ML19327C106

Monthly Operating Repts for Oct 1989 for LaSalle County Nuclear Power Station.W/891110 Ltr

ML19327C106
Person / Time
Site:	LaSalle
Issue date:	10/31/1989
From:	Diederich G, Thunstedt J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8911150287
Download: ML19327C106 (24)

Text

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i 08WROMP98001E h

.,.g i o LaSal 7 County Nuclear Stat: n i i o Rural Route #1. Box 220 t IAar6ellies, Illinois 61341 "

Telephone 815/357 6761 t l

i November 10, 1989 i i

+

T Director of Nuclear Reactor Regulation  !

United States Nuclear Regulatory Commission Mall Station P1-137  !

Washington, v.C. 20555  !

t AT'IN : Document Control Desk  ;

I Gentlemen

• i Enclosed for your information is the monthly performance report covering f LaSalle County Nuclear Power Station for October,1989.  ;

r Very truly yours, I l

AT- s Y ko G. J. Djederich hrStationManager l LaSalle County Station f GJD/JWT/sjj  !

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Enclosure j i

L xc A. B. Davis, NRC, Region III j NRC Realdent Inspector LaFalle i Ill. Dept. of Nuclear Safety  ;

P. Shemanski, NRR Project Manager I D. P. Galle, CECO i D. L. Tarrar, CECO INPO Records Center L. J. Anastasia, AIP Coordinator, Nuclear Services J. E. Kuskey, GE Resident {

T. J. Kovach, Manager of Nucleer Licensing i W. T. Haughton, Nuclear ruel Services Manager (

C. F. Dillon, Senior Financial Coordinator, LaSalle i Terry Novotney, INPO Coordinator, LaSalle Station [

T. A. Hammerich, Rogulatory Assurance Supervisor J. W. Gleseker, Technical Staff Supervisor Central File hd l I 8911150287 891031 ZCADTS/5 POR ADOCK 05000373 s r

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t LASALLE~ NUCLEAR PONER STATICat UNIT 1

' MONTHLY PERFORMANCE REPORT OCTOBER 1989 y>

COBOIONWEALTR EDISON COMPANY

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NRC DOCKET NO. 050-373 i

LICENSE NO. NPF-11 L

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I TABLE OF CONTENTS  ;

3. INTRODUCTION l

l

!!. REPORT A. SUMMAkY OF OPERATING EXPERIENCE l B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED l MAINTENANCE  !

1. An.endments to racility Licenso or Technical Specifications l

2. Changes to procedures which are described in tho Safety  ?

Analysis Report ,

3. Tests and Experiments not cevered in *,he Safety Analysis Report I

4. Corrective Maintenance of Safety 4 Rela;ed Equipment 6

5. Completsd Safety-Related Modifications C. LICE.NSEE EVENT REPORTS f

D. DATA TABULATIONS f

1. Operating Data Report 3

2. Average Dolly Unit Powe.' Level *

3. Unit Shutdowns and Power Reductions i E. UNIQUE REPORTING REQUIREMENTS [

1. Main Steam Relief Valve Operations

2. ECCS System Outages i

3. Off-Site Dose Calculation Manual Changes [

4 Major Changes to Radioactive Waste Treatment System

5. Indicatione of Failed Fuel Elements t i

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1. 141'RODUCTICd

, ;The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Harseilles, Illinois. Each unit is a Boiling Water Reactor with a designed not electrical output of 1075 Negawatts. 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 Commornwealth Edison Company.

Unit One was issued operating license number NPT-11 on April 17, 1982, Initial criticality was achieved on June 21, 1982 and commercict power operation was commenced on January 1, 1984.

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

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• j e.  !!, NCEtTMLY REPORT

• A. Sl404ARY OF OPERATING EKPERIENCE

[

Day Time Event c

1 0000. Reactor subcritical, generator off-line, L1R03 in e, p progress.

31 2400 Reactor suberitical, generator off-line, L1R03 in progress.

