ML20079P443

Monthly Operating Repts for Oct 1991 for LaSalle County Nuclear Power Station,Units 1 & 2

ML20079P443
Person / Time
Site:	LaSalle
Issue date:	10/31/1991
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9111120425
Download: ML20079P443 (24)

Text

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/^ C:mmonw;alth Edis n

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LaSace County Nxteaf f,tation Rural Houte 41, Don P20 k.z-\

' b# Matsedies, !!hno s 61341 Telephone 815/357-6701 November 10, 1991 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hall Station PI-137 Hashington, D.C. 20555 ATIN: Document Control Desk Gentler.an:

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

Very truly yours, kl T('Station G. J.Manager Diederich 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 Hanhger D. P. Galle, CECO D. L. fairar, 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 H. H. Servoss, OA/NS Off Site Review Station file 91111dMit, v11ojl PDR ADOCK O'.300(1373 R ppg ZCADTS/5 d' d{

6 LASALLE NUCLEAR POWER STATION UNIT 1 HONTHLY PERf0RMANCE REPORT OCTOBER 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPf-11 a

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TABLE Of CONTENTS (UNIT 1)

1. INTRODUCTION

11. REPORT A.

SUMMARY

Of OPERATING EXPERIENCE B. AMENDMENTS TO FACIL11Y LICENSE OR TECilNICAL SPECiflCATIONS C. MAJOR CORRECTIVE MAINTENANCE 10 SAFETY-RELA 1ED EQUIPHlNT D. LICENSEE EVENT REPORTS E. DATA TABul.ATIONS

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 failed fuel Elements ZCADTS/5

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1. INTF:000CT10H (Unit 1)

The LaSalle County Nucledr PcL'er Station is a two-unit facility owned by Commonwealth Edison Company and located near Harseilles, Illinois, tach unit is a 1101110g Hater Reacter 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-t.p and blowdown. The architect-engineer was Sargent and Lunoy and the primary construction contractor was Commonwealth Edison Company.

Unit One was issued operating litcnse number NPT-il on Anril 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power operation was conrnonced on January 1,1984.

This report was ccapiled by Michael J. Ciallowski, telephone number (315)357-6761, extension 2427.

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II .HCWTHLY REPORT i A. SUMHARY Of OPERATING EXPERIENCE (Unit 1) i 1

Day Time Event l 1 0000 Reactor critical, generator on-line at 1130 Hwe 0300 Reduced power level to 1015 Hve due to system load.

1100 Increased power level to 1130 Hwo.

5 0300 Reduced power level to 835 Hwe due to system load.

1400 Increased power level to 1130 Hve.

l 1800 Reduced power level to 1080 Hwe due to '10' Reactor Recirculation Pump flow Control Valve problems.

18 0535 Hanual shutdown of unit to perform maintenance on the

'18' Reactor Recirculation Pump flow Control Valve.

71 0429 Reactor critical.

2012 Generator on-line.

2215 Increased power level to 177 Hwe (power level held due to Turbine Control Valve problems and to perform Turbine surveillances).

22 1600 Increased power icvel to 365 Hwe (power level held due to Turbine Control Valve Maintenance).

2230 Increased power level to 760 Hwe.

23 1000 increased power Icvel to 1110 Hwe.

24 0200 Reduced power level to 745 Hwe to perform red set.

24 1400 Increased power level to 1125 Hwe.

31 2400 Reactor critical, generator on-line at 1125 Hwe.

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AMENDHENTS TO Tile TACILITY LICENSE OR TECilHICAL SPECif1CA110N Anticipated transient without scram-recirculation pump trip (A1HS-RPT).

C. KAJOR CORRECTIVE MAINTENANCE TO SAFE 1Y-RELAIED t00lPHEN1 (including SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPOR15 (Unit 1)

LER HILmhet Date Destdp.11pII. . . . . _ _ . . , _ _

91-011-00 10/02/91 Hissed Technical Specification Surveillance Requirement to Obtain a Sample of the Drywell

'ad Suppression Pool During Primary Containment Purge.

91-014-00 10/15/91 Loss of the Station Vent Stack Paticulate Composite Sanple for July 1991.

91-016-0G 1G/I4/71 Otv!;;si. :!: :25 Vsit DC Sy;t:c 0:c!: red Inoperable Oue to a loose Cable Connection.

