ML20128L908

Monthly Operating Repts for Jan 1993 for LaSalle County Nuclear Station,Units 1 & 2

ML20128L908
Person / Time
Site:	LaSalle
Issue date:	01/31/1993
From:	Cialkowski M, Spedl G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9302220043
Download: ML20128L908 (26)

Text

.

.. g-m, ;

+

=

n,

'\\l >.

~

y

.c t t,,

Commcnw

alth Edison 1 W'.' u M

trSa!!e County Nuclear Station

' :I 9

.?60 N,215', Rdc_ _ _

i.

- Marser,tesilflinois 61341

. 1elephone 815/3574) 31 =

~)

+

'rebruaryf11,1993 i

Director of Nuclear Reactor Regtlation g

United - States Nuclear Regulatory Commission

• l Mail Station P1437 Mashington, D.C.

2055L ATIWs Docenent Control Desk p

l --

L __

Centlement t

Enclosed for ' vur infonnation in the toonthly performar.ce report covering; LaSallo County Nuclent Power Station for January 1993..

[_

vos;y truly yours i

h l Cary F. Spedi.

t

, Station Manager 0

1.nSalle County Station-

9.

y l'.

N Enclosure l I.

l met - A.'O._ Davis,.NRC, Region III l'

D. E. Ellis.. NRC Resident Inspector T.aSalle 4

l

- J. L. Roman,- IL Dept. of Nuclear Safety.

l-

.U. Stransky, NRE Project Manager N.'.J. Wallace, CECO-lk

- D. L. Farrar, CECO-INFO Records Center-l-

.D. R.-Eggett, NED-l P. D. Doverspike, GE.Rosident T. K. Schuster;.- Manager of 'Huclear - Licensing T. ' A. Ricek, Nuclear = Fuel,5crvices Manager

(,

J. E. I.ockwood,JRegulatory Assurance Supervisor

. W. P. Pietryga,- QAINS Off Site Review L_

Station File.

..s.G

.19.100:

- - i h~9 J

/

9ao222co4a Saoiai-PDH ADOCK 05000373 R:

PDR VM't W

7 e

Y I

E N

l.AHALI,E NLICf. EAR IMMEH S*> TI(Rv (TNIT 1 WMTilLT PERFORNANCE HEIORT JAHtJARY 1993 CCNWWWEAlmi ED1504 C(MPANI HMC 1.CCKET NO. 050-373 t.ICf3SE NO. Hl'F-11

.m.

- - ~ -.

-.~

e TABLE OF C(MTDrrS (UNIT 1)

I.

IrrtRO!XJCTI(N 11.

RI'. PORT A.

SUMMARY

t>F OPERATING EKP3 RID'CE II.

ANNENt1HrHT!i TO FACILIT1 1.ICF2iSE OR TF;CUHICAL fiPft'IFICATICMS C.

MAJOR C0JRECTIVT, MAINTENANCE "IU SAFETY-R31.ATED t.UJIIMrE

D.

l.ICTESEE INDIT REPOPTfi E.

DATA Tant'JLATICE9 1.

Operating Data Report 2.

Avorage Dolly Unit Power Leval 3.

Unit Shut. downs and l'ower Reductions Y.

UNIGJE REPOITf!NG HEgJIRL;4r:NT'l 1.

Main Stena Safety Mclief Valve Operations 2.

ECCli System Outages 3.

Of f-filte Dose Cniculation Menual Changer 4.

Major Changes to Radioactive Waste Treatment Systen 5.

Indicat.lons of Failed Fuel Elements

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

m-_~

I INTROL JCTICW (LMIT 1)

W 1.

l The 1,aSalle County Nuclear Power Static:a la a two-Unit facility twned.

'l by Cosmoonwealt.h Edison Company and locate 6 near Marsellies,1111mois.

Each unit is a Holllag Nater Reactor with a designed not electrical-output. of 1078 Megawatta. Waste heat is rejected to a man -anade cooling pond using t.he 1111mois river for make-up and blowdown. The atchitect-engineer was Sargent end ! undy and the contractor.was-Comenonwealt.h Edison Company.

l Unit one wen issued operatsag license raaber NPF-11 on J.pril 17, 1982. Anillal criticality wah achieved on June 21, 1982 and comunercial power operatics was commenced on. January 1,1901.

