ML20044C024

Monthly Operating Repts for Feb 1993 for LaSalle County Nuclear Power Station,Units 1 & 2.W/930310 Ltr

ML20044C024
Person / Time
Site:	LaSalle
Issue date:	02/28/1993
From:	Cialkowski M, Spedl G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9303160297
Download: ML20044C024 (23)

Text

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Commonwnith Ediron

. LaSalle County Nuclear Station 2601 N. 21st. Rd.

Marseilles, Illinois 61341 Telephone 815/357-6761 March 10, 1993 '

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l Director of Nuclear Reactor Regulation United States Nuclear Regulatory Comunission Mail Station F1-137 Washington, D.C. 20555 I

I ATIN: Document Control Desk ,

l l Gentlemen:

l l Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for February 1993.

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Very truly yours Y

1 Gary . Spedl Station Manager LaSalle County Station Enclosure l xc: A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Rossan, IL Dept. of Nuclear Safety B. Stransky, NRR Project Manager M. J. Nallace, CECO l D. L. Farrar, CECO I INPO Records Center l D. R. Eggett, NED l P. D. Doverspike, GE Resident l T. K. Schuster, Manager of Nuclear Licensing T. A. Rieck, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor W. P. Pietryga, QA/NS Off Site Review Station File l

9303160297 930228 pg PDR- ADOCK 0500

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a LASALLE NUCLEAR PONER STATICM UNIT 1 M3rIHLY PERFORMANCE REPORT FEBRUARY.1993 CGeeWNtEALTH EDISGI CCMPANY NRC DOCEET NO. 050-373 l LICENSE NO. NPF-11 l I

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1 TABLE OF CW TENTS l (UNIT I)

I. INTRODUCTIN d

II. REPORT

, A. SUBS 4ARY OF OPERATING EKPERIENCE B. AteENDNENTS *IO FACILITY LICEllSE OR TECIREICAL SPECIFICATIWS  ;

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4 C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPBENT k i j D. LICENSEE EVENT REPORTS ,

E. DATA TABULATINS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREBENTS

1. Main Steam Safety Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes l 4. Major Changes to Radioactive Maste Treatment System

5. Indications of Failed Fuel Elements i

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. L I. INTRODUCTICM (UNIT 1)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commnonwealth Edison Company and located near Marseilles, Illinois.

Each unit is a Boiling Water Reactor with a designed net electrical .

output of 1078 Megawatts. Maste 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 contractor was Commnonwealth Edison Company.

Unit one was issued operating license number NPF-11 on April 17, j 1982. Initial criticality was achieved on June 21, 1982 and comunercial power operation was comunenced on January 1, 1984.

This report was contpiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.

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I II. MONTHLY REPORT i

• l  ; ,A. SIDetARY OF OFERATICC EXPERIENCE (U31t 1)  !

I Day ' ting Event i 1 0000 Reactor critical, Generator off-line, forced outage i due to high turbine bearing vibrations.

1245 Generator on-line at 66 Mwe. f 3 0400 Generator off-line, perfonned turbine overspeed test. j 0531 Generator on-line.

2215 Increased power level to 350 Mwe.

4 0300 Upshifted Reactor Recirculation p eps, power level l increased to 448 Mwe. ,

l 0554 Increased power level to 624 Mwe. .

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! 5 1000 Increased power level to 850 Mwe. l 8 0100 Reduced power level to 600 Mwe to perfom rod set.

0800 Increased power level to 940 Mwe.

13 2000 Comunenced shutdown to perform maintenance on the 1E51-F063 valve.  ;

14 0110 Downshifted the Reactor Recirculation pumps, power level reduced to 524 Mwe. l 0345 Generator off-line.

1445 Reactor sub-critical. l l

19 1648 Reactor critical. I t

i 20 1325 Generator on-line at 50 Mwe. l t

21 0345 Upshifted the Reactor Recirculation pumps, power level increased to 380 Mwe. t

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2200 Increased power level to 975 Mwe. ,

24 0530 Reduced power level to 890 Mwe, placed the '

B' Turbine Driven Reactor Feed pump on-line. ,

i 2.5 0200 Reduced power level to 650 Mwe, performed rod set. 3 l

2200 Increased power level-to.1130 Mwe.

27 2000 Comunenced shutdown to perform maintenance on the _ l 1E51-F063 valve.