91-017-00 10/23/91 Reactor Core Isolation Cooling Hechanical Overspeed Turbine Irlp During Performance of Cold Quick Start Surveillance.

E. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Tabic 2)

2. Average Daily Unit Power Level (See labic 3)

3. Unit Shutdowns and Significant Power Reductions (See Table 4) 7CADTS/5

C. TR8tE I (Unit 1)

HAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT .-

HORK REQUEST EESULYS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LO6083 Control Room HVAC Filter. Spurious aiarms. Replaced filters.

Ammonia Detector OXY-VC125B I

009945 Hydraulic Control Valve leakage. None. Replaced valve cartridge.

Unit 06-35 '

t l

LO9967 Low Power Range Low power range monitor Spurious alarm. Replaced card. ,

Monitor 32-57C card.

! L10956 Reactor Building Damper springs. Degraded operation. Replaced damper springs.

! Ventilation Isolation  :

Damper IVR04YA

Le1033 Reactor Core Turbine governor valve Turbine tripped on mechanical Replaced valve bonnet Isolation Cooling bonnet shaft seals. ovespeed during testing. shaft seals.

Turbine IE51-0002 LliO67 Division III 125 Volt Cable connection. Batteries inoperable. Tightened cable connection.

DC Battery Cell #1 (No SOR Fai ,this eonth.) r a

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. T ABLE 2 -

,- . C.! 0PERAi!NG M1A t[r0t1 IX1CLET NO. 050-373 UNil LALALLE ONE Mit Nneeer 10,1991 007.PLETED FY h.J. CIAtt0WSE! l IELEPH3.NE (815)-357-6761 DPERAllNSSTATLG

1. REPOR11NG TERIDD: Otteber1991 62005HMS?NREPORi!W5>!kl0D: 744

2. CUitENTLY AUTH0FlZED PMt LEVEL (Nth 3.323 Mat IUEO CAFAClit (NeNeth 1,6%

151&N ELEttilCA'. KATING (NrNeth i,070

3. 00WER LEVEL 10 UHICH RESTRICTED (IF ANY) (NrNeth N/A-

4. REALONS FOR RESTEICi!DN (if ANih I REPORTING FER10P MTA 1

. ..... ....... . j Tills MDWTH YErd-10-MTE cud.ULATIVE 5,283 4 45,8925 I

- 5. KACTOP tili! CAL IlaE (H30PS) 676.2

4. REACIOR FESENE SHUTD00N TihE (HOURS) - 0.6 09 1441.2 7.= BENERATOR ON-LINE IIME (HOURS) 657.9 5,165.6- 44,$14,4 8l UNIT RESEWE SHUTDOWN TIME (HMS) 0.0 0.0 1.0

9. THERRAL ENEk6f GENERATED thWt) 't,353,644 ~14/11,1J4 129,410,725

10. ELECTRICAL ENERGY GENERATED (NHe4ress) 491.5M 5,469,161 C,472,449 .

i

11. ELEtit! CAL ENERBY GENERATED (NHe-Net) 667,560 5.,259,079 41.629,961 .

-12<REACIOP$EIVICEFACTOR(1) 99.9 72 A 66.0

! !3. REACTOR AVAllat!Liff FACTOR (X) 90.9 - 72.4 69.2 i 14. tiWII SERVICE FAC10E (%) 88.4 70.9 65.4 I

.'15.UNITAVAILIIILITYFACTOR(1) 88.4 70.8 65.4

16) ItNil CAFACITY FAETOR (USING HIO (1). 96.6 69.6 58.5 l

17. UNIT CAFAClif FACIOR (USING DES!6N Net (1) 83.2 66.9- 5(.3 118. LLN!i FORCED OUTAGE FACTOR (5) 11.7' 2.8 : 7.9

19. 9fJTDOWS SCHE 10 LED DVER THE NEXT 6 M3NTHS (TYPC, DATE - AND MATION OF EACHh

{29. IF SHUTDOW AT END OF_ FEP0tt PER10D, ESilhATED MTE Of STARIUP:

N/A t'

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. 10C6[I NO.03-373 1ARE3 UN!1LASALLE(WC

[.2 - AVESAGE Mlli UNIT F0WER LEVfL (MWe-Net) MTE Neventer 10,1991 Li COMLE1[Dl'fM.J.CIAt(0W$t!

