ML20246M118

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Monthly Operating Repts for June 1989 for Lasalle Units 1 & 2
ML20246M118
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 06/30/1989
From: Diederich G, Thunstedt J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8907190064
Download: ML20246M118 (21)
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- Commonwrith Edison..

' bSails County Nuclear Station i Rural Route #1, Box 220.

[; Marseilles. Illinois 61341 =

j- Telephone 815/357-6761 t

July 7, 1989

- Director of Nuc?. ear Reactor Regulation United States Nuclear Regulatory Commission Mail 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 June, 1989.

Very truly yours,

.( th G. J. Diederic ,

  • Station Manage LaSalle County Station

- GJD/JWT/sjc

- Enclosure xc: A. B. Davis, NRC, Region III MRC Resident Inspector LaSalle 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

'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 Terry Novotney, INPO Coordinator, LaSalle Station T. A. Hammerich, Regulatory Assurance Supervisor J. W. Gieseker, Technical Staff Supervisor Central File DOCUMENT ID 0043r/0031r 8907190064 890630 PDR ADOCK 05000373  ;

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I LASALLE NUCLEAR POWER STATION UNIT 1.

MONTHLY PERFORMANCE REPORT JUNE 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 DOCUMENT ID 0043r/0031r l.

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a I. INTRODUCTION 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 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 One was issued operating license number NPF-11 on April 17, 1932.

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

This report was compiled by John W. Thunstedt, telephone number (815)357-6751, extension 2463.

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I.. INTRODUCTION.

i' II. REPORT U

A.

SUMMARY

OF OPERATING EXPERIENCE D. 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.

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 DOCOMENT ID 0043r/0031r m_ _____________.___.Z___..__ - - _ _ _ _ . - . _ _ - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ . - _ _ _ _ - - _ _ _ _ _ _ _

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SUMMARY

OF. OPERATING EXPERIENCE' DJy limg - Event

_- L LOOOO. . Reactor Critica1'and generator on-line at 1100 MWe.

12 0000 Load' drop to-850 MWe for Load Dispatcher.

0400 Recovery from load: drop.

3, 0000. Load drop to 850 MWeJfor Load' Dispatcher 0400 Recovery from load drop.

ll 14 .0000 Load drop to 850 MWe'for. Load Dispatcher 0400 Recovery from load drop.

l 5 0000 Load drop'to 850 MWe for-Load Dispatcher.

E 0400 ' Recovery from load drop.

6 0000' L'oad drop.to 850 MWe for Load Dispatcher 0400 . Recovery from load drop.

L j 7 0000' . Load drop to 800 MWe:for Rod pulls.

L 0400' Recovery from load drop.

l 8 0000 Load drop to.850 MWE for Load Dispatcher 0400 _ Recovery from load drop.

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30 '2400 Reactor Critical, generator on-line at.1100 MWe.

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

1. Amendments to the Facility License or Technica1' 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)

4. Major corrective maintenance to Safety-Related Equipment.

(See Table 1)

5. Completed Safety-Related Modifications.

(None)

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! ". C . ' LICENSEE EVENT REPORTS l

.. LER Number . Datg ' ~ Description l

l 89-021-00 06/09/89 Failure of IE51-T008 to Open.

D. DATA TABULATIONS

1. Operating Data Report (attached)
2. Average Daily Unit Power Level (attached)
3. Unit Shutdowns and Power Reductions (attached) i I

DOCUMENT ID 0043r/0031r I

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D.i OPERATIE DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ole DATE Aly it,1999 COMPLETD BY J.W. THUNSTElf j TELEPHONE (B15)-357-6761 r:.y OPERATING STATU6 GR098 HOURS IN REPORTING PERIOD: 720

f. KPORTIE PERI 00: JUNE 1999 MAX EPDil CAPACITY (MWe-Net): 1,036 3,323
2. CURRENTLY AUTHORIZED POWER LEVEL (1981):

KSIGN ELECTRICAL RATING (MWe-liet) 1.078 (None)

'3.' POWER LEVEL TO WICH RESTRICTD (IF AIIY) (MWe-Net):

4. REA9ONS FOR fulTRICTION (IF ANT): (N/A)

REPORTINGPERIODDATA TNIS MONTH YEAll-TO-DATE . CLBRLATIVE 720.0 4,269.3 30,288.6

5. TIME REACTOR CRITICAL (HOURS) 0.0 0.0 1,641.2

'6.-TIME REACTOR RESERVE SHUTDOWil (HOURS) 720.0 4,259.1 29,573.6

.7. TIME GENERATOR ON-LINE (HOURS) 0.0 0.0 1.0

8. TIME GENERATOR RESERVE SHUTDOW (HOURS!

2,214,696 13,422,238 82,200,816

9. THERMAL ENERGY GENERATO (fttit-Gross) 736,560 4,561.109 27,206,863
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 708,376 4,396,465 25,971,994
11. ELECTRICAL ENERGY GENERATED (MWHe-Nei) 100.0 98.3 62.9 12.-REACTOR SERVICE FACTOR (%)-