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II. MGETHLY REPORT 4

A. SUBMARY OF OPERATI%G EXPERIENCE (Unit 1)

DDy Ijang Event  ;

28 0200 Reduced power level to 545 Mwe. ,

0215 Downshif ted React.or Recirculation pumps, power level reduced to 220 Mwe.

j 0350 Generator off-line. ,

2400 Reactor critical, Generator off-line, forced outage in progress. ,

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B. AleENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATIGt '

Revised Lhe Technical Specification design features to allow '

increased spent fuel storage capacity.

C. MAJOD CORRECTIVE MATA"/'h16ANCE *ID SAFETY-RELATED EQUIPMENT (including SOR differential pic,sure switch failure reports ).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1) l i

LER Ntudter Date Description 93-004-00 02/10/93 Loss of the Reactor Core Isolation Cooling System 93-005-00 02/23/93 High radiation door violation.

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93-006-00 02/16/93 Inadvertant group 1 insolation.

93-007-00 02/26/93 Reactor Core Isolation Cooling valve 1E51-F063 l inoperable.

E. DATA TABULATIGtS (Unit 1) ,

1. Operating Data Report (See Table 2) i

2. Average Daily Unit Power Level (See Table 3) l

3. Unit Shutdowns and Significant Power Reductions (See Table 4)

F. UNIQUE REPORTING REQUIREMENTS (UNIT 1)

1. Safety Relief valve operations (None)

2. ECCS System Outages (See Table 5) l 3. Changes to the Off-Site Dose Calculation Manual

! (None)

4. Major Changes to Radioactive Maste Treatment Systems (None)

5. Indications of Failed Fuel Elements fone)

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C. TABLE 1 (Unit 1) . ,

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REQUEET _CEBERGBENT CAUEE OF MAIEUNCIEXI_ GRE M QP_KRATIJEf . .. CORRECTIVE ACTIJII LO8649 Control Room HVAC Flow switch OPDS-VC011 Air conditioner Replaced flow switch supply fan not available L16575 HPCS Diesel Meter not functioning Varmeeter inoperable Replaced Varmeter Generator varmeter L17909 Intermediate Range IRM burned out IRN inoperable Replaced IBM Monitor Channel E L18384 Reactor Core Valve 0-Ring Valve failed to close Replaced 0-Ring.

Isolation Cooling  ;

enhaust vacuum breaker valve IE51-F384 L18620 Feedwater inboard Valve gasket Valve failed leak rate Replaced gasket.

check valve test.

1B21-F010A L20960 Control Rod Drive Scram valves leaking Valves were slow to Replaced valves. 'y Hydraulic Control initiate during testing

. Unit 10-39 c

L21001 Control Rod Drive Scram valve solenoids Scram valves slow to Replaced solenoids.

Hydraulic Control open during testing i Unit 42-35 l

4 L21014 Control Rod Drive Nitrogen leaking None Replaced nitrogen charging Hydraulic Control fitting.

4 Unit'26-39 L21707 Interusediate Range Voltage preregulator Unable to adjust Replaced preregulator.

Monitor Channel H preregulator d

(Ec SOR failures this month.)

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TABLE 2 _i

E.1 OPERATING DATA REPORT  ;

l DOCKET NO. 050-373 l UNIT LASALLE ONE ,

DATE March 10, 1993 COMPLETED BY M.J.CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357-6761 ,

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1. REPORTING PERIOD: February 1993 GROSS HOURS IN REPORTING PERIOD: 672

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 l 1,036 i MAX DEPENDABLE CAPACITY (MWe-Net):

DESICH ELECTRICAL RATING (MWe-Net): 1,078 l

3. POWER LEVT,L TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A

4. PEASON FOR PESTRICTION (IF ANY):

THIS' MONTH ' YEAR TO DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 549.9 718.3 54,643.1  !

