ML20012B691

Monthly Operating Repts for Feb 1990 for LaSalle Units 1 & 2.W/900310 Ltr

ML20012B691
Person / Time
Site:	LaSalle
Issue date:	02/28/1990
From:	Diederich G, Thunstedt J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9003160115
Download: ML20012B691 (26)

Text

m r p iJ , 2, . - +? Commonwealth Edison I +.

,, , LaSal3 County Nuclear Sttion

' Rural Route #1, Box 220 Mart,ellies, Illinois 61341 Telephone 815/357-6761 March 10, 1990

!- Director of Nuclear Reactor Regulation y United States Nuclear Regula*.ory Commission Y Mail Station F1-137 washington, D.C. 20555 s ATTH: Document Contrca Desk p Gentlemens Enclosed for your informe'clon i'; the monthly performance report coverJ ng LaSL11e Ccunty Nr.cioar Power Station for February, 1990.

~Very trt.ly yours, s

G. J. D ederich-ation Manager LaSalle County Station GJ ps 3 Enclosure 4 xc A. B. Davis, NDC, Region III NRC Resident Inspector LaSalle

.Ill. Dept. of Nuclear Safety .

-P. Shemanski, NRR Project Manager D. P. Galle, CECO i D. L. Farrar, CECO INPO Records Center '

L. J. Anastasia, AIP Coordinator, Nuclear Servicas 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 p T. A. Hammerich, Regulatory Assurance Supervisor

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'J.'W. Gieseker, Technical Staff Supervisor ,

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!9003360115 900310

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LASALLE NUCLElst '30KTR STATION- l UNIT 1 i

!. f HCRTELY PERTORMANCE Rr POL 1' -!

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TEDr.QhnY 1990 -.

COtet0NWY,ALTH ED;3CN CtEPANt I i

L NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 .t

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i TABLE OF CONTENTS 1 I. . INTRODUCTION l I

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II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED-MAINTENANCE j 1.' ' Amendments.to Facility License or Technical Specifications

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

3. . Tests.and Experiments not covered in the Safety Analysis Report  !

4. Corrective Maintenance of Safety-Related Equipment

5. Completed Safety-Related Modifications l

C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report l

2. Average Daily Unit Power Level ,

3. Unit. Shutdowns and Power Reductions 1 E.

UNIQUE REPORTING REQUIREMENTS 1.. Main Steam Relief Valve _ Operations q

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 The LaSalle County Nuclear Power Station is a two-unit f acility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each unit is a Boilfng 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, 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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' .f --: i II . - MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE t

Day- Ilma Event 1 0000 Reactor critical, generator on-line at 2750 MWT.

0700 Returned to. full power 2- 2100 Reduced power to 2800 MWT for Turbine-driven feed pump problems.

3 0700 Increased power to 3000 MWT i

4 0045. Reduced power to 1902 MWT for rod pulls and i surveillances  :

t 5 1900 Increased power to 3320 MWT 6 0000 Reduced power to 3100 MWT for CRD exercising 0800 Returned to full power l

9- 0100 Reduced power to'2512 MWT for System load 1300 Returned to full power

'll 0100 Reduced load to 3000 MWT for System load 2 l

1400 Returned to full power 12 2300 Reduced power to 2300 MWT for CRD exercising I

13 1200 Returned to-full power i

15 0200 Reduced power to 2500 MWT for Heater Bay inspection l 1000 Returned to full power l

2359 Reduced power to 2000 MWT for Heater Bay work l 17 1500 Returned to full power l

19 2359 Reduced power to 3155 MWT for CRD exercising. j l

20 0800 Returned to full power 21 2300 Reduced power to 2500 MWT for System load l 22 1000 Returned to full power I l

27 0200 Reduced power to 2900 MWT for CRD exercising l l

1000 Returned to full power '

'28- 2400 Reactor critical, generator on-line at 3320 MWT l

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i .# v 'B. PLANT.OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTEN ANCE.

< 1 ~. Amendments to the Facility License or Technical Specification.

