ML20117K886

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Monthly Operating Repts for May 1996 for Lasalle County Station Units 1 & 2
ML20117K886
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 05/31/1996
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606130060
Download: ML20117K886 (17)
v • d • e


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. Onnmonw ealth litivut Compan) 8

[Aal!c Generating Station

, EOl North 2ht Road j

. Marseilles,11.613 il-9 $'

TelHI435"6?61 l l

l June 10,1996 l

l United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

LaSalle County Station Units 1 and 2 Monthly Performance Report i NRC Docket Numbers 50-373 and 50-374.

Enclosed is the LaSalle County Station Monthly Performance Report for the month of May,1996, i

L Respectfully, 1

D.

Ray R

Station Manager LaSalle County Station Enclosure f

l cc: H. J. Miller, NRC Region 111 Administrator i

P. G. Brochman, NRC Senior Resident Inspector - LaSalle D. M. Skay, Project Manager, NRR - LaSalle C. H. Matthews, IDNS Resident inspector - LaSalle D. Deppa, IDNS Reactor Safety - Springfield P. Doverspike, GE Representative - LaSalle D. L. Farrar, Nuclear Regulatory Services Manager INPO - Records Center

! Central file

130013

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9606130060 960531 PDR ADOCK 05000373 R PDR A t nicom onupan> I

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I LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT May 1996 CotedONNEALTH EDISON COMPANY l NRC DOCKET No. 050-373 LICENSE No. NPF-11 l

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TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION  ;

II. REPORT A. StBe8ARY OF OPERATING EXPERIENCE

3. aNS TO FACILITY LICENSE OR TECHNICAL SPECUICATIONS 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 l
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 i l

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  • 1 .- 1 j l I. INTRODUCTIoti (UNIT 1) l The Lasalle County Nuclear Power Station is a two-Unit facility owned by Comunonwealth Edison Company and located near Marseilles, f Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Wasts heat is rejected to a

]j man-made cooling pond using the Illinois river for make-up and I

I blowdown. The architect-engineer was Sargent and Lundy and the contractor was Comanonwealth Edison Company.

I Unit one was issued operating license number NPF-11 on April 17, 1982. Initial criticality was achieved on June 21, 1982 and l coensercial power operation was commenced on January 1, 1984.

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

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I,3 . MONTELY REPORT A. StBMARY OF OPERATING EXPERIENCE (Unit 1) y D Time Event 1 0000 Reactor criticat (criticality achieved on 04/21/96), Generator off-line, refuel outage (L1R07) in progress, i 6 2306 Generator on-line at 60 Mwe, refuel outage (L1R07) ends.

7 0500 Power level at 125 Mwe.

2138 Main Turbine trip for overspeed testing.

l l 2234 Generator on-line at 60 Mwe.

8 0200 Power level at 220 Mwe.

9 1040 Upshifted Reactor Recirculation pusps, power level at 400 Mwe.

1700 Power level at 800 Mwe, 1800 Power level at 900 Mwe.

10 2230 Power level at 1000 Mwe.

12 0107 Manual Reactor scram due to high vibrations levels on the Main Turbine bearing #12.

13 0945 Reactor critical.

17 0927 Generator on-line at 60 Mwe.

18 0050 Upshifted Reactor Recirculation pumps, power level i

! at 465 Mwe.

0320 Power level at 760 Mwe.

1040 Power level at 900 Mwe.

22 0600 Power level at 990 Mwe.

I i 23 0415 Power level reduced to 718 Mwe for performance of a

( rod set.

I 1630 Power level increased to 1130 Mwe.

31 2400 Reactor critical, Generator on-line at 1130 Mwe.

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. D. E N S TO THE FACILITY OR TECHNICAL SPECIFICATION (N ne)

]

C. SU M TTED LICENSEE EVENT REPORTS (Unit 1)

Occurrence LER No. Date Description 96-004 04/12/96 "B" Reactor Protection Systesa Motor i Generator Set EPMA breaker inadvertently tripped due to personnel error.96-005 04/23/96 Missed Technical Spr'ification serveillance, Manua' Scram Instrumentation Functional Test, due to a human performance error. 1 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)
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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) a 4

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TABLE 1 0.1 OPERATING DATA REPORT DOCKET NO. 050 373 UNIT LASALLE ONE DATE June 10, 1996 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815) 357 6761 OPERA 71NG STATUS l 1. REPORTING PERIOD: May 1996 GROSS HOURS IN REPORTING PERIOD 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CA/ACITY (MWe Net): 1,036 l DESIGN ELECTRICAL RATING (MWe N 1,078
3. POWER LEVEL TO WHICH RESTRICTED (!F ANY) (MWe-Net): N/A l 6. REASONS FOR RESTRICT!DN (IF ANY): N/A REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