6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 f 7 GFNERATOR ON-LINE TIME (HOURS) 485.3 500.1 53,407.7 l

8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0

9. THERMAL ENERGY GENERATED (MWHt) 1,201,443- 1,238,411 156,298,569 ,

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 388,306 390,448 52,182,797 l

11. ELECTRICAL ENERGY GENERATED (MWUe-Net) 371,035 364,189 50,012,279

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12. REACTOR SERVICE FACTUR (%) 81.8 50.7 68.0

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13. REACTOR AV?ILABILITY FACTOR (%) 81.8 50.7 70.0  ;

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14. UNIT SERVICE FACTOR (%) 72.2 35.3 66.5 j

.15. ;11 NIT J VAU:IBILITY TACTOR (%) 72.2 35.3 66.5

16. UNIT CAPACITY FACTOR (USING MDC) (%) 53.3- 24.8 60.1

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 51.2- 23.9 57.7  !

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18. UNIT FORCED OUTAGE FACTOR (%) 27.8 29.3 7.2

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

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No Outages Scheduled

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 03/06/93 J l

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

DOCKET NO. 050-373 UNIT LASALLE ONE DATE March 10, 1993 COMPLETED BY M.J. CIALKOWSKI -

TELEPHONE (815)-357-6761 REPORT PERIOD: February 1993 DAY POWER DAY POWER 1 56 17 -12 2 173 18 -12 ,

3 188 19 -12  ;

4 652 20 74 6 5 771 21 765 6 796 22 947 7 786 23 929 8 846 24 921 I

9 885 25 998 I 10 890 26 1,090 11 896 27 1,044 12 892 28 49 13 828 29 14 43 30 15 -12 31 16 -12 l

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TABLE 4 E.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 20%

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DONN ACTIONS /COBSEENTS SEQUENTIAL DATE F: FORCED DURATIN THE REACTOR OR (LER/DVR S if NUMBER IIDGED_D] SI_SCMIMLLED LBQUES1_ REASQ[ REDJCING_PQNER applicable) 5 930131 F 12.8 A 4 Manual turbine trip due to high bearing vibrations (the reactor remained critical) 6 930203 S 1.5 B 4 Manual turbine trip to perform the main turbine

. overspeed trip test (the reactor remained critical) l 7 930214 F 153.7 A 1 Unit shutdown to repair i

an inoperable valve on the RCIC system (LERl93-004-00 DVR501-01-93-014) 8 930228 F 20.2 A 4 Unit shutdown to repair an inoperable valve on the RCIC system (LERl93-007-00 DVR501-01-93-023)

SUBSEARY OF OPERATIN:

The unit entered the month in a forced outage due to high bearing vibrations on the main turbine. The Unit was returned to service on 02/01/93. A scheduled turbine overspeed test was performed and the unit was returned to service. For the remainder of the month the unit experienced two additional forced outages due to an inoperable valve on the RCIC system. The Unit remained off-line at the end of the month with an expected return to service of 03/06/93

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Table 5 l F.2 ECCS System Outages l I

Note: The year and unit data has been removed fross the outage nusnber. l WTAGE_NO2 Emil1NHT BIREDSE {

4 (U-0) 0083 ODG01K Inspection and lubrication r

0085 ODG009 Repack Valve f I

(U-1) 0175 1E51-N010 Repair steam leak 0177 IE51-F063 Repair valve j 0179 0205  !

0244 j 0245 i 0199 1E51-C004 Motor replacement 0204 1E22-5001 Varmeter replacement i I

0;!19 IE22-F038 Ashninistrative control 0221 1E22-S001 Lubrication l 0238 1E12-F064C Aihninistrative control 4

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LASALLE NUCLEAR PONER STATIGE l

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MOITHLY PERFOEBUNCE REPORT i.

