ML20066D654

Monthly Operating Repts for Dec 1990 for LaSalle County Nuclear Power Station

ML20066D654
Person / Time
Site:	LaSalle
Issue date:	12/31/1990
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
ZCADTS-5, NUDOCS 9101150259
Download: ML20066D654 (24)

Text

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N) C:mm:nT;;alth taSalle County Nuclear Edis:n Station l

l f __._ :' RuralRoute #1, Box 220  !

\ ~' Marseilles, Illinois 61341 Teiephone 615/357 t3701 1

x%. I 1

January 10, 1991 l

Director of Nuclear Reactor Regulation United States Nuclear Regulatory Conunission Mall Station P1-137 Washington, D.C. 20555 ATTN: Document Control Desk Gentlement Enclosed for your information ic the monthly performance report covering LaSalle County Nuclear Power Station for December, 1990.

Very truly yours,

, f

1 G. J. Diederich Station Manager LaSalle County Station GJD/MJC/djf Encionute xc A. B. Davis, NRC, Region 11I NRC Resident Inspector LaSalle Ill. Dept. of Nuclear Safety R. Pulsifer, NRR Project Manager 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 W. F. Naughton, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle T. R. Novotney, INPO Coordinator, LaSalle Station

' . A. Hammerich, Regulatory Assurance Supervisor J . '4 Gieseker, Technical Staff Supervisor l

Staticn File D 209 901231 l

, F< f OCK C5000373 j

bht 25/5 '

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LASALLE NUCLEAR POWER STATION .

UNIT 1 MONTHLY PERFORMANCE REPORT DECEMBER 1990 COMMONWEALTil EDISON COMPANY NRC DOCKET No. 050-373 LICENSE NO. NPF-11  :

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s TABLE OF CONTENTS (UNIT 1)

1. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE l

.B. PLANT OR PROCEDURE CilANGES , TESTS, EXPERIMENTS, AND SATETY RELATED MAINTENANCE (50.59) I

1. Amendments to racility License or Technical Specifications

2. Changes to procedures which are described in the Safety Analysis Report

3. Changes to facility which are described in the Safety Analysis Report. j

4. Tests and Experiments not covered in the Safety Analysis Report l

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT i I

D. COMPLETED S AFETY-RELATED MODITIC;.TIONS E. -LICENSEE EVENT REPORTS P. DATA TABULATIONS 1.- Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions G. 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 Waste Treatment System

5. Indications of ralled fuel Elements 1

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i I. INTRODUCTION (Unit 1) i The LaSalle County Nuclear Power Station is a two-unit Iacility owned by Conunonwealth Edison Company and located near Marsellies, 1111nols. Each unit is a Bolling Water Reactor with a designed not electrical output of

1070 Megawatts. Waste heat is rejected to a man-made cooling pond using i the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was

.!' Commonwealth Cdison Campany.

Unit One was isnuted operating license number NPT-11 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 complied by Michael J. Clalkowski, telephone number (815)357-6701, extension 2427.

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11. . MONTit!J Rtl' ORT A. SUMMAltY Or Ol' ELATING EXPERIENCE (Unit 1)

Iley %11D2 EEent i

1 0000 iteactor critical, generator on-line at 975 MWE Iteoucing powet due to rod 50-47 drift.

0230 itecuced power to 750 MWC to pull rod 50-47.

? 0000 Increased power to 975 MWE.

1 1 2300 Increased power to 1130 MWE.

4 0000 l< educed power to 1000 MWE for CRD exercising.

1 1100 Ipercased power to 1130 MWE.

11 0100 Itecuced power to 050 MWE for rod set.

1200 incronced power to 1130 MWE.

2 !> 1000 iteduced power to 1000 MWE for system load.

p 1900 Increased power to 1104 MWE. ,

i 2h 2100 iteduced power to 650 MWE to accomplish rod moves and i to take the turbine driven reactor feed pump off line.

30 1100 Increased power _to 1130 MWE.