100.0 98.3 66.3

13. REACTOR AVAILABILITY FACTOR (%)

100.0 98.1 61.4

14. SERVICE FACTOR (%)

100.0 98.1 61.4

15. AVAILABILITY FACTOR (%)

95.0 97.7 52.0

16. CAFACITY FACTOR (USING HDC) (%)

91.3 93.9 50.0

17. CAPACITY FACTOR (USIE DESIGN MWe) (%)

0.0 1.9 10.7

18. FORCD OUTAGE FACTOR (%)
19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYFE, DATE, AND DURATION OF EACH):

Refuel 9-03-89 12 Weeks

20. IF SHUTIt0WN AT END OF REP 0lti FERIOD, ESTIMATO DATE OF STARTUP:

(N/A)

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-UNITLASALLEOK AVEFAGE BAILY UNIT poler LEVEL owe-Net) DATE July it, 1989

-0.2 COMPLETED BY J.W. TituMSTEDT

'TELEPHO E (815)-357-6761' REPORT PERIOB: JUNE 1989 BAY ' POKR ' ' MY POWER

,1. 1,031 17 977 2 ' 998 ft 975 3- 976. 19 976 4 919 20 975 5 928 21 981 6 973 22 983 7 956 23 1,051 1,026 - 24 -1,026 8

9 989 25 940 to 976 26 998 11 826 27 1,015 936 28 951 12 -

13 1,026 29 986 14 1,063 30 1,052 15 1,007 31 16 1,001 l

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N.* , 'E.' UNIQUE REPORTING REQUIREMENTS
1. Safety / Relief. valve operations VALVES NO & TYPE PLANT ' DESCRIPTION DATE! ACTUATED ACTUATIc"i CQHDLTIDH 'QF EVENT 4

(None)-

2. ECCS System Outages DUTAGE NO. EQUIPMENT PURPOSE (Unit 0) 0-182-89 0 D/G Replace shutdown solenoid LUBLT ll '

1-318-89 1E51-F063 Replace butt-splice (RCIC) 1-322-89 0 RHR Clean seal-water cooler 1-328-89 1E12-F026B~ EQ Inspection (RH) 1-329-89 1E12-C002B Clean seal-water cooler (RH) 1-337-89 1E12-F093 Perform LES-EQ-112 (RH) 1-347-89 1E51-F063/76 (Administrative)

,( RI )

1-348-89 1E51-F008 Trouble-shoot / repair (RI).

1-349-89 1E51-F008 (Administrative)

(RI) 1-352-89 1E12-F049A EQ Inspection (RH) 1-353-89 1E51-F059 EQ Inspection (RI)

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J- '1-354-89 1E51-F059 Rebuild Limitorque (RI) 1-356 1E51-F022 (Administrative)

(RI) i.

1-357-89 1E12-F040A (Administrative)

(RH) 1-371-89 1E12-N512C Repair (RH) 3-374-69 1E12-F336B Perform LES-EO-112 (RH)

IH 1-375-89 1E12-F336B Rebuild operator (RH) 1-390-89 1B D/G Change filter.

1i392-89 1B D/G Change head gaskett A Air-start comptessor 1-393-89 1B D/G Change head gaskets B Air-start compressor 1-395-89 1E12-F040A Inspect torque switch (RH) 1 400-89 1F12-F008 (Administrative)

(RH)

3. Off-Site Dome Calculation Manual (None)
4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indications of Failed Fuel Elements.

(None) l l

i DOCUMENT ID 0043r/0031r l

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i' LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT JUNE, 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 1

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DOCUMENT ID 0036r/0031r j j

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I. INTRODUCTION The LaSalle 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 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 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.

DOCUMENT ID 0036r/0031r

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l l TABLE OF CONTENTS l

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
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 Failed Fuel Elements DOCUMENT ID 0036r/0031r

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l II. MONTHLY. REPORT L

l A.

SUMMARY

OF OPERATING EXPERIENCE Day Time Event 1 0000 Reactor critical and generator on-line at 1000 MWe.

Dropping load to 830 MWe for CRD exercising and MSIV Testing.

0500 Return to full power.

6 0000 Load drop to 880 MWe for Load Dispatcher.

0430 Return to full power.

9 0000 Load drop to 950 MWe for Load Dispatcher.

16. 1700 Load drop to 630 MWe for MSIV closure.

30 2400 Reactor critical and generator on-line at 900 MWe.

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

1. Amen &nents to the Facility License or Technical Specification.

Increased spent fuel storage capacity.