L B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SATETY RELATED MAINTENANCE.

1. Amendments to the racility License or Technical Specification.

(None)

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

(Hone)

L.

3. Tests and Euperiments not described in the Safety Analysis i Report.

(None)

4. Najor corrective mair.tenance to Safety Related Equipment.

(See Table 1)

5. Completed Safety-Related Modifications. .[

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MAJOR CORRECTIVE MAINTENANCE TO ,.

SAFETY-RELATED EQUIP 9ENT .

'AORK REQUEST RESULTS AND EFFECTS a--

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NUMBER COMPONENT CAUSE OF MALFUNCTION W SAFE PLANT OPERATION CORRECTIVE ACTIN (Unit 0) (None)

(Unit 1)

L92525 1VDO3C . Faulty overload relay Fan will not rum Replaced relay ZCADTS/S -

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C. : LICEIISEE EVENT REPORTS'

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LER Mumber DALs Daggription 89-024-00 10/13/89 Control Room floor fire barrier degraded.

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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)

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• D.i 04 RAi!3 C IA EPORT 10CtET C. 650-373  !

, UN!iLASALLEONE

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COMPLETO tri J.W. THUNSTDT TELEPHONE (815) 357-6761 l L l OPERAi!E STATUS  ;

1. E POR11NG K RIOD: OCTOKR lit? CROSS HOURS IN REPORI!E KRIOD: 745 2., CURRENTLY AUTWORl!D P0KR LEVEL (M1): 3,323 NAX KPEND CAPACITY (Mlle-Neth 1,036 .}

. M SIGN EllETRICAL RAllNG (MWe-Ne() 1,070 '

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[ 3, PDS LEVEL TO IMICH ESTRICTED (IF ANY) (MWe-Net): 0

' 4. ' E ASONS FOR RESTRICTION (!F ANY): Reisellt4

[.' EPORr!NG MRIOD NTA r

t TH16 MONTH YEAR-10-MTE Cl#RL411VE E

5.1 TIME EAC10R ERITICAL (HOLRS) 0.0 6,114.8 32,134.1 0.0 0.0 1,641.2 6 1 TIME REACTM E SERVE SHUTDOWN (HOURS)

7. TIME GENERATOR DN-LI E (HOURS) 0.0 6,103.8 31,419.3 l

8. TIME GENERATOR AESERVE CWTDOWN (HOURS) 0.0 0.0 1.0 19,054,999 67,833,569

9. THERNAL INERGY GENERATED (MW!i-Gross) 0 .[t it. ELEClRICAL' EERGY GENERATO (MIME-Cross) 0 6,422,787 29,063.541

11. ELECTRICAL CERGY GENERAfD (MWHe-Net) -B,575 6,172,005 27,747,534 12 REACTOR SERVICE FACTOR (I) 0.0 83.5 62.9 13.' REACTOR AVAILAl'!LITY FACTOL (2) ed $3.5 66.0

14. SERVICE FACTOR (!) 0.0 83.4 61.4

k 15. AVAILIFILITY FACICR (1) 0.0 03.4 61.4 16', CAFACITY FACTOR (USING OC) (!! 1.1 81.4 -52.3

17. CAPACITY FACT 0R (USIE KS!!,H MWei (1) 1.1 78.2 58.3 18, FORCD OUTAGE FACTOR (I) 0.0 1.4 10.1

, it. SHUTDOWNS $ CHEM.D DVER THE NEXT 4 M)NTHS (IYPE, DATE, AND DURATION OF EACH):

(None)-

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20. IF SHUTDOWN AT END OF REPORT PER109, ESilMAID MTE OF STARTUP:

December 14, 1989 l

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8.2 ' AVERAGE MILY talli P0MER LFVEL (ftle-itet) j A -' ' '

COWtITE) DY J.W. THWN$fEpi .j

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54 9/15/89 5 745 C 4 Reftaeling Outage (L1303) .

