ML19351A269

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Monthly Operating Repts for Sept 1989 for LaSalle County Nuclear Power Station Units 1 & 2.W/891010 Ltr
ML19351A269
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 09/30/1989
From: Diederich G, Thunstedt J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 8910190060
Download: ML19351A269 (26)
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j,< CefuMRORupeellit Edit 0R LaSalle County Nucleer Stat 2n {

Rural Route #1, Bex 220 f.

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!Aarsellies, Illinois 61341 Telephone $15/357 6761 1

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October 10, 1989 l

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l p Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission  :

Mail Station PI-13*/ )

Washington, D.C. 20555  ;

i l AT7N: Document Control Desk l Gentlemen Enclosed for your information is the monthly performance report covering l i

LaSalle County Nuclear Power tation for September,1989.  !

Very truly yours, j i

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. ?24 tar lZ,

. J. Diederich StationManager/rb .

LaSalle County Station [

GJD/JWT/sjj i

Enclosure met A. B. Davis, NRC, Region III NRC Resident Inspector LaSalle  ;

Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager  :

D. P. Galle, Ceco r D. L. Tarrar, CECO l-INPO Records Center L. J. Anastasia, AIP Coordinator, Nuclear Services [

J. E. Kuskey, GE Resident l T. J. Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear ruel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Terry Novotney, INPO Coordinator, LaSalle Station j T. A. Hammerich, Regulatory Assurance Supervisor ,

J. W. Gieseker, Technical Staff Supervisor i Central File 6010190060 890930 ,

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.t' LASALLE NUCLEAR POWER STATION l i

UNIT 1 l 1

NONTHLY PERTORMANCE REPORT j l

SEPTEMBER 1989 COD 040NWEALTH EDISON COMPANY ,

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NRC DOCKET NO. 050-373  !

LICENSE NO. NPF-11 t

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TABLE Or CONTENTS

[ I. INTRODUCTION I

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!!. REPORT

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A.

SUMMARY

OF OPERATING EXPERIENCE l

B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED l KAINTENANCE  !

1, Nwendments to racility License or Technical Specifications i

2. Changes to procedures which are described in the Safety Analysis Report
3. Tests and Experiments not covered in the Safety Analysis Report l
4. Corrective Maintenance of Safety-Related Equipment  !
5. Completed Safety-Related Nodifications l t  !

C. LICENSEE EVENT REPORTS l D. DATA TABULATIONS

1. Operating Data Report
2. Average Daily Unit Power Level j
3. Unit Shutdowns and Power Reductions l E. 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 Naste Treatment System  !
5. Indications of railed ruel Elements ,

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l, 1. INTRODUCTION l

[ 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 not electrical output of 1078 Negawatts. Maste heat is rejected to a man-made cooling pond using the Illinois River for make-up an6 blowdown. The architect-engineer was r g Sargent and Lundy and the primary construction contractor was ,

Commonwealth Edicon Company.

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

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

! This report was compiled by John W. Thunstedt, telephone number (415)357-6761, extension 2463.  ;

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! "- .  !!. MONTHLY REPORT A.

SUMMARY

Cet OPERATING EXPERIENCE I f ,

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1 0000 Reactor critical, generator on-line, at 1080 MWE.  !

Load reductions due to Load Dispatcher requests are generally reported as part of Paragraph D.3 (Unit Shutdowns and Power Reductions.)

& 0600 Reduced power to 698 MWE for rod pulls.

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2300 Increased power to 3124 MWT. s 11 0030 Reduced power to 1338 MWT for CRD exercising. (

l 12 1400 Increased power to 3320 MWT.

1700 Reduced power to 3000 MWT to swap to the Motor-Driven Reactor Teed Pump.

13 1200 Increased power to 3136 MWT.

14 0100 Reduced power to 1887 MWT for flux tilt test. I 1100 Increased power to 2908 MWT. l 1230 Reduced power to 2650 MWT for vibration measurements on the B Deactor Feed Pump.

