ML20095E881

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Monthly Operating Repts for Nov 1995 for LaSalle County Nuclear Power Station
ML20095E881
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 11/30/1995
From: Ciakkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9512180193
Download: ML20095E881 (16)
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Text

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, G>mmonwealth litivin unnpany li.t$.111e Generating Station

, 2601 North list Road

4 .\tarwilles. IL 613 41-975 l

'Tel H15 35Ni 61 December 12,1995 i

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U.S. Nuclear Regulatory Commission ,

Document Control Desk Washington, D.C. 20555 f i

t Enclosed for your information is t'ae monthly performance report covering LaSalle County Nuclear Power Station for November,1995.

D. J. Ray D Station Manager LaSalle County Station l l i

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DJR/mkl  !

l Enclosure I cc: H. J. Miller, Regional Administrator - Region III i NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle IL Department of Nuclear Safety - Springfield, IL NRR Project Manager - Washington, D.C.

GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Licensing Operations Director - Downers Grove i Nuclear Fuel Services Manager - General Office j Off-Site Safety Review Senior Participant - Downers Grove

INPO Records Center i Central File il e ,e .. g .

1 O s .!. v h, 95121R0193 951130 1 /

PDR ADOCK 05000373 #p\

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.A I?nicom Osmpany (/

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l LARALLE NUCLEAR PONER STATION UNIT 1 BCNTELY PERFORMANCE REPORT November 1995 ColdCHWEALTE EDISON CCMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 4

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l TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION 1 II. REPORT A. StSO4MW OF OPERATING EXPERIENCE B. AMENDMDITS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TABULATIONS '

1. Operating Data Report
2. Average Daily Unit Power Level j
3. Unit Shutdowns and Power Reductions i E. UNIQUE REPORTING REQUIREMENTS l
1. Main Steam Safety Relief Valve Operations i
2. Major Changes to Radioactive Naste Treatment System
3. Static O-Ring Failures
4. Off-Site Dose Calculation Manual Changes l l

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I. INTRODUCTICH (UNIT 1) .

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The Lasalle county Nuclear Power Station is a two-Unit facility owned by coasmonwealth Edison Company and located near Marseilles, Illinois. ,

Each unit is a Boiling Water Reactor with a designed not electri si l output of 1078 Megawatts. Waste heat is rejected to a man-made cooling 1 pond using the Illinois river for make-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was I comanonwealth Edison company.

Unit one was issued operating license number NPF-ll on April 17, 1982. Initial criticality was achieved on June 21, 1982 and commercial power operation was commaanced on January 1, 1984.

This report was compiled by Michael J. cialkowski, telephone number i (815)357-6761, extension 2056.

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i II. MONTELY REPORT A. StBeGLRY OF OPERATING EEPERIENCE (Unit 1) l y

D Time Event j 1 0000 Reactor critical, Generator on-line at 1000 Mwe.

2 0100 Reduced power level to 920 Mwe for scram solenoid pilot valve replacement.

2400 Reduced power level to 775 Mwe for scram solenoid pilot valve replacement.

3 1000 Increased power level to 1000 Mwe.

4 0030 Reduced power level to *i00 Mwe for performance of scram time testing.

1200 Increased power level to 1130 Mwe.

6 0030 Reduced power level to 920 Mwe for scram solenoid pilot valve replacement.

1 1000 Increased power level to 1045 Mwe.

2400 Reduced power level to 800 Mwe for performance of scram j time testing.

i 7 1600 Increased power level to 1035 Mwe.

2 2400 Reduced power level to 800 Mwe for scram solenoid pilot valve replacement.

S 1000 Increased power level to 1010 Mwe.

2300 Reduced power level to 800 Mwe for scram solenoid pilot valve replacement. l 9 0600 Increased power level to 1000 Mwe.

2330 Reduced power level to 800 Mwe for scram solenoid pilot  ;

valve replacement. ,

l 10 0900 Increased power level to 995 Mwe.

2400 Reduced power level to 800 Mwe for scram solenoid pilot valve replacement. J 11 1700 Increased power level to 1100 Mwe.

i 13 0100 Reduced power level to 840 Mwe for scram solenoid pilot valve replacement.

0200 Increased power level to 920 Mwe.

2400 Reduced power level to 750 Mwe for scram solenoid pilot j valve replacement.

14 0300 Increased power level to 930 Mwe.

2330 Reduced power level to 775 Mwe for scram solenoid pilot valve replacement.

15 0700 Increased power level to 960 Mwe.

16 0100 Reduced power level to 700 Mwe for scram solenoid pilot valve replacement.

