ML20065R119

Monthly Operating Repts for Nov 1990 for LaSalle Nuclear Power Station Units 1 & 2

ML20065R119
Person / Time
Site:	LaSalle
Issue date:	11/30/1990
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9012180214
Download: ML20065R119 (27)

Text

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r,. Crmm2nw:alth Edissn 4- yp' LaSalle County Nuclear Station Rural Route #1, Box 220 '

. Marseilles. Illinois 61341 A Telephone 815/357 6761 December 10, 1990 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission

. Mall Station P1-137 Washingtong D.C. 20555 ATTH: Document Control Desk Gentlemen

~ Enclosed for your'information'is the monthly performance report covering LaSalle County Nuclear Power Station for November, 1990.

Very truly yours, O _

G. J. Diederich 6/ Station Manager LaSalle County Station GJD/MJC/djf Enclosure xc3 -A'..D. Davis, NRC, Region.III NRC Resldent Inspector LaSalle Ill. Dept. of Nuclear- Safety R. Pulslfer,'NRR-Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records'Conter D. : R. Eggett, NED J. E. Kuskey,.GE. Resident T.EJ. Kovach, Manager of Nuclear Licensing W 'W. F. Haughton,- Nuclear Fuel Services -Manager C.-F. Dillon, Senior Financial Coordinator, LaSalle T.'R. Novotney, INPO Coordinator, LaSalle Statlon T. A. linmmerich, Regulatory Assurance Supervisor II J. W. Gleseker, Technical Staff Supervisor i St.ation File 9012180214 901130 PDR ADOCK 05000373 .

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LASALLE NUCLEAR POWER STATION UNIT 1 i

MONTHLY PERFORMANCE REPORT NOVEMBER 1990 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l

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. t TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A.

SUMMARY

' Or OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTEN ANCE ( 50. 59 )

1. Amendments to Facility 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.

4. Tests and Experiments not covered in the Safety Analysis Report C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. COMPLETED SAFETY-RELATED MODIFICATIONS E. LICENSEE EVENT REPORTS F. 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 Failed Fuel Elements ZCADTS/5

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, i I. INTRODUCTION (Unit 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 Mater Reactor with a designed net electrical output of 1078 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 Company.

Unit one was issued operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved on .!une 21, 1982 and commercial power operation was commenced on January 1, 1984.

This- report was compiled by Michael :1. Cialkowski, telephone number (815)357-6761, extension 2427.

-ZCADTS/S

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,II.- MONTHLY REPORT A.

SUMMARY

OF OPERATINO EXPERIENCE (Unit 1)

Day Time Event 1 0000 Reactor critical, generator on-line at 1120 MWE 4 2330 Reduced power to 1080 MWE for system load.

5 1000 Increased power to 1120 MWE.

2230 Reduced power to 1080 MWE for CRD exercising. l 6 0600 Increased power to 1120 MWE. I 13 0100 Reduced power to 850 MWE for monthly surveillances.

1000 Increased power to 1120 MWE.

14 0130 Reduced power to 740 MWE for scram time testing, rod set and strong back removal.

1300 Increased power to 1120 MWE.

19 0130 Reduced power to 1050 MWE for condensate pwnp transfer.

0800 Increased power to 1120 MWE.

20 0200 Reduced power to 850 MWE for system load and for CRD exercising.

1000 Increased power to 1120 MWE.

^

2400 Reduced power to 850 MWE for system load.

21 1100 Increased power to 1120 MWE.

22 0200 Reduced power to 850 MWE for system load.

23 2000 Increased power to 1120 MWE.

26 2300 Reduced power to 2000 MWE for system load.

27 1000 Increased power to 1120 MNE.

28 0300- Reduced power to 900 MWE for system load.

1300_- Increased power to 1120 MWE.

29 1100 Reduced power to 803 MWE due to Division 1 battery charger problems.

2100 Increased power to 1000 MWE.

30 3730 Increased power to 1120 MWE.

2400 Reactor critical, generator on-line at 960 MWE reducing power to 750 MWE for CRD problem.

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D. -PLANT OR PROCEDURE CHANGES, TESTS, OR EXPERIMENTS.(50.59)L(Unit 1)' .