15 1230 Reduced power to 1057 MWT to down-shift Reactor k Recirc. Pumps. [

2100 Reduced power to O MWT (manually shutdown reactor, generator off-line, end of cycle, start refueling >

outage (L1R03). .

30 2400 Reactor subcritical, generator off-line, L1R03 in progress

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.. B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED  ;

NAINTENANCE. l i

1. Amendments to the Facility License or Technical Specificction.

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(None) i i

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

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! 3. Tests and Esperiments not described in the Safety Analysis [

Report. l (None)  !

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4. Maj?r corrective maintenance to Safety-Related Equipment. (

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- p MAJOR CORRECTIVE MAINTENANCE TO

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SAFETT-RELATED EQUIPMWT , ~*

WORK REGUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION OK SAFE PLANT OPERATION CORRECTIVE ACTION (UO)

L90156 ODGOO6 Broken valve stem 180 control of flow Replaced e- ,:0 internels.

(U-1)

L91965 OVE04CA Damaged internals Low oil pressure, loud seize, Repaired int.etaal:-

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. . ' C. LICEWSBB EVIntT REPORTS l i

.\. LER Eh Data naaeriptiam f j :, I 89-023-00 09/08/89 Spurious Closure of 1933-F019  ;

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, D. DATA TABULATICBIS

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1. Operating Data Report (attached) [

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2. -Average Daily Unit Power Level (attached) ]

3.. Unit Shutdowns and Power Reductions (attached) t l l l t l.

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METHOD Of YEARLY TYPE SHUTTING DONN SEQUENTIAL F: FORCED DURATION THE REACTOR OR COPSICYIVE NUMBER DATE S: SCHEDULED (HOURS) REASON RNCL""* --; ec.m ACTIONS /COBSEFNTS 46 3 S 0.0 F 5 Lead Dispatcher 47 4 S 0.0 B 5 Rod pulls 48 5 S 0.0 F 5 Load Dispatcher 49 11 S 0.0 B 5 CRD Esercising 50 11 S 0.0 F 5 Load Dispatcher 51 14 S 0.0 B 5 Flux-tilt test 52 14 S 0.0 B 5 "B" Reactor Feed Ptamp Vibration 53 15 5 0.0 8 5 Down-Shif t RR Pianps a

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, I!, UNIQUE REPORTING REQUIREMENTS ,

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1. Safety / Relief valve operations

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VALVES NO & TYPE PLANT DESCRIPTION

l.  !! ATE ACIVATED ACIDATION C{RfDITIC3[ Or EVENT l 1

(None)  ;

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2. ECCS System Outages GUTAGE NO. EOUIPMENT PURPOSE '

! LUnit 0)

0-293-89 "0" D/G Modify starting circuit ,

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IUMII._.11 1-568-89 1A RH Pump Perform LEP-GM-110 i 1-156-89 1E51-r006 (RCIC Steam Iso) Replace limiter plate  ;

1-572-89 1C RH Pump Inspect breaker >

1-573-89 1C RH WS Pump Inspect breaker  !

1-579-89 1E12-C300D (RH) Inspect breaker

~1-580-89 1E12-C002B (RH) Inspect breaker 1-605-89 HPCS Flushing Water Install / remove spool piece 1-606-89 LPCS Flushing Water Install / remove spool piece 1-633-89 RCIC Interlocks Inspect relays i

1-636-89 RCIC Logic Perform LES-GM-163 ,

1-742-89 1B D/G Perform LES-HP-102, 103  !