~

s

- This report was cosipt'ed by filchael J. Cinikowr;ki, telephone number (015)357-6761, 6AL.Onnlon 2427.

t i

?

I b

'?

e

. }

r 1

?

t

^

p n

-. = -.

, +

~.---:.

I e

me s en t

.r-ve d-

-w eees

+-e+-

e

/

w y

-e-e e v 'y 4-y ahe-

- f

~... ~..

11! HCDi*nILY. REIVRT A.

SITMMARY OF OPERATJNC EXPERIENCE (linit 1) 1)ay Time T, vent 1

0000 Renet.or sub-critical, Conurat.or of f-line, Refuel outage (L11105). In progress.

23 1354 Weactor criticaj.

26 2320 Hanual roactor scrtwa 390 to a safety rollef valve st.lchng in t.be open poultion.

28 0900 Reactor critical.

I 30 1300 Conorator on-line at 60 W u.

1510 Man sal turbine t.rlp due t.o high bearing vlbratirms, 2A20 Generator on-line et 60 Wo.

31 0010 Hanun1 t.urbino trly due t.o high bearing vibratJnta.

0720 Generatoc on-line at 60 Mwn.

1710 Manual turblue t.rlp due to high bearing vibrations.

2400 Reactor otitical, Generato off-line, forced out. age in progress.

b I'

?

.t.

s W

.. I z

.. ~,.

-,-,..=,.

I 11.

A4NDit'U2fTS 'IC TIIE FACILITY OR TECHNICAI, SPECIF1CATIOff -

E(.t.ablished *!cchnical Specification requirtuments for the set m discharge coJune vent and drain valves.

Revleed the Technical Spacification bases for '.he cont.rol rod housing support.

C.

MAJON CO'AREC'f1VE MAITTTENANCE 'ID SAFETY-tKI.ATT D ISillWrtf7 (including SOR differential pressure switch failure reports ).

(See Table 1)

D.

1.1CDISKE EVmT REPOliTS (Unit 1)

LGB ffumber Date Descticidon 43-001-00 01/05/93 1 ist.rument spike which resulted in a Division II low prensure cora inject.lon purp st.ar t and a 1A diesel generator start.

93-002-00 01/26/93 11121-F013A Inflod to cluso during startup tes t.I ng.

93-003-00 01/29/93 Fallure of the reactor core Isointion cooling baroidetric condenser pe:p.

E.

I?ATA TALIUI.AT10NS (Unit 1) 1.

Operating Dat.a Report (See Table 2) 2.

Average Dally Unit Power Level (Son Table 3) 3.

linit Shut. downs and Significut Power Reductions (See Tabjc 4

C. TABLE 1 (Unit 1)

MAJOR CDROECTIVE MAINTENANCE TO SAFETI-RELATED EQUIPMENT FORK RN AND EFFLTTS RE N

. CCBG52ENT N__14ALFFICTICtL_

Ot_f M F N R W v ggz6,24vA ACIIQi LO6691 250 volt Battery Charger failure board Inaccurate output Replaced railetre Board Chargar 1DCO?E voltage indication L11120 Reactor Recire Test card Upscale trip setpoint replaced test card flow sn====t failed to repeat 1B33-Kf,07A L1361C Reactor Core Limitorque motor valve failed to Replaced motor Isolation Cooling operate min. flow valve IISt-F019 L14731 MSIV Leakage Vent valve leakage None Replaced valve Control pressure transmitter PT-1E32-NC21A L15237 Reactor Core Pump shaft seal leak None Adjusted packing.

Isolation Cooling barometric cond.

vacuum pump-1E51-C0C5

[

L15545 Ulgh Pressure Valve leakage None Replaced gasket.

Core Spray inj.

valve IE22-FOO4 i

L16598 Reactor Core -

Air regulator _ leaking None Replaced air regulats-r.

