ML20076F416

Monthly Operating Rept for Sept 1994 for LaSalle County Nuclear Power Station

ML20076F416
Person / Time
Site:	LaSalle
Issue date:	09/30/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9410170147
Download: ML20076F416 (17)

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Commonwsalth Edison '

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

. . Marseilles, Illinois 61341 Telephone 815/357-6761 l

l October 11,1994 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 September,1994.

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D. J. Ray Station Manager LaSalle County Station DJR/tmb Enclosure cc: John B. Martin, Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project Manager - Washington, D.C.

GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Licensing Operations Director - Downers Grove Nuclear Fuel Services Manager - General Office Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Station File 7 , o 9410170147 940930 PDR ADOCK 05000373 /

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I.ASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT September 1994

-COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 I

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TABLE OF CONTENTS (UNIT 1)

1. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE  !

B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS 1 l

D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions 1 E. UNIQUE REPORTING REQUIREMENTS

1. Main Steam Safety Relief Valve Operations

2. Major Changes to Radioactive Waste Treatment System

3. Static O-Ring Failures

4. Off-Site Dose Calculation Manual Changes

4 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 not electrical output of 1078 Negawatts. 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 i commercial power operation was commenced on January 1, 1984. l l

This report was compiled by Nichael J. Cialkowski, telephone number 1 (815)357-6761, extension 2427.

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4 II. MONTELY REPORT 1

A. *

SUMMARY

OF OPERATING EXPERIENCE (Unit 1) I l

RAI Time Event l 1 0000 Reactor critical, Generator on-line at 1120 Mwe.

2 0330 Reduced power level to 1050 Mwe due to syster load.

0700 Increased power level to 1125 Mwe. j l

1400 Reduced power level to 850 Mwe due to system load.

1 3 1000 Increased power level to 1126 Mwe. 1 4 0400 Reduced power level to 900 Mwe due to system load.

1200 Increased power level to 1130 Mwe. .

5 0100 Reduced power level to 900 Mwe due to system load.

1 1200 Increased power level to 1130 Mwe.

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

6 0800 Increased power level to 1130 Mwe.

18 0530 Reduced power level to 1045 Mwe to take the '1A' circulating Water pump off-line for oil sampling. j 1100 Increased power level to 1130 Mwe.

21 0300 Reduced power level to 1020 Mwe due to system load.

0900 Increased power level to 1125 Mwe.

29 2330 Reduced power level to 1000 Mwe due to system load.

30 0700 Increased power level to 1135 Mwe.  !

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

4 B. ANENDNENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (Nor.e)

C. ' LICENSEE EVENT REPORTS (Unit 1)

(None)

D. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 1)

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

3. Unit Shutdowns and Significant Power Reductions (See Table 3) i E. UNIQUE REPORTING REQUIRENENTS (UNIT 1)

1. Safety Relief Valve Operations (None)

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

3. Static O-Ring Failures (None)

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

TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ONE DATE October 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 OPERATING STATUS l

1. REPORTING PERIOD: Septenber 1994 GROSS HOURS IN REPORTING PERIOD 720 l

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

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

6. REASONS FOR RESTRICTION (IF ANY):

REPORTING PER100 DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

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5. REACTOR CRITICAL TIME (HOURS) 720.0 3,277.7 64,604.6

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

7. GENERATOR ON-LINE TIME (HOURS) 720.0 3,094.1 63,107.8 1

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

9. THERMAL ENERGY GENERATED (MWHt) 2,364,833 8,926,872 186,252,509

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 797,037 2,963,933 62,218,304

11. ELECTRICAL ENERGY GENERATED (MVHe-Net) 769,900 2,818,030 59,666,784

12. REACTOR SERVICE FACTOR (%) 100.0 50.0 68.5

13. REACTOR AVAILABILITY FACTOR (%) 100.0 50.0 70.3

14. UNIT SERVICE FACTOR (%) 100.0 47.2 67.0

15. UNIT AVAILIBILITY FACTOR (%) 100.0 47.2 67.0

16. UNIT CAPACITY FACTOR (USING MDC) (%) 103.2 41.5 61.1 1F. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 99.2 39.9 58.7

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 20.6 8.2

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

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

4 DOCKET NO. 050-373 TABLE 2 UNIT LASALLE ONE D.2 AVERACE DAILY UNIT POWER LEVEL (MWe-Net) DATE october 10, 1994 COMPLETED BY M.J. CIALK0WSKI liLEPHONE (815)-357-6761 REPORT PERIOD: September 1994 DAY POWER DAY POWER

....... ......... ....... ......... l 1 1,081 17 1,076 2 1,005 18 1,069 3 1,010 19 1,078 4 1,053 20 1,074 l

l 5 1,031 21 1,068 6 1,044 22 1,083 7 1,081 23 1,086 l

8 1,081 24 1,086 1

9 1,079 25 1,084 10 1,067 26 1,083 11 1,069 27 1,085 12 1,066 28 1,088 ,

1 13 1,072 29 1,085 14 1,075 30 1,064 15 1,076 31 16 1,082 4

TABLE 3 .

