ML20058M477

Monthly Operating Repts for Nov 1993 for LaSalle County Nuclear Station

ML20058M477
Person / Time
Site:	LaSalle
Issue date:	11/30/1993
From:	Cialkowski M, Schmeltz J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9312210001
Download: ML20058M477 (18)

Text

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4. ..- Commonwraith Edison

, LaSa!!e County Nuclear Station 2601 N. 21st. Rd.

Marseilles, Illinois 61341 Telephone 815/357-6761 I

December 9,1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for November 1993.

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Joseph V. Schmeitz Acting Station Manager LaSalle County Station JVS/tmb Enclosure cc: Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project Manager - LaSalle GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Manager of Nuclear Licensing - Downers Grove Nuclear Fuel Services Manager - General Office QA/NS Off-Site Review - General Office INPO Records Center Station File 2109IO TTi bl T'624#

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT NOVEMBER 1993 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPP-11

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1 TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATINO EXPERIENCE B. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions P. UNIQUE REPORTINO REQUIREMENTS

1. Main Steam Safety Relief Valve Operations

2. EOCS System Outages

3. .Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Failed Fuel Elements

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d I. INTRODUCTION (UNIT 1)

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 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 compiled by Michael J. Cialkowski, tLlephone number (815)357-6761, extension 2427.

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' II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

RAI Time Event 1 0000 Reactor critical, Oenerauor on-line at 1135 Mwe.

s 5 2300 Reduced power level to 1300 Mwe due to system load.

6 0300 Increased power level to 1135 H$ee.

18 0100 Reduced power level to 750 Mwe to perform a rod set. ,

1000 Power level at 1135 Mwe.

24 0200 Reduced power level to 1065 Mwe to transfer the condensate pumps.

1100 Increased power level to 1135 Hwe.

30 2400 Reactor critical, Generator on-line at 1135 Mwe.

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d B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

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

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1)

(None)

E. DATA TABULATIONS (Unit 1)

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 1)

1. Safety Relief Valve Operations (None)

2. ECCS System Outages Note: The year and unit data has been removed from the outage number.

OUTAGE NO. EOUIPMENT PURPOSE 0801 IDG08CA Relief valve repair.

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

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

5. Indications of Failed Fuel ElementJ (None)

C. TABLE 1- (Unit 1)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESUT-TS AND EFFECTS REOUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L25663 Average Power Range K14 Relay Spurious alarms Replaced relay.

Monitor Channel E i

(No SOR failures this month.) ,

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. TABLE 2 )

. E.1 OPERATING DATA REPORT _

l DOCKET NO. 050-373 UNIT LASALLE ONE DATE December _7, 1993 l COMPLETED BY M.J.CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357-6761

1. REPORTING PERIOD: November 1993 GROSS HOURS IN REPORTING PERIOD: 720 ,

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

- DESIGN ELECTRICAL RATING (MWe-het): 1,078

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

.4. REASON FOR RESTRICTION (IF ANY):

THIS MONTH YEAR TO DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 720.0 6,658.2 60,582.9

6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 7.- GENERATOR ON-LINE TIME (HOURS) 720.0 6,362.1 59,269.7

~ 8. UNIT RESERVE SHUTDOWN TIME (HOURS)- 0.0 0.0 1.0 9 ', THERMAL ENERGY GENERATED (MWHt) 2,373,650 19,961,175~ 175,021',333

- 10. ELECTRICAL ENERGY GENERATED'(MWHe-Gross) 811,006 6,678,568 58,470,917

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 789,221 6,443,550 56,091,640

12. REACTOR SERVICE FACTOR (%) 100.0 83.1 69.7-13., REACTOR AVAILABILITY FACTOR (%) '100.0 83.1 71.6

14. UNIT SERVICE FACTOR (%) 100.0 79.4 68.2 15.. UNIT AVAILIBILITY FACTOR (%) 100.0 79.4 68.2-16 UNIT. CAPACITY FACTOR (USING MDC) (%)~ 105.8 77.6 62.3

17. UNIT CAPACITY FACTOR'(USING DESIGN'MWe) 101.7 '74.6 59.8 4

18. UNIT FORCED OUTAGE' FACTOR.(%) -0.0 12.9 '7.6

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

Refuel, 03/18/94, 11 Weeks *

.- 20. IF SHUTDOWN'AT END OF REPORT PERICD, ESTIMATED DATE OF STARTUP:

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TABLE 3 ,

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

DOCKET NO. 050-373 UNIT LASALLE ONE DATE December 7, 1993 COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761 REPORT PERIOD: November 1993 DAY POWER DAY POWER 1 1,100 17 1,086 2 1,098 18 1,026 3 1,087 19 1,097 '

4 1,093 20 1,098 5 1,085 21 1,102 6 1,101 22 1,101 i

7 1,102 23 1,100  !