Isolation Cooling barometric cond.

l pump stop valve 1E51-FOG 4 i

- L17251 Control Rod..Dri=a

.kre water accumulator None

' Replaced accuarulator.

Hydraalle Control leaking Unit 54--27 4

w m

-m e

- =

i-

=

-a---

w

g1 C. TABLE 1 (Ibit 1) -um A AmtTED MA.FI3 CORRECTIVE MAINIENANCE TO

~

SATETI-RELATED EQU2PMENT WORK RESULTS AND r.rreA.15 EECUESI

_CDMRQt02fT CALSE OF MALEUNCIIDL1_

W _ SAFE PLANI _D1%RJCIDtf

_.15;ps(A_ms ACTI@

L18211 MSIV Leakage Valve leakirg valve failed local Lapped valve disc and Control isolation leak rate testing repacked vaAve.

valve IE32-F001E L18256-MSIV Leakage Thermal overloads Unable to remotely Replaced thermal overloads.

Control steam open valve tunnel diss-harge valve'IE32-r008 L18382 Reactor Core Valvo leaking Valve failed local Lapped valve disc and Isolation Cooling leak rate testing replaced gasket.

i isolation valve 1E51-F064 L13954 Reactor Core ILigh valve packing Unable to test valve Replaced packig.

Isolation Cooling loads turbine exhaust isolation valve 1E51-F086 L18960 Reactor Core High valve packing Unable to test valve Replaced packing.

Isolation Cooling loads turbine exhaust stop valve IE51-r080-L19154 Control Rod' Drive. Directional control Rod bypassed Replace control valves.

Dydraulic Control valves' Unit 02-27

[

L19217 Main Steams Isol.

Air control valve None Replaced air control valve IB21-F022B.

leaking valve L19433 Control Rod Drive Scram water accummulator Unable to =aintain-Replaced accummulator.

Hydraulic Control

. le=H wy pressure

. Unit 18-15

C. TABLE 1 (UQit 1) --Clm usu s:.

MAJOR CORRECTIVE MAINTENANCE TD SAFETY-RIIJLTED EQUIPMENT NORK RESULTS AND r.1eu.n, REDUEIET

_.CCMECNENT CAUSE DE_bALUREh, CNMELJJfT OPERA %ICtf

_1vxpanvs ACI1CiN L19506 chan=1 C Pre-asplifier None 2eplaced pre-amplifier Intermediate Range Monitor IC51-K601C L19522 cha,wl 3 Selector switch Erratic indication Replaced selector switch.

Intereediate Wa y Monitor recorder IC51-R603B

. L19534 Feedwater check Solenoid leaking None Replaced solenoid valve IB21-F032A L19563 Reactor Recire.

fimit Evitch Inaccurate valve Replaced limit switch.

Isolation valve indication IB33-F345B L19701 Hydrogen Recomb.

Flow indicator Inaccurate flow Replaced flow indicator flow i dication IFI-HGO22 indication

, L19933 Switchgear Heat Damper actuator Daueper failed to Replaced actuator.

Removal Recire open damper XVID3Y 1

- L20093 Reactor Core Iso.

Motor brushes frayed Hone Replaced motor brushes.

Cooling bsrometric condenser vacuum pump 1E51--C005 L20365 Control Rod Drize Directional control None Replaced the directional dydraulic Control valve valve.

Unit 30-11 (No~SOR fallures this month)

..~_m._

l'4,,

TABLE 2

' U E.1 'OTERATIl10 DA*AA REPORT DOCKET No. 050-373-UllIT LASALLE OtlE DATE rebruary 10, 1993-COMPLETED BY H.J.CIALKOWSKI

- OPERATING STA'11)S TELEPHOtlE (815) 357 6761-

.1.

REP 0f(TItIG PERIODS January 1993

_ GROSS llOURS !!! lirPORTING PERIOD:

i44-s.

-2 CURRENTLY At!Til0H12ED POWER LEVEL (! fit):

3,323 MAX DEPENDABLE CAPACITY (MWo-Net.):

1,036 DESIGN ELECTRICAL RAT!!1G (MWe. Net):

1,078 ~

l 3.

l'OWER LEVEL TO W}lICl! RESTRICTED (IT MlY) ( MWe-tie t. )

N/A s

4.