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• E. UNIQUE REPORTI'20 REQUIREMENTS

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUAT10t( CVtIDlTION QLEVENT (None)

2. ECCS System Outages ,

QQIAGE NO. EQQU'Nt2[T PURPOSE (Note the year and unit numbers have been ommitted from the Outage Number) t IUAIL Q) i 298 0 De G Install mod M-1-1-87-012 IURII_ll 881 1E51-r069 (RI) Perf orm LES-EQ-112 882 1E51-T080 (RI Perform LES-bO-112 883 IF,bl-T086 (RI) Perform LES-EQ-112 i 834 1E51-T013 (RI) Perform LES-EQ-112 I #

865 IE51-F019 (RI) Perform LES-EQ-112 >

886 1E51-F031 (RI) Perform LES-EQ-112 887 1E51-r068 (RI) Perform LES-EQ-112 l 948 IB D/G Torque bolts 949 IE12-F020 (RH) Perform 1.LRT's  ;

957 1E12-D300A (RH) Replace cover-gasket i L f 959 1A RHR WS Pump Repair discharge valve ,

960 1A RHR Hz Repair walds 980 HPCS Repair spool piece 1051 1E12-r050A (RH) Repair valve j 1062 1E12-C002A (RH) Perform LES-GM-129 1064 1C RHR Pump Perform LES-GM-129 ZCADTS/5 i

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1066 IB RHR Pump Perform LES-GM-129 1067 1A RHR Hz Repair tube-side relief valve 1075 1E22-S001 (DG) Perform inspection 1109 1E12-T017A (RH) Perform LES-EQ-112 1110 1E51-r076 (RI) Perform LES-EQ-112 1111 1E51-T063 (RI) Perform LES/EQ-132/LES-AP-101 1112 1E51-F063 (RI) Repack valve 1117 IE12-F040A/B (RH) Perform LS-GH-163

'1119 1B RHR Perform HTA Relay LES 1130 1E12-T068B (RH) Repack valve 1145 HPCS Pump Inspect breaker 1159 1E51-C005 (RI) Perform LES-DC-104 1164 B/C RHR (Various) 1165 B/C RHR (Various) 1166 B/C RHR (Verious) 1168 1E31-N012BA (RH) Clean check valve 1169 B RHR Hz Repair tube-side relief valve 1170 1E31-N012A (RH) Clean check valve 1171 1E12-F074B (RH) Inspect torque switch 1172 1E12-rC11B (RH) Perform EQ inspection 1173 1E12-T042B (RH) Perform EQ inspection 1174 1E12-T016B (RH) Perform LES-EQ-112 l

1175 1E12-T024B (RH) Perform EQ inspection 1176 1E12-T064C (RH) Perform LES-EQ-112 1177 1E12-T048B (RH) Pcrform EQ inspection l'

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1178 IE12-F053B (RH) Perform EQ inspection

!- 1179 1E12-r021 (RH) Perform LES-EQ-112 L 1180 1E12-F0998 (RH) Perform LES-EQ-112 1181 1E12-F042C (RN) Perform EQ inspection 1182 1E12-T064B (RH) Perform LES-EQ-112 1196 IB RHR Pump Install Appendix R modification r

1206 1E12-R525 (RH) Replace piping section 1218 1E12-T027A (RH) Perform LES-EQ-112 i

f- 1233 IE12-C002C (RH) Perform EQ inspection 1235 IB RHR Pump Perform EQ inspection 1249 1B RHR H Hydrolase tubes 1251 1B RHR Pump Perform mod M-1-1-87-013 1262 1A D/G Replace instruments 1263 1H13 P601 (RH) Install jacks 1264 1A D/G Perform LES-GM.129/123 1265 1A D/G (Various) 1266 1A D/G Install Appendix R modification 1267 1A D/G (Various) 1271 1A D/G Pe form mod M-1-1-87-002 1272 1A D/G Perform mod N-1-1-87-002 1276 1E51-T065 (RI) (Admin control) 1278 RCIC Refurbish condensate pump 1279 1E51-F005 (RI) Install live-load packing system 1297 RCIC (Various) 1305 1E51-T045 (RI) Repack valve ZCADTS/5 u

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• 3. Chang:s t9 th) Off-Sito Dos) CalculOtics N;2u:1 l t

(None); however, the September 1989 report (submitted on j

October 10, 1989) should have included the following statements  !