7' 31 2400 Reactor critical, generator on line at 1130 MWE.

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PLANT OR PROCEDURE CHANGES, TESTS, OR EXPERIMENTS (50.59) (Unit 1)

B.

1. Amendments to the Pacility License or Technical Specification.

Primary Containment Peneration Overcurrent Protection

2. Changes to procedures which are described in the Safety Analysis Report.

a) LaSalle Special Test LST-90-133, " Control Room HVAC System (VC) Air Flow Data Collection", was approved to reposition the balancing dampers on Control Room / Auxiliary Electric Equipment Room HVAC System. The purpose of this test is to take data on the VC System and input to engineering.

This test consists of the data collection portion of approved LST-90-054. This test will only change the flowrate to ensure the control room meets the requirements of Technical Specification 4.7.2.d. The safety evaluation concluded that the temperature in the control room will be maintained between 55 F and 1040 F to ensure that the equipment is maintained operable.

3. Changes to f acility which are described in the Safety Analysis Report.

a) LaSalle Temporary System Change (TSC) 1-879-90 was performed to bypass Division 1 125 VDC Dattery Charger DC Voltage Lo/ Failure Alarm due to chattering, causing a nuisance alarm. This alarm is discussed in UFSAR 8.3.2.1.1. Even though continuous ind)"% tion of this alarm condition is lost during the time that it is bypassed, charger voltage indication is still available in the control room and recorded shiftly. The Safety ,

Evaluation concluded that there are redundant alarms available (DC Bus Undervoltage) which would also alert operators to charger problems and lifting of this alarm lead in no way affects the ability of the charger to perform its design function.

4. Tests and Experiments not described in the Safety Analysis Report.

(None)

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

(See Table 1)

D. COMPLETED SAFETY-RELATED MODIFICATIONS.

(None)

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C TABLE'1 (Unit 1)

. MAJOR CCERECTI7E MAIhraANCE TO .

SAr r u-RELATED EQUIPMDTI .

WORK REQUEST' RESULTS AND. EFFECTS EUMBER; COMPONENT CAUSE OF MALFUNCTICN ON SAEE PLANT CPERATION CORRECTIVE ACTION LG4237 Main Steam Line Eigh' Switch Switch out of calibration Replaced switch Differential Pressure Switch LO4271 .RCIC Pump Suction Contactor- Erratic operation Replaced contactor Valse [

r i

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(No SOR failures .this month)

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E. LICENSEE EVENT REPORTS (Unit 1)

, LEILHlunktI DAlt DEECL1911gn '

90-013-00 12-07-90 30 day missed sury, testing of Eli IDt Vent Valves due t.o procedure deficiency.

[

90-014-00 12-2$-90 --30 day loss of Unit 1 250 Volt Batterles/RCIC

i. System. -

T. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 3)

2. Average Daily Unit Power Level (See Table 4)

3. Unit Shutdowns and Significant Power Reductions (See Table b) i -

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f.! OtllAllNG DATA LIP 0kt DUCI,fi NN 050373 l UNIT LGALLI DN[

1 14t[ JANUARY (0,19h I

CDNPLilfD IV LJ. CIAll:0WLK1

!= 1[LLh0NE (It$13574761

! OPERAllNG!.1ATUS l

i. ; R[tuht!NG l'LL10h DCCIMFfk1990 GR0ts HOURS IN t[t0KllNG PEkl0D 744

]

