ML20092F442

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Monthly Operating Repts for Aug 1995 for LaSalle County Nuclear Power Station
ML20092F442
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/31/1995
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9509180187
Download: ML20092F442 (17)
v • d • e


Text

8 Commonw ealill lbson Company

$ e, l 1%alle Generating Mation

'. 2N)I North list Road Wrwilles. 11.61311 9757

'Tcl HIV357476I i

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l September 11,1995 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 August,1995.

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D. J. Ray Station Manager

> LaSalle County Station DJR/mkl I Enclosure cc: H. J. Miller, Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle 4

IL Department of Nuclear Safety - LaSalle IL Department of Nuclear Safety - Springfield, IL NRR Project Manager - Washington, D.C.

GB 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 Central File Tf.C73G 9509180187 950831 PDR ADOCK 05000373 ,

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I LABALLE NUCLEAR POWER STATION UNIT 1 NDNTELY PERFORMANCE REPORT I i

l August 1995 l

CCDedDNNEALTH EDISON CCBdPANY l r

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' NRC DOCKET No. 050-373 LICENSE No. NPF-11 l

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's ll TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. 81460LRY OF OPERATING EXPERIENCE B. AMENDNENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TABUL..TIONS

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 Waste Treatment systesa
3. Static O-Ring Failures
4. Off-site Dose Calculation Manual Changes k l

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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 4 output of 1079 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 conmonwealth Edison Company.

Unit one was issued operating license number NPF-11 on April 17, 1982. Initial criticality was achieved on June 21, 1992 and commercial power operation was commenced on January 1, 1994.

1 This report was compiled by Michael J. Cialkowski, telephone number (015)357-6761, extension 2056.

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[I . MONTHLY REPORT A. SUbeOJtY OF OPERATING EXPERIENCE (Unit 1)

Dy Time Event 1 0000 Reactor critical, Generator on-line at 1090 Mwe.

9 2300 Reduced power level to 1000 Mwe due to system load.

10 0700 Increased power level to 1110 Mwe.

16 2016 Reactor scram from Main Steam Isolation valve closure due to main steam tunnel high temperature which was caused by the loss of the reactor building ventilation system.

21 0950 Reactor critical.

22 0638 Generator on-line at 60 Mwe.

0715 Generator at 95 Mwe.

2230 Generator at 150 Mwe.

23 0545 Generator at 275 Mwe.

5 0745 Generator at 365 Mwe, upshifted Reactor Racirculation Pumps.

0900 Generator at 565 Mwe.

0945 Generator at 650 Mwe.

I 1040 Generator at 710 Mwe.

2030 Generator at 830 Mwe.

24 0300 Generator at 975 Mwe.

I 0415 Generator at 1075 Mwe.

25 0245 Reduced power level to 750 Mwe for performance of a rod set.

4 0745 Increased power level to 1090 Mwe.

i 30 0650 Reduced power level to 1000 Mwe due to high lake temperature .

l 1015 Increased power level to 1060 Mwe.

31 2400 Reactor critical, Generator on-line at 1090 Mwe.

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.B. AMENDMENTS TO TEE FACILITY OR TECENICAL SPECIFICATION on August 2, 1995, Amendment 104 was issued to license NPF-11 (Unit 1).

This amendment allowed the extension of surveillance test intervals and allowed outage times for certain actuation instrumentation.

l On August 15, 1995, Amendment 105 was issued to license NPF-11 l

(Unit 1). This amendiment revised the pressure alarm setpoint allowable l

values for the Emergency Core Cooling System and Reactor Core Isolation i Cooling system " keep filled" pressure instrumentation channels.

l C. SUBMITTED LICENSEE EVENT REPORTS (Unit 1) occurence LER No. Date Description 95-013 09/08/95 During a review of the calibration procedure for the Diesel Generator low lube oil pressure shutdown switch it was found that the pressure switch (PS-1E22-N515) for the "1B" Diesel Generator was not calibrated within the required time frame.

D. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 1)

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2. Average Daily Unit Power Level (See Table 2)
3. Unit Shutdowns and Significant Power Reductions (See Table 3)

E. UNIQUE REPORTING REQUIREMENTS (UNIT 1)

1. Safety Relief Valve Operations Date of Type of
Valve Actuation Actuation Reason for Actuation 1B21F013D 08/16/95 Automatic Post Scram Reactor Pressure Control l 1B21F013E 08/16/95 Automatic Post Scram Reactor Pressure Control 1B21F0135 08/16/95 Automatic Post Scram Reactor Pressure control )

1B21F013U 08/16/95 Automatic Post Scram Reactor Pressure control I

2. Major Changes to Radioactive Waste Treatment Systems (None)
3. static 0-Ring Failures l

(None)

4. Changes to the off-site Dose Calculation Manual (None)

TABLE 1 8.1 QPERATING DATA REPORT DOCKET No. 050 373 UNIT LASALLE ONE DATE September 8, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 GPERAT!NG STATUS

1. REPORTING PERIOD: August 1995 GROSS NOURS IN REPORTING PERIOD 744
2. CURRENTLY AUTHORIZED POWER LE4EL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Met): 1,036 DESIGN ELECTRICAL RATING (MWe-N 1,078
3. POE R LEVEL TO WNICN RESTRICTED (IF ANY) (MWe Met):
4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERICD DATA THIS MONTN YEAR TO-DATE CUIRJLATIVE

5. REACTOR CRITICAL TIME (HOURS) 634.5 5,461.4 72,101.3
6. REACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1,641.2
7. GENERATOR ON LINE TIME (NOURS) 613.7 5,402.1 70,513.3
8. WIT RESERVE $NUTDOWN TIME (NOURS) 0.0 0.0 1.0
9. THERMAL ENERGT GENERATED (NWNt) 1,946,859 17,407,489 210,094,314
10. ELECTRICAL ENERGY GENERATED (MWNo Gross) 633,712 5,834,114 70,229,005
11. ELECTRICAL ENERGY GENERATED (MWNo-Met) 609,485 5,652,123 67,421,267
12. REACTOR SERVICE FACTOR (%) 85.3 93.7 70.5
13. REACTOR AVAILABILITY FACTOR (%) 85.3 93.7 72.1
10. UNIT SERVICE FACTOR (%) 82.5 92.6 68.9
15. UNIT AVAILIBILITY FACTOR (%) 82.5 92.6 68.9
10. UNIT CAPACITY FACTOR (USING 2 C) (%) 79.1 93.6 63.6
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 76.0 89.9 61.1
18. UNIT FORCED QUTAGE FACTOR (%) 17.5 4.8 8.0
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): 01/27/96 4
20. IF SNUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 3

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DOCKET No. 050 373 <

I TABLE 2 UNIT LASALLE ONE D.2 AVERADE DAILY UNIT POWER LEVEL (MWe Net) DATE september 8,1995  ;

COMPLETFD BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761

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REPORT PERIOD: August 1795 DAY POWER DAY POWER l

1 1,047 17 12 l 2 1,052 18 -12 3 1,055 19 12 4 1,055 20 12 5 1,048 21 12 6 1,033 22 58 7 1,052 23 523 8 1,054 24 983 9 1,055 25 995 10 1,040 26 1,057 11 1,056 27 1,045 12 1,054 28 1,044 13 1,052 29 1,044 14 1,053 30 1,020 15 1,047 31 1,051 16 879 l

. . . _ _. . - . . . - . . . ... . . - . - . . . . . - . . - - - - . = . - - . - . . . . . - . _- _- ,. . . .

TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 204 (UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCaeENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER 8 if ,

NUMBER (YYMOD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)  !

4 950816 F 130.4 A 3 Au e - tic Reactor Scram (LERS95-014) i Sime&RY OF OPERATION:

The unit r-ined on-line at high power throughout most of the month. The unit experienced a forced outage on 08/16/95 and was returned to service on 08/22/95. Minor power reductions were required due to rod pattern adjust ==nts and lake temperture.

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LASALY2 NUCLEAR POWER STATION 4

UNIT 2 s

HONTELY PERFORMANCE REPORT 4

August 1995 i

CceeONNEALTE EDISOP CGdPANY NRC DOCKET NO. 050-374 l'

LICENSE NO. NPF-19 i

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1 TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A. Sthe4ARY OF OPERATING EEPERIENCE B. AMENDNENTS 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 Waste Treatment System
3. Static O-Ring Failures
4. Off-Site Dose Calculation Manual Changes i

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4 I. INTRODUCTION (UNIT 2)

The Lasalle County Nuclear Power station is a two-Unit facility owned by Comunonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed not electrical output of 1970 Meganatts. Waste heat is rejected to a i 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 two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and conumercial power operation was comunenced on October 19, 1984.

This report was compiled by Michael J. Cialkowski, telephone number (S15)357-6761, extension 2056.

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1 II. MONTHLY REPORT

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A. SUB4GRY OF OPERATING EXPERIENCE (Unit 2)

Day Time Event 1 0000 Reactor critical, Generator on-line at 960 Mwe. Reducei power level due to oscillations of the 'A' Reactor Recirculation flow control valve.