1-746-89 ODG01K Install modification 1-1-86-085 t

1-751-89 IB D/G Air Compressor Replace Cooler 1-752-89 1B D/G Cooling Water Hydrolate Cooler 1-753-89 HPCS D/G Perform LES-DG-102 '

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, 1-754-89 HPCS D/G (Various) 1-766-89 Head spray & RCIC Prevent leakage 1-784-89 RCIC Perform LES-RI-101A >

1-795-89 1B D/G Perf orm LES-ON-129 t l

1-796-89 HPCS Perform LES-GN-129 1-797-89 1E22-F007 (HP) Replace valve 1-798-89 1833-F319A (HP) Clean ,

1-799-89 1B33-F3198 (HP) Clean ,

1-800-89 1833-T317A (HP) Clean 1-801-89 1833-T317B (HP) Clean 1-802-89 1B D/G Calibrate relays  !

i 1-831-89 1E12-F090A (RH) (Administrative) 1-842-89 0 D/G Install "Appendia R" modification .

1-813-89 A RHR LPCS 0 D/G Perform LES-RH-100, 105 .

1-845-89 1E12-P087A (RH) (Administrative) }

1-846-89 1E12-T064B (RH) Perform LIS-RH-303

3. Changes to the Off-Site Dose Calculation Manual (None) i
4. Major changes to Radioactive Waste Treatment Systems.

(See Attachment A) -

5. Indications of railed Fuel Elements. I A small pin-hole leak has been identified; precise location ,

and disposition will be determined during L1R03.  ;

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I . . ATTACMMENT A l ..

KAJOR CRANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS To oupport the chemical decontamination (LOMI) process of the Unit 1 p Reactor Recirculation piping in September of 1989, various bead resin wastes

will be 9tnerated requiring dowatering and disposal. Our present redwaste vendor will be unable to process these LOMI wastes. LaSalle Station has therefore opted to contract the services of LH Technologies to process the LONI wastes.

LN Technologies' PCP uses an NRC accepted system for the processing of the LOMI wastes. LN's pystem has been designed to >:omply with all c.f the applicable codes, regulations, and industry standards including:

10CTR20, Standerls for Protection Against Radiation 10CTR50, Licensing of Production and Utilization racilities.

10CTR61, Licensitg Requirements for Land Disposal of Radioactive. Wastes 10Crk71, Packaging of Radioactive Materials Therefore, there is me reduction in the conformance of the waste product compared to current waste criteria.

LN's dewatering oporating procedures will be reviewed and accepted by LaSalle Station's Onsite Review and Investigative function under Onsite Review 89-057 (LN's operating procedurcs, waste processing procedures onsite review).

Technical Specification 6.9--Major Changes to Radioactive Waste Treatment Systems 6.9.1.a.1 A copy of this review will be included in the Monthly Operating report to the Commission. This document provides sufficient infonnation to verify that the change was made in accordance with 10CTR50.59.

6.9.1.a.2 A copy of this revjew, and the 10CTR50.59 review from OSR 89-057 (LN's operating procedures, waste processing procedures onsite review) will be included in the Monthly Operating Report to the Commission. These documents provide suf ficient information to verify the rational for the change.

6.9.1.a.3 The following procedures were included in OSR 89-057 (LN's operating procedures, waste processing procedures onsite review), and provide detailed descriptions of the equipment, components, and processes involved in the solidification, and describe interfaces with other plant systems 3702-301, Operating Procedure for the LaSalle Unit One Recirculation Piping Documentation 3702-002, System Set Up/ Removal for LN Quick Dry Dewatering System No. 3291.

3702-003, Process Control Program for Dewatering Bead or Powdered Resin with Quick dry Dewatering System No. 3291.

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, ., ATTACHMENT A (conticued)  !

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. 6.9.1.a.4 Thers are no anticipated new gaseous releases due to this  !

procees).ng. There are no anticipated new liquid releases due l t

to this processing. One liner of dewatered resin (120 cu. j f t.) is espected to result f rom the oecontamination. The .

license application and unendments did not predict any LONI )

wastes. I 6.9.1.a.5 The espected masimum esposure to an individual in the I unrestricted area, and to the general population, will not )

change. Tae waste processing is being performed inside the  ;

L1 restricted area, just as any other waste processing.

l 6.9.1.a.6 There are no anticipated radioactive liquid effluents. There are no anticipated radioactive gaseous effluents. It is l anticipated to have one liner, with an estimated 140 curies total, as solid waste. This waste will supplement the normal i solid waste produced during the period. l 6.9.1.a.7 An estimated 10 man rem of esposure to plant personnel will result due to the decontamination and waste processing.