- 1 A determination has been'made that this change will not reduce L the accuracy nor reliability of dose calculations nor setpoint j L determination. i

4. Major changes to Radioactive Waste Treatment Systemt.

l (None)

5. Indications of Failed Fuel Elements.  !

I A pin-hole

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. LASALLE NUCLEAR POWER STATION ..>

I' i: . < UNIT 2 ,

'I m, r-N'. , MCatTMLY PRRFORMhMCE REPORT s  ;.

J.t ' OCTOBER, 1989'

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l NRC DOCKET NO. 050-374

' LICENSE NO. NPF-18

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i TAttE OF CONTENTS o.

, 4 1. INTRODUCTION a.

11. REPORT A. Stt.4 MARY OF OPERATING EXPERIENCE B. P' ANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Am9ndments to racility License or Technical Specifications

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

3. Tests and Experfments not covered in the Safety Analysis Report.

4. Corrective Maintwnance of Safety-Related Equipment

5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS 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 Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of railed fuel Elements i

1 ZCADTS/7

3. INTRODUCTION  !

c The LaSalle County Nuclear Power Station is a two-unit facility owned by l Commonwealth Edison Company and located near Marseilles, Illinois. Each  !

unit is a Boiling Water Reactor with a designed not electrical output of f 1078 Negawatts. Waste heat is rejected to a man made cooling pond using [

the Illinois River for make-up and blowdown. The architect-engineer was  !

Sargens and Lundy and the primary construction contractor was l Commonwealth Edison Company.  ;

i Unit Twv was issued operating Ilconse number NPT-18 on December 16, (

1983. Initial criticality was achieved on March 10, 1984 and commercial L power operation was commenced on June 19, 1984.  !

This report was complied by John W. Thunstedt, telephone number [

(815)357-6761 extension 2463. j L

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. o  !!. MONTHLY REPORT

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SUMMARY

OF OPERATING EXPERIENCE A .'

' Day Ilms Event {

n l 1 0000 Reactor suberitical, generator off-lines forced j outage due to damaged main generator. j i

l., 14 0510 Reactor critical

• 2000 Generator on-line. l Generator off-line for control valve testing. I b 2200 r

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[ 15 0645 Generator on-line, inc'.vasing power to 2181 MWTH. j f- ' 'l L 17 1650 Reduced load to 1433 MWTH for rod-eet.

i, 18 2200 Increased power to 3170 MWTH.

21 2300 Peduced power to 2000 MWTH for rod-pattern adjustment.

i 23 1000 Increased power to 3260 MWTH. ]

( i 28 2400 Reduced power to 2540 MWTH for rod movement. l 29 2000 Increased power to 3309 MWTH.  !

l

.i 31 2400 Reactor critical, generator on-line, at full power.  ;

L H. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SATETY RELATED [

MAINTEN ANCE. .

1. Amendments to the Facility License or Technical Specification.

Amendment 52 revised Table 3.8.3.2-1 to reflect RH feeder )

breaker location changes. .!;

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

Analysis Report. [

(None) e I

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

(None) [

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4. Major corrective maintenance to Safety-Related Equipment. ~

(See Table 1) {

5. Completed Safety-Related Modifications.

(None)

ZCADTS/7

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P D.- . DATA TABULATICets  ;

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1. Operating Data Report (Attached)  :(

2. Average Daily Unit' Power Level (Attached)-  !

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-3. Unit Shutdowns and Power Reductions (Attached) l '.  !