L .2.~CURRENTLYAutH0t!![DPOW[kLLVfL(NWtU 3,323 hu IttIW!) CA4tlif(MWeNet): 1,036 1451GN [LEC11'ICAL LAi!NG (MWe-Neth 1,070 l

i- 3. 00WCR LlVll TO WHICH t($1RICTIL III ANY) (MWi+Nd h (NDN[)

j 4 RLASONDFDRttC!Eltil0N(ifANYh +

i, ttPOR11NGlit1DD!>ATA i

! TH15NDNTH YEAR 104 Alt CUMULATIVE i- -5 REACTOR tRITICAL TIME (HOLEB) 744.0 C,413 40,609.4-3 6,;RIACTORt[EERVESHUIDOWWf!ML-(H00l$1 0.0 0.0 1,641.2

t CENTRA 10R DN-LINE TIME Ot00k5) 744.0 B,310.5 39,740.8

, 'O. 'UNii REB (RVE $HulDOWN llNE (H30kS)' O.0 0.0 1.0 h 9,'THERMALINERGYGlNERAftD(HWHtt 2,409,000 26,370,C33.4 114,203,601 10, [L(CTRICAL' [NIRGY GENChAl[b (MWHa GtMO B24,000 0,934,747 30,003,208 f 796,6E3 0,637.300 '36,370,082

[ -1.1.[LEC1RICALENERGYf.ENERAlfD(hWHeNet)

12. RfAC10R SiRVICE FACTOR (%) 100.0. 96.0 66.1

13. ktACTOR AVAILAlIL11Y fACfDR (%) 100.0 94.8 60.B 14, UNIT' OtRV!CC FAC10t (%) 100.0 95.1 64.7 15.UN!1 AVAIL!BIL11YTAC10R(2) 100.0- 95.1 64.7 r . th UNii CAPACITY FACIDR (USING bbC) (D 103.4 95.2 57.2 i

-l 117. UNIT CAPAC11Y FA010R (DSING DESIGN HWe) (D 99,3 91.5 55.0 -

L -10,UN11TORCEDOUTACLFACTOR_(U 0.0 - 1.6 - 8.5  !

(

-19, SHulDOWNS SCHEDULED DVCR THE NEXT 6 MONTHS-(iYPE, DAit. AND DURAi!0N Of EACHh

. RefuellM (LikO4)-02/16/91 10 WEEKS 2L lf SHulD3WN AT IND Or REPORT llL100, E51thATED DATE Or SinRTUP; i

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! TAlti 4 UNifLMAMION(

l f .2 AVERAi,( LA!LY UNIT P0kTk LIVil N-Net) LAf( JANU6LY lo, 1991 C0tL[filt il t .). CIAlfNi4!

l TElli'HMt (015)*357 f761 i

4 l I l e mon stuors 0tet utt i m 1

g LAY 10WER pef tWik I t

l l:. .1 916 17 i,09$ i L

2 1,020 10 1,095 3- 4,100 19 i,00E p -4 . $ , Der 20 1,m

j s i .m ' 2i i ,07r 6 1,099 22 1,073 l r

!- 7 i,096 23 1.071

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$ t,096 ?4 - 1 ,071 -

P 9 t,096 2$ 1,0$7 10 t 004' 26 1.014

, - - 1

i L ii- t,026 27 i,070 /[

1 t l -i 12 .1,099 20 t,020' i) 1,097- 29 929 4  ;

i 14 : 1,0f? 3( i,007 15 -1,091 31 1,109  !

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TABLE: 5 T.3 UNIT deva.745 AND PCWER RwAalCNS > 2% .

(Un.it 1) ,

METECD OF CCERECTIVE Seu uING DCNN ACTIONS /C N ,

TEARLY TYPE

-T: FORCED DURATION THE REACTOR CR (LEE /DVR 5 if SECUENTIAL DATE applicable)

(EOURS) EEASCU EEEUCING M*ER NUMBER (YTMMDD) S: Sthe_uULED (None)

SUMMARY

OF OPERATION:

The Unit remained on line at high power throughout the month. Several minor power reductions were required due to low grid demand, routine surveillances, and Rod 50-47 Drift.

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G. UNIQUE REPORTING REQUIREMENTS (Unit 1) l

1. -Safety / Relief valve operations i VALVES NO & TYPE PLANT DESCRIPTION DATE AC1VATED ACTUAIIDH C2HDIT10H or EyINT i i

(None)

2. ECCS System Outages (See Table 6)

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

4. Major changes to Radioactive Haste Treatment Systems.

(None)

5. Indications of ralled ruel Elements.

(None) r l

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.* (Unit 1)

. Table 6 0.2 ECCG System Outages tiote s - The year and unit data has been removed from the outage number.

