j-  !!. MONTHLY REPORT s

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A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2) 1 i DA.Y limt Event 1

0000 Reactor critical, generator on line at l'c2 MWE.

! 1

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6 0100 Reduced power to 1070 MWE for CRD exercising.

i 1 1300 Increased power to 1132 MWE.

13 0100 Reduced power to 1000 MWE for motor- driven reactor

• j- feed pump seal maintenance.

'000 Increased power to 1134 MWE.

20 0130 Reduced power to 925 MHE for conthly surveillances, i

1700 Increased power to 1134 MHE.

26 2355 Reduced power to 1070 MWE for CRD exercising.

27 1100 Increased power to 1134 MWE.

28 0530 Reduced power to 1034 MHE to intert rod 26-19.

1100 Reduced power to 950 MHE due to feedwater transient.

2400 Reactor critical, generator on line at 875 MHE due to forced rod set, pulling and scram timing of rod 26-19.

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ZCADTS/7

B. AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIf! CATION (None)

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED E0ulrHENT (including ,

SOR differential pressure switch failure reports).

(See Table 1)

I D. LICENSEE EVENT REPORTS (Unit 2)

LER Number QAlg Des cr_iotion (None)

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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2CADTS/7

C TABLE 1 (Unit 2) i MAJOR CORRECTIVE MAINTENANCE TO -

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SAFETY-RELATED EQUIPMENT

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MORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION

- i LO2189 2PL77J Post LOCA Hydrogen bottle regulator. None. Replaced hydrogen bottle Panel regulator.

[

LO5120 Average Power Range Quad trip card. Spurious fixed neutron Replaced quad trip card.

l Monitor 'B' hal f-scrans -  ;

LO5188 RCIC Turbine Inlet Damaged cable. Level switch failed to alarm. Replaced damaged cable.  ;

Steam Line Level-

, LO5309 2A Diesel Generator Thermal overload relay. None. Replaced thermal overload i Space Heater relay.

LO5369 Hydraulic control Pressure switch.- Degraded control rod operation. Replaced pressure switch.

Unit 26-11 i-i i

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9 m T ~

T

1 Al'.E 2 l E.1 0FEFA11NG !>ATA FEf 0F1 D3CtET NO. 0$0-314 UNIT LA';AILE TJO

! ATE Match it, 1991 00YtETEb tY e..l. CIALV0VSil itLif h0NE (615)-3$7-6761 Or D ATI M Sh TUS

t. REF1 0!% !!PI0t Februatr 1991 0F055 H')UF$ .'N tEPORT]NT. $U10}. 672

2. COMEN1Li kJTHOR17ED P0 9 sEYEL tnt)- 3.323 MAX DEPEC CAPACITT (Ne-Net); i.036 DESIGN ELECTRICAL RA!!% (Ne-Net): i,078

3. POWER LDft 10 WICH RESTRICIEP (If ANY) (Nie-Net): (None) 4 FEA$$3 f tA PES 1RICIl0N (If ANY):

REPORTING f 8 1 % 1,ATA-

-THl$NONTH TE ATM04 ATE _- CUMULA!!vE

5. REACT 08 CRiflCAL 11ME (H00RS) (72.0 1,416.0 37,906.2

6. FEACICA PELERVE $HUit0WN TIME (HOURS) 0.0 0.0 1,716.9

?. (Et'EkAT0lt ON-i!NE TIME WJJM) 672.0 t,416.0 37,263.2

8. UNIT PESERVE MJiDOWN TIME (HOURS) 0.0 0.0 0.0

9. THU%L EhUGY LENERATED (NHt) 2,213,909 4,664,326 119,163,$03

19. ELECIFICAL IAERGY GEkERATED (NJHe4 toss) 752,092 t,594,664 36,468,496 H. ELEtiRICAL ENERCY LEND ATED (me-ht) 720,676 1,535,218 34,954,300

10. FEAC10E EERflCE FICTOR (1) 100.0 100.0 67.9

13. REAC1% AtAIL41LITY FRTOR (1) 100.0 100.0 71.0

14. UNIT SERilCE FACTOR (t) 100.0 100.0 66.8

'15. UNIT AVAltil;Illif FACTOR ( ) 100.0 i00.0 66.6

16. UNIT Ct/ACITT ftCTOR (051% @C) (%) 104.7 ~~104.7- 60.5

- 17. UN11 EA!EITY FACIDR (0S1% DESIGN Nt) (!) 100.6 109.6 $8.1

19. UNIT FORCEt OUTA;E FACTOR (%)

0.0 0.0 14.4

19. SWJTICW3 SCHENLEt DVER THE NEXT 6 MONTHS (f1PE, DATE, A6 NRATION OF EACH):

(EE) 1 If EHUIDOM A1 END OF FEftti FERIOD, ESil!tiTED PATE Of 51HTUP (N/A)

,- -..... - .-~._ - - ._ _ - .- -. - _- - - .. _ ..--. --.. __ _ .......- .- - ~.-..- -- . - -

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! D00kii WD. M H 74 1 TABL( 3 LMlf LASALLI 183 ,

+ (,2 4'LWE LAllt (NT ftWER LEVEL (Mks-Net) )ATEParttit,ifft C0HITU tYM.J.C1tu Mil  !

1ELEf ENE (5151-MM761 l

t REFMT (Et10D: February 1991 .

i HY F00 LAf itWER 1 1,H 4 17 I A91 +

2 1,992 la 1,074 3 ijf3 19 1,094 4 1,073 20 1,035 i

5 1,092 21 1,992 6 1,071 22 1,096 7 i.093 23 i,994 .

, r 1,093 ?A

^

B 1 A96

! 9 1 A94 25 1,697 10 t A94 26 i A94 ii i d?? 27 1,076 12 i.993 28 978 13 i A7t 29 14 1,091 30 l

1 l 15 1,090 31 i

16 1,M9 l

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TABLE 4 E.3 UNIT SHUTDOANS AND PONER REDUCTIONS >201 (UMIT 2) ,

METHOD OF CORRECTIVE YEARLY. TYPE SHUTTI E DONN ACTIONS /00PMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYp000) S: SCHEDULED (HOURS) REASON REDUCIE PONER applicable)

(None)

SUPMARY OF OPERATION:

The unit remained on line at high power throughout the month. Several minor power reductions were' required for routine surveillances, motor driven reactor feed pump maintenance and control rod 26-11 maintenance.

ZCADTS/7

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l F. UF!!QUE REPORTING REQUIREMENTS (Unit 2)

1. Safety / Relief Valve Oprations VALVES ND & TYPE PLANT DESCRIPTION DAll ACTUATED ACTUATI.QRS CONDITION OF EVENT (None)

2. ECCS System Outages (See Table 5)

3. Changes to the Of f-Site Dose Calculation Manual.

(None)

4. MajorchangestoRadioactiveHasteTreatmentSystems.

(None)

5. Indications of Failed fuel Elements.

(None) 2CADTS/7

(Unit 2)

Table 5 f.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.

DUTAGE NO. E0VIPMENT PURPOSE 55 2E51-F010 Repair valve flange.

61 2DG08CA Valve inspection.

ZCADTS/7 i

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