ML20085D191

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

ML20085D191
Person / Time
Site:	LaSalle
Issue date:	09/30/1991
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9110150329
Download: ML20085D191 (24)

Text

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C:mm:n=Cith Edison LhSatie Coun'y Nuclear Station

, Rural Route si, Box ??O Mart.edles, llMots 01341 leirphone 815/357 > 6761 October 10, 1991 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hall Station PI-137 '

Hashington, D.C. 20d55 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for September, 1991, 2

Very truly yours, O

h H{W' r G. J. Diederich y/StationHanager LaSalle County Station GJD/HJC/djf Enclosure xt: A. B. Davis, NRC, Region III T. H. 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 Reconds Center D. R. Eggett, NED J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing H. F. Haughton, Nuclear fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor H. H. Servoss, QA/NS Off Site Review

,,,. , Station File

'hikc1b3$29 910930 PDR ADOCK 05000373 R PDR /y{

I ICADTS/S t)

LASALLE NUCLEAR P0HER STATION UNIT 1 HONTHLY PERFORMANCE REPORT SEPTEMBER 1991 COMMONHfALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPf-11 l

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TABLE Of 00NTENTS (UNIT 1)

1. INTRODUCTION II. REPORT A.

SUMMARY

Of OPERATING EXPERIENCE B. AMENDHENTS 10 FACILITY LICENSE OR TECilNICAL SPECIFICATIONS C. HAJOR CORRECTIVE HAINTENANCE 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 Reller 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 l

l l ZCADTS/S

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1. INTh000CTION (Urit 1)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Negawatts. Haste heat is rejected to a man-made cooling pond using the III'nois River for make-up and b1c,wdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was-Commonwealth Edison Company.

Unit One was issued operating license number NPT-11 on April 17, 1982.

Initial criticality was achieved on June 21. 1982 ar,d commercial power operation was commenced on January 1, 1984.

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

-ZCADTS/S

,. e II. MONTHLY REPORT A. SlM4ARY Of OPERATING EXPERIENCE (Unit 1) i Day Time Event 1 0000 Reactor critical, g?nerator on-line at 1110 Mwe  !

0500 Reduced power level to 850 Mwe due to systeni load. l 1300 Increased power level to 1110 Mwe.

2400 Reduced power level to 850 Pee due to system load. I I

2 1500 Increased power level to 1110 Mwe.

2330 Reduced power level to 1040 Mwe due to system load. [

performed weekly survelliances.

3 0730 Increased power level to 1110 Mwe. .

4 -0400 Reduced power level to 930 Mwe due to system load, t 1000 Increased power level to 1110 Mwe. -

6 0100 Reduced power level to 850 Mwe due to system load. >

0730 Increased power level to 1100 Mwe.  ;

10 2330 Reduced power level to 1090 Mwe to perform weekly surveillances. -t 12 0200 Reduced power level to 750 Mwe to perform scram f time testing. ,

-t 1200 Increased power level to 1115 Mwe.

13 1700 Reduced power level to 900 Mwo due to main transformer '

cooling problems.

= 14 0200 Increased power level to 1115 Mwe.

17 0200 Reduced power level to 1045 Hwe to perform weekly surveillances.

0700 Increased power level to 1120 Mwe.

. 18 0400 . Reduced power level to 1070 Mwe to remove the.'A' Heater Drain pump from service and place the 'C' y Heater Drain pump in service.

1000 Increased power level to 1120 Mwe.

23 2330 . Reduced power level to 1000 Mwe due to system load, performed weekly and monthly surveillances. ,

1000 Increased power level to 1130 Mwe.

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2CADTS/5

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II. MONillLY REPORT A. SUMHARY OF OPERATING EXPERIENCE (Unit 1) (Continued) 042 1151 LYfal.

25 0200 Reduced power level to 1000 Hve dde to system load.

0700 increased power level to 1130 Hwe.

30 2400 Reactor critical, generator on-line at 1130 Hwe.

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B. AMENDHENTS TO Tile FACILITY LICENSE OR TEOINICAL SPEClflCATION (None)

C. MAJOR CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1)

LIR Number DAtc Description 91-009-00 09/20/91 Inadvertant Division 11 Reactor Water Cleanup Isolation Occurred During A Reactor Vessel low Hater Level 1/ Level 2 Isolation Logic functional Test.