OTIAGE_1101 LQU1EllEtil P11EEDSI (U-0) 420 ODG023B Inspection of check valve.

424 ODG023A Inspection of check valve.

425 ODG01K Routine calibration and surveillances

-(U-1) 607 1DG01K Lubrication.

694 1E12-r047A Administrative control.

695 1E12-r047A Perform surveillance-LES-EQ-112.

701 1E51-r064 Administrative control.

-706 1E12-r007A Perform survelliance LES-EQ-112.

714 1E51 C003 Perform inspection.

715 '1E51-r010 Perform surveillance LES-EO-112.

ZCADTS/5+

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!.ASALLE NUCLEAR POWER STATION UNIT 2 MONTIILY PERFORMANCE REPORT DECEMBER 1990 COMMONWEALTl! EDISON COMPANY NRC LOCKET NO. 050-374 LICENSE NO. NPF-18 1

ZCADTS/7

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TABLE OF CONTENTS (Unit 2)

I. INTEODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE ( 50. 59)

1. Amendments to Tacility Lacense or Technical Specifications

2. Changes to procedures which are described in the Safety l Analysis Report.

3. Changes to f acility which are described in the Safety Analysis Report. q

4. Tests and Experiments not covered in the Safety Analysis Report.

C. MAJOR CORRECTIVE MAINTENANCE TO SATETY-RELATED EQUIPMENT D. COMPLETED SATETY-RELATED MODITICATIONS

)

E. LICENSEE EVENT REPORTS T. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

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

1. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Teiled Tuol Elements '

ECADTS/7

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1. INTRODUCTION (Unit 2)

I I The LeSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1070 Megawatts. Waste 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 Cornpany.

l Unit Two was issued operating license number NPT-18 on December 16, 1903. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.

This report was complied by Michael J. Cialkowski, telephone number (016)357-6761 extension 2427.

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, II. MONTHLY REPORT A.

SUMMARY

OF OPERATINO EXPERIENCE (Unit 2)

Day Ilme Event 1 0000 Reactor critical, generator on line at 1135 MWE 4 2330 Reduced power to 1070 MWE for CRD exercising 5 1000 Increased power to 1135 MWE 7 2100 Reduced power to 850 MWE for lubrication of the "B"

-Turbine Driven Reactor Feed Pump and to place the Motor Driven Reactor Feed Pump on line 8 0600 Increased power to 1000 FME 10 0200 Increased power to 1135 MWE 12 0300 Reduced power to 1050 MWE for CRD exercising and insertion of FCL rods 1000 Increased power to 1135 MWE 13 1130 Reduced power to 260 MWE due to leakage in the "23C" Low Pressure Feedwater Heater 15 0155 Generator off line 1300 Reactor suberltical 19 1300 Reactor achieves criticality

-20 1819 Oenerator on line 21 2300 Increased power to 500 MWE 22 0600 Increased power to 1013 MWE 0900 Reduced load to 900 MWE due to "A" Turbine Driven Reactor Feed Pump Lube Oil Pump fire

-1500 Increased power to 1013 MWn after transfer of the "A" Turbine Driven Reactor Feed Pump with the Motor Driven Reactor Feed Pump 26 0100 Reduced power to 800 MWC for weekly surveillances, monthly surveillances and for final rod set 2100 Increased power to 1120 MWE 2300 Reduced power to 1000 MWE due to a high level alarm from the "21A" Low Pressure Feedwater Heater 30 0200 Increased power to 1130 MWE 31 2400 Reactor critical, generator on line at 1130 MWE ZCADTS/7

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• PLANT OR PROCEDURE CHANGES, TESTS OR EXPERIMENTS (50.59) (Unit 3)

. . D.