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20% ,

(UNIT 1)

NETHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COBetENTS EEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None)

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SIDetARY OF OPERATION:

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

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LASALLE NUCLEAR POWER STATION UNIT 2 NONTHLY PERFORNANCE REPORT September 1994 CONNONWEALTH EDISON CONPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l

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V TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EIPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS 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 Safety Relief Valve Operations

2. Major Changes to Radioactive Naste Treatment System

3. Static O-Ring Failures j 4 Off-site Dose Calculation Manual Changes

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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 Marsellies, 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 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. MONTELY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day, Time Ev6nt 1 0000 Reactor critical, Generator on-line at 1110 Mwe.

2 9000 Reduced power level to 740 Mwe to perform a rod set.

0600 Increased power level to 1125 Mwe.

3 0130 Reduced power level to 1000 Mwe.

0600 Increased power level to 1125 Mwe.

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

1000 Increased power level to 1130 Mwe.

2300 Reduced power level to 950 Mwe due to system load.

6 1000 Increased power level to 1130 Mwe.

7 0030 Reduced power level to 840 Mwe due to system load.

1000 Increased power level to 1130 Mwe.

9 2330 Reduced power level to 850 Mwe for surveillance activities.

10 0700 Reduced power level to 630 Mwe due to loss of the '26A' Feedwater Heater.

1900 Increased power level to 1000 Mwe. I 11 1300 Increased power level to 1115 Mwe.  ;

12 0700 Reduced power level to 1000 Mwe to perform a rod set.

1100 Increased power level to 1118 Mwe. I i

18 0230 Reduced power level to 900 Mwe due to system load. I 1200 Increased power level to 1120 Mwe. l 22 0100 Reduced power level to 825 Mwe to perform a rod set. j 0800 Increased power level to 1130 Mwe.

26 1000 Reduced power level to 800 Mwe for saintenance on the

'2A' Condensate / Condensate Booster Pump with the '2D Condensate / Condensate Booster Pump in standby (high vibration levels). ,

1300 Increased power level to 840 Mwe.

i 30 2400 Reactor critical, Generator on-line at 840 Mwe.

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• l B. ANENDNENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

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C. LICENSEE EVENT REPORTS (Unit 2)

(None)

D. DATA TABULATIONS (Unit 2) )

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1. Operating Data Report (See Table 1)

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

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

E. UNIQUE REPORTING REQUIRENENTS (UNIT 2)

1. Safety Relief Valve Operations (None)

2. Najor Changes to Radioactive Naste Treatment Systems (None)

3. Static O-Ring Failures (None)

4. Changes to the off-Site Dose calculation Manual (None) i l

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TABLE 1

. D.1 OPERATING DATA REPORT DOCKET Wo. 050 374 UNIT LASALLE TWO DATE October 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 OPERATING STATUS

1. REPORTING PERIOD: September 1994 GROSS HOURS IN REPORTING PERIOD: 720

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

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

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4 REASONS FOR RESTRICTION (IF ANY):

REPORTING PERICO DATA j THis MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 720.0 6,183.9 63,109.5 l

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

F. GENERATOR ON-LINE TIME (HOURS) 720.0 6,023.5 61,905.8

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

9. TdERMAL ENERGY GENERATED (MWHt) 2,243,119 19,303,479 187,403,932

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 755,874 6,539,768 62,524,408

11. ELECTRICAL ENERGY GENERATED (MWHe Net) 729,930 6,333,656 60,089,547

12. REACTOR SERVICE FACTOR (%) 100.0 94.4 72.3

13. REACTOR AVAILABILITY FACTOR (%) 100.0 94.4 74.3

16. UNIT SERVICE FACTOR (%) 100.0 91.9 71.0

15. UNIT AVAILIBILITY FACTOR (%) 100.0 91.9 71.0

16. UNIT CAPACITY FACTOR (USING HDC) (%) 97.9 93.3 66.5

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 94.0 89.7 63.9 a

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 3.9 10.8

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

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

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, TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE October 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 REPORT PERIOD: September 1994 DAY POWER DAY POWER 1 965 17 1,081 2 1,018 18 1,026 3 1,074 19 1,078 4 1,086 20 1,077 5 1,051 21 1,079 6 1,048 22 1,050 7 1,041 23 1,086 8 1,084 24 1,088 9 1,083 25 1,088 10 735 26 943 11 1,040 27 812 12 1,066 28 801 13 1,0 72 29 802 14 1,078 30 800 15 1,079 31 16 1,081

4 TABLE 3 .

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

NETHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CONNENTS SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable) r (None)

CUMMARY OF OPERATION:

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

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