E. DATA TABULATIONS (Unit 1)

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)

ZCADTS/5

C. TABLE I (Unit 1) .

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMINT .

HORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LO8973 "A" Reactor Recircu- Mode meter card. Flow unit initiated half scram Replaced mode meter lation Flow Converter during functional testing. card.

LO9331 Hydraulic Control Air solenoid valve 118. None. Eeplaced air :olenoid Unit 30-15 valve.

LO9814 Average Power Range Power meter. None. Replaced power meter.

Monitor 1E LO9970 Division II DC Firing board. Charger amps oscillating. Replaced firing board.

Bettery Charger (No SOR Failures this month.)

i ZCADTS/5+

TAllLE 2 a- .

E1 0M LAllWB M1A E rcil t0DIT NO, 0%-373 UN!! LALALLE DNE Mif October 10,1951 COMPLETED Ti M.J. CIAlt0W5kl ILLEFONE (B15)+357-6761

~

0FEIA11NG$1ATUS 1 FEtDR11NS HRIOD: futett1er1991 U DES O JR$ IN REF0il!6 IEll0lh 729

- 2. COMENTLY AUTH2Rl!EV POWER LEVEL (Nth 3,323 MX KitWD (MAC11f (Nt4tth 1,036 X51fN ELEEl&ICAL EA11NS WJe Weth 1,078

3. POPER IIVEL 10 WHICH ESTRICIEll (if ANY) (MWe-Neth N/A

4. REASONS FOR RE$ikiCil0N (If ANVh kit 0R11NB MRIOD MTA 1H15 MONiH YEAR-TO-MTE CUMULAIM 5..RfAC10RCR11ICALTinE(HOURS) 720,9 4,6H.9 45,2'6.3

6. REAt10R REEERVE SW110WN TIME (H01RS) 0.0 00 1,641,2 7 BCNERA10R ON-LINE T!hE (MURS) - 720,0 4,t07.7 44,25615

- 0,' ' UNIT ESERVE SHUTDOWN 11ME (OURS - 0.0 0,0 1.6

?

h 9 ' THELML DARGY DENERAf[D (NWHt) 2,353,644 14,001.124 129,410,725 to, ELECTRICAL ENER6Y LENilATED (f.WHe-Beast) 795.702 4,777,631 42,76E.919

- 11. ELECTRICAL. D6RBY GD! ELATED (MW4t-Wet) 768,643 4,572,319 4,962,401 12,'Et410RSER910ETAC10R(1) 100.0 70.3 66.6 -

-13,REAC109AVAILAi!LlifFAC10R(%) 100.0 70.3 49.0

-14, UNil FWICE FACTOR (f) 100.0 60.8 = 65.1 15iUNITAVA!LillLlifFAC10R(1) 100.0 68.8 65.1 16.. UNIT CAFACITY FAtiOR (UElNG MIC) 15'. 103.0 67,7 50.2 17l UNii (AFAEITT FACT 0R (U!!NG KSIGN MWt) (1) 99.0 65.0 55.9

= 18'. UNIT FORCED OUTAGE FACTOR (1) 0.0 1.4 7,8

19. 91UIMJN3 $CHEIOLED DVER THE NEIT 6 MONTHS (Tin, IATE, AG DJRai!ON OF EACHh 20, IF SHUT 10WN At EG Dr REPOR1 IER100, ES11 HATED MIE DT 51ALTUh N/A

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,-. I D00t[i NO. 0$9-373 l 1AkE 3 UNll LA%LLE Ont i E,2 MI AGt MILT DWII PMR Ltvit (Ne-Net) M fC Cttet.et 10,1991 l CMPLCl[L If B.,1, CIAtt0.'St!

l TELEPONE (015) 35N761 l I

KP0FI Pf RIOD: tertenet 1991 IAY F0WR IAY PMR I 1,009 17 1,000 i 2 962 18 1,081 i 3 1,062 19 1,072  !

4 1,659 20 1,092 I

$ 1,660 Il 1,0B0 6 .1.M1 22 1,991 - _

7 1,070 23 l__,094 _

t 8 1,074 24 1,M8.  !