1 1.- Amendments to the racility License or Technical Specification.' i (None): _

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

a) LaSalle Operating . Procedure LOP-WF-30, " Transfer of ricor-Drain Process System Tank Water to Equipment Drain -: and Waste Collector (WE) Tank (1WE03T)" was' used to transfer-evaporator head tank water to the 11guld radwaste sample tank to make use of the 30,000 gallon volume of 1WE03T to hold water; while'WE filter gasket repairs were underway.

The safety function of redwaste is to limit radioactive concentrations released to the environment. Prior- to going to the head tank, the water would have- been processed through an evaporator. Af ter getting to WE, it will be sampled and routed accordingly. The Safety Evaluation concluded that redwaste is not the basis for any Technical Specification margin of safety and the radioactive effluent dose limits of Technical Specification 3/4.11.2.3 still remain valid.

b) LaSalle Special Procedure LLP-90-075, " Auxiliary Building HVAC (VA) Purge", was performed to allow the. purge of the Auxiliary Duilding office areas without endangering the required differential pressure criteria of the control room envelope. This change allowed cool outside air into-the office spaces -while the HVAC compressor is being-repaired.' The Safety Evaluation prepared for. this test-

-stated that ' the VA system is non-safety and its failure-doesn't affect any safety systems. VA normally uses outside air for makeup.

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

i

-a). LaSalle Temporary System Change (TSC) 1-766-90 was-

-performed to defeat Drywell Drain Sump fill up rate alarm,-.

due - to having a faulty transmitter. on its flow = element, -

which was causing a -nuisance alarm. The unidentified leakage-totalizer will remain operable for sump monitoring and identified leakage . technical specifications will not-i be affected. The safety evaluation concluded that the-i- alarm- circuit is non-safety and does not affect the

(. consequences.of an accident.

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

p- (None)

L U

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

i SOR difforential pressure switch Iallure reports).

(See Table 1)

D. COMPLETED SAFETY-RELATED MODIFICATIONS.

(None)

'ZCADTS/S l~

C TABLE 1 (Unit 1)' , ,,

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT .

WORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTICN LO3574 IVYO4C 74 Relay None -Replaced 74 relay LO3582 1A Main' Steam Line Control Module None Replaced control module Radiation Monitor LO3601 APRM "F" Power Supply Improper voltage to APRM Replaced power supply LO3662 Division 1 Post Regulator, cell Erratic oxygen samples Replaced regulator, cell, LOCA Oxygen Monitor amplifier board LO3924 Control Rod Number Pilot solenoid valves None Replaced pilot solenoid 50.47 valves 4

4 (No SOR failures this month)

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r- .i E. LICENSEE EVENT REPORTS (Unit 1)

LER_IlmnhtI DAlt DIECLiption (NONE)

F. 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 5) 1 ZCADTS/5

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1W.E 3 D.1 OrtRAT M, DATA RD ORT DUtRET NO. 050-373

. [ NIT LABNil OfE DATE MCEMICR 10,1W0' 1 00 METED ff M.J. CItGOLSKI - ,j TELEf4DE '815)-357-6?61

. IRAATlHG EIATLS jf. f90 MING fir 100: NDVID ER ,19y0 GRDM H0$$ IN PLPOPTlif, ffR10D' 720 I i

?. - CURREN7LY AUTW.RIIED F1MER LFVEL ("adt)- 3.323 MAY KT1% CTACITY (We-Net): 1,036 CESIG't ELEC1RICAL RAT!0 (MWH&th 1,078 ,

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3. POWER LEVEi.10 WHICH RE9TRICTED (If ANY) (IMe-Net): Ol04E) 4, REASONS FOR PESTRICTION (!F ANY).

RE M Tit 6 PERIOD DATA THIS MONTH YEAR-TO-DATE COM.ATM

$. kEACTOR CRITICfL TIME GiDUnS) 720.0 7,731.3. 39,065.4

, 6, REACTOR RESERVE SiUIDOWN TIME ODURS) 0,0 0.0 1,641.2

.7. GEKRATOR ON-LINE 11ME HOURS)- 720.0 7,586.5 39,004.8

-8. LNIT RESEPVE SiUlDOW TIPC DOURS) 0.0 0.0 1.0

39. THERNAL EMIGY CDERATED (Wit) 2,317,704 -23,961,033.4 111,794,601

' 10. ELECTRICAL ENERGY COERAIS)lWHe-Gross) 78?,091 .B,110,747' 37,179,288 l 11. ELECTRICAL DERGY CU6.RAlED (Nie-Wt) 764,t00 7,843,697 35,573,399 l 12.REACTORiERVICEFACTOR(%) 100.0 96.4 65.7-j 13. REACTOR AVAILAB1LITY FACTOR (if '100.0 96.4~ 60.4' 1:

l.  : 14. UNIT SERVICE FACTOR X%) 130.0 94.6L 64.3~

15. UNIT AYMLIBlLITI f ACTOR d) J100.0 94.6 64.3

16. UNIT Ct#ALITY FACTOR (LEING h:0.(D - 102,4 94.4: 56.6

17. LHIT C/I ACllY FACfDR (USIK, DESIGN h!M (%)-- 98.5 90.7 54,4.

10. tNIT FORCED OUI ACE FACTOR (%). 020 1.B. 8.6 192 DiUIDOJG EDEDULED DVER TK HCXT 6 h0NTHS (TYPE, DATE, AND MATION OF EACH):

L -Refacijng--(L1R04) 02/tl/91 0 Weeh L

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20. IF 901N4H AT END OF PHORT FERIOD, ESTIMATED DATE OF STARTUP:

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j T ARE 4 tNIT LASA!LE Ort j . - F.2 AVERF.0 MILY 13!11 FTER LEVEL U@-Net) IM E K CEn!(R 10,1990 l CONFLETED BY M.J. ObtGV3KI -

n TELEh&E (015)-357-6761 I -l p <

l REPORI fD10D: 10/Eh!{R ,t900 i l- i

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! i i,09, 17 1,073 c-J .:

2 1,093 10 1,093 .

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j l -~ 3 1,073 19 i E3  !

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.4 i,091 20 1,043 '

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'6 1,037 22 e48 i

.7 i:,075 23 1,010

.0 1,094 24 1,094 1 9 .1493 25 t,093 10 .1,094 26 1,085 I

.ii i l047 ' 27 1,07?

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. 12 i,0?3 't i,057 j

I3- 1,005 29 922 14 996 30 i,037 -I

'15 1,076 31~

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TABLE 5 . .

F.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(Unit 1) .

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METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR R if WUMBER (YYMMDD) S: SCHEDULED (EOURS) REASON REDUCING PO'ER applicable) 1 8

(None) 4

SUMMARY

OF OPERATION: s The Unit remained on line at high power throughout the month. Several minor power reductions were required due to low grid demand, routine surveillances, Division 1 Battery Charger and CRD problems.

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l G. UNIQUE REPORTING REQUIRCHENTS (Unit 1)

1. Safety / Relief valve operations VALVES Nr ' TYPE PLANT DESCRIPTION DAIE ACTUATED A' ,o ATION CONDITION OF EVENT (None) 2 JCCS System Outages (See Table 6)

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

4. Major changes to Radioactive Weste Treatment Systems.

(None)

5. Indications of failed Fuel Elements.

(None) l ZCADTS/5 l

(Unit 1) c Table 6 G.2 ECCS System Outages He' e s- The year and unit data-has been removed from the outage number.

DUTAGE No. EQQ1ftirJiT PURPOSE (U-0) 377 ODG01K Lubrication (U-1) 601 1E12-C300C Lubricate pump coupling IE12-C300D 603 1E12-r093 Administrative 606 1E12-F026A Perform Surveillance LES-EQ-112 608 1DG035 Perform Surveillance LES-EQ-112-609 1E12-F026A Valve inspection 614 1E21-C001 Change oil 616 1DG035 Valve inspection 617 1E21-C001 Megger Motor 618 1E21-C001 Perform LES-GM-129 623 1DG035 Valve inspection 625 1E12-r026A Valve inspection 632 1E12-C300D Perform LES-GM-105 -

642 1E51-C004 Perform LES-DC-104 1E51-C005 643 1E51-C003 Lubricate coupling

'644 1E51-F360 Remove turbine govenor 660 1E22-D300 Strainer inspection ZCADTS/5+

__ _ _ _ _ . . _ _ . . _ . _ _ _ . _ _ _ _ _ _ _ . . , _ = . . . _ _ _ . . _ _ _ _ . . . . . .

LASALLE NUCLEAR POtiER STATION UNIT 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1990 COMMONWEALTH EDISON COMPMiY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7