6.9.1.a.8 The proevssing of LONI wastes will be reviewed and approved by ,

the Onsite Review and Investigative Tunction under OSR 89-057 (LN's cperating procedures, wasto proces61ng procedures onsite review).

6.9.1.b This change becomes effective after approval of OSR 69-057 (LN's operating prc,cedures, waste processing procedures onsite review). ,

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LASALLE NUCLEAR POWER STATION UNIT 2 ,

MONTHLY PERFORMANCE REPORT SEPTEMBER, 1989  ;

COMMCNWEALTH EDISON COMPANY ,

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i NRC DOCKET NO. 050-374 LICENSE NO. NPT-18 ,

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If. 1 TADLE OF CONTENTS -

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I. INTRODUCTION  !

II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE  :

1. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SATETT RELATED >

Mall '.EN ANCE  !

1. Amendments to racility License or TecS ita's Specifications
2. Changes to proc 9dures which are dowcrib.o 1. the Safety Analysis Report.
  • F. Tests and Experiments not covered in cr.a Cafety Analysis Report.
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety Related Modifications '

C. LICENSEE EVENT REPORTS

  • r D. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions ,

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations

.2. ECCS System Outages <

3. Off-Site Dose Calcu'ation z Manual Changes
4. Major Changes to Radioactive Waste Treaumont System
5. Indications of ralled Fuel Elements l

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t-I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit f.acility owned by Commonwealth Edison Company and located near Marsellies, Ill!nois. Each unit is a Boiling 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 end Lundy and the primary construction contractor was Cemmonwealth Edison Company.

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

This report was compiled by John W. Thunstedt, telephone number (815)357-6761 extension 2463.

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, 'II. MONTHLY REPORT r

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A.

SUMMARY

OF OPERATING EXPERIENCE' Day Tima Event

'l 0000 Reactor suberitical, generator off-line due to repair j

of w.ain generator.  ;

31 2400 Reactor subcritical, generator off-line due to repair' of main generator. ,

-B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SATETY RELATED MAINTEN ANCE. r

1. Amendments to the Facility License or Technical Specification. '

(None)

2. Changes to procedures which are described in the Safety  !

Analysis Report.

(None)

3. Tests and Experiments not described in the Safety Analysis >

Report.

(None) l ', 4.

l Major corrective maintenance to Safety-Related Equipment.

(See Table 1) ,

5. Completed Safety-Related Modifications. i (See Table 2)

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MAJOR CORRECTIVE MAINTENANCE TO .

SAFETT-RELATED EQUIPMLTI WORK REQUEST RESULTS AND EFFECTS NUMEEE COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L92329 2E12-F004B Stem bound by excessive - Valve would not stroke Adjusted packing nut force from packing nut e

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COMPLETED SAFETY RELATED MODIFICATIONS f' MODIFICATION i NUMBE.R DESCRIPTION L

M01-2-89-016 Modify the VR-dampers indication lights to provide a greer i light when the damper is fully closed, a red light when l the damper is in fully open position and both lights in i the intermediate position.

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89-013-00 09/07/89 Full Group 1 Isolation during sutveillance.

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D. DATA TABULATIONS

1. Operating Data Report (Attached) .;

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2. Average Daily Unit Power Level (Attached)
3. Unit Shutdowns and Power Reductions (Attached) j kt 1

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.! UNIT LASALLE TWO MTE Ociober 10,i i999 g ". h"e.p.s 4

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f( 26 CURENTLY AUTHOR!!D POWER LIVEL (MWt)f.., ESICM ELECTRICAL 8tATING (MWe-Net)

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9.0 4,801.2 28,279.2 1 v 5.[ TIE FJACTOR CRI71 CAL (HOWS) . ,

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p, .i.RTIMEREACTORRE5ERVESHUTDOWN(HOURS) 0.0 0.0: 1,716.9  ?