HEASON FOR RESTRICTION (IT AIIY):

THIS MotiTil YEAR TO DATE. CUMULATIVE 5

FEACTOR CRITICAL TIME (llOURS) 168.4 160.4 54,093.2 6.

REACTOR 11ESERVE SifUTDOWN TIME (HOURS) 0.0 0.0 1,641.2l 7

GENERATOR OH-LINE TIHE (HOURS) 14.8 14.8 S2,922.4 8.

UNIT RESERVE Ei!UTDONI TIME (llOURS) 0.0 0.0 1.0 t

9.

Ti!ERMAL EllERGY GENERATED (MWIIt) 36,968 36,968 15$,097,126 l

-10. ELECTHICAL ENERGY GENERATED (MWile-Gross) 2,142

'2,142

-51,794,491

11. ELECTRICAL ENERGY GENERATED (HWile-Net)

-6,846 6,846-49,64.1,244 l

l

12. - REACT 0ft SERVICE FACTOR (%).

22,6 22.6-67.9.

1;

13. IfEACTOR AVAILABILITY FACTOlt (%)

22.6 22.6 69.9J R

3 4. UNIT S"R"tCE TACTOE (%)

2.0-2.0

'66.4

-;15.' UNI.T AVAILIBILITY TACTOR (%)

2.0 2.0

66.4

16. UNIT CAPACITY TACTOlt (US11tG MDC)"(%)-

-0.9

.0.9:

60.1

17. UNIT CAPACITY TACTOR (USING DESIGN 101e) 0.9-0.9-

'5748',

i

10. - UNIT FCRCED OUTAGE FACTOR (%)

~57.7 57.7 6.9l 7

l

-19. Sl!UTIXNNH SCllEDULED OVER Tile NEXT 6 MONTHS (TYI'E, DATE, AND DURATION OF EACH) t.

tio Outages Scheduled

20. Ir U!!UTDONN AT END OF REPORT PERIOD, ESTIMA'1ED DATE OF STARTUP -

02/01/937 1

l

. b., - -

c u.

. a

.I '

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

. -, - -.. - --... ~ -.. -.. --...-,.,-.

O y1.*

TABLE 3.

- K,2 AVEliAGE L AILY ' UNIT PCMER ' LEVEL (MWe-Net). DOCKET N 9

s UNIT-LASALLE ONE DI.TE rebruary 10, 1993 I

CCHPLETED DY M.J.'CIALK0WSKI TELEPHONE (815).357k 761 5

l

. REl' ORT PERIODI January 1993 DAY POWER DAY POWER 1

-12 17 12 2

12 18 12-i 1

3

-12.

19 12 f

4

-12 20

--12 5

21 2 21

-12.

l f

-12 2 2 --

-12 7

-12 24

.12

i 0

32 24 12-

.[

9

-12 25

-12 4t

+

10

-12

.26

-12~

11-

-12 27-12 12-

-12 28 22 13

-12 29

-12L 14

-12 30-9 15

. 31 53-16 12.

- I I

f s

+

3. -w y

-e

.~

TABLE 4 E.3 UNI *x SEUIDONNS AND POWER EEIXX"TIONS 3 20%

(sWIT 1)

METHO) OF CORRECTIVE HHUTTING LOWN ACTICES/CD4MENTS TEAELY iTPE 5gNENTIAL DATE F: FORCED DURATICE "IEE EEACIDE Og (r.E2/Dvu 8 if RUMTiG IIDeGDJ S1._SCIIEDDi.5D LBQUES1_

REASCS RED 5F M R apstihablei 1

921003 5

541.9 C

1 Refuel outage (LIROS) 2 930130 F

6.2 A

4 Manual turbine trip due to high bearing vibrations (the reactor remmainad critica.1)

I l

t 3

920131 Y

7.2 A

4 Manual turbine trip due to high bearing vibrations (the reactor r m,ined critical) l 1

4 930131 F

6.8 A

4 Manual turbine trip due to ',igh bearing vibrations l

(the reactor reinained critical)

L I

l L

SQeGRT OF OPERATIO'.

l The unit entered a scheduled refuel outage on 10/03/92. The unit was returned to service 01/30/93.