9 1,078 25 1,077

.!$ 1,078 26 - 1,097 11 1,062 27 1,099 f 12 - 981 IB 1,106 13 1,055 - 29 1,995 14- 1,075 39 1,097

. '15 1,000 31 16 . 1,081  !

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e TABLE 4 .

E.3 UNIT SHUTDOMIS AND POMER REDUCTIONS > 201 (Unit 1)

METHOD OF CORRECTIVE

' YEARLY- TYPE SHUTTING DONN ACTIONS /COsmENTS SEQUENTIAL DATE 'F: FORCED DURATION THE REACTOR OR (LER/DVR # 1f NUMBER .(YYMP00)' S: SCHEDULED (HOURS) REASON REDUCING POMER applicable)

(None)

SUDMARY OF OPERATION:

i The Unit remained on-line at high power throughout the month. Several minor power reductions were required due to systen j loading, surveillances and maintenance activities. .

t 6

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i

f. UNIQUE REIORTING REQUIREMENIS (Unit 1)

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIP110N DAll ACTUA1ED 6ClljallM CONDITIM Q[_LYLNT (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)

ZCADTS/S

(Unit 1)

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

OllIAGLN_1 EOUIPMENT Ltl@SL (U-0) 1490 1E22-C003 Lubrication.

1505 IE12-C0028 Lubrication.

1506 1E12-C002C Install drain valve.

1507 IE12-C002B Install drain valve.

1508 1E12-C00."C Lubrication.

1511 1DG01K Clean oil strainer.

1520 IE21-C001 Install drain valves.

1524 1E22-C003 Determinate motor.

ZCADTS/5+

l

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT SEPTEMBER 1991 l

COMMONWEALTH EDIS0N COMPANY l l

NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l

l ZCADTS/7

TABLE OF CONTENTS (Unit 2)

1. INTRODUCTION II. REPORT A. SUHKARY OF OPERATING EXPERIENCE B. AMEHDHENTS TO FACILITY LICENSE OR TECilNICAL SPECIFICATIONS C. MAJOR 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. 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 s

ZCADTS/7

L 1

. l I. INTR 000CTION (Unii 2)

The LaSalle County Nuclear Power-Station is a two-unit facility owned by Commonwealth Edison Company and located near Warsellies, Illinois._ Each unit is a Boiling Water _Reartor with a designed net electrical output of 1070 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 operating license number NPF-18 on December 16, >

1983. Initial criticality was achieved on Nirch 10, 1984 and commercial power operation was commenced on June 19, 1984.

This report was complied by Michael J. Cialkowski, telephone riumber- l (815)357-6761 extension 2427. ,

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[ZCADTS/7

, ,- ._ _ .-. _ _ . _ _ _ . . m_ __ ,_ _._ . _ _ _ . _ .- __ _

II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Time Event 1 0000 Reactor critical, generator on-line at 1100 Hve.

2 0400 Reduced power level to 940 Hwe due to system load.

1400 Increased power level to 1105 Hve, L 4 0100 Reduted power level to 1080 Hwe to perform weekly surveillances.

1000 Increased power level to 1100 Hwe.

6 0100 Reduced power level to 850 Hwe to perform rod set ano to perform maintenance on the 'A' Turbine Driven Reactor Feed Pump.

0525 Commenced manual shutdown due to Turbine Electro-Hydraulic Control Icakage.

0615 Hanually scramed due to Turbine Electro-Hydraulic Control leakage.

10 1634 Reactor critical.

11 1425 Generator oa-line.

1735 Increased power to 185 Hwe, 13 0000 Increased power level to 300 Hve.

0135 Increased power level to 570 Hwe.

0710 Increased power level to 914 Hwe (power level due to Heater Drain pump motor problems).

23 0300 Reduced power level to 825 Hwe to perform rod set.

1900 Increased power level to 1115 Hve.

24 0015 Reactor scram due to intercept valves closing on an erroneous Turbine Electfo-Hydraulic Control overspeed signal.

30 2400 Reactor subtritical, Generator off-line, i

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_ . ._ _ _ m _ _ _ . . . _ _ . . - . _ _.

s .

. B. AMENDMENTS 10 THE FACILITY LICENSE OR TECHNICAL SPECIFICATION (None).