! 5. REACTOR CRITICAL TIME (HOURS) 639.4 1,450.2 75,527.5

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

7. GENERATOR ON LINE TIME (HOURS) 4 71.7 1,054.0 74,394.1
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 1
9. THERMAL ENERGY GENERATED (MWHt) 1,398,076 2,809,844 221,264,661
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 882,631 73,926,483 412.227
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 397,491 821,794 70,960,222
12. REACTOR SERVICE FACTOR (%) 85.9 39.8 69.4
13. REACTOR AVAILABILITY FACTOR (%) 85.9 39.8 70.9 i
14. UNIT SERVICE FACTOR (%) 63.4 28.9 68.3
15. UNIT AVAILIBILITY FACTOR (%) 63.4 28.9 68.3
16. UNIT CAPACITY FACTOR (USING MDC) (%) 51.6 21.8 62.9
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 49.6 20.9 60.5
18. UNIT FORCED OUTAGE FACTOR (%) 21.4 10.9 7.9
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): N/A l

l 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A l~

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DOCKET NO. 050 373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE June 10, 1996 COMPLETED BY M.J. CIALK0W5KI TELEPHONE (815) 357-6761 REPORT PERIOD: May 1996 DAY POWER DAY POWER

.1 -12 17 124 2 -12 18 743 3 12 19 859 4 12 20 866 5 12 21 855 6 9 22 896 7 94 23 1,003 l

8 212 24 1,093 9 525 25 1,080 10 856 26 1,080 11 969 27 1,080 12 33 28 1,081 13 12 29 1,081 14 12 30 1,078 l

l 15 12 31 1,0 73 1

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l TABLE 3 '.

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 1) +

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METHOD OF CORRECTIVE YLARLY TYPE SHUTTING DOWN ACTIONS /CCBAENTS SEQUENTIAL DATE F: IDRCED DURATION THE REACTOR OR (LER # if i NUMBER (YDedDD) S: SCHEDULED j. N.) REASOtt REDUCING POWER applicable) l 01 960125 S 143.1 C 2 Refuel outage

! (L1R07) 02 960507 5 0.9 B 4 Main Turbine overspeed trip test.

03 960512 F 128.3 A 2 Unit shutdown due to high vibration levels on the Main Turbine bearing #12.

SIme(ARY OF OPERATION: The unit started the month in a scheduled refueling outage. The unit was returned to service on 05/06/96. Following the Main Turbine overspeed testing the unit -noed a ramp to power. The Main Turbine experienced high vibration levels and the unit was subsequently scramed on 05/12/96. The unit was returned to service on 05/17/96 and r===ined on-line for the r===inder of the month.

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l LASALLE NUCLEAR POWER STATION UNIT 2 MONTEL7 PERFORMANCE REPORT May 1996 CCnWONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 1

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TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A. StBWARY OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TABUIATIONS

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

l l E. UNIQUE REPORTING REQUIREMENTS l 1. Main Steam safety Relief Valve Operations

2. Major Changes to Radioactive Waste Treatment System l 3. Static O-Ring Failures
4. Off-site Dose calculation Manual changes l l

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  • I. INTRODUCTION (UNIT 2)

The LaSalle County Nuclear Power Station is a two-Unit facility j owned by casumonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net

, electrical output of 1078 Megawatts. Waste heat is rejected to s j man-made cooling pond using the Illinois river for make up and blowdown. The architect-engineer was Sargent ana Lundy and the

, contractor was Comunonwealth Edison Company.

Unit two was issued operating licenso number NPF-18 on December j 16, 1983. Initial criticality was achieved on March 10, 1984 and comunercial power operation was comunenced on October 19, 1984.

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

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II. MONTELY REPORT A. SUt64ARY OF OPERATING EXPERIENCE (Unit 2)

Day Time Event 1 0000 Reactor critical, Generator on-line at 950 Mwe, power level held due to Turbine control valve #3 remaining in a closed position. ,

l 15 2215 Reduced power level to 800 Mwe due to system load.

16 0335 Increased power level to 900 Mwe. l 1400 Increased power level to 950 Mwe.

! l 20 2100 Reduced power level to 870 Mwe due to #1 Turbine '

bypass valve opening. ,

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2330 commes.ced unit shutdown due to problems with the Electro-Hydraulic Control system.

l 21 0220 Power leval at 490 Mwe.

0310 Power level at 300 Mwe.

0901 Generator off-line.

0951 Hanual reactor scram. 1 l

24 0600 Reactor critical.

2207 Generator on-line at 45 Mwe.

25 0915 Upshifted Reactor Recirculation pumps, power level at 400 Mwe.

1300 Power level at 780 Mwe.

26 1700 Power level at 950 Mae.

28 0200 Power level at 1130 Mwe.

0900 Reduced power level to 960 Mwe due to problems with the Electro-Hydraulic Control system.

29 0700 Increased power level to 1135 Mwe.

31 2400 Reactor t.. itical, Generator on-line at 1120 Mwe.

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. D. E N s TO THE FACILITY OR TECHNICAL SPECIFICATIC'I

,- (Nine) 4 