ML20064F858

Monthly Operating Rept for Feb 1994 for LaSalle County Nuclear Station

ML20064F858
Person / Time
Site:	LaSalle
Issue date:	02/28/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403150471
Download: ML20064F858 (19)

Text

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, Commonwealth Edisors LaSalle County Nuclear Str tion 2601 N. 21st. Rd.

Marseilles, !!finois 61341 Telephone 815/357-6761 March 7,1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 l

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Enclosed for your information is the monthly performance report covering i LaSalle County Nuclear Power Station for February 1994. j td \ x c D. J. Ray ]. ,

Station Manager j LaSalle County Station l

DJR/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 N[Mh R --

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LASALLE NUCLEAR POWER STATION j UNIT 1 l MONTHLY PERFORMANCE REPORT FEBRUARY 1994 COMMONWEALTH EDISON COMPANY NRC DOCKET No. 050-373 LICENSE NO. NPF-11 i

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1 TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING 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 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 Waste Treatment System S. Indications of Failed Fuel Elements 1

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l 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. I l

Unit one was issued operating license number NPF-11 on April 17, ,

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

This report was compiled by Michael J. Cialkowski, telephone number )

(815)357-6761, extension 2427. l l

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4 II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

Day Time Event 1 0000 Reactor critical, Generator off-line.

0630 Generator on-line at 60 Mwe.

2 0220 Power level at 335 Mwe.

0524 Power level at 460 Mwe.

• 2200 Power level at 1070 Mwe.

3 2300 Reduced power level to 725 Mwe for a rod set.

4 0430 Increased power level to 1130 Mwe.

B 0030 Reduced power to 900 Mwe to perform heater bay valve maintenance. '

0300 Increased power level to 1125 Mwe.

12 0000 Reduced power level to 1115 Mwe due to rod pattern.

17 1400 Reduced power level to 1075 Mwe, swapped the Condensate / Condensate Booster pumps. ,

1500 Increased power level to 1100 Mwe.

18 1400 Reduced power level to 750 Mwe for Main condenser seal inspection.

1900 Manual reactor scram for *cpair of the Main Condenser seal.

28 2400 Reactor sub-critical, generator of f-line, forced outage in progress.

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l B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION l Request for exigent Technical Specification ammendment to the reactor ,

protection system and end of cycle recirculation pump trip standard {

functional test interval from quarterly to monthly. I

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Request for additional information concerning ammendment to Technical Specification 3/4.0.

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

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1)

LER Number Date Rescription 94-003* 01/20/94 Reactor Protection System instrumentation surveillance was not performed due to cold weather.94-004 02/03/94 Rod Position Indication System was inoperable for a period greater than allowed by the station's Technical Specifications.

• At the time of the completion of the January Report a LER number was not assigned to this item. Upon further investigation it was decided that this item will be reported as an LER.

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 (None)

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)

. - l C. TABLE 1 (Unit 1) '

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REOUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L27030 Suppression pool Digital display Inaccurate indication Replaced digital display.

i water level wide range recorder '

ILR-CMO28 I L27105 'O' Diesel Alarm relay Contacts failed to Replaced relay.

Generator lube operate freely oil soak back pump

. L27106 'O' Diesel Overload relay Relay failed to operate Replaced relay.

Generator space heater L27118 Main steam Thermal overload Breaker failed trip Replaced breaker.

isolation valve test leakage control system pipe heater 1E32-B001E r

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! (No SOR failures this month.)

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TABLE 2 E.1 OPERATING DATA REPORT DOCKET NO. 050 373 UNIT LASALLE ONE DATE March 7, 1994 COMPLETED BY M.J. CI ALK0WSK!

TELEPHONE (815) 357-6761 OPERATING STATUS

- 1. REPORTING PERIOD: February 1994 GROSS HOURS IN REPORTING PERIOD 672 l

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe Net)l1 1,036 l DESIGN ELECTRICAL RATING (MWe-N 1,078 )

3, POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): N/A e

4. REASONS FOR RESTRICTION (if ANY): l REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE'

5. REACTOR CRlTICAL TIME (HOURS) 427,0 958.3 62,285.2

6. ~ REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2

7. GENERATOR ON-LINE TIME (HOURS) 420.5 946.3 60,960.0

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

9. THERMAL ENERGY GENERATED (MWHt) 1,322,746 2,959,412 180,285,049

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 438,672 1,000,026 60,254,397

11. ELECTRICAL ENERGY GENERATED (MWHe Net) 421,250 959,905 57,808,659

12. REACTOR SERVICE FACTOR (%) 63.5 67.7 69.9

13. REACTOR AVAILABILITY FACTOR (%) 63.5 67.7 71.7

14. UNIT SERVICE FALTOR (%) 62.6 66.8 68.4

15. UNIT AVAILIBILITY FACTOR (%) 62.6 66.8 68.4

16. UNIT CAPACITY FACTOR (USING MDC) (%) 60.5 65.4 62.6

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 58.2 62.9 60.2

18. UNIT FORCED OUTAGE FACTOR (%) 36.8 20,8 7.7 o.

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

20. lF SHUTDOWN AT END OF REPORT PER100, EST! MATED DATE OF STARTUP: 06/02/94

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DOCKET NO. 050-373 TABLE 3 UNIT LASALLE ONE E.2 AVERACE DAILY UNIT POWER LEVEL (MWe Net) DA1E March 7, 1994 COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357 6761 REPORT PERIOD: February-1994 DAY POWER DAY POWER 1 120 17 1,062 2 759 18 757 3 958 19 -12 l

4 1,040 20 -11 5 1,095 21 -11 i

6 1,095 22 -11 1 7 1,095 23 12 8 1,067 24 -12 i I

9 1,090 25 -12 l 10 1,089 26 -12 11 1,085 27 -12 l l

12 1,080 28 -12 '

l 13 1,075 29  ;

i 14 1,072 30

! 15 1,067 31 16 1,064

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

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METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 2 940131 F 6.5 A 4 Turbine trip due to a Moisture Separator Reheater pressure transmitter high level controller out of service.