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPMENT (including SOR differential pressure switch failure reports). ,

-(See Table 1) '

O. LICENSEE EVENT REPORTS (Unit 2) '

LER Number DAlt Description 91-009-00 09/05/91 Inadvertant Residual Heat Removal Shut Down Cooling and Steam Condensing Isolation .

During Performance of the Main Steam Tunnel  !

High Differential Temperature Isolation  ;

functional Test.

91-010-00 09/06/91 Manual Reactor Scram Due to Turbine  !

Electro-Hydraulic Control Leakage at the #2 l Turbine Control Valve.

91-011-00 09/07/91 Drywell Personnel Airlock Door-Interlock Test was not performed in the Allowed Time Frame as required by the Technical Specification Surveillance Requirements.

012-00 09/23/91 A Reactor Scram Resulted when an Crroneous Turbine Electro-Hydraulic Control Overspeed .

Signal caused the Kain Turbine Control .j Valves to Close.  :

E. . DATA TABULATIONS (Unit 2)

, 1. Operating Data Report, j (See Table 2)

-2.. Average Daily Unit PC,wer Level.

(See Table 3)

3. Unit Shutdowns and Significant Power Reductions.

(See Table 4)

L l ~ZCADTS/7

C.. TABLE 1 (Unit 2) - -- ,

- i l MAJOR CORRECTIVE MAINTENANCE TO  !

SAFETY--RELATED EQUIPMENT '-

WORK REQUEST . RESULTS AND EFFECTS  ;

i NUMBER- COMPONENT CAUSE OF MALFUNCTION- ON SAFE PLANT OPERATION CORRECTIVE ACTION E

[ LO9587 2B HPCS Olesel Fuel' Circuit breaker. Breaker tripped on initial Replaced circuit breaker.

Transfer Pump motor start.

i LO9907 Intermediate Range Regulator and pre . None. Replaced regulator and [

l.. Monitor "H" regulator. pre-regulator.

LO9972 Hydraulic Control Directional control valve. Degraded control rod operation. Replaced directional l Unit 18-55 control valve. t

, i i L10358 Reactor Protection Circuit breaker. Breaker failed during testing. Replaced circuit breaker.

i- System EPM Alternate >

Feed

L10440 Reactor Protection EPA board. Unable to set under-frequency. Replaced EPA board. .

l System Alternate l l Power . Supply s

j (No SOR Failures this month.) l l

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. E.1 0FEFAi!NS MTA REFORT 103EI ND. (M 374 i UNIT LA M E TU)  ;

MIE 'ktet.er 10,1991 i C0MPLETED I-f hJ. CIAlt0JR1  :

TELEPH ME fB15)-357-6761 ,

i OPilATINGS1ATUS f

I

- 1, ret 0Pild FER10D: September 1991 EiDSSHOURS14EEf0R11NGFEF10D: 726

2. . CUFREWILY AUTCi!IED P0JER LEVEL trWth 3.323 MAX KPUD CAFAClit We-Nath 1,036 KS!6N ELECIRl(kl EAllNB We4eth 1,67B i

3. POWER tB'EL TO WHICH RESi81CICE (If ANT) We4tth N/A i

4. DEASONS FOR (CSillCilDN (IF ANYh t FEP0tilNB FER10D MIA  ;

I THIS MONTH YEA H 0- M TE Cu(AATIVE t

5. REAttDR ERlTICAL ilME 000RS) 445.7 6_Ji6.7 42,766,9

4. REAC10R PE50 VE SHUTICUN !!ME 1H30R5). 9,0 0.0 1;716,9  !

.i 7,' GENERATOR ON-LINE ilHE !H3VR51 424.0 6,255.0 42,102.2 I 8.' 0.0 0.0 I UNIT RESE WE SHUTIDWN 1]KE (HOUR 5) 0.0

9. THERMAL ENERGY 6ENEFATED WHt) - 1,157,945 20,228,465 125,667,640 10f ELCC'RICAL ENERGY BENERATED Wde-6tets) . 379,116 6,794,322 41.678,154

11. ELECillCAL E O GY GE O ATED W He-Net) 3!2,H0 6,574,014 37,993,164- -

?l2,REACl*JRSEWICEFACTOR(t) 61.9 95.0 76.2 1

13. REACTOR AVAILABILITY FACIOR (1) 61,9 95.8 73.0 <

14. UNil SERVICE FACIOR (1) _ 59.9 95,5 69.1 1

15. UNIT AVAILIBIllif FAC10R 0) 50.9 95.5 69.1

16. UNii CAPAClit FACTOR (US!h6_MDC) (1) 43.5 96.9- 63.4

' 17. UNii CAFACITY FAC10R (USlkB DESIGN MWe) (1) 4/ ' 93.1 69.9 .