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5' OPEMTIE $1ATUS

t. EPORTIE PERIOD: OCf 0ER iP8f GRDBS HOURS IN REPORT.1E PERIOD: 745

$ 2. CURRENTLi AUINORIED POWER LEVEL (Mt):3,323 Mr KPEG CFACITT (MWe-Net): 1,036  :

K SIGN ELECTR!tAL KAi!NG OiWe-Net) 1,078

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' 3.. POWER LEVEL TO WICH RESTRICID (IF MY) (We-ktt): (Now)  !

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c 4 M A90NS FOR ESTRICTION (!F ANT): (N/A)

F REPORTING PERIOD MTA I

• TNis NONTH YEAR TO- MTE CUMULAi!VE r . . . _ . . . . . - - - . . .....

i;5.117EACTORCRITICAL(HOURS) 427.0 5,229.0 28,707.0

6. ?!E E ACTOR RESERVE S WTDOWN (HOURS) 0.0 0.0 1,716.9 i

' . 7.' T!3 GENGAf0R DN-l!NE (HOURS) 403.4 5,151.9 28,242.9

8. TIME GEERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 i

9. TERML LERGY GEERATO (MWHi-Gross) t t57,856 15,632,760 81,572.368

10. ELECTRICE ENERGi GENERAID (MWNe-Gross) 390,054 5,123,117 26,826.05  !

372,500 4,924,463 25,663,713  :

L11. ELECTRit4'. ENERCY GENERATO (MWHe-Net)

I 12.' KACTOR SERVICE FACTOR (ti 57.4 71.4 65.6

.13! REACT 0kAVAILABILITTFACTOR(%) 57.4 76.4 68.9 i

14, SERVICE IACTOR (1) 54.1 70.4 64.0 15.AVA! Lit!LITTFACTOR(1) 54.1 70.4 64.0 48.3 64.9 56.1

.16. CAPACITT FACTOR (USING O C) (%) f

17. CPACITT FACTOR (USING MSIGN MWe) (1) 4f.4 62.4 53.9 .

18. FORCED Olf! AGE FACTOR (t) 45.9 17.5 17.0 l

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19. SHUTDOWNS SCHEDULD DVER THE Eri 6 MONTNS (TYPE, MTE, AND DURATION OF EACH):

Refseling 03/17/89 12 Weeks i

d. IF SHUTDOWN AT EO 0F REPORT FEklGD, ESTI MT D MTE OF STARTUP:

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-D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS 520% d f

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METHOD OF-YEARLY TYPE SHUITING DOWN SEQUENTIAL F: FORCED DURATION THE REACTOR OR CORRECTIVE NUMBER DATE S: SCHEDULED (HOURS) REASON CODE' REDUCING POWER ACTIONS /CObeENTS 26 8/26/89 F 341.6 G 4 Forced outage' continues to complete repairs on Main Generator caused by water injection.

27 14 S 0.0 B 1 Control valve testing.-

28 17 S 0.0 B 5 Control rod set.

29 2 '1 S 0.0 B 5 Rod pattern adjustment.

30 28 S 0.0 -B 5 Control rod adjustment.

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ZCADTS/7 l

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E.' , UNIQUE REPORTI!G REQUIREMENTS

< q 1. SOfsty/R3110f V&lva Opercticns

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VALVES NO & TYPE PLANT DESCRIPTION DATE ACTLIATED AC21]ATLQtiS CQtIDIT10t{ OF EVENT (None)

'2. ECCS System Outages QUIAGLHD EQELEM MI E11REQSE NOTE: The year and unit designators have been ommitted f rom the Outage Number.

942 2A RHR Prevent vessel drain 947 RI flow instrument Prevent isolation 952 2E12-F024B (RH) Prevent inadvertent draining 958 2E12-F087A (RH) (Administrative)

3. Changes to the Of f-Site Dose Calculation Manual None; however the September 1989 report (submitted on October 10, 1989) should have included the following statement:

A determination has been made that this change will not reduce the accuracy nor reliability of dose calculations nor setpoint determination.

4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indications of Failed Fuel Elements.

(None)

ZCADTS/7

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