ML20072V115

Monthly Operating Rept for Aug 1994 for LaSalle County Nuclear Station

ML20072V115
Person / Time
Site:	LaSalle
Issue date:	08/31/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9409190198
Download: ML20072V115 (16)

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

Marseilles, Illinois 61341 Telephone 815/357-6761 September 12,1994 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 forJuly.1994.

$ ust-D. J. Ray 4 Station Manager LaSalle County Station DJR/tmb Enclosure cc: J. B. Martin, Regional Administrator - Region III W.D. Reckley, Project Manager, NRR P.G. Brochman, Senier Resident Inspector, LaSalle D. L. Farrar, Nuclear Regulatory Services Manager, NORS R. D. Zuffa, IL Department of Nuclear Safety - LaSalle L.F. Gerner, Regulatory Assurance Supervisor, LaSalle T.A. Rieck, Nuclear Fuel Services Manager - General Office Licensing Operations Director - Downers Grove Off-Site Safety Review Senior Participant - Downers Grove GE Representative - LaSalle INPO Records Center Station File i

C2hSb 94o919019s 940831 I l PDR ADOCK 05000373 I R PnD i

IA5ALLE NUCLEAR POWER STATION UNIT 1 MONTELY PERPORMANCE REPORT August 1994 COMMONWEALTE EDISON COMPANY NRC axX3tET NO. 050-373 LICENSE NO. NPF-11 I

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4 TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION m

II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECENICAL 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

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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 Eoiling 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 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 1

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

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I II. MONTHLY REPORT

'A.

SUMMARY

OF OPERATING EIPERIENCE (Unit 1) i Ear Time Event 1 0000 Reactor critical, Generator on-line at 1110 Mwe.

2 0000 Reduced power level to 676 Mwe for performance of a i Reactor Recirculation system surveillance.

i 0900 Increased power level to 1122 Mwe.

7 0200 Reduced power level to 1000 due to system load.

. 1200 Increased power level to 1120 Mwe.

! 9 0200 Reduced power level to 890 Mwe due to system load.

l l 0700 Increased power level to 1125 Mwe.

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13 0100 Reduced power level to 850 Mwe to transfer the Condensate / Condensate Booster pumps and to perform a heater bay inspection.

0700 Increased power level to 1125 Mwe.

l 14 2300 Reduced power level to 890 Mwe to' transfer the l I Condensate / Condensate Booster pumps and to perform a I heater bay inspection.

0700 Increased power level to 1125 Mwe.

l 16 0230 Reduced power level to 890 Mwe to transfer the l

Condensate / Condensate Rooster pumps. I l

1100 Increased power level to 1120 Mwe. l I

31 2400 Reactor critical, generator on-line at 1120 Mwe. j i

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3. %4ENDNENTS TO THE FACILITY CR TECHNICAL SPCCIFICATION License change to approve the lack of a Main Steam Line high radiation trip of the condenser mechanical vacuum pump.

C. LICENSEE EVENT REPORTS (Unit 1)

LER Number Date Description 94-012 08/13/94 Untested contacts in the Neutron Monitoring and the Reactor Protection systems.

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)

E. UNIQUE REPORTING REQUIREMENTS (UNIT 1)

1. Safety Relief Valve Operations (None)

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

3. Static O-Ring Failures (None)

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

i TABLE 1 l D.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ONE DATE September 10, 1994 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815)-357-6761 l

l OPERATING STATUS

1. REPORTING PERIOD: August 1994 GROSS HOURS IN REPORTING PERIOD 744

2. CURRENTLY AUTHORIZED Pr.ER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036.

l DESIGN ELECTRICAL RATING (MWe-N 1,078 i

, 3. POWER LEVEL TO WHICH RESTRICTED (!F ANY) (MWe* Net):

I j 4. REASONS FOR RESTRICTION (!F ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE l S. REACTOR CRITICAL TIME (HOURS) 744.0 2,557.7 63,884.6

6. REACTDR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 l 7. GENERATOR ON-LINE TIME (HOURS) 744.0 2,3 74.1 62,387.8 l

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

9. THERMAL ENERGY GENERATED (MWHt) 2,450,269 6,561,989 183,887,626

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 821,495 2,166,896 61,421,267

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 793,254 2,048,130 58,896,884

12. REACTOR SERVICE FACTOR (%) 100.0 43.9 68.3

13. REACTOR AVAILABILITY FACTOR (%) 1s0.0 43.9 70.1

14. UNIT SERVICE FACTOR (%) 100.0 40.7 66.7

15. UNIT AVAILIBILITY FACTOR (%) 100.0 40.7 66.7

16. UNIT CAPACITY FACTOR (USING MDC) (%) 102.9 33.9 60.8

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (f.) 98.9 32.6 58.4

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 25.3 8.3

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

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

DOCKET NO. 050-373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE September 10, 1994 COMPLETED BY M.J. CIALK0WSK! j TELEPHONE (815)-357-6761 l

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REPORT PERIOD: August 1994 DAY POWER DAY POWER j I

I 1 1,067 17 1,073 I

l 2 994 18 1,070 3 1,070 19 1,074 4 1,075 20 1,077 5 1,078 21 1,076 l 6 1,077 22 1,073 l i

7 1,044 23 1,073 I I

8 1,077 24 1,075 l I

9 1,074 25 1,070 l 10 1,036 26 1,065

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11 1,081 27 1,065 I 12 1,079 28 1,067 13 1,050 29 1,065 .