1[LII'H3NE tB15)-357-6761 REPORT fli!0D: - October 1991 i

NT NAl[R %f FNEl  !

q 1 1,078 17 944  ;

2 1,6Bs 19 26

-3 1,694 19 -12 4 1,06S 20 -12 5 1,005 21 11 6 1,947 22 314 7 1,048 23 992 9 1.046 24 1,033 9 1,042 25 1.097-10 1,042 26 1,097 11 1,041 27 1,139

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. 12 1,040 - 28 1,097 l

13 1,041 29 1,696 i 14 1,041 30 1,096 15 1,042 31 1.600 16 1,041 l

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TABLE 4 i E.3 UNIT SHUIDOHNS AND POWER REDUCTIONS > 207.

(Unit 1) .

HETit0D OF CORRECTIVE YEARLY TYPE SHUTTING DONN ACTIONS /CDMMENTS SEQUENTIAL DATE F: FORCED DURATION TliE REACTOR OR (LER/DVR # if NUMBER (YYW.DD) S: SCitEDULED (liOURS) REASON REDUCING P0HER applicable) 04 911018 F 87.1 A 1 Unit shutdown to perform maintenance on the 'IB' reactor recirculation flow control valve.

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SUMMARY

OF OPERATION:

The Unit experienced a forced outage due to reactor recirculation flow control valve problems. The Unit was returned to service on 10/21/91. For the remainder of the month, the Unit remained on-line at high power. Several minor power reductions were required due to system loading, surveillances and maintenance activities.

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f. UNIQUE REPORTING REQUIREMENTS (Unit 1)

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIP110N 0bJ1 KThilfD ACTUATION CQNJllllQN OF EVENT (None)

2. ECCS System Outages (3ee 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) s i

l ZCADTS/5 1

(Unit 1)

Table 5 F.2 ECCS System Outages Note: 1he year and unit data has been removed from the outage number.

WJAGE NO. LOUIPMENT BJR20S[

(U-0) 334 ODG01K Relay calibration.

(U-1) 1534 1DG01K Relay calibration.

1582 1E12-f074B Replace contrc.1 transformer.

1536 1600 1E51-C002 Inspect and repair turbine govenor l valve.

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LASALLE NUCLEAR POWER STATION UNIT 2 HONTHLY PERf0RMANCt REPORT OCTOBER 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7

TABLE OF CONTENTS (Unit 2)

1. IN1R000CTION II. REPORT A. SUHHARY OF OPERATING EXPERIENCE B. AMENDHENTS 10 FACILITY LICENSE OR TECHNICAL SPEClflCATIONS C. MAJOR CORRECTIVE MAINTENANCE 10 SAFETY-RELAlED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Snutdowns and Power Reductions F. UNIQUE REPORTING REQUIREHENTS

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 ZCADTS/7

I. INTRODUCTION (Unit 2)

The LaSaIIe County Nuclear Power Station is a two-unit facility owned by Commonwealth Edisen Company and located near Harseilles, Illinois. [ach unit is a Bolling 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 Commo9 wealth Edison Company.

Unit Two was issued operating license number NPT-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation war commenced on June 19, 1984.

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

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11. ' MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Time Event 1 0000 Reactor subcritical, generator off-line.

0910 Reactor critical.

3 0025 Generator on-line.

0055 Increased power level to 170 Mwe.

]

093S Increased power level to 270.Hwe. l 1500 Increased power level to 380 Mwe. 1 2000 Increased power level to 680 Mwe. i 4 1800 Increased power level to 1115 Mwe.  !

7 0041 Reduced power level to 690 Mwe to perform rod pattern adjustments, j I

0345 Increased power level to 930 Hwe (power IcVel held due to system load).

0415 Increased power level to 1090 Mwe. i 1800 Reduced power level to 1060 Mwe. due to low section -;

pressure on the '2B' Condensate Booster pump  !

9 0110 Reduced power level to 970 Mwe to~ perform weekly '

surveillances and rod exercising.

12 '1100 Reduced power level to 650 Mwe due to low suction i pressure on the '28' Condensate Booster pump. ->

13 0900 Increased power level to 1120 Hwe.

16 0040 Reduced power level to 1060 Hwe for rod exercising. i 1100 Increased power level to 1120 Mwe.

20 00001 Reduced power' level to 730 Mwe due to lleater Drain pump forward valve probleins.