The unit experienced three forced outages due to high bearing vibrations caused bw the newly installed main turbine low pressure rotors.

-~ -

]

F.

UNIQUE REPORTING REQUIREMENTS (UNIT 1)

' i 1.

Safety Eellet valve operations i

Valves Type of Plant Description j

Date Ac.tuated Actuation Condition oI_E ren t___

t 01/26/93 1821-F013A Manuni Startup Startup tealing (1.ER S 93-002-00) l 01/26/93 1D21-F013C Manual Startup Startup testing;

(

01/26/93 1821-F013D Manual Startup Etartup testing i

i' 01/26/93 1H21-F013E Manual Startup Startup testing 01/26/93 1821-F013K Manual Startup Startup testing' 01/26/93 1H21-F013P Manual Startup Startup testlag 01/26/93 1821-F013H - Manual Startup St arttip testing 01/26/93 1921-F013S Manual St.artup

- Startup testing-01/26/93 IB21-F0130- Mauual St.artup Startup' testing 01/26/93 11121-F013V - Manual Startup Startup testing

=!

01/28/93 1H21-F013A Manual Startup Startup testing 01/28/93

- 1H21-F013H Manual Startup Stattup testing 01/28/93 IB21-F013D Manual Startup-Startup testing 01/28/93 1821-F013F Manual Startup Startup testing 01/28/93 1821-F013G Manual Startup Startup' testing 01/28/93 IB21-F013B Manual Startup Startup testing 4

01/28/93 1821-F013J Manual Startup Startup. testing 01/28/93' 1821-F0131.

Manual Startup Stat tup testing 01/28/93 1H21-F013M Manual Startup Startup testing 01/28/93 IH21-F013N Manual' Startup Startup Lesting t

01/28/93 11121 -F013 P Manual S t.ur tup _

Startup testing 01/28/93 11121-F013V Manual

- Startup Startup testing 2

ECCS Syst.em Out. ages i

(See Table 5)

- i 3.

Changes t.o the Of f-Sit.e Dose Calculation Mapual.

(None) 4.

Major Changes to Radioactive Maste Treatment Systens (None)

L S.

Indications of Failed Fuel Elements (None)

- t

?

?

6 I

b w e se, ve,2--

.e-em-w+,-:..

r-31--

3-+,

-s r

r

<-ow--eve---

v-- - - - -

w---~w--,

~ew-v -vs- ' w mr-er

- +

cw-w

(tJNIT 1)

Tabic 5 P.2 ECCS System Outages Hot es The ye ar and unit data has been rmaoved f rom the outage utsaber.

WIAGE.FQ.

MRl11W YI WRWSE (U-0) 0005 ODCOBCA Inspectit.n 0006 ODGOBCD Innpection (U-1) 0012 1K51 F008 A&ninistrativo control 0019 1E51-F013 Logle testing 0024 IDG035 Lim 1t orque spring pact replacement 0028 1E12-F08711 A&ninlutrative control 0044 IDGOBCII Air leak repaira 0045 1E12-F02411 A&olnistrative control 0047 IE51-F064

< Administrat.lvo cont.r p1 0050 1E12-F004C Thormal overload replacement 0051 1E21-F034 Ada.inistrat.lve control 0060 1E51-C005 Motor inspection 0123 1E51-C002 Inspection' e

0144 3DG01K Lubrient.lo'l 0155 IE51-C004 Pump motor replacchment i

j i

LASALI.E NUCLEAR NFE1 STATION UNIT 2 iKMTHLY l'r.RFORNANCE RF IURT JANUARY 1993 C04MONMEAl.TH EDISON COMI%MY NRC DOCI:17T WO. 050-374 LICIMSE NO. NI'F-18 I

I I

l

l

+

TABLE OF CCNTENTS (UNIT 2) 1.

