ML20077F323

Monthly Operating Rept for Nov 1994 for LaSalle County Nuclear Station

ML20077F323
Person / Time
Site:	LaSalle
Issue date:	11/30/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9412140027
Download: ML20077F323 (17)

Text

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C:mm::nw:alth Edison LaSalle County Nuclear Station 2601 N. 21st. Rd.

Marseilles, Illinois 61341 Telephono 815/357-6761 December 8,1994 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 November,1994.

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

1 GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Licensing Operations Director - Downers Grove Nuclear Fuel Services Manager - General Office 1

Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Central File 1400LV 9412140027 941130 PDR ADDCK 05000373

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT November 1994 COMMONWEALTH EDISON COMPANY NRC DOCKET No. 050-373 LICENSE No. NPF-11

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TABLE OF CONTENTS (UNIT 1)

I.

INTRODUCTION II.

REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B.

AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

LICENSEE EVENT REPORTS r

D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIREMENTS 5

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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I.

INTRODUCTION (UNIT 1) l

.The Lasalle County Nuclear Power Station is a two-Unit facility owned.

I 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 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, telephone number (815)357-6761, extension 2427.

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MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

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.1 0000 Reactor critical, Generator on-line at 1140 Mwe.

2 0030 Reduced power level to 1060 Mwe for performance of Motor Driven Reactor Feed Pump testing.

0400 Increased power level to 1140 Mwe.

13 2200 Reduced power level to 850 Mwe for performance of a rod set.

14 0700 Increased power level to 1140 Mwe.

15 0030 Reduced power level to 1080 Mwe to perform surveillance testing.

0700 Increased power level to 1140 Mwe.

19 2100 Reduced power level to 1040 Mwe due to system load, transferred the Heater Drain system pumps.

20 1100 Increased power level to 1140 Mwe.

1930 Reduced power level to 900 Mwe due to system load.

21 1000 Increased power level to 1140 Mwe.

2400 Reduced power level to 1070 Mwe to transfer the Condensate / Condensate Booster Pumps.

22 0500 Increased power level to 1135 Mwe.

30 1500 Reduced power level to 1070 Mwe to transfer the Condensate / Condensate Booster Pumps.

0600 Increased power level to 1140 Mwe.

2400 Reactor critical, Generator on-line at 1140 Mwe.

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3.

AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

C.

LICENSEE EVENT REPORTS (Unit 1)

LEILNei Date Dstcriptig.n 94-013 11/14/94 Difficulty establishing flow rate during Reactor Core Isolation Cooling Governor surveillance.94-014 11/21/94 High Pressure Core Spray Pump, intitiation logic and the ACB 1432 CP logic de-energized due to the control power to Bus 113 being inadvertantly taken out of service.

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.

Major Changes to Radioactive Waste Treatment Systems (None) 3.

Static O-Ring Failures (Hone)'*"

4.

Changes /t6'the Off-Site Dose Calculation Manual (None)

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

DEPORTING PERIOD:

November 1994 GROSS HOUR $ IN REPORTING PER100 720 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):

3,323 MAX DEPEND CAPACITY (MWe Net):

1,036 DESIGN ELECTRICAL RATING 'MWe N 1,073 3.

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

j 4.

RfASONS FOR RESTRICTION (!F ANY):

REPORTING PER100 DATA THIS MONTH YEAR-T0*DATE CUMULATIVE 5.

DEACTOR.a!TICAL TIME (HOURS) 720.0 4,742.7 66,069.6 6.

REACTOR RESFRVE SHUTDOWN TIME (dOURS) 0.0 0.0 1,641.2 7.

GENERATOR ON LINE TIME (HOURS) 720.0 4,559.1 64,572.8 8.

UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 9.

THERMAL ENERGY GENERATED (MWHt) 2,375,927 13,757,495 191,083,132

10. ELECTRICAL ENERGY GENERATED (MwHe-Gross) 811,646 4,611,459 63,865,830

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 787,340 4,414,472 61,263,226

12. REACTOR SERVICE FACTOR (%)

100.0 59.2 69.0

13. REACTOR AVAILABILITY FACTOR (%)

100.0 59.2 70.7

14. UNIT SERVICE FACTOR (%)

100.0 56.9 67.5

15. UNIT AVAILIBILITY FfCTOR (%)

100.0 56.9 67.5

16. UNIT CAPACITY FACTOR (US!NG MDC) (%)

105.6 53.2 61.8

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%)

101.4 51.1 59.4

18. UNIT FORCED OUTAGE FACTOR (%)

0.0 15.0 8.1

19. SHUTDOWNS SCHEDULED OVER THE a oNTHS (TYPE, DATE, AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORY ft 600, ESTIMATED DATE OF STARTUP:

DOCKET No. 050 373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net)

DATE Decenber 10,1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 REPORT PERIOD:

November 1994 DAY POWER DAY POWER 1

1,097 17 1,100 2

1,097 18 1,100 3

1,098 19 1,089 4

1,099 20 1,048 5

1,097 21 1,048 6

1,098 22 1,095 7

1,096 23 1,099 8

1,098 24 1,099 9

1,098 25 1,100 10 1,099 26 1,101 11 1,099 27 1,102 12 1,100 28 1,104 13 1,087 29 1,103 14 1,072 30 1,097 15 1,088 31 16 1,098 l

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

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if N@fBER iTDOLDD1 E1_ECHE2HLER (HOURS)

REASON Rgp_UCING POWEB apolicable)

(None)

SUMMARY

OF OPERATION:

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

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

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. l TABLE OF CONTENTS (UNIT 2)

I.