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TABLE Or CONTENTS (Unit 2)

1. INTRODUCTION II. REPORT A.

SUMMARY

.Or OPERATING EXPERIENCE B. PLANT OR PROCEDURE CNANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTEN ANCE . ( 50. 59)

1. Amendments to Facility License or Technical Specifications

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

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

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

C. MAJOR CORRECTIVE MAINTENANC2 TO SAFETY-RELATED EQUIPMENT D. COMPLETED SAFETY-RELATED MODIIICATIONS E. LICENSEE EVENT REPORTS F. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Redections 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 Failed Fuel Elements l

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I. INTRODUCTION (Unit 2)

The LaSalle County Nuclear Power Station is a two-unit f acility owned by Commonwealth Edison Cornpany and located near Marseilles, Illinois. Each unit is a Bolling Water Reactor with a designed net electrical output of 1078 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 Company.

Unit Two was issued operating license number NPF-18 on December 16, 1983. Initial critica11ty was achieved on March 10, 1984 and commercial power operation was commenced r>n June 19, 1984.

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

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, 11. MONTilLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2) hay Ilme Lunt 1 0000 Reactor critical, generator on-lino at 1130 MWE 4 0300 Reduced power to 850 MWE for heater bay work 1600 Increased power to 1130 MWE 13 0200 Reduced power '.o 1070 MWE for condensate booster pump alignment 0800 Increased power to 1130 MWE.

17 0100 Reduced load to 820 MWE for feedwater pwnp work and rod set.

0330 Increased power to 980 MWE (holding power level due to feedwater pump problems) 10 1600 Increased powr to 1130 MWE 21 0030 Reduced power to 1060 MWE for CRD exercising 1300 Increased power to 1130 MWE 28 0130 Reduced pou r to 950 MWE for monthly surveillances 1100 Increased power to 1130 MWE 30 2400 Reactor critical, generator on-line at 1130 MWE ZCADTS/7

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

, 1.. Nnendments to the Focility License or Technical Specification. l (None) 2.- Changes to procedures which are Jescribed in the Safety Analysis R? port.

(None.)

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

(None)

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)

E. LICENSEE EVENT REPORTS (Unit 2)

(None)

F. DATA'TALULATIONS (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

ss C TABLE 1. (Unit' 2) , ,

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MAJCR CCERICTIVE MAINTENANCE TO SArr.,u -RELATED EQUIPMENT -

RESULTS AFD EFFECTS WORK REQUEST CORRECTIVE ACTICN COMPONENT ' CAUSE OF MALFUNCTICS Ct3 SAFE PLANT OPERATION NUMBER .

Pressure switch Inaccurate acctunulator Replaced pressure switch LOO 694 CRD HCU Accumulator preswura readings Firing board Pwer reduction per Replace firing board LO3897 'Div. I 1257 Battery Charger Tech Spec Pump motor space heater Motor oil improper temperature Replaced space heater L91250 RCIC Baro vacuum Pump

-(See attachA 3OR failure report) 1 ZCADTS/7

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j SOILdp_. Switch railur e_D at.a_..She e t )

I Equipms.::c Piece Number 2E12-N010fA Model Number: 103-AS-B202-NX-JJTTX6 Serial Number: 85-6-3587R Applieation Reta.iital_Re.at_RemRYal RinimwiLricw_ Switch Date and Time of Discovery: 10_L2.5.LEQ 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br /> Reactor Mode Run Power Level: 1201 Calibration Tolerance: 23.6-22.4"WC Nominal Setpoint: 23.0"WC Action Limits: <24.7 or >21.3"WC Reject Limits: <17.7 or >28.3"WC Technical Specification Limit id.Q"WC As Found Setpoint: "WC Date and Time of Return to Service 12426/90 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> Model Number of Replacement Switch: 103As-B202-NX-JJTTX6 Serial Number of Replacement Switch: 89-2-3874 DVR Number: 01-2-90-0'2 Causes D.uring routine calibraticn. praggure differential switch 2E12-11010E1L ggtpnint was f ound to be erratic and not repeatable. Durina inspection of the gwitch. slight corrosion was fqund.cn the bearing and shaft. The cause of the failure was de.telmingd to be due to corrosion induced shaft binding.