. A. StmedARY CF CPERATING EXPERIENCE (Unit 1)

(continued)

Day Time Event 16 0500 Increased power level to 940 Mwe.

2300 Reduced power level to 800 Nwe for scram solenoid pilot valve replacement.

17 0700 Increased power level to 1050 Mwe.

19 2400 Reduced power level to 925 Nwe due to system load.

1900 Increased power level to 1030 Nwe.

23 0000 Reduced power level to 885 Nwe, placed the 'A' Turbine Driven Reactor Feed pump off-line for maintenance.

1000 Increased power level to 1000 Mwe.

25 2330 Reduced power level to 950 Nwe for surveillance testing.

26 1400 Increased power level to 1000 Mwe.

30 2400 Reactor critical, Generator on-line at 970 Nwe.

B. AMENDNENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

C. SUBMITTED LICENSEE EVENT REPORTS (Unit 1) occurence LER No. Date Description 95-017 10/10/95 safety related contact testing of the Reactor Building and Fuel Pool Cooling Ventilation High u n diation Monitoring Trip system was not performed in accordance with the Station Technical specifications.

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

TABLE 1 0.1 OPERATING DATA REPORT DOCKET No. 050-373 4

UNIT LASALLE ONE DATE Decaster 11, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-o761

[ OPERATING STATUS i

1. REPORTING PERIOD: November 1995 GROSS NOURS IN REPORTING PERIOD 720,
2. 11NtRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 i DESIGN ELECTRICAL RATING (MWe-N 1,078 i.
3. POE R LEVEL TO WNICN RESTRICTED (IF ANY) (MWe Net):
4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIts DATA THIS MONTH YEAR-TO-DATE CUNULATIVE

5. REACTOR CRITICAL TIME (NOURS) 720.0 7,558.1 74,198.0
6. REACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1,641.2
7. GENERATOR ON-LINE TIME (NOURS) 720.0 7,485.0 72,596.1
8. UNIT RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWNt) 2,095,224 23,787,607 216,474,432
10. ELECTRICAL ENERGY GENERATED (MWNo-Gross) 707,792 7,906,779 72,377,670
11. ELECTRICAL ENERGY GENERATED (mdNe Met) 684,375 7,727,825 69,496,969
12. REACTOR SERVICE FACTOR (X) 100.0 94.3 71.0
13. REACTOR AVAILABILITY FACTOR (X) 100.0 96.3 72.6
14. UNIT SERVICE FACTOR (%) 100.0 93.4 69.5
15. UNIT AVAILIBILITY FACTOR (%) 100.0 93.4 69.5 16, WIT CAPACITY FACTOR (USING MDC) (%) 91.7 93.1 64.2
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 88.2 89.4 61.7
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 4.7 7.9
19. $NUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACN): 01/27/96
20. IF SNUTDOW AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A

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l l DOCKET N0. 050-373 l f TABLE 2 UNIT LASALLE ONE 1 D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Met) DATE December 11, 1995 j COMPLETE 0 BY M.J. CIALK0WSKI l

TELEPHONE (815) 357-6761 1 REPORT PERIOD
November 1995 l

i DAY PohER DAY P0bER I i 1 1,022 17 976 1

2 894 18 996 3 920 19 947 I

4 1,026 20 905 5 1,087 21 977 1

6 975 22 969 i

7 925 23 936 8 920 24 957 4

9 928 25 953 l l

i 10 901 26 901 11 1,002 27 948 1,046 12 28 940 13 876 29 935

+ 14 863 30 931 15 896 31 i 16 886

TABLE 3 +

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

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DETHOD OF CONWCTIVE YEARLY TYPE 5 BUTTING DOWN ACTIONS /CCDGENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # *,f Nt24BER (YYleeD) 5: SCHEDULED (HOURS) REASON REDUCING POWER applicable)  !

(None) i-I L

i CtDedhRY OF OPERATION:

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

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LASALLE NUCLEAR POWER STATION f 1

l UNIT 2  !

l MONTELY PERFORMANCE REPORT Novesaber 1995 CCaedDNNEALTH EDISON COMPANY l

i NRC DOCKET NO. 050-374 LICENSE No. NPF-10 i

l TABLE OF CONTENTS (UNIT 2)

! I. INTRODUCTION II. REPORT A. StBe&RY OF OPERATING EXPERIENCE B. AMENDMENTS To FACILITY LICENSE OR TECHNICAL SPECIFICATIONS l

C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions l

E. UNIQUE REPORTING REQUIREMENTS

1. Main Steam Safety Relief valve Operations
2. Major Changes to Radioactive Waste Treatment System j 3. Static O-Ring Failures