INTRODUCTION II.

REPORT A.

SUMMARY

OF OPERATING EXPERIENCE 4

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 Waste Treatment System i

3.

static O-Ring Failures 4.

Off-site Dose Calculation Manual Changes D

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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.

e II.-

MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Time Er.snt 1

0000 Reactor critical, Generator on-line at 1090 Mwe.

6 2200 Reduced power level to 840 Mwe to perform a rod set.

7 0300 Increased power level to 1000 Wes.

0 0200 Reduced power level to 845 Mwe to place the Motor Driven Reactor Feed Pump Off-line and place the

'B' Turbine Drivsn Reactor Feed Pump on-line.

1700 Increased power level to 1135 Mwe.

17 0200 Reduced power level to 1000 Mwe to perform a rod set.

0800 Increased power level to 1140 Mwe.

15 0200 Reduced power level to 990 Mwe to system load.

0900 Increased power level to 1135 Mwe.

20 0400 Reduced power level to 900 Mwe due to system load.

1200 Increased power level to 1140 Hwe.

2100 Reduced power level to 1050 Mwe to transfer the Condensate / Condensate Booster Pumps.

21 0700 Increased power level to 1140 Mwe.

24 0300 Reduced power level to 1000 Mwe due to system load.

25 0700 Increased power level to 1140 Mwe.

27 0400 Reduced power level to 730 Mwe to perform a rod set.

1600 Increased power level to 1140 Mwe.

29 0800 Reduced power level to 1105 Mwe to transfer the Heater Drain system pumps.

0830 Increased power level to 1140 Mwe.

30 2400 Reactor critical, Generator on-line at 950 Mwe, power level being reduced for Feedwater system testing.

E.

AMENDMENTS TO THE FACILITY OR 7dCHNICAL BPECIFICATION (None)

C.

LICENSEE EVENT REPORTS IUnit 2)

LER_No.

DAt.e DelEIAD119n 94-009 11/02/94 Loss of the Reactor Core Isolation Cooling system fill and vent declaring the system inoperable.

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) 4.

Changes to the Off-site Dose Calculation Manual (None)

TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050 374 UNIT LASALLE TWO DATE December 10,1994 COMPLETED BY M.J. CIALK0WSK!

i TELEPHONE (815) 357 6761 G2ERATING STATUS 1.

REPORildG PERIOD:

November 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 (HWe Net):

1,078 3.

POWER LEVEL TO WHICH RESTRICTED (if ANY) (MWe Net):

4.

REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THl3 MONTH YkAR-TO DATE CUMULATIVE 5.

REACTOR CRITICAL TIME (HOURS) 720.0 7,538.4 64,464.0 6.

REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 7.

GENERATOR ON LINE TIME (HOURS) 720.0 7,359.2 63,241.5 8.

UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 9.

THERMAL ENERGY GENERATED (MWHt) 2,320,363 23,234,367 191,334,820

10. ELECTRICAL ENERGY GENERATED (MWHo Gross) 793,903 7,877,235 63,861,875

11. ELECTRICAL ENERGY GENERATED (MWHe Net) 770,336 7,627,260 61,383,151

12. REACTOR SERVICE FACTOR (%)

100.0 94.0 72.7

13. REACTOR AVAILABILITY FACTOR (%)

100.0 94.0 74.6

14. UNIT SERVICE FACTOR (%)

100.0 91.8 71.3

15. UNIT AVAILIBILITY FACTOR (%)

100.0 91.8 71.3

16. UNIT CAPACITY FACTOR (USING MDC) (%)

103.3 91.8 66.8

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%)

99.2 88.3 64.2

18. UNIT FORCED OUT/GE FACTOR (%)

0.0 4.8 10.7

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURAil0N OF EACH):

Refuel Outage (L2R06), 02/18/95,13 Weeks

20. IF SHUTDOWN AT END OF REPORT PERl00, ESilMATED DATE OF STARTUP:

e DOCKET No. 050-374 TABLE 2 UNIT LASALLE TWO D.2 AVLPAGE f)AILY UNIT POWER LEVEL (MWe Net)

DATE December 10,1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 REPORT PERICO:

November 1994 DAY POWER DAY POWER 1

1,044 17 1,100 2

1,043 18 1,101 3

1,041 19 1,100 4

1,037 20 1,049 5

1 031 21 1,081 6

1,018 22 1,098 7

955 23 1,103 8

1,033 24 984 9

1,099 25 1,078 10 1,098 26 1,097 11 1,092 27 1,033 12 1,101 28 1,100 13 1,101 29 1,105 14 1,101 30 1,097 15 1,079 31 16 1,097

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

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMME *S SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if hTM3XR LYYMMDJ1 S: SCHEp1TLED fHOURS)

REASoli REDUCING POWEB aoolicable)

(None)

SUMMARY

OF OPERATION:

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