FEBRUARY 1993 COSIGNEALTH EDISGB CGEPANY l 6

NRC DOCKET NO. 050-374 LICENSE NO. NPF-18  ;

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t TABLE OF CCMTENTS (UNIT 2)

I. INTRODUCTIN II. REPORT A. SUletARY OF OPERATING EXPERIENCE B. ADSEENDMENTS "!O FACILITY LICENSE OR TECMICAL SPECIFICATINS '

C. MAJOR CORRECTIVE MAINTENANCE '!O SAFETY-RELATED EQUIPMENT i D. LICENSEE EVENT REIVRTS E. DATA TABULATINS l

1. Operating Data Report  !

2. Average Daily Unit Power Level [

3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS

1. Main Steam Safety Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Maste Treatment System

5. Indications of Failed Fuel Elements l

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I. INTRODUCTIGE (UNIT 2) '

l 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 Beactor with a designed net electrical output of 1078 Megawatts. Maste heat is rejected to a man-made l cooling pond using the Illinois river for make-up and blowdown. The l erchitect-engineer was Sargent and Lundy and the contractor was {

Commonwealth Edison Company. J 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 October 19, 1984. ]

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This report was compiled by Michael J. Cialkowski, telephone number l (815)357-6761, extension 2427.

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II. MCEtTHLY GEPORT A.

SUMMARY

OF CPERATIDG EKPERIENCE (Unit 2)  :

Day *line Eyggt 1 0000 Reactor critical, Generator on-line at 1075 Mwe.

0200 Reduced power level to 895 Mwe due to system load.

0430 Increased power level to 1135 Mwe.

i 2 0000 Reduced power level to 850 Mwe due to system load.

0500 Increased power level to 1135 Mwe.

2330 Reduced power level to 950 Mwe due to system load. i 1

3 0300 Increased power level to 1135 Mwe.

2300 Reduced power level to 850 Mwe due to system load.

4 0500 Increased power level to 1135 Mwe.

5 0100 Reduced power level to 1000 Mwe due to system load.

0430 Increased power level to 1135 Mwe. l 6 0000 Reduced power level to 1000 Mwe due to system load.

0400 Increased power level to 1135 Mwe.

7 0100 Reduced power level to 830 Mwe due to system load. i 0500 Increased power level to 1135 Mwe.

8 0100 Reduced power level to 993 Mwe due to system load.

0400 Increased power level to 1135 Mwe.

9 2100 Reduced power level to 850 Mwe, performed rod set and monthly surveillances.

10 0400 Increased power level to 1000 Mwe.

0600 Increased power level to 1050 Mwe.

1400 Increased power level to 1135 Mwe.

2300 Reduced power level to 1020 Mwe due to system load.

11 0500 Increased power level to 1100 Mwe.

0800 Increased power level to 1133 Mwe.

II. MGETHI.T REIVRT A. SIDE (ARY OF OPERATING EKFERIENCE (Unit 2)

Ray Time Event 15 2300 Reduced power level to 1000 Mwe, performed Feedwater system testing. ,

16 0400 Increased power level to 1100 Mwe. ,

0700 creased power level to 1135 Mwe.

17 2200 h%duced power level to 890 Mwe, placed the 'B' Turbine Driven Reactor Feed pump off-line for maintenance.

18 0330 Increased power level to 1006 Mwe.

21 0400 Reduced power level to 850 Mwe, placed the 'B' turbine Driven Reactor Feed pump on-line.

0830 Increased power level to 1050 Mwe.

1330 Increased power level to 1100 Mwe.

22 0630 Increased power level to 1135 Mwe.

24 0000 Reduced power level to 1085 Mwe due to system load.

0200 Increased power level to 1135 Mwe.

25 2100 Reduced power level to 890 Mwe, placed the 'A' Turbine ,

Driven Reactor Feed pump off-line for maintenance. l l

26 0400 Increased power level to 1000 Mwe.

2200 Increased power level to 1020 Mwe.

27 0100 Reduced power level to 900 Mwe, placed the 'A' Turbine Driven Reactor Feed pump on-line.

1400 Increased power level to 1075 Mwe.

2200 Increased power level to 1130 Mwe.

28 2400 Reactor critical, Generator on-line at 1132 Mwe.

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B. AMMENDMENTS *IO THE FACILITY OR TECHNICAL SPECIFICATICM (None)

C. MAJOR CORRECTIVE MAINTENANCE *IO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports ).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 2)

JER NumbgI Date DerglipliDD 93-001-00 02/22/93 Reactor Core Isolation Cooling high flow isolation SOR switch failure.

93-002-00 02/23/93 Failed to obtain required Reactor Core Isolation Cooling system flow.