1. Amendments to the Pacility License or Technical Specification.

Primary Containment Penetration Overcurrent Protection. I

2. Changes to procedures which are described in the Safety Analysis Report.

(None.)

3. Changes to f acility which are described in the Safety Analysis Report.

(None)

4. Tests and Experiments not described in the Safety Analysis  !

Report.

(None)

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

(50e Table 1)

D. COMPLETED SATETY RELATED MODIr1 CATIONS.

(None)

E. LICENSEE EVENT REPORTS (Unit 2)

LER_itumhet DAtn Desctlption 90-012-00 12/15/90 30 day missed tech spec on H2 Analysers 90-013-00 12/17/90 30 day MSIV isolation during performance of LIS-MS-406 90-014-00 12/22/90 30 day 2A Turbine Driven Reactor reed Pump fire F. DATA TADULATIONS (Unit 2)

1. Operating Data Report.

(See Table 3)

2. Average Daily Unit Power Level.

(See Table 4)

3. Unit Shutdowns and Significant Power Reductions.

(See Table 5)

ZCADTS/7

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C TABLE 1 (Unit 2) .

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MAJOR CORRECTIVE MAINTENANCE TO SAs r u-REIJLTED EQUIPMENT ,

LiORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LOO 567 Hydraulic Control Filter leaking None Replace filter Unit 34-39 LO2677 Hydraulic Control Withdrawal valve 122 Degraded cantrol rod operatica Rebuilt withdrawal valve Unit'46-07 122 LO4502 LPRM 40-09B Power supply None Replaced power supply t

e (No SOR failures this month) l 4

ZCADTS/7

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i TARE 3 f.1 ~ CITMfDL IATA RETW1 DOCKET NO, 050-374 041T LA%1E i@

DATE A U S,Y 10; 1971 C0hFtE1[0 ?Y M.J. CIAL W 2K1 TELEF M (815)-357-6761 V .

, OfGATING STATUS p"

al. -REPORID0 PERIOD DfCEMPER1990 GROSS Km$ IN PDORTIE PERIOD. 744 p

2. LVRD(ILY AUTWA! ZED FWEL 1.EVEL (NO: 3,323 MAX DEPEND f/fACITY (Ne-Net): 1,636

=IESIGN ELEClRIC/t RATING (MWrNeth 1,078 :

3. _1%9 LEVEL 10 UHICH RESTRitiLD (If ANY) (MWe-ikt): 00 0 ]

1 l- 4. ;EEASONS FOR RESTRICTION Of (MD l

Fif M i M FERIOD CATA J

N THIE NONTH YUkT0-DATE CUddLATIVE

{

-5. REACICR CP'TICAL TIME '(h00kS) 64 M 6 343.1 36.490.2 l - .

6. REACTOR RESERVE f!fJt00VH Tlit UtiURS) 04 0.0 1 ,716.9 -  :

--70 CE6U;ATOR ON-LINE 11hE.dQlRS). 607.5 6,164,1 35,647.2 i

[

l B. UNIT _ PISERr "Hl.flDOWN TIME OR11S) 0.6 0.0 0.0 n -

j ' 9. THERNAL ENERGY GOiERATED ( O D - .1,740,166' 19,10,127.2 105,439ji?S j

10. FLSCTRICAL-ENER5Y GENERA!G (4 4 -Gro w ) 395,234 6,43?d06 34,863,832 7 a

g-11[ ELECTRICAL DGGY GENEi#0; thW-ket). $73,540- 6,163,705 33,4j9,090 u_

b il2iREAC10RSIWACEFADOR 'J .- B7.-i - 77.4 67,1 1 e1

_-13.-REtciDR AVAILABILITY FACD< (%) :87.1 72.4 :70.3 li4fLHIT SERVICE Fh' TOR (%) -C).7 70.4' 65.9

. 15. UNIT AVAILIDiLITY FACCR W 81;7: 70.4 65.9

.._ S UNIT CFACNY FACTOR (UGDC Ntn (%) 74.4 -68.1 -59.3

-i

i. 17. (Hlf CAf%Ilf FMICR (U31% tfhlLN M1M (%) : 71.5 .63.5. 57.0 {

18. (PHT FORCED OUTAGE-FACIOP (%) ' 16.3' 74- ' 14.9 -

[- . - . - . _ _ _

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h 19. Sh0TDCWS SCHEDULED OVEP 1)E NDT 6 h0MHS (TYFL DATE, NiD 00 RAT 10N OT.EACH):