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11. HONillLY REFORT (Continued)

A. SUMRARY Of OPERATING EXPERIENCE (Unit 2)

Day Time Event 22 0000 Increased power level to 1120 Hwe.

23 0010 Reduced power level to 1020 Hwe due to lleater Drain problems.

1200 Increased power level to 1120 Ewe.

25 0000 Reduced power level to 1020 Hwe for rod pattern adjustments.

0900 Increased power level to 1120 Hwe.

26 0000 Reduced power level to 750 Hwe ici rod set.

1200 Increased power level to 1120 Hwe.

29 0730 Reactor scram from turbine trip caused by high vibration readings.

30 1420 Reactor critical.

31 1101 Generator on-line.

1200 Increased power level to 130 Hwe.

2400 Reactor critical, Generator on-line at 136 Hwe.

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3. AMENDMENTS 10 THE FACIt.lTY LICENSE OR TECHNICAL SPICiflCA110N j Anticipated transient without scram-recirculation pump trip l (ATHS-RPT). l C. MAJOR CORRECTIVE MAINTENANCE 10 SAFETY RELATED EQUIPHENT (including  ;

SOR differential pressure switch failure reports).

(See Table 1) 1 D. LICENSEE EVENT REPORTS (Unit 2)

EER Number Dits DutrjpilDD

)

91-013-00 10/07/91 failure of the D Auxiliary Electric Equipment Room Ventilation Supply fan l Breaker. J 91-014-00 10/29/91 A Reactor Scram Has Initiated Hhen the Hain Turbine Tripped due to High Vibrations on Dearing #6.

E. DATA TAllulATIONS (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)

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C. TABLE i (Unit 2) ,

MAJOR CORRECTIVE MAINTENANCE 10 SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS ,

NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERf.T!ON @ RECTIVE ACTION LOS237 Hydraulic Control Drain valve. Degraded operation. Rebuilt drain valve.

Unit 50-31 L10168 Low Power Range Power supply. Failed testin,. Replaced power supply.

Monitor 4D-08-25 L10399 Hydraulic Control Leaking solenoid valves Degraded operation. Repaired solenoid valves.

Unit 38-23 117 and 118.

L10621 'B' Aux Electric 480 VAC circuit breaker. Circuit breaker failed. Replaced circuit breaker Equipment Room Supply relay coll.

Fan OVE01CB (No SOR Failures this month.)

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TAILE 2 i E.1 CPERAllNG NTA REf0k' 10Cf[i N3. 650-374 UNil LASALLE TU0 IATE Nevener 10,1991 00r/LETEli F1 M.), (IAltNSX1 TELEPHONE (815)-357-6761 0FERATIG STATUS GRDSS H0 IRS IN REPMil4 FEE!0D: 744

1. REPORTING FERIOD: October 1991 3.323 mat KFEND CAFACITY (hJe4eth 1,036

2. CUEFENlt Y CH'Sh:D FOUER LEVEL (MJth DESIRi ELECTRICAL FATING (Nue-Neth 1,07E 3

3. F0ER LEVil 10 WICH EESTRICIED (If ANY) (Ne- Net): N/A 4, 2EA50N3 F0K RESTRICIION tif AN1h IEF0211NS FER10D IATA THIS MONIH YEAR-10 IATE CUMJLATIVE 5, REACTGR CRITICAL ilhE 000RS) /04.9 6.981.6 43A?1.8 0.0 0,0 1,716.9

6. REACTOR RESERVE SHuiWW Tine (H.)ukS) 7, SENERATOR Ot'LINE 11mE GiDURS) 645.1 6 ,9 % .1 "17.3 7 B, LWli RESERVE CHUIDDWN TINE (H3URS) 0.0 0.0 0 9, 1,976 F 22,205,328 m ;3 THERhAL ENERG1 GENERATED thWHt)

10. ELECTRICAt. ENER6Y FGERATED (FJHe4ress) 660,H 6 7.454,728 -

& A

11. ELECTRIA L E); ERG 1 GENERAIED (NHe-NO) G7,47, 7.211,438 40,630,578

'!:, itACTOR SFRVICE FACICR (1) 94.7 95 7 "6.5 i

i, REAtiO2 AVAILAIILITY FAC10R (1) 94.7 95.7 73.3 f

e.