IffTROLK1CTitM II.

REPORT A.

SUMMARY

OF Oi?ERATING KKPERIDICE 6

11 AMMENiMENTF '1V FACILITY LICTJfSE OR YECIINICAL SPECIFICATICMS i

C.

MAJOR CORRECTIVE MAINTENANCE 'IO SArt"fY-RELATEt> EQll!!MDfT U.

1.1Cl?iSEE f:VFKf REPORTS E.

DATA TAllULATIONS 1.

Operatirq Unta Report 2.

Average Dally Unit. Power 1.cen) 3.

Unit Shutdowns and Pneur Moductions s

F.

UN!QUf: REPOltTING REQUIREMDITS 1.

Main Sterna Safety Rollef Vulvo Ope. =Llona 2.

ECCS System Ontages 3.

Of f-Sit.e Dose Calculation Manual Changes 4

M:.130r Changes to Radlonctivo Maste Treatment Systeun 5.

Indications of Failed Fuel Elmoonts -

e D

\\

s 1

.1

1.

INTitOttlCTICM (UNIT 2)

The LaSallo County nuclent Power St.ation la a two-Unit f acility owned by Corrsnonwonith Edison Company and located near Marsellies, Illinois.

Each unit is a Bollbg Water Reactor with a destgoed net, niectrical output of 1070 Megnwat.t.s. Haute heat is rejected to a man-snade cooling pond using the 1111r.ols river for sanke-up and blowdown. The archltect-engineer wan Sargent and L udy and the contractor was Cormnonwealth F,dit:on Company.

Unit two was lasted operating 11cern e number NPT-18 on Decinnber 16, 1903. Initial criticality vas achloved on March 10, 1984 cad conwnerciel power operation was ccanenced on October 19, 1984.

This report was complied by Michael J.- Clulkowskl, telephone nir ber (815)357-6761, extension 2477.

4._

=

II. WMTIHJ REf' ORT A.

SUMHARY OF OPERATING EXi'KRIFNCE (tinit 2)

Day Ilmo fiYent.-

1 0000 Henctor critJctil, Genernt.or on-line at 1133 Mwe.

0300 Reduced power invel t.o 1000 Mwe due tt, system Joad.

2000 Increased power level to 1110 Mwe.

2 0230 lleduced power level to 850 Mwe due to system load.

1130 Increased power level to 1135 Mwe.

3 0300 Faduced power level to 850 Mwe due to system load.

i 1800 Increased power level t.o 1135 Mwe.

4 0000 Reduced power level t.o 845 Mwe due to syst.em load.

l 1300 Increased power 1cyc1 to 1135 Mwe.

5 0200 Reduced power level to 845 Mwe due to syntam load.

1400 Increased power level to 1135 Mwe.

6 0100 Reduced power level to 845 Mwe due to system land.

1200 Increased power level t.o 1135 Mwe.

8 0200 Reduced pcrier lovel to 995 Mwe due to system load.

l 1000 Increened pewar level to 1140 Mwe.

10 0200 Reduced power level to 845 Mwe due t.o eystem lond.

1100 7.ncreased power level to 1135 Mwe.

12 0200 Reduced power level to 895 Mwa dua to system load.

1000 Increnaed power level to 1135 Mwe.

i 13 0030 Reduced power lovel to 1000 Mwe to perform monthly survel]1ance.4 and CRD eFore181Dg.

l 1100 Increased power level t.o 1135 Mwe.

l 15 0400 deduced power level to 945 Hwe due to 6.ystem load.

l 1300 Increared power level to 1135 Mwe.

l i

m

.y.

y e-~v.

j

.*O-

=

t-

11. MurIHC,Y REPOtrf A.

HUptMRY OF OPERATING EXPFRIENCE (Unit 2)

.i DM Tliec TvJnt_

Ifi 0330 Reduced power level to 1000 Mwo due to system load..

100n increased power level to 1135 Mwe.

17 0330 Reduced power level to 995 Mwe'due to' system Icad.