' (60ND 20 IF SHJiDCUM AT ENT) 0F REFET '4RIOD, ESlihMED DATE OF STARIUP.

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.o"s DOCKETNO' 050-374 -!

- TA8LE 4. .UNITLASALLETWD- j

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4.2 . AVERA;E DAILY t*ll POWER' LEVEL (MWe-Net) 'DATE JANUARY 10,1991, COnPtETED BY M.J. CIALK0WSKI . -

TELEPHONE (015)-357-6761 0

-REPORTPfRIOD: DECEMBER 1990

_ DAY -F0W!R DAY POWER

. ....... ......... . . . . . . . . . . . . . . . . . (

-; ' .1 1,097 - 17 -12

, 2 1,099 to 12 3 1,191-. 19 -12

.j ..

t !90 20 21 5 t.W - 21 349 .

-6 6,h 22- 091 -

4

-7 -1,61 23 - 951 GL 949- 24 -953- :c 4

l 9' 1,001- _-- 25 =?$4

-L10 . ~1,090 -961 :t 11_ l.,099 - 27 965'  !

12 =1,085 28 . 974'.

213: '552 - 29 .1,012

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_14l  : 200 30 t ,094 - ,!

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15 - .7 3i . - g ;o94 - t

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TABLE 5  ;

F.3 UNIT SHUTDOWNS AND POWER REDUCTIONS >20%

(UNIT 2)-

METHOD OF CORRECTIVE YEARLY TYPE SHUTIING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACIDR OR (LER/DVR S'if ,

NUMBER (YYMMDD) S: SCHEDULED (HOURS) REASON PJEDUCING POWER applicable) 14 901213 .. F 0.0 A 4 Power level reduced due to major tube ' leaks in the 23C Low -Pressure Heater 15 901214 F O.0 A 4 Continuation' of power -

level reduction due to tube leakage ,

16 901215 F 135.5 A 1 Repair of tube leais in the. 23C Low Pressure Heater a

SUMMARY

OF OPERATION:

The unit remained on line at high power.throughout.most the month. Several minor power reductions.were required due to routine surveillances and turbine driven reactor feed pump work. The unit experienced a forced outage due to leakage in the "23C" Low Pressure Feedwater Heater. The outage started on. 12/15/90.and the unit was returned to service on 12/20/90.

ZCADTS/7

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• 0. UNIQUE REPORT?,HG REQUIREMENTS (Unit 2)

1. Safity/ Relief- Valve Operations VALVES NO & TYPE PLANT DESCRIPTION DAIE AC211ATED- ACIMAT10Rfi CONDITIQtl QLEV ENT (None)

'2 . ECCS Syste.n Outages '

(See Table 6)

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

(None) 4.- Major changes to Radioactive Waste Treatment Systems.

(Hone)

5. Indications of ralled ruel Elements.

(None)

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. t*, (Unit 3)

• Table 6 0.2 ECCS System Outages '

Note: The year and unit data has been removed f rom the outage number, GlTAGE_llCh EOUIPMENI ITff.Q$E 1804 2E51-C004 Inspection per Procedure LES-DC-104 1805 2E51-C005 Inspection per Procedure LES-DC-104 Replaced motor heater 1807 2E51-F360 Replaced motor in 11mitorque 1809 2E51-C002 Lubricate and change oil 1820 2E51-F064 For completion of on-site review 2E51-F091 190-043 1887 2E22-S001 Perform calibrations i l

ZCADTS/7 1

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