J a. UNIT SERVICE FACIOR (%) $6.7 v4.6 6?.3 1

86,7 94.6 69.3

15. UMT AVAILIBILIII FAC10P (t)

16. UNIT CAFACITf FACTDR (UGIW hDC) (1) B2.7 95.4 '3.6  :

17, UNii CAPACITY FACTOR (U516 EESIGN Ne) (1)  ??.5 91.7 ol.1

~

13.4 5,4 13.5

15. UNil FDRCED OUTA6C FACT 05 (%)

19. SHU11MNS SCHEDULED DVER THE NEXT 6 MarIls (Tf PE, DALE, AND WEAllDN OF EACMH REF0EllNB (LOR 04) 01/0452 11 WEEKS

29. IF SfJTDOW AT END OF REP 0i1 FERIOD, E511 MATED DATE OF STAR!UF:

N/A l

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. . DOCKET NO. C50-374

- 3 IAlti 3 - UN11 LASALLE-Tua E.2 AVERAGE MILY DNIT PDUER LEVEL, (MWe-Net) MTE Nevenber it, ~1991

.COMPLETET) Bf M.J. CIALt0W5t!

TELEPHONE (B15)-357-6761 REPOE1 ff fl0D: October 1991-NY P00ER MT- POWER 1: -12 17 1,083 -

2 -12 19 1,077

.3 275 19 1,076 I

4 953 26 1,006 5 1 053 21 951 6 1,011 22 1,077

- 959 23 1,064 0 1.013 - 24 1,076

,9 991 _25 1,036 10 - .T,007 26 1,024 i l

11- ?99

27 1,1 '.

12 931. 20 1,087 l

13 1,066 2v 32? _

. 14 1,084 39 -12 1

- 15 1,081 31 -69

- 16 1.479 ,

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TABLE 4 E.3 UNIT SHUTDOWNS AND POWER HEDUCTIONS >20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CO>MENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/EVR # if NUMBER (YYMMDD) S1 SCHEDULED (HOURS) REASON REDUCING POWE2 applicable) 3 910924 F 48.4 A 2 Main turbine stop valves closed due to erroneous turbine electro hydraulic control overspeed signal LER #91-012-00 DVR #1-2-91-0045 4 911029 F 51.5 A 3 Turbine trip due to high vibration readings on bearing R6.

LER #91-014-00 DVR #1-2-91-0055

SUMMARY

OF OPERATION:

Unit 2 started the month shutdown following a scram due to turbine electro-hydraulic control problems. The unit was returned to service on 10/01/91. A scram was initiated on 10/29/91 due to a turbine trip from high vibration readings.

The unit was returned to service 10/31/91. For the remainder of the month the unit remained at high power, several minor pocer reductions.were required due to system loading and routine surveillances.

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.- F . UNIQUE REPORTING REQUIREMENTS-(Unit 2)-

1. Safety / Relief Valve Operations VALVES 710 & TYPE Pil.NT DESCRIPTION DAIL ACTUATED 6CAIATIONS CONDITION OF EVENT AutoLatic- Scram (LERE 91-014-00) 10/29/91 2821-F013C 1 10/29/91 28'i l-F0130 Automatic 1 Scram (LER# 91-014-00) 10/29/91 2821-F013E Automatic 1 Scram (LER# 91-014-00) 10/29/91 2821-F013K Automatic 1 Scram (LER# 91-014-00) 10/29/91 2B21-F013S Automatic 1 Scram (LER# 91-014-00) 10/29/91-2B21-F013V Automatic 1 Scram (LER# 91-014-00)

-2. ECCS Systes Outages (See Table 5.)

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

(None.'s

4. Major changes to Radioactive Haste Treatment Systems.

(None)

5. Indications-of Failed Fuel Elements.

(None)

I ZCADTS/7 L

(Unit 2)

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

(XIIAGE 3L EQUIPMENT PURPOSL 562 2DG0lK Relay calibration.

588 2E12-F006A Repack valve.

599 2E12-C002B Lubricate and meggar pump motor.

601 2E12-f064B Replace breaker and meggar motor.

604 2E12-C002B Install pump motor oil reservoir drain valve.

614 2E22-5001 Remove and test relief valves, 615 2E22-C001 Meggar motor.

616 2E22-C003 Lubricate pump coupling and replace minimum flow orifice.

619 2E22-C001 Install oil reservoir drain valves.

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