! 4. Off-site Dose Calculation Manual Changes I

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I. INTRODUCTION (UNIT 2)

The Lasalle County Nuclear Power station is a two-Unit facility owned by Commnonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed not I electrical output of 1079 Megawatts, waste heat is rejected to a saan-anada cooling pond using the Illinois river for snake-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 comunercial power operation was comunenced on October 19, 1984. l This report was compiled by Michael J. Cialkowski, telephone number l (815)357-6761, extension 2056. j I

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MONTELY REPORT j A. StBedhRY OF OPERATING EXPERIENCE (Unit 2)

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

12 0100 Reduced power level to 600 Mwe for performance of a rod I set.

i l l 1100 Increased power level to 1130 Mwe.

4 24 0400 Reduced power level to 1045 Mwe to swap the Circulating Water pumps.

0800 Increased power level to 1140 Mwe.

30 2400 Reactor critical, Generator on-line at 1130 Mwe.

B. AMENDHENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None) i C. SUSNITTED LICENSEE EVENT REPORTS (Unit 2) l l

Occurence  !

_LEP . Date Description 95-010 10/07/95 Rollup fire door 615 was left open without a fire )

impairment due to personnel error.

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 I (None)
3. Static O-Ring Failures (None)
4. Changes to the off-Site Dose Calculation Manual (None)

l TABLE 1 0.1 OPERATING DATA REPORT DOCKET No. 050 374 UNIT LASALLE TWO DATE December 11, 1995 COMPLETED SY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 OPERATIM STATUS

1. REPORTI M PERIOD: November 1995 GROSS HOURS IN REPORTI M PERIOD: 720
2. CURRENTLY AUTNORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078
3. Po wR LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Met):
4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTN YEAR TO-DATE CultiLATIVE

5. REACTOR CRITICAL TIME (HOURS) 720.0 5,337.6 70,545.6 1
6. REACTOR RESERVE SHUTDOWN TIME (NOURS) 0.0 0.0 1,716.9 I
7. GENERATOR ON-LINE TIME (HOURS) 720.0 5,112.0 69,097.5
8. UNIT RESERVE SHUTDOWN TIME (NOURS) 0.0 0.0 0.0
9. THERMAL ENERGY CENERATED (MWNt) 2,380,968 15,790,064 209,541,992
10. ELECTRICAL ENERGY CENERATED (MWHe-Gross) 818,168 5,376,123 70,064,692
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 792,434 5,163,408 67,348,170
12. REACTOR SERVICE FACTOR (%) 100.0 66.6 72.4 ,

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13. REACTOR AVAILASILITY FACTOR (%) 100.0 66.6 74.1
14. UNIT SERVICE FACTOR (%) 100.0 63.8 70.9
15. UNIT AVAILISILITY FACTOR (%) 100.0 63.8 70.9
16. UNIT CAPACITY FACTOR (USING MDC) (%) 106.2 62.2 66.7 l
17. UNIT CAPACITY FACTOR (USING DESIGN IRde) (%) 102.1 59.8 64.1
18. UNIT FORCED OUTACE FACTOR (%) 0.0 3.6 10.1
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): N/A
20. IF $NUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A

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DOCKET No. 050 374 l YABLE 2 UNIT LASALLE TWO 1 0.2 AVERAGE DAILY UNIT poler LEVEL (MWe-Net) DATE December 11, 1995 l COMPLETED BY M.J. CIALK0WSKI l TELEPHONE (415) 357 6761 REPORT PERIOD: November 1995 1

DAY poler DAY poler I 1 1,101 17 1,105 1 l

2 1,101 18 1,107 l 3 1,104 1$ 1,105 4 1,107 20 1,105 l 5 1,107 21 1,105 6 1,106 22 1,105 7 1,106 23 1,103 8 1,106 24 1,099 9 1,106 25 1,102 10 1,104 26 1,100 11 1,102 27 1,099 12 1,012 28 1,102 13 1,104 29 1,102 14 1,104 30 1,101 15 1,106 31 16 1,105

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i TABLE 3 D.3 UNIT SEUTDOWNS AND POWER REDUCTIONS > 204 (UNIT 2) 8 unrsOD Or ConRECTIVE YEARLY TYPE SEUTTING DOWN ACTIcetS/CCeedzNTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if i 5: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

NUMBER (YYMOD)

(None)

SUte4hRY OF OPERATION:

The unit mined on-line at high power throughout the esenth. Several minor power reductions were required during the month due to rod pattern adjustments, maintenance and surveillance activities.

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