4 1600 Increased power level to 1030 Mwe.

18 1750 Reduced power level to 990 Mwe to reduce Main condenser back pressure.

19 0700 Increased power level to 1050 mwe.

30 0030 Reduced power level to 1000 Mwe due to high lake tosperature .

0930 Increased power level to 1030 Mwe.

31 2400 Reactor critical, Generator on-line at 1030 Mwe.

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.B. AMENDHENTS TO THE FACILITY OR TECHNICAL SPECIFICATION l On August 2, 1995, Jumendment 90 was issued to license NPF-18 (Unit 2).

This amendment allowed the extension of surveillance test intervals and allowed outage times for certain actuation instrumentation.

On August 15, 1995, Annendment 91 was issued to license NPF-19 (Unit 2).

This amendment revised the pressure alarm setpoint allowable values for the Emergency Core Cooling System and Reactor Core Isolation Cooling system " keep filled" pressure instrumsntation channels.

C. SUBMITTED LICENSEE EVENT REPORTS (Unit 2)

(None)

D. DATA TABULATIONS (Unit 2)

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 REQUIREMENTS (UNIT 2)

1. Safety Relief Valve Operations (None)
2. Major Changes to Radioactive Waste Treatment Systems (None)
3. Static O-Ring Failures (None) i l
4. Changes to the Off-Site Dose calculation Manual I l

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D.1 OPERATING DATA REPORT DOCET No. 050 374 UNIT LASALLE TWD DATE September 8,1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 OPERATING STATUS

1. REPORTING PERIOD: August 1995 GROSS NOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEW CAPACITY (IRde Net): 1,036 DEllGN ELECTRICAL RATING (MWe-Net): 1,078
3. POWER LEVEL TO WICN RESTRICTED (IF ANY) (MWe Net):
4. REASONS FOR RESTRICTION (If ANY):

REPORTING PERIOD DATA THIS MONTN YEAR TO-DATE CUIEJLATIVE

5. REACTOR CRITICAL TIME (NOURS) 744.0 3,329,7 68,537.6
6. REACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1,716.9
7. GENERATOR ON*LINE TIME (NQURS) 744.0 3,116.5 67,102.0
8. UNIT RESERVE SNUTDOWN TIME (NQURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWNt) 2,335,157 9,545,663 203,297,591
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 772,086 3,248,650 67,937,219
11. ELECTRICAL ENERGY GENERATED (MWHe Met) 744,199 3,100,009 65,292,771
12. REACTOR SERVICE FACTOR (%) 100.0 57.1 71.9
13. REACTOR AVAILABILITY FACTOR (1) 100.0 57.1 73.7
14. UNIT SERVICE FACTOR (1) 100.0 53.4 70.4
15. UNIT AVAILIBILITY FACTOR (1) 100.0 53.4 70.4
16. UNIT CAPACITY FACTOR (USING W C) (1) 96.6 51.4 66.1 l

l 17. UNIT CAPACITY FACTOR (USING DEllGN mie) (%) 92.8 49.4 63.6

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 10.2 Ir
19. SNUTDOWNS SCHEDULED OVER THE NEXT 6 MONTNS (TYPE, DATE, AND DURATION OF EACN): N/A

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

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. 0002T leo. 050 374

, TASLE 2 Utili LASALLE TWO D.2 AVERAGE DAILY UIIIT POWER LEVEL (MWe-Met) DATE september 8,1995 COMPLETED BY M.J. CIALK0WSKI 1

TELEPliOIIE (815) 357 6761 l

REPORT PERIOD: August 1995 i l

DAY POWER DAY POWER 1 928 17 1,005 2 935 18 990 3 934 19 1,000 4 966 20 1,006 5 1,016 21 1,004 6 1,011 22 1,007 7 1,012 23 1,005 8 1,013 24 1,011 9 1,018 25 1,011 10 1,019 26 1,014  ;

11 1,013 27 1,011 )

12 1,014 28 1,010 13 1,012 29 1,006 l 14 1,014 30 989 1

15 1,016 31 1,001 1,012 l 16 l

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e i TABLE 3 D.3 UNIT SHUTDOWNS AND POIER REDUCTIONS > 20%

(UNIT 2) 3ETHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CObeENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NtheER (YYleeD) 5: SCHEDULED (HOURS) REASON REDUCING POIER applicable)

(None) stmeaRY OF OPERATION:

The unit m ined on-line at high power throughout the month. The unit experienced several sainor power reductions during the amonth due to lake temperature, i

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