ML20244A865

Monthly Operating Repts for Mar 1989 for LaSalle Nuclear Generating Station,Units 1 & 2

ML20244A865
Person / Time
Site:	LaSalle
Issue date:	03/31/1989
From:	Diederich G, Thunstedt J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 8904180237
Download: ML20244A865 (25)

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT.

l MARCH 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 I

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1 TABLE OF CONTENTS

.I..

' INTRODUCTION II.

REPORT

~

'A.

SUMMARY

OF OPERATING EXPERIENCE B.-

PLANT'OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND'-SAFETY RELATED MAINTENANCE 1.

-Amendments'to Facility License or Technical-Specifications 2.

Changes to' procedures which are described in the Safety.

Analysis Report'

-Tests.and Exper ments not covered' in the' Safety l Analysis Report i

l 3.

4.

Corrective Maintenance 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..

' 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 i'

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INTRODUCTION [

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.The' LaSalle_ County. Nuclear Power Station is'a two-unit facility owned by Commonwealth Edison Company and-located near Marseilles, Illino i s... Each' unit.is a Bolling Water Reactor with a' designed net electrical output of'

,j 1078. Megawatts. Waste heat is rejected to.a man-made cooling pond usingL 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-ll 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 John W. Thunstedt, telephone number (815)357-6761,- extension 2463.

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MONTHLY. REPORT

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-A.

SUMMARY

OF OPERATING EXPERIENCE p3y '

Time Event 1

0000 Reactor critical, generator on-line, 960 MWE.-

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2' 2302~

. Reactor scram, turbine trip, due to fault of U-2' SAT' l:L lightning' arrestor.

l 6

0042 Reactor! critical.

1055 Generator.on-line, ramping to 1050 MWE.

-8, 2200

. Reduced load to 600 )DfE for rod-set.

9 0030 Ramping to 1130 MWE.

31' 2400 Reactor critical, generator on-line, 1080 MWE.

B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS'AND SAFETY RELATED~

MAINTEN ANCE.

1.

Amendments to the. Facility License or Technical Specification.

(None) 2.

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

(None)

,s 3..

Tests and Experiments not described in the Safety Analysis Report.

(None) 4.

Major corrective maintenance to Safety-Related Equipment.

(See Table 1) 5.

Completed Safety-Related Modifications.

(None)

-DOCUMENT ID 0043r/0031r

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C...' LICENSEE EVENT REPORTS-x.

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. Date.

Description LER NumbgI.'

89-009-00_

03/02/89-

Reactor'. Scram Due to Loss of. Transformer L

'242/ Fault in Lightning Arrestor.

1 89-010-00 03/03/89 Reactor Vessel Low Water Level-Confirmed,

-ADS /Setpoint Draft:

89-011-00 03/04/89 HPCS. System Inoperable 89-012-00 03/09/89

-RCIC Hi Steam Flow' Isolation SOR Failure l-l

89-013-00 03/31/89 Suppression Pool Hi Level Alarm Setpoint Non-conservative.

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D.

DATA TABULATIONS 1.

Operating Data Report (attached) 2.

Average Daily Unit Power Level (attached) 3.

Unit Shutdowns and Power Reductions (attached)

DOCUMENT ID 0043r/0031r

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' D.i DPERATING SATA REPORT

-DOCKET NO.'050-373 UNIT LASALLE ONE lDATEApril 10,1989-j

. COMftETED BY J.W. THUNSTEDT TELEPHONE (815)-357-6761

' OPERATING STATUS

1. REPORTING PERIDD:

MARCH 1989 GROSS HOURS IN REPORTING FERIOD:

744:

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):

~3,323 MAX DEPEND CAPACITY (MWe-Net):

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

1,078 3.: P0"ER LEVEL TO WHICH RESTRICTED (If ANY) (MWe-Net):

(None).

LL REASONS FOR RESTRICTION (IF ANY):

(N/A)

REPORTING PERIOD DATA-THIS MONTH YEAR-TO-DATE CUMULATIVE

-5.7TIGEREACTORCRITICAL(HOURS) 670.3 2,086.3 28,105.6

6. TIME. REACTOR RESERVE SHUTDOWN (HOURS) 0.0~

0.0 1,641.2 7.

TIME GENERATOR DN-LINE (HOURS) 660.1 2,076.1 27,390.6-

8. -TIME GENERATOR RESER7E SHUTDOWN (HOURS) 0.0 0.0 1.0

9. THERNAL ENERGY GENERATED (MWHt-G'ross)

'2,068,000 6,647,664.