14 1,075 30 1,072 15 1,030 31 1,080 l

16 1,071 l

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

(UNIT 1)

NETHOD or CoRRECTIva YEARLY TYPE SEUTTING DOWN ACTIONS /COMENTS CEQUENTIAL DATE Fs FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER acclicable)

(None)

CUteEARY OF OPERATION:

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

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• LASALLE NUCLEAR POWER STATION i l i

UNIT 2 .

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I MONTHLY PERFORMANCE REPORT i 4

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I August 1994 ,

t CONHONWEALTE EDISON COMPANY I

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

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! TABLE OF CONTENTS I

(UNIT 2)

I. INTRODUCTION II. REPORT A. SUa0ULRY OF OPERATING EXPERIENCE B. ANENDMENTS 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 REQUIRENENTS

1. Main Steam Safety Relief Valve Operations l

2. Major Changes to Radioactive Waste Treatment System

3. Static O-Ring Failures

4. Off-site Dose Calculation Manual Changes 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. j 1

Unit two was issued operating license number NPF-18 on December 16, J 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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o 1I. MONTELY REPORT A. SUBAGARY OF OPERATING RIPERIENCE (Unit 2)

Daz Elan Event 1 0000 Reactor critical, Generator on-line at 1112 Mwe.

20 0030 Reduced power level to 850 Mwe due to system load.

0800 Increased power level to 1120 Mue.

25 0328 Reactor scram due to spurious opening of a Main Steam bypass valve.

27 1342 Reactor critical.

30 1623 Generator on-line at 60 Mwe.

31 0400 Power level at 400 Mwe.

1700 Power level at 1115 Mwe.

2400 Reactor critical, Generator on-line at 1110 Mwe.

B. AMENDMENTS TO THE FACILITY OR TECENICAL SPECIFICATION License change to approve the lack of a Main Steam Line.high radiation trip of the condenser mechanical vacuum pump.

C. LICENSEE EVENT REPORTS (Unit 2)

LER Number Date Description 94-005 08/08/94 Failure of the Reactor Core Isolation Cooling system turbine exhaust diaphragm pressure switch.94-006 08/25/94 Reactor. scram due to spurious opening of the 2B21-MSRPV01 bypass valve.

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)

5. UNIQUE REPORTING REQUIRENENTS (UNIT 2)

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) i

. TABLE 1 1 0

• D.1 OPERATING DATA REPORT DOCKET NO. 050-374  ;

UNIT LASALLE TWO  ;

DATE September 10, 1994 COMPLCTED BY M.J. CIALK0WSK!

TELEPHONE (815)-357-6761 ,

I l OPERATING STATUS l

1. REPORTING PERIOD: August 1994 GROSS HOURS IN REPORTING PERIOD: 744

2. CU33ENTLY 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):

l 4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA l l

i .............................................. i THIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 685.8 5,463.9 62,389.5

! l l ' 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 l l-l 7. GENERATOR ON-LINE TIME (HOURS) 611,1 5,303.5 61,185.8 l

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

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9. THERMAL ENERGY GENERATED (MWHt) 2,000,234 17,060,360 185,160,813 l

! 10. ELECTRICAL ENERCY GENERATED (MWHe-Gross) 666,728 5,783,894 61,768,534 l

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 643,353 5,603,726 59,359,617 l

12. REACTOR SERVICE FACTOR (%) 92.2 93.7 72.1

13. QEACTOR AVAILABILITY FACTOR (%) 92.2 93.7 74.1

14. UNIT SERVICE FACTOR (%) 82.1 91.0 70.7

15. UNIT AVAILIBILITY FACTOR (%) 82.1 91.0 70.7

16. UNIT CAPACITY FACTOR (USING MDC) (%) 83.5 92.8 66.2

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 80.2 89.1 63.6

18. UNIT FORCED OUTAGE FACTOR (%) 17.9 4.4 10.9 l

l 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:

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DOCKET NO. 050-374 TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Wet) DATE September 10, 1994 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815)-357-6761 )

i REPORT PERIOD: August 1994 l

DAY POWER DAY POWER I 1 1,076 17 1,073 2 1,074 18 1,071 3 1,074 19 1,076 4 1,078 20 1,051 '

5 1,082 21 1,080 6 1,084 22 1,073 7 1,083 23 1,0 75 8 1,081 24 1,078 9 1,078 25 147 10 1,083 26 -12 I

11 1,086 27 -12 12 1,081 28 -12 i

13 1,078 29 -12 j l

14 1,083 30 55 15 1,081 31 800 16 1,077 l

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I TABLE 3 .

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COceeDITS CEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYletDD) S: SCHEDULED fHOURS) REASON REDUCING POWER apolicable1 5 940825 F 132.9 A 3 Reactor scram due to -

spurious opening of a Main steam Line bypass valve.

LER# 94-006 SUIstARY OF OPERATION:

The unit remained on-line at high power throughout most of the month. On 08/25/94 the unit experienced a ceram due to spurious opening of a Main steam line bypass valve. The unit was returned to service on 08/30/94.

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