8 1,102 24 1,098 9 1,102 25 1,101 10 1,104 26 1,099 l

1 11 1,104 27 1,100 l

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i 12 1,104 28 1,101 j

.l 13 1,102 29 1,090 j i

14 1,101 30 1,098 15 1,100 31 16 1,101

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

(UNIT 1)

METHOD OF CORRECTIVE

!' YEARLY _ TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None).

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SUMMARY

OF OPERATION:

The unit remained on-line at high power throughout the month. Several minor power reductions were required during the month due to routine surveillance activities.

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LASALLE NUCLEA.R POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1993 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 b

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4 TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATINO EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

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

1. Main Steam 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

I. INTRODUCTION (UNIT 2)

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 not electrical output of 1078 '4egawatts. 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 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 October 19, 1984.

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

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II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Ti_ma Event 1 0000 Reactor sub-critical, Generator of f-line.

30 2400 Reactor sub-critical, Generator off-line, refuel outage in progress.

B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

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

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 2)

LER Number Ra_te Descrip_ tion 93-009 11/29/93 Alternate feed to the Reactor Protection System tripped while starting the Reactor Recirculation system.

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

OUTAGE NO. EOUIPMENT PURPOSE 1480 2E51-F022 Repair oil leak.

1530 2E12-F040A Replace motor, circuit breaker and thermal overloads.

1600 2E12-F042C Valve repair.

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)

b' C. TABLE 1 (Unit 2) . .

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REOUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L13186 Main Steam excess Poppet and spring Valve failed to return Replaced poppet and flow check valve to the open position spring.

2B21-F367 L15541 Low Power Range Auxiliary card Signal drifting Replaced auxiliary monitor 40-33 card.

Ll6905 Residual Heat Valve packing leakage None Repacked valve.

Removal min flow bypass stop valve 2E12-F064C L18953 Residual Heat Valve packing leakage None Repacked valve.

Removal heat exchanger outlet stop valve 2E12-F068B L24215 Hydraulic Control Scram valve pilot air None Replaced valve fittings.

Unit 38-35 isolation valve L25238 Nuclear Boiler Poppet and spring Erratic Valve operation Replaced poppet and system excess spring, flow check valve 2B21-F382 L25381 Source Range SRM cable Inaccurate indication Replaced cable.

Monitor Channel A L25410 High. Pressure Field flash time delay None Replaced relay.

Core Spray Diesel relay Generator-2E22-S001 L23766 Reactor Recirc Valve handwheel does None Replaced handwheel pump B suction not engage nut and thrust washers.

vent valve 2B33-F025B (No SOR failures this month)

. TABLE 2

. E.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE TWO '

DATE December 7, 1993 COMPLETED BY M.J.CIALKOWSKI-OPERATING STATUS TELEPHONE (815) 357-6761

1. REPORTING PERIOD: November 1993 GROSS HOURS IN REPORTING PERIOD: 720

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

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

4. REASON FOR RESTRICTION (IF ANY): ,

THIS MONTH YEAR TO DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 0.0 5,719.8 56,733.3

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

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7. GENERATOR ON-LINE TIME (HOURS) 0.0 5,697.4 55,753.8

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

9. THERMAL ENERGY GENERATED (MWHt) 0 17,910,531 167,925,418 10 ELECTRICAL ENERGY GENERATED (MWHe-Gross) O 6,030,629 55,931,938

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) .-8,035 5,800,382- 53,713,315

12. REACTOR SERVICE FACTOR (%) 0.0 71.4 71.0

13. REACTOR AVAILABILITY FACTOR (%) 0.0 71.4 73.1

14. UNIT SERVICE FACTOR (%) 0.0 .71.1- 69.7  !

15. UNIT AVAILIHILITY FACTOR (%) 0.0 71.1 69.7- ,

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16. tmIT CAPACITY FACTOR (USING MDC) (%) -1.1- -69.8 64.9

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.0 67.11 62.3

'18.' UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 11.5 1

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

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20 'IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 12/20/93

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. TABLE 3

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

, . DOCKET NO. 050-373 UNIT LASALLE 'IMO l DATE December 7, 1993 l COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761 l

REPORT PERIOD: November 1993 DAY POWER DAY POWER  ;

1 -11 17 -11 2 -11 18 _11 ,

3 -11 19 -11 4 -11 20 -11 S -11 21 -11 i

6 22 -11  !

7 -11 23 -11 8 -11 24 -11  !

9 -11 25 -12 l

10 -11 26 -12 11 -11 27 -12 12 -11 28 -12 13 29 -12 14 -11 30 -11 ,

15 -11 31 16- -11 I

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E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2) .

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL .DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable) 3 930904 S 720 C 2 Refueling Outage

'(L2R05)

SUMMARY

OF OPERATION:

The unit entered a scheduled refueling outage on 09/04/93.

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