.75,426,242

'10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 767,667 2,278,676 24,924,430

'11. ELECTRICAL ENERGY GENERATED (MWHe-Nei) 683,022 2,193,413 23,768,942

12. REACTOR SERVICE FACTOR (%)

90.1 96.6 61.1 h

. REACTOR AVAILABILITY FACTOR (%).

l -13 90.1 '

96.6 64.7 i

l"14.'SERVICEFACTOR(I) 88.7 96.1 59.5

.15. AVAILABILITY FACTOR (Z) 68.7 96.1 59.5 L

88.6 98.0 49.9 L

16. CAPACITT FACTOR.aSING MDC) (%)

L L 17. CATACITY FACTOR (USING DESIGN MWe) (%)

85.2 94.2 47.9 l

18.' FORCED CUTAGE FACTOR (I) 11.3 3.9 11.5 I

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i f'19.SHUIDOWNSSCHEDULEDDVERTHENEXT6 MONTHS (TYPE,DATE,ANDDURATIONOFEACH):

l.

Refineling Sept 5, 1989 12 Weeks l

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

i (N/A) l I.

a

• a DOCRET NO. 650-373 N

UNIT LASALLE ONE.

- D.2 AVERAGE DAILY UNIT POWER LEVEL'(MWe-Net)-

DATE April 10, 1989 i

COMPLETED BY J.W. THUNSTEDT.

TELEPHONE (815)-357-6761 i

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REPORT PERIOD:

MARCH 1989 DAY POWER DAY POWER i

'899 17 1,099 2

882 18 1,096 3

-il 19 1,099

l 4-

-11 20 1,100 5

-11 21 1,101 6

101 22 1,089 7

695 23 1,098 8

958 24 1,095 9

950 25 1,096 10 1,094 26 1,092 11

't,098 27 1,071 -

12 1,098 28 1,065 13 1,099 -

29 1,063 14 1,098 30

~t,090 15 1,079 31 1,087 16 1,098 I

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'E. UNIQUE: REPORTING REQUIREMENTS' 11~. ; Safety / Relief. valve operations.

' VALVES NO & TYPE

PLANT,

-DESCRIPTION

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DATE ACTUATED ACTUATION CONDITION

'OF EVENT' p

'(None) 2.

'ECCS System Outages 8

' OUTAGE NOi EOUIPMEEI PURPOSE l'

(Unit 0)-

0-8'-89

.O D/G Cooling Water. Pump Lubrication.

2 0-83-89 0 D/G Air-Start Solenoid Repair / replace regulator.

and: Regulator.

.JUNIT 1) 1-122-89.

'HPCS D/G Strainer'

' Adjust valve stroke 1-125-89

)C12-D311B-(RH);

Replace "B" RHR vent sight-glass..

'1-126-89 "C" RHR Pump Replace motor.oll.

'l--127-89' "B" RHR Pump Replace. motor' oil.

1-128-89 RHR Service Water pumps C&D Lubricate coupling.

1-130-89 1E12-F073B Install limiter. plate.-

1-133-89'

.lA'D/G Lubricate.

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1'-134-89 1A D/G' It stall.. gasket on bypass. lube-oil vtlve.

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DOCUMENT ID 0043r/0031r

.E.~2.' ECCS System'Outtgrs (Cont'd)'

OU.TAGE NO.

EQUIPMENT PURPOSE' 1-147-89 1E12-C002A Lubricate."1A" RHR motor.

1-148-89 1E21-C001' Lubricate HPCS motor 1-149-89 1E21-C002 Lubricate HPCS water-leg pump coupling.

1-150-89 RHR Service-Water Pumps Lubricate' coupling.

1-153-89 1E51-F059-(RCIC)

(Administrative)

~

1-156-89' 1B D/G Lubricate and change filters.

1-157-89 1E22-C003.HCPS Water-leg Replace oil.

1 Pump 1-158-89 1E22-C003 HPCS Water-leg Lubricate coupling.

Pump 1-159-89 1E22-C003 HPCS Water-leg

' Lubricate motor bearing.

pump 1-160-89 1DOO2P HPCS D/G Fuel Pump Replace oil.

1-161-89 1DOO2P HPCS D/G Fuel Pump Lubricate motor.

1-162-89 1DOO2P HPCS D/G Fuel Pump Lubricate coupling.

1-163-89 HPCS Pump Lubricate motor.

3..

Off-Site Dose Calculation Manual Changes (None) 4.

Major changes to Radioactive Waste Treatment Systems.

(None) 5.