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)

4. Major corrective maintenance to Safety-Related Equipment.

(See Table 1)

5. Completed Safety-Related Modifications.

(None) i DOCUMENT ID 0036r/0031r

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l . .c C.. LICENSEE EVENT REPORTS LER Humber Date Description 39-007-00 06/12/89' Loss of System Aux Transformer (SAT) 89-008-00 06/14/89 HPCS DG Feed Breaker Failure 89-009-00 06/19/89 Failure of RCIC High Steam Flow Switch (SOR)

D. DATA TABULATIONS l

1. Operating Data Report (Attached)
2. Average Daily Unit Power Level (Attached)
3. Unit Shutdowns and Power Reductions (Attached)

DOCUMENT ID 0036r/0031r

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D.i OPERATIE NTA REPORT DOCRET NO. 950-374 UNIT LASALLE TWO DATE July it,1989 COPFLETED BY J.W.THUNSTDT TELEPHONE (015)-357-6761 OPRATIE STATUS GROSS HOURS IN REPORTIE PERIOD: 720

i. K PORTING PERIOD: . JUNE 1999 MAX DEPEW CAPACITY (MWe-Met): 1,036 2, CURRENTLY AUTHORIZED POWER LEVEL (Mt): 3,323 DESIGN ELECTRICAL RATIE (MWe-tiet) 1,076 l

(None)

3. POWER LEVEL TO WHICH RESTR M D (If ANY) (MWe-ht):
4. REASONS FOR RESTRICTION (IF ANY): (N/A)

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE 720.0 3,429.1 26,907.1

-5. TIME REACTOR CRITICAL (HOURS) 0.0 0.0 1,716.9 6.1 TIE REACTC:: RESERVE SHUTDOWN (HOURS) 720.0 3,377.5 26,468.5

~ 7. TIhE GENERATOR ON-LINE (HOURS) 0.0 0.0 0.0

8. TIME GENERATOR RESERVE SHUTDOWN (HOURS) 2,120,352 10,255,008 76,194,616
9. THERMAL ENERGY GENERATD (MWHf-Gross) 686,427 3,384,220 25,087,558
10. ELECTRICAL ENERGY GENEP.ATED (MWHe-Gross) 660,742 3,262,995 24,002,245
11. ELECTRICAL ENERGY GENERATO (MWHe-tiet) 65.3 j 100.0 79.0
12. REACTOR SERVICE FACTOR (%)

100.0 79.0 69.5

13. REACTDR AVAILABILITY FACTOR (%)

(60.0 77.8 64.3

14. SERVICE FACTOR (%)

100.0 77.8 64.3

15. AVAILABILITY FACTOR (1) 88.6 72.5 54.3
16. CAPACITY FACTOR (USING MDC) (I) 85.1 69.7 54.1
17. CAPACITY FACTOR (USIE DESIGN We) (1) 0.0 0.2 15.1
18. FORCED OUTAGE FACTOR (2) . ........
19. SHUTDOWNS SCHO ULED DVER THE NEXT 6 liDNTHS (TYPE, DATE, AND DURATION OF EACH):

j (None)

20. IF SHUTDOWN AI END OF REPORT PERIOD, ESTIMATED DATE OF STARTijP:

(N/A)

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BOCKET 2 . 056-374

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IA'IT LAGALLE TWO DAh' Jety it,1999 D.2 AVERAGE MILY 1511 POER LEVEL Olle-Net)

COMPLETED BY J.s. THUNSTEDT.

TELEPHONE (815)-357-6761 K

' REPORT PERIOD: JtBE 1989 LAY POWER HT POER~

973 17 779 1

1,052 18 - 775 2

3 1,H5 19 778 935 20 775 4

1,034 . 21 775 5

776 's 4 999 22

- 7: 1,040 23 787 1,034 24- 785 8

9 1,000 25. .771 1,003 26- 818 10-11 1,039 27 880 -

1,026 28 870 -

12 1,004 29 879 13 14 'i,097 30 884 15 6,033 31 16 976

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2. ECCS System Outages QQTAGE NO. EOUIPMENT ' PURPOSE. b 7-2-615-89 '2B'D/G haplace control,+.oom meters.

'2-616-89 2B D/G- Install watt r.eters.

. ,  ; 7:

2-617-89 '2B D/G- Calibrate watt meters.

.2-618 2B D/G: . Replace air-start motors.

. 2-623-89. 2B D/G Change' fuel-oil assembly.

2-624-89 2B D/G- (Administrative)

. 2-625-89 2B'D/G- Inspect diesel.

o 2-626-89 12B D/G Inspect diesel'.. 1

'2-628-89 U-2 SAT reed Megger HPCS motor.

to. Bus 243 2-629-89 2B D/G ~ Move exciter.

2-630-89 .2B D/G Remove engine / generator' coupling.

i. . 2-643-89 2B D/G Replace turbo-charger motor.

2-656a89 HPCS Injection Perform LST-89-071 YJ valve 2-657-89 2TE03PA (DG) Lubricate coupling

' 2-667-89 '2E12-F008 ( A&ninis trative )

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3. Off-S2
  • Dose Calculation Manual (None)
4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indicatioits of Failed Fuel Elements.

(None)

- DOCUMENT-ID 0036r/0031r

_x--___-----._--.____._____J_._______,_

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