{

i 0900 Increased power level to 1140 Mwe.

l 19 0200 Reduced power level to 1040 Mwe due to systews load.

{

0700 Incrensed power level to 1140 Mwe.-

21 0230 Reduced power level to 995 Mwe duo to system load.

1000 Increased power level to 1140 Mwe.

2330 Reduced power level to 1040 Mwe thu to system load.

22 0900 Increased power level to 1135 Nee.

24 0300 Reduced power level to 850 Mwn due to-system Joad.

1300 Increased power level t.o 1135 'Mwe.

26 0000 Reduced power : level to.1000 Mwe due to system load.

1000 Increased puner leyc1 to 1135 Mwe.

I:

27 0130 keduced power level to 1000 Mwe due-to _ system 3 cad.

0800 Increased power leve? to 1135 Mwe.

31 0130 Reduced power loves 1 to 995 Mwe duo to systeen lort 0830 Increased power level to 1135 Mwo.

3400 Reactor critical, Generator on-llan at 1075 Mwe due to system lond.

]

I i

~

l I

l q

i,

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

~

.... ~

4 II.

AMHFRIMIMTS *tU Mif. FACit41TT OH TECilNICAL SPECIFICATI(M 11 Est.nblished Technical Speelfication regulrreents for the screws dischatge volume vent a.nd drain valves.

j Revised tise Technical Speelficat.lon bases for the control rod housing support.

)

C.

MAJOR CORRECTIVE MAINTtWANCF. 'IU SAFETY-tmLATED EQtillWENT (including j

SOW differential pressure switch failure reporto ).

(Sen Table 1)

D.

L.ICENSEE IWENT REIVRTS (Unit 2)

(Noue) f5.

DATA TAIRJ1.ATI(M!i (tInit 2) 1.

Operating Data Report (See Table 2) 2.

Average Dally Unit. Power I,erol (See Tablo 3) 3.

Unit Shutdowns and Significant Power Reductions (See Table 4 r

y-y w

m-4-e w-p

C. N LE I (Unit 2)

MAJC] t.mivI MJLINTZNANCE TO SArrIT-EELAT E EQUIPMENT KORK RESOLTS AND EFFECTS IDEUEST

._COMLunni CAUSE OF MMJTNCTICN_

(ELSATE_I1J487_QcIRAILCM _. umau cr i vs ACnDN

~

L19577 High Pressure Brealer spring charging None Replaced charging anotor.

Core Spray Diesel motor Generator output breaker L19801 Control Room EVAC Drive motor Spurious alarms Replaced drive anotor.

anemonia detector OXY-VC165A 1

L

(!ro SOR. f ailures this month.)

t J

L e

rs

,~.

m

.s

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

i

\\

' TABLE 2.

j E.1 OPERATING DATA REPORT j

J DOCKET NO. 050 373 L y

UNIT LASALLE TWO DATE Jebruary 10, 1993 COMPLETED BY H.J.CIALKOHCK!

=OPERATIttG STA*nlS TELEPHONE (815)_357 6761._

'l gJ, REPORTIIIG PERIOD:

January 1993

.OROS? 1101RS IN ItEPORTING PERIOD:

744 r

2.

CURRENTLY AUTHol'IZED POWEH LEVEL (HWt):

3,32.1-

'{

HAX DEPENDADLE CAPACITY (MWe-Not):-

1,036 DESIGN ELECTRICAL RATING (MWe-Net):

1,078

-l

-3.

POWER LEVEL TO WHICH RESTRICTED (II* ANY) (HWe.tf e t )

=N/A I

.i e4.

REASON FOR. RESTRICT!Ot1 (IF A!IY)

Tills MOtlT11 YEAk TO DATE CUMULATIVIF 5.

HEACTOR CRITICAL TIME (110URS) 744.0

-:744.0 51,757.'5 6.

REACTOR DESERVE StalT1XMil TIME (HOURS) 0.0 0.0 1,716.9 i

s 7,

GENEHATOR Ctl LINE TIME (HOURS) 744.0

.744.0 50,800.4 8

Uh!T RESE11VE SilOTDOWN TIME (HOURS) 0.0 0.0

,0.9 o

'9.