Indications of Failed Fuel Elements (None) i l

DOCUMENT ID 0043r/0031r

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2--_ = = _ _ _ _ _ _ _.. _ _ _. - _ _.

i

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT MARCH, 1989

-COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 DOCUMENT ID 0036r/0031r w

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(TABLE OF. CONTENTS i

. ~I.

INTRODUCTION

~

.II.

REPORT

.A.

SUMMARY

OF.' OPERATING EXPERIENCE B..

. PLANT OR' PROCEDURE CHANGES, TESTS, EXPERIMENTS,'AND SAFETY RELATED' MAINTENANCE'

~1.

Amendments to Facility License or Technical Specifications'

2.

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

3.

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

4.

Corrective Maintenance'of Safety-Related Equipment

.5.

Completed Safety Related Modifications C.;

LICENSEE EVENT. REPORTS D..

' DATA TABULATIONS I

,1.

LOperating 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 Failed fuel Elements J

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INTRODUCTION-:

The LaSalle. County Nuclear Power' Station 'is a; two-unit f acility. owned by Commonwealth Edison Company and' located near Marseilles, Illinois.. Each e

unit.is a Boiling ?!'er 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, i

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

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

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-II.

MONTHLY REPORT

~

A..

SUMMARY

OF OPERATING EXPERIENCE-

' Ray -

IiHLu Event l'

'0000 Reactor critical, generator on-line, 1100 MWE.:

2 1230 Reduced load to.950.MWE-to remove 1st-stage feedwater.

heater for maintenance.-

1 a

2300-Reduced load to 8850 MWE to recover. internal loads lost-by fault on SAT.

03 0300 Ramping to.950 MWE.

07 2000' Reduced' load to 700 MWE for feedwater heater-maintenance.

I-08 0530 Ramping to 1070 MWE.

09 0130 Reduced load to.950 MWE to remove "B". turbine-driven reactor ' feed pump for maintenance.

10.

0400 ~

' Ramping to.1130 MWE.

)

11-1430 Reducing load to 850 MWE for feed-water heater maintenance.

R

.12 0630 Ramping to 1130 MWE.

17 2130 Reducing load to 800 MWE for feedwater-heater maintenance.

18 0030 Ramping to 1130 MWE.

23 2130

' Reducing load to 850 MWE for feedwater-heater maintenance.

24 0830 Ramping to 1130 MWE.

l 31 2400 Reactor critical, generator on-line, 1120 MWE.

B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1.

Amendments to the Facility License or Technical Specification.

(None) i f

I l

DOCUMENT ID'0036r/0031r i

2.

Changes to procedures which are described in the Safety j

Analysis Report.

(None) l,-

3.

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

(None) 4.

Major corrective maintenance to Safety-Related Equipment.

See Table 1.

5.

Completed Safety-Related Modifications.

See Table 2.

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B;5 ~ TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS 4

MODIFICATION S N1111BER DISERIPTION M01-2-86-103 Snubber.' reduction on subsystem 2RH08 per the snubber.

reduction program.

'M01-2-87-050 Complete the installation of the inside Drywell Cooling area coolers.

M01-2-87-067

. Snubber reduction'on subsystem main steam and MSIV leakage control per the snubber reduction program.

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LICENSEE EVENT REPORTS LER Number Date Description (None) l J

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I D.

DATA TABUL.'.TIONS

1. Operating Data-Report (Attached)

2. Average Daily Unit Power Level (Attached)

3. Unit Shutdowns and Power Reductions (Attached)

DOCUMENT ID 0036r/0031r j

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D.i DPERATIDG DATA REPORT DOCRET NO. 05tMI?4 a '

UN'T LAEAU.E TWO DATE April'16,1989 c41PLETED BY J.W.ThlHSTECT-ItLui 3 E (615)-357 6761-OPERATING STATUS 51.' REPORTING PERIOD:

-MARCH 1989 GROSS NOURS IN REPCRTING PERIC!h 744

. 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):

3,323 MAX DEPEND CAPACITY fMWe-Neth 1,036 DESIGN ELECTRICAL RATING (MWe-Net) 1,078 l

. 3i. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Neth (None)

'4.. REASONS FOR RESTRICTION (IT ANY):

(N/A)

REPORTING PERIOD DATA THIS MONTH YEAR-TD-DATE CUMULATIVE'

%.TIMEREACTORCRITICAL(HOURS) 744.0 1,246.1 24,724.1 I

6. -TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.6 1,716.9

7. T!!:E GENERATOR DN-LINE (HOURS) 744.0 1,194.5 24,285.5

'8.