Corrective Action: The switch was replaced, qalibrated and returned to antvice. The._Iailed.Awitch_na .diaAnanntic1AnLinanented.

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SOILdp_ Swit clLEa ilure_Dat.a_ Sheet i

Equipment Piece Number 2131-No10B 14odel Number 102 - AS -B 3 0 5-NX-JJUfd Serial Numbert 85-1-2446 Applieation: Main._ Sic antline_hislLFloLMS1Y_.lanla_tio n Date and Time of Discovery: 11I22110 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br /> Reactor 14 ode s nun Power Levels 100%

l Calibration Tolerance: 102-104 PSID Nominal Setpoints 111 PSID Action Limits: <1tL.2 or >107. 8 PSID Reject Limits: <94.8 or >111.2 PSID Technical Specification Limit: lli PSID As Found Setpointi 121 PSID Date and Time of Return to Service: 11/27/90 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> 14odel Number of Replacemenit Switch: 102-As-B305-NX-JJTTX6 Serial Number of Replacement Switch: 86-10-562 DVR 11 umber: 01-2-90-073 Cause Instrument setpoint drift.

! Corrective Action: The switch was repla,qe d. calibrated and returned t_q agIvice. The failed switch was disasmembled and inspected. Internal inroection of the switch was performed with no abnormalities found.

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EDILdpJiwit clLTAilur e_ Data _0 he e t Equipment Piece 11 umber : 2 E 31 -11011B 14odel 11 amber: 102-AS-403-NX-JJT1FJ Serial 11 umber : 85-1-241Q Applieation: 11ain_Etcam Line.J11gILY.1stv_14SIV_ ism 1AticttL Date and Time of Discovery: 11/28110 110.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Reactor 14 ode: nun Power Level: 100%

Calibration Tolerance: 102-104 PSID llominni Setpoints 111 PSID Action Limits: <90.2 or >107 1 PSID Reject Limits: <94.8 or >1112 PSID Technical Specification Limitt 115 PSID As Found Setpoint: 101 -

107 PSID Date and Time of Return to Service: 11/30/90 1739 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.616895e-4 months <br /> 14odel 11 umber of Repiscement Switch: 1.02 - A S - 4 0 3 -ItX-JJTTX 6 Serial 11 umber of Replacement Switch: 36-10-563 DVR 11 umber: 01-2-90-074 Cause: Ihe_.. switch was found to not maintgin a constant setypint. After gligggsembly and inspection, slight corrosion of the bearings and a scratch on the crosaghaft was noted. The failure was due to corrosion induced sitaf t binding.

Corrective Action: The switch was replaced. calibrated and returned to agryice. The failed switch was disassembled and inspected.

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TABLE S. ,

F.3' UNI ~ ScuwudNS AND POWER Ewuti1CNS >20% *

(UNIT 2)

METEOD OF CORRECTIVE TEARLT TYPE MiUTIING DCWN ACTIONS /CCPMENTS SEvJr.:eiIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR 5 if NUMBER (YTMMDD) S: S A ULED (ECURS) REASON REDUCING POWER applicable)

(25one )

SLMY OF OPERATION:

The unit remained on line at high power througho ;t the month. Several minor power reductions were required due to low grid demand, routine surveillances, heater bay and feedwater pump work.

i V

ZCADTS/7

,G. Utilmf t REPORT 1140 Rt9U2REMCl4TS (Unit 3)

• 1. Safrty/h011ef Valve Operations

~

VALVES NO & TYPE PLANT DESCRIPTIO!i DATE ACTUATED bCIVAll0116 C.OllD121011 OL IVRfT ,

(Hone)

2. ECCS System Outages (See Table 6)

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

(None)

/

4. Major changes to Radioactive Waste Treatment Systems.

(None)

$. Indications of Talled Tuel Elements.

(Hone) w ZCADTS/7

(Unit 2)

, Table 6

, G.2 ECCS System Outages Note: The year and unit data has been removed f rom the outage munber.

fM TAGE ltQ EQU11HDIT PURPOSL 17a4 2EL1-r316 Repack valve 1767 2E12-C3004 depair oil leak 1701 2022-C302A Replaced motor 1702 2E12-C00;D Change oil 1707 2DG006 Repack valve 1792 2E22-DJ00 Inspection 1794 2E22-D300 Replace gasket ZCADTS/7

._, ,,. - . _ _