THERMAL EllER0Y GEllERATED (MWHt).

2,402,397 2,402,397 152,417,284

[

10. ELECTRICAL EllERGY GEllERATED (Wie-Gross) 819,637 819,637

$0,720j946

11. ELECTRICAL EHERGY GENERATED (MWHe. Net) 792,884 792,884=

48,705,817._

12 REACTOR SERVICE FACTOR (%)

100.0 100.0

- 71. 2 !.

]

13. REACTOR AVAlfABILITY FACTOR (%)

100.0-100 0 73.6

14. UllIT GERVICE FACTOR (%)

100.0~

100.0; 69.9 U

715. UNIT AVAILID3LITY FACTOR g%)

.100.0 100.0 69.9 r;

-16.-Ull!T CAPACITE FACTOR (USING MDC) (%)

.10 2. 9 '.

102,9

_.64.7-4 7. UNIT CAPACITY FACTOR -(USING DESIGli MWo).

90.9' 98.9' 6h.2-1

18. UNIT FORCED OUTAGE FACTOR (%)

0.0 0.0 10.4-v

19. SHU'I7XMUS SCHEDULED UVER Tile NEXT 6 MOtiTHS (TYPE, DATE, AND DURATION OF;EACll)t

-No Outages Scheduled l

.20...IF--SilUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt

__ y 2

g. -

l

_t a

+

v

TABi l: 3

• E.2 AVERAGE DAILY UllIT l'CMElt LEVEL ( % -Net)

DOCTET 110. 050-373 Uti1T LASALLE TviO DA7E Tebruary 10, 1993 COMPLETED l'Y 11.J. CIALrtNSEI TELEPIICHIE (815)-357-0?01 REI' ORT ITRIODI Jeuuary 1993 DAY l'LH E.R DAY MME!!

I 1,017 17 1,083 2

1,038 1h 1,094 3

982 19 1,091 4

1,012 20 1,097 5

1,014 21 1,070 6

1,012 22 1,017 7

1,097 23 1,097 6

3,071 24 1,022 9

1,089 25 1,094 10 1,03'1 26 1,063 13 1,096 27 1,074 12

' 059 28 1,094 13 1,058 29 1,089 14 1,090 30 1,092 15 1,072 31 1,068 16 1,083

TARTE 4 E.3 UNIT SILTIDOMHS AND PM KwutatCES > 20%

(UNIT 2) l METHOD OF t m 1 ave YF.lutLY TYPE ben tAANG DONN AQGIS/COGENTS SEUGENTIAL DATE F: FORCED DOEATIGE THE REACTOR OR (LER/DVE 8 if NUMea IIneopt s._ S Q m K!L E fBOURS)-

EL% SON REDUCpG PON!3t agi;tlicablel (None)

SIDE (ARY OF OPERATIGI:

The unit ru. air.ed on-line at high pour throughout the month. Several =6r powar reductions were required due to systesa load and surveillance activities.

1 l-F.

UNIGIE REPORTING REQt!!HEMFXIT (UNIT 2) 1.

Safety Re11e[ valve operations-(None) 2.

ECCS System Outages (See Table 5) 3.

Changes t.o the Off-Site Dose Calculatina Manual (None) 4.

Major Changes to Radioactive Wast e Treatment Syntet.as n

(None) 5.

Indications of Failed Fuel Elements (None)

P

+.

+

+

f

.m (UNIT 2)

Table 5 r.3 ECCS System Outa.jes Notte The year end unit dat a. taan been ranovud frown thn _ outage number..

W7AGA NO.

WillMMT JMR11EE 0005 2E21-C001-Luarlcation 0011 2E51-F064 Achelnistrative cont rol 2E51-r091 0012 2DG01K Instrument en11brations.

0029 2DG01K Lubrication 0034 2E22-M010 Synchroscopa replacement 0018 2E22-5001 Lubrication 0040 2E22-5001 Spsing charging motor replacement t

a b

L l.

i-i-<

j up 1-7-v3 g

,M..i

+'

,e e'