E. DATA TABULATIONS (Unit 2)

1. Operating Data Report (See Table 2)

2. Average Daily Unit Power Level (See Table 3)

3. Unit Shutdowns and Significant Power Reductions (See Table 4)

F. UNIQUE REPORTING REQUIREMENTS (UNIT 2)

1. Safety Relief valve operations (None)

2. ECCS System Outages (See Table 5)

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

4. Major Changes to Radioactive Maste Treat 2nent Systems (None)

5. Indications of Failed Fuel Elements (None) l l

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C. TABLE 1 (Unit 2)

• 4 MAJOR CORRECTIVE MAINTENANCE TO "

• SAFETY-RELATED EQUIPMErr .

NORK RESULTS AND EFFECTS

_R!KRDIST CGEPGEENT OAllSE _OF MALENICTIGL_. GLSAFE PLANT OPERATILEt CORREt.nys._ ACTIGI L21566 Reactor Core Pressure switch Switch failed testing Replaced switch.  ;

Isolation Coollag 2E31-N013A Leak Detection Isolation logic I

(See attached SOR failure report.)

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.' TABLE 2 l

.' . E.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE TWO DATE March 10, 1993  ;

COMPLETED BY M.J.CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357_6761 {

1. REPORTING PERIOD: February.1993 GROSS HOURS IN REPORTING PERIOD: 672' ,

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPENDABLE CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078 i

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe_ Net): N/A

4. REASON FOR RESTRICTION (IF ANY):

THIS MONTH YEAR TO DATE CUMULATIVE ,

5. REACTOR CRITICAL TIME (HOURS) 672.0 1,416.0 52,429.5 l

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

7. GENERATOR ON-LINE TIME (HOURS) 672.0 1,416.0 51,472.4 <

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8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 -0.0 0.0

9. THERMAL ENERGY GENERATED (MWHt) 2,137,284 4,539,681 154,554,568 i

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 727',675 1,547,312 51,448,621

11. ELECTRICAL ENERGY GENERATED (MWHe_ Net) 702,021 1,494,905 49,407,838

12. REACTOR SERVICE FACTOR (%) 100.0 100.0 71.5

13. REACTOR AVAILABILITY FACTOR (%) 100.0 100.0 73.8

14. UNIT SERVICE FACTOR (%) 100.0 100.0 70.2

15. UNIT 1.VATLIDiLI7Y FACTOR (%) 100.0 100.0 70.2

16. UNIT CAPACITY FACTOR (USING MDC) (%) 100.8 101.9 65.0

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 96.9 97.9- 62.5 i

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 12.3  !

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

No Outages Scheduled-

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

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

DOC 7;ET NO. 050-373 ,

UNIT LASALLE TWO DATE March 10, 1993 '

COMPLETED BY M.J. CIALKOWSKI  ;

TELEPHONE (815)-357-6761 l k

REPORT PERIOD: February 1993 DAY POWER DAY POWER 1 1,048 17 1,083 1,031 18 948 3 1,066 19 977 4 1,022 20 976 5 1,072 21 972 6 1,064 22 1,083 i

7 1,035 23 1,088 n 1,069 24 1,084 I l

9 1,070 25 1,075 10 1,001 26 953 11 1,063 27 953 Ji 1,091 28 1,084 l' 1,091 29 14 1,094 30 15 1,092 31 l

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E.3 UNIT SHUTDONNS AND POWER REDUCTIOi45 > 204 (UNIT 2)

METIKE OF CORRECTIVE YEARLY TYPE SHUTTING DONN ACTIONS /COBeEENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR I if NUMBER (YYleEDD) SJ_H N .ip0URS)_ REASQE! REDRCING POWER applicable)

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SUDGEARY OF OPERATION:

The unit remained on-line at high power throughout the month. Several minor power reductions were required due to system loading, maintenance and surveillance activities.

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. Table 5 ,

F.2 ECCS System Outages ,

Note: The year and unit data has been removed from the outage number.

GITAGE_IlQ, EQUIPMEllT BIREQ6E 0119 2E51-F025 Solenoid coil replacement '

2E51-F026 ,

0122 2E51-F008 Administrative control I

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