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27. TIMEGENERAT'ORONd!NE(HOURS)', 0.0 4,748.5 27,839.5

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p10(ELECTRICALENERGTGENERATE9.(MWHe-Gross).. 0 4,734,253' 06,437,501 If

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~11iELECTRICALENERGYGELRATED(MWHe-Net) -B,680 4,551,963" '25,29ha3 i

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x. u 412; REACTOR SERVICC FACTOR (X) 0.0 _~ 73.0 - 65.1

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(14 SERVICE FACTOR.t!) 0.0 72.2 64.1 I

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  • e;C i&E CAP.\ CITY FACTOR (USING MDC) (!)-

hj7(CAPACITYFACTCAMINT,ESIGNMWe)(%) -l.1 64.2 54.0 .j m.,.. .

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M 18.'FDRCEO OUTAGE FACTOR (I) 100.0 13.7 16.4

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[. JRefueling March 17,1990 12 Weeks  !

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, , DOCKET ND. 050-374 UNIT LASALLE TWO t.2 AVERV.E DAILY UNIT F0WER LEVEL (MWe-Net) DATE October .'0, 1989 L,y. 00HPLETED !Y J.W. THUNSTEDT

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,. .P.EPORTPERDD: $EPTEMPER 1989 MY TOWER DAY POWER 1 -11 17 -15 2 -11 18 -17 3 -11 19 -16 4 -11 20 -i' 5 -11 21 -12 6 -11 22 -11 7 . 11 23 -11 8 -11 24 -12 9 -11 25 -11 to -11 26 -11 11 -11 27 -12 12 -11 28 -13 13 -11 29 -13 14 -ti 30 -12 15 -12 31 16 -15 1

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METHOD OF YEARLY TIPE SHUTTING DOWN SEQUEriTIAL F: FORCED DURATION THE REACTOR OR CORRECTIVE NUMBER DATE S: SCHEDULED (HOURS) REASON CODE REDUCING POWER ACTIONS /CODGENTS 26 8/26/89 F 744.0 G 4 Forced outage continues to complete repairs on Main Generator caused by water injection.

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DAIE AC'IJATED AC'IVATIfES CONDITION OF EVENT . j

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2. ECCS System Outages ,

OUTAGE _HQi EQUIPMENT PURPOSE t

2-861-80 Sh 2E12-F004D (RH) Inspect motor

,2-862-89 2E12-F004D (RH) Adjust packing ,

IV i 2-863-89 2E12-F006B (RH) Administrative Z-878-89 2E12-F094 (RH) Inspect torque switch  ;

2-879-89 2Elt-F093 (RH) Inspect torque switch l

2-880-89 2E51-F059 (RH) Inspect torque switch ,

2-881-89 2E51-F069 (RH) Inspot torque switch

2-882-89 2E61-F031 (RH) Inspect torque switch  ;

n 2-887-89 2E12-F011B (RH) Inspect torque switch 2-i388 2E12-F040B (RH) Iaspect torque switch t

2-889-89' 2E12-F073B (RH) Inspect torque switch .

'2-894-89 2E12-F027A (RH) Inspect torque switch 2-895-d9 2E12-F074A (RH) Inspect torque switch ,

2-898-89 2E12-F090A (RH) Replace seal-tite k 2-907-89 2DG035 Remove motor 2-909-89 2DG035 Repair valve ,

i 2-919-89 2DG035 Repair valve internals

3. .., Changes to the Off-Site Dose Calculation Manual (None)
4. Major hanges to Radioactive Kaste Treatment Systems.  ;

(None)

^

5. Indications of Failed Fuel Elements.

(None) u l*

l l

ZCADTS/7

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