3 940218 F 245.0 A 2 Unit shutdown to repair a main condenser boot seal leak.

SUMMARY

OF OPERATION:

The unit entered the month in a forced outage due a moisture separator reheater pressure transmitter high level controller being out of service. The unit was returned to service on 02/01/94. The unit then remained on-line at high power until 02/18/94 when the unit entered a forced outage. This outage was' required due to a main condenser boot seal leak. The month ended with the unit off-line.

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT FEBRUARY 1994 i COMMONWEALTH EDISON COMPANY NRC DOCKET No. 050-374 LICENSE NO. NPF-18 i

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TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A.

SUMMARY

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

l. 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 Waste Treatment System

5. Indications of Failed Fuel Elements l

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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 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 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) par Time Event l

1 0000 Reactor critical, Generator on-line at 1130 Mwe.

0130 Reduced power level to 1070 Mwe, swapped the condensate / Condensate Booster pumps.

0300 Increased power level to 1130 Mwe.

6 0300 Reduced power level to 990 Mwe for performance of a Feedwater pump surveillance.

1000 Increased power level to 1140 Mwe.

9 0130 Reduced power level to 1065 Mwe, swapped the Condensate / Condensate Booster pumps.

0600 Increased power level to 1130 Mwo.

10 0200 Reduced power level to 1065 Mwe, swapped the Condensate / Condensate Booster pumps.

1000 Increased power level to 1130 Mwe.

12 0100 Reduced power level to 850 Mwe to perform a rod set.

0600 Increased power level to 1140 Mwe.

17 1630 Reduced power level to 1070 Mwe due to system load.

1800 Increased power level to 1130 Mwe.

18 0000 Reduced power level to 1040 Mwe due to system load.

0800 Increased power level to 1140 Mwe.

20 0000 Reduced power level to 1000 Mwe due to system load.

0600 Increased power level to 1140 Mwe.

21 0200 Reduced power level to 1000 Mwe due to system load.

0800 Increased power level to 1140 Mwe.

22 0030 Reduced power level to 1070 Mwe due to system load.

0600 Increased power level to 1130 Mwe.

28 2400 Reactor critical, Generator on-line at 1130 Mwe.

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B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Request for exigent Technical Specification ammendment to the reactor l protection system and end of cycle recirculation pump trip standard I functional test interval from quarterly to monthly. )

Request for additional information concerning ammendment to Technical specification 3/4.0.

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 Date Description 94-002 02/21/94 Reactor Core Isolation Cooling system ,

turbine exhaust diaphragm ruptura disc blew out exhausting steam into the turbine room. ,

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

OUTAGE NO. EQUIPMENT PURPOSE 0110 2DG049A Repair air compressor discharge check valve.

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)

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 L27319 Low power range Power supply Power supply failed Replaced power supply. ,

monitor 40-09D testing (No SOR failures this month) l l

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TABLE 2 E.1 OPERATING DATA REPORT DOCKET No. 050-374 UNIT LASALLE TWO DATE March 7, 1994 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815)-357 6761 OPERATING STATUS

.1. REPORTING PERIOD: February 1994 GROSS HOURS IN REPORTING PERIOD: 6 72

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

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

4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THl$ MONTH YEAR-To-DATE CUMULATIVE

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, 5. REACTOR CRITICAL TIME (HOURS) 672.0 1,201.5 58,127.1

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

7. GENERATOR ON-LINE TIME (HOURS) 672.0 1,133.7 57,016.1

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

9. THERMAL ENERGY GENERATED (MWHt) 2,215,273 3,593,099 171,693,552

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 757,812 1,226,238 57,210,878

11. ELECTRICAL ENERGY GENERATED (MWHe Net) 734,209 1,182,793 54,938,684

12. REACTOR SERVICE FACTOR (%) 100.0 B4.9 70.8

13. REACTOR AVAILABILITY FACTOR (%) 100.0 B4.9 72.9

14. UNIT SERVICE FACTOR (%) 100.0 B0.1 69.4

15. UNIT AVAILIBILITY FACTOR (%) 100.0 80.1 69.4

16. UNIT CAPACITY FACTOR (USING MDC) (%) 105.5 80.6 64.6

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 101.4 77.5 62.1

18. UNIT FORCED OUTAGE FACIOR (%) 0.0 0.0 11.2

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

20. IF SHU1DOWN AT END OF REPORT PER100, ESTIMATED DATE OF STARTUP:

. DOCKET No. 050-374 TABLE 3 UNIT LASALLE TWO E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE March 7, 1994 r COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 -'

REPORT PERIOD: February 1994 DAY POWER DAY POWER 1 1,090 17 1,098 ,

2 1,095 18 1,079 3 1,097 19 1,094 4 1,100 20 1,078 5 1,100 21 1,077 6 1,080 22 1,091 7 1,096 23 1,101 8 1,099 24 1,066 9 1,094 25 1,100-10 1,093 26 1,097 11 1,095 27 1,101 12 1,069 28 1,103 13 1,099 29 14 1,099 30

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TABLE 4 t

E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

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METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS l SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

I (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 maintenance and surveillance activities.

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