TIME GENERATOR RESERVE SHUTDOWN (HOCRS) 0.0

- 0.0 0.0

9. THERMAL ENERGY GENERATED (MWHt-Gross) 2,321,964 3,349,968 49,289,576

10. ELECTRICAL E;U.GY GENERATED (MWHe-Gross) 773,972 1,106,044

-22,810,182 iiJELECTRICALENERGYGENERATED(MWHe-Net) 747,725 1,064,936.

21,004,106

12. REACTOR SERVICE FACTOR (%)

100.0 57.7 63.4

13. T(EACTOR AVAILABILITY FACTOR (%)

100.0 57.7 '

67.8

14. SERVICE FACTOR (I) 100.0 55.3 62.3 i

15. AVAILABILITY FACTOR (I) 100.0 55.3

'62.3 116. CAPACITY FACTOR (USING MDC) (%)

97.0 47.6 54.0

'17. CAPACITY FACTOR (USING DESIGN HWe) (%)

93.2 45.7 51.9 18e FORCED OUTAGE FACIOR (%)

0.0 0.6 16.2

19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, ARD DURATION OF EACH):

(None)

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' 20. IF SHUTDOWN AT END Of PEPORT PERIOD, ESTIMATED DATE OF STARTUP:

(N/A)

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DOCXET NO. 030-374 UNIT LASALLE TWO f

D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)

DATE April to, 1987 COMPLE1ED BY J.W. THUNSTEDT TELEPHONE (815)-357-6761 f

I REPORT PERIOD:

-MARCH 1989 DAY POWER DAY POWER f

i 1,028 17 1,059 2

942 18 941 3

904 19 1,077

(

I 4

912 20 1,079 5

912 21 1,079 6

910 22 1,077 7

887 23 1,045 8

891 24 952 9

906 25 1,071 10 1,017 26 1,069 11 993 27 1,043 12 955 28 1,041 13 1,082 29 1,042 f

14 1,062 30 1,000 15 1,077 31 1,042 16 1,060 l

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DEL DU ED CE ERH POC F

S S

5 S

YFS T

FS 9

9 9

9 9

8 8

8 8

8

/

/

/

E 1

7 3

T 2

7 1

1 2

A

/

/

/

D 3

3 3

3 3

LA I

T Y' NR LE E R UB AQM 3

4 5

6 7

EE U YSN l

1,(

y .., * / E. - ' UNIQUE (REPDRTING REQUIREMENTS rf "

.. J ' :1. Safety / Relief; Valve Operations-DESCRIPTION VALVES

'NO'&. TYPE'

' PLANT-

'DATE' ACTUATED'

'ACTUATIONS:

CONDITIQt{ -

.OF EVENT _

3

-(None)

I' 2.

ECCS System Outages I

-OUTAGE NO.

EOUIPMENT PURPOSE 2-391-89 2B D/G Cooling' Water Replace' oil.

4

Pump-

'2-392-89 2B D/G.

Replace flexible conduit 2-408-89.

2E51-F012 (RCIC)

Repack valve.

2-42'l-89 2FWO1PC.

Replace-seals.

2-450-89 2A D/G-Replace immersion heater.

2-451-89 2A D/G Lubricate.

2-453-89'

2DG01P Lubricate coupling.

2-454-89 2DOO1P Lubricate coupling.

l 1

-DOCUMENT ID 0036r/0031r l

._____ _ i_______ _ - -- _ -

i

e:

L 4

i 3.

Off-Site Dose Calculation Manual (None)

Major c' anges, to Radioactive Waste Treatraent Systems.

4.

n (None) 5.

Indications of Failed Fuel Elements.

(None) l 4

I l

i l

l l

DOCUMENT ID 0036r/0031r

]

l o

Commonwealth Edison j

LaSalle County Nuclier Station Rural Route #1, Box 220 Marseilles, Illinois 61341 2

Telephone 815/357-6761 -

l l

April 10,1989 3

i 1

Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mall Station F1-137 Washington, D.C.

20555 ATTN Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for March, 1989.

Very truly yours, M

0 W

G. J. Diederich 8#Station Manager LaSalle County Station GJD/JWT/sjc Enclosure xc A.

B. Davis, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager D. P. Galle, CECO D. L.

Farrar, CECO INPO Records Center L. J. Anastasia, AIP Coordinator, Nuclear Services M. A. Ortin, GE Resident H.

E. Bliss, Manager of Nuclear Licensing W. F. Naughton, Nuclear ruel Services Manager C.

F.

Dillon, Senior Financial Coordinator, LaSalle Dennis Carlson/ Tech Staff Terry Novotney/INPO Coordinator, Tech Staff l

Central File l

1 1

DOCUMENT ID 0043r/0031r