18, UNIT FORCED CUTAGE FACTDR 0) 41,1 4.5 -13.5 ,-

' 19. SHUTD0"WS SCHEDULED OVER THE NEXT 6 h0NTHS (TYPE, NIE, AND fCRATIDN OF EACHh  !

REFUEllNB (L2R04)- 01/04/92 11 WEEKS ,

' 26..!F SH'JTDOW AT EhD Of REPOEI FERIOD, ESiinATED MTE OF STARIUh 10/03/91 ,

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3. : 10CIII NO. 050374 .

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1AILE 3 UW!i LA %tti TWO

E.2 MIA5E IslLY tlNil P06TP LEV [L We-Net) IAll Octeter 10,1951 1 COMP! Elf t BY LJ. CIALIN5t!

• TELErwNE 1815k357-(741 FEMfi Tft10D: Sertseter 1991 i -

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IAY FDM Inf 10WER 1 1,063 17 67e  :

'2 1,023 16 E69 l 1,044 I 3 19 t:67 i

f i 4 1.059 - 20 065 I  :

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5 1,008 21 862  !

l.. 6 219- 22 555 1

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t 7 -12. 23 982 t

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.8 -12 24

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.9 -12 25 -12 i i

. 10 12 26 12 - ,i

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i 51 27 -12 i 11 -

i 12' 151 28 -12 4

I, 13' 787 29 -12 .;

j 14 844 20 -12 I i

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16 670 f

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TABLE 4

• E.3 UNIT SHITfDOWNS AND POWER REDUCTIONS >20%

(UNIT 2) '

METHOD OF CORRECTIVE YEARLY iTPE S3tTITING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if FUMBER (YTMMDD) S: SCHEDULED (BOURS) REASON REDUCING POWER applicable) 1 91e906 F 0.0 A 1 Turbine Electro-Hydraulic Control Fluid Leakage.

LERK 91-010-00 DVRf I-2-91-0038 2 910906 F 128.2 A 2 Turbine Electro-Hydraulic Control Fluid Leakage LERf 91-010-00 DVRf1-2-91-0038 3 910924 F 167.8 A 2 Main Tarbine Stop valves Closed due to Erroneous Turbine Electro-Hydraulic Control Overspeed Signal LERf91-012-00 DVRf 1-2-91-0045 EUMMARY OF OPERATION:

Unit 2 experienced two forced shutdowns, both due to Turbine Electro-Hydraulic Control prObiems. The unit is presently in mode 4 (cold shutdown) and is expected to be returend to service 10/G3/91. For the remainder of the month the unit remained at high power, several minor power reductions were required due to system loading and routine surveillances.

ZCADTS/7

f. UNIQUE r.EIORTING REQUIREMENTS (Unit 2)

1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION DALE AClUAILQ AC111A11MS CMDlI10N Qf EVENT 09/24/91 2B21-f013E Automatic 1 Scram (LER# 91-012-00) 09/24/91 2B21-f013K Automatic 1 Scram (LER# 91-012-00) 09/24/91 2021-f013S Automatic 1 Scram (LER# 91-012-00) 09/24/91 2B21-f013U Automatic 1 Scram (LER# 91-012-00)

2. ECCS System Outages (See Table 5.)

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

(None.)

4. 4ajor changes to Radioactive Haste Treatment Systems.

(None)

5. Indications of failed fuel Elements.

(None) c i

ZCADTS/7

O a

(Unit 2)

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

Qu1AGEJ E [0ullEMI EURE0SI 423 2DG09DB Perform survelliance LES-Gi-108.

424 2E22-C002 Repair relay.

479 2DG035 Perform surveillance LES-EQ-112, 481 2012-F040A Perform diagnostic testing.

2E12-f026A 488 2E12-C002A Install drain valves.

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. -_ _ _ _ _ , , , , _ . - - - , _ _ _