(None) i

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, including any SOR switch failure reports.

(See Table 1)

5. Completed Safety-Related Modifications.

(See Table 2)

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~ MAJOR CORRECTIVE MAINTENANCE TO-

SAFETY-RELATED EQUIPMENT . ..

WORK REQUEST. RESULTS'AND EFFECTS-

-NUMBER COMPONENT CAUSE OF. MALFUNCTION' ON SAFE PLANT OPERATION CORRECTIVE ACTION (Unit 0)

L96849 ODG01K UF Relay. Loose Linkage Cannot Reset Relay Adjusted Linkage (Unit 1)

L96682 1DG01K Governor Oil Leak Low Oil in Governor Installed Washer See attached report for SOR switch 1E31-N012AA.

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SOR-do Switch Failure Data Sheet 1

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4 Equipment Piece Number: 1E31-N012AA Model Number 103AS-B203-NX-JJTTX6 Serial Number: 85-1-2429 l 1

Application: Residual Heat Removal Shutdown Coolina Hiah Shutdown Flow Isolation Switch Date and Time of Discovery: 01/05/90 012Q hours Reactor Mode: 2 (Startuo) Power Level: 0%

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Calibration Tolerance: 167,4 - 169,4 'WC.

Nominal Setpoints 168,4 'WC D Action Limits: <163.0 or >173,8 'WC Reject Limits:' <158.8 or >178,0 "WC l

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Technical Specification l Limit

186,0 'WC 1

L As Found Setpoint N/A 'WC 1*

l Date and Time of Return to Service: 01/05/901712 hours l'

Model Number of Replacement Switch 103AS-B203-NX-JJTTX6 Serial Number of Replacement Switch 88-6-123 Causes Found a 1/2' tear in diaohraam between the cylinder disk outside diameter and 0-rina sealina surface. The root cause for the tear could not be determined.

Corrective Action: Inspected failed switch. Replaced and calibrated new switch.

DVR Number: 1-1-90-001

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.. in COMPLETED SATETY-RELATED MODITICATICHS NUMBER DESCRIPTION M01-1-84-074 The installation Of six (6) drywell area coolers and their associated structural, electrical, and mechanical components.

This required tie-ins with the= existing Chilled Water System

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and sump drain lines. This mod also required main structural steel be stiffened to support the new area coolers.

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M01-1-87-002 Detailed Control Room Design Review (DCRDR) for resolution of miscellaneous Human Engineering Discrepancies at Control Room Panel 1PM01J.

M01-1-87-003 Detailed Control Room Design Review (DCRDR) for replacement of '

Containment Monitoring Panel IPM13J in the Control Room. .t M01-1-87-026 Detailed Control Room Design Review (DCRDR) for-the resolution of miscellaneous Human Engineering Discrepancies at Control Room Panel 1H13-P601.

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1 le, LER Number.- Date Description-s g- :90-003-00 02/01/90 RCIC Isolation t, .-

!': 90-004-00 02/13/90~ Auto Start of "B" VC/VE Emergency Make-up Train D.- DATA TABULATIONS-i,, >

1. Operating Data Report.(attached)

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

3. - Unit Shutdowns and Power Reductions (attached)

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[ D i OPERATING DATA REPORT DOCKET NO. 650-373

- UNIT LASALLE ONE DATE March 10, 1990 q( COMPLETED DY J.W. THUNSTEDT

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TELEPHDNE(815)-357-6761 5 OPERATING STATUS'

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1.,REPORTINGPERIOD: FEBRUARY 1990 ' GROSS HOURS IN REPORTING PERIOD: 672 2.-: CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036_ 3 DESIGN ELECTRICAL RATING (MWe-Net) 1,078

3. POER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): '(None)'

4.[REASONSFORRESTRICTION(IFANY): (N/A)

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

5. TIME REACTOR CRITICAL (HOURS) 672.0 1,289.9 33,424.0-

- 6.s TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 - 0.0 1,641'.2 a.

!?. 1 TIME GENERATOR OH-LINE (HOURS) 672.0 1,189.2 32,607.5 .l 8.' TIME GENERATOR RESERVE SHUTDOWN tHOURS) 0.0 0.0 1.0

- 9. THERMAL ENERGY GENERATED (Mult-Gross)- 2,142,685.4 3,554,'279.4 9t',387,847.4

10.' ELECTRICAL ENERGY GENERATED (MWHe-Gross)- 736,052 1,210,624 30,279,165

11. ELECTRICAL EERGY GENERATED (MWHe-Net) 712,276 1,168,831 28,901,533

12. REACTOR SERVICE FACTOR (!)' 100.0 91.1 61.8

. 13. REACTOR AVAILABILITY FACTOR (Z) 100.0 '91.1- 64.9

14. SERVICE FACTOR-(%) 100.0 84.0 60.3

15. AVAILIBILITY FACTOR (%) 100.0 84.0 60.3

16. CAPACITY FACTOR (USING MDC) (1) 102.3 79.7 51.4.

'- 17. CAPACITY FACTOR (USING DESIGN MWe) (%) 98.3- 76.6 49.6

-10.' FORCED OUTAGE FACTOR (2) 0.0 4.0 10.0 I \

- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

(None)

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

(N/A)

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B' DOCKET NO. 056-373

. UNIT LASALLE ONE -

D.2 AVERAGE DAILY UNIT POWER LEVEL OlWe-Met) DATE N rch 10, 1990 COMPLETED BY J A THUNSTEDT R TELEPHONE (015)-357-6761 REPORT PERIOD: FEBRUARY 1990 3

- J f ' DAY ' POWER DAY POWER

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l' 11,046 17 962 2 1,088 18 1,102-c 3 976- 19 1,102 -

4 741 20 1,095 5' i,000 21 1,084 6 1,079- 22 1,035

.7 1,001 23 1,106 8 1,065 24 1.103 9 1,031 25 1,103 10 1,105. 26 1,101

. 11-. i.089 27 1,085 12- 1,103 . . 28 1,098 13 1,069. ' 29 14- 1,105 30 15 1,045 31 16 1,084 3

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. D.3 UNIT SHUTDONNS AND PONER REDUCTIONS > 20%- -

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NOTE: - This page is a correction to the JANUARY 1990 Report-- revised information is'noted by an *.- .

METHOD OF-YEARLY TYPE SHUTTING DONN

' SEQUENTIAL F: ' FORCED  : DURATION THE REACTOR OR CORRECTIVE NUMBER DATE S: SCHEDULED ^ -(HOURS) REASON REDUCING PONER ~ ACTIONS /COMENTS

• 54 9/15/89 S '*166.3 C 4 . Refueling Outage (L1R03)

1. 1 7 F *59.9 B *9 Unable to synchronize generator; shutdown reactor during maintenance ~on-generator exciter

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• 2 12 S 0 B 5 Turbine trip testing

1. 3 28 S 0 H 5 System load

• 4 29 S- 0 H :5 System load-a d

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. TYPE SHUTTING DONN YEARLY CORRECTIVE F: FORCED DURATION THE REACTOR OR SEQUENTIAL ACTIONS / Cope 6ENTS S: SCHEDULED -(HOURS) REASOtt REDUCING POTTER ,

NUMBER _- DATE O B 5 :..

Rod' pulls and surveillances.:

5 4 S O F 5 Systesa load 6 9 S

' CRD exercising-0 B. S' 7 12 S-0 -F 5 Heater Bay Inspection 8 15 S O 3 5 Heater Bay Work-9 15 S O F- 5 System load l 10 21 S

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E.' UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT

~(None)'-

2. ECCS System Outages OUTAGE NO. EQUIPMEtIT P_LIRPOSE the year and unit numbers have been ommitted from the Outage Number)

(Notes (Unit 0) 50 0 D/G Repair UV Reset Relay (Unit 1):

102- 1N62-C001A (D/G) Lubricate Coupling 105 B D/G Glycol Pump Lubricate Coupling 106 -1DG01P Lubricate Coupling 117 1DG08CB Check Hold-Down Screws 121- 1E12-C002A'(RH) Replace Bearing Oil

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

4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indications of Failed Fuel Elements.

(None)

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LASALLE NUCLEAR POWER' STATION UNIT 2 MONTHLY-PERFORMANCE REPORT FEBRUARY, 1990 COMMONWF.ALTH EDISON COMPANY NRC DOCKET NO. 050-374.

LICENSE NO. NPF-18 k-7.

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TABLE OF CONTENTS

1. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE .i 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. '

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L 4. Corrective Maintenance of Safety-Related Equipment

5. Completed. Safety Related Modifications 7 C. LICENSEE EVENT REPORTS i

! D. DATA TABULATIONS 2 age a yU t Power Level

( 3. Unit Shutdowns and Power Reductions L E. UNIQUE-REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations  ;

2. ECCS System Outages j 3. Off-Site Dose Calculation Manual-Changes Major Changes to Radioactive Naste Treatment System 4 .-

5.= Indications of Failed Fuel Elements l

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- I.. INTRODUCTION 1

The LaSalle County Nuclear Power Station.is a two-unit facility owned by i 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 neat is rejected to a man-made cooling pond using '1 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.

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SUMMARY

OF OPERATING EXPERIENCE  :

' pay --' ' Ih '. Erant 1 0000 Reactor critical, generator on-line at 3307 MWT 4 2350 Reduced load to 2960 MWT.for System load 5- 1200 Returned to full power 6 0930 Reactor scram due to spurious noise spike on ARPM "E" Neutron detector while part of Reactor Protection (APRM "F") was in 1/2 scram due to routine surveillances 7 2245 Reactor critical '!

8 1320 Generator on-13 ne 10 1700 Returned full power .. j 14 0300 Reduced load to 2526 MWT for CRD exercising 2200 Returned to full power ,

20 0030 Reduced power to.3100 MWT for CRD exercising

-0700 Returned to full power 12 8 ' 0200 Reduced power to 3110 MWT for CRD exercising 0600 Returned to full power 2400 Reactor critical, generator on-line at 3323 MWT c.

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

1. Amendments to the Facility License or Technical Specification.

p (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, _lucluding '

any SOR switch. failures.

(None) i,

5. Completed Safety-Related Modifications.

(None)1

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>M a.' 'C.. LICENSEE EVENT REPORTS LER Number D'a te ' Description 90-001-00 02/06/90 ' Reactor Scram During APRM Testing 002-00' 02/09/90 Surveillance Critical Date Exceeded ,

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.D. ' DATA.TABULATIOUS~

-1. Operating _ Data Report (Attached) l

2. Average Daily Unit Power Level (Attached)

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3. Unit Shutdowns and Power ~ Reductions (Attached) 9 F

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h UNIT LASALLE TWO . .,

DATE March 10, 1990 COMPLETED BY J.W.THUNSTEDT y TELEPHONE (815)-357-6761 ,

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OPERATING STATUS =

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i. SEPORTING PERIOD: -FEBRUARY 1990 GROSS HOURS IN REPORTING PERIODi 672

.2. CURRENTLY AUTHORIZED POWER LEVEL ( Mt): 3,323 MAIDEPENDCAPACITY(Me-Net): :1,036 KSIGN ELECTRICAL RATING (MWe-Net) 1,078

, ' 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) ( We-Net): (None) 4.'- REASONS FOR RESTRICTION'(IF ANY): (N/A) ,

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

< , I .5TIME REACTOR CRITICAL (HOURS)- 634.8 1,378.8 31,525.9,

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

7. TIME GENERATOR DN-LINE (HOURS) 620.2 1,364.2 31,047.3 t

8. TIME GENERATOR RESERVE SHUTDOWN (HOURS)-- 0.0 ' 0.0 0.0

9. THERMAL ENERGY GENERATED (MWHt-Gross) 1,983,048 4,400,983.2 99,721,031.2

~10.' ELECTRICAL ENERGY GENERATED ( WHe-Gross) 676,542 1,501,554 29,952,480.

Jil..ELECTRICAI. ENERGY GENERATED (MWHe-Net) 654,290 1.449,385- 28,684,690 ,

7,7 12. REACTOR SERVICE FACTOR (!) 94.5 97.4 67.0 t

.13. REACTOR AVAILABILITY FACTOR (%) 94.5 97.4 70.7 ,

14.SERVICEFACTOR-(1) 92.3 96.3 66.0 +

115.' AVAILIBILITY FACTOR (!) 92.3 96.3 66.0

16. CAPACITY FACTOR (USING MDC) (1) 94.0 98.8 58.9

17. CAPACITY FACTOR (USING DESIGN M e) '%) 90.3 95.0 '56.6-

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,18. FORCED OUTAGE FACTOR (%) 7.7 3.7 15.9 19.' SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Refueling 03/l?/90 12 Weeks

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

(N/A) t

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. . , _ DOCKET NO. 950-374 UNIT LASALLE TWO-D.2 AVERAGE MILY UN!i POWER LEVEL (MWe-Net) MIE March 10,1990-  !

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

REPORT PERIOD: FEBRUARY 1990 l,l MY' POWER ~ MY POWER I 1,093 17 1,095 2' 1.096 19 1.099 3 i,092 19 1.095 4 1,082 20 1,094

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$ i,065 21 1.087

-6 423 22 1,992 7 23 1,093 e

9 104 24 1,094 9- 805 25 1,090 1,056 26 1,067 11 1,060 27 1,087 4

-12 I.055 28 i,077 -

13 1,053 29-14 1,009 30 ,

15- 1,092 31 16 1,096 1

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YEARLY TYPE . SHUTTING DONN

! SEQUENTIAL ~ F: FORCED DURATION' THE REACTOR OR- CORRECTIVE

l. NUMBER DATE S: SCHEDULED . (HOURS) . . REASON CODE REDUCING PONER ACTIONS /COpeENTS .

i l 4 '6 F I51.8- H 3 -Spurious.. noise spike

- while in'1/2 protection, I

5 14 S- !O ~B 5 CRD exercising i

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L ;1. Safety / Relief _ Valve Operations VALVES NO & TYPE PLANT DESCRIPTION h vi DAIK ACTUATED ACTUATIONS CONDITION OF EVENT I

-(None) )

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-2. ECCS System Outages DUIAGE_ND_.. EQUIPMENT PEREOSE NOTE: The year and unit designators have been omitted from the Outage Number.

117 - 2A D/G

- Lubricate

'124 HPCS Water-leg pump Replace breaker.

126 2E12-F047B (PH) Perform EQ inspection

.127 2E12-F087B (RH) Perform LES-EQ-112 ,

128 2E12-F087B (RH) Inspect Limitorque operator 131 2E12-F049B (RH) Inspect torque' switch .

135- 2DG08CB Tighten screws 144. RCIC- Perform LES-DC-104, replace solenoids 146- RCIC Perform EQ inspection ,

148- 2E51-F360'(RI)' Rebuild Limitorque operator ,

' 150 ~ 2E51-C005 (RI) Repack-pump-151 2E51-F046 (RI) Perform LES-GM-130 152 2E51-F045 (RI) Perform LES-GM-130 153 ~2E51-F010 (RI) Perform LES-GM-130

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1163 2E12-F040A (RH) Inspect torque switch 164 2E12-F026A-(RH) Inspect torque switch 169 2C RHR Pump Repair Seal Cooler 173 2E12-C002C (RH) Megger motor 174 2C RHR Pump Isolate leakage Seal Cooler o

177 2A RHR Pump Perform LFP-GM-120 198~ 2E12-C300C (RH) Perform LES-GM-105 199 2E12-C300D (RH) Perform LES-GM-105 ZCADTS/7

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4 4.. Major-changes to Radioactive Waste Treatment Systems. .

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, 5. - Indications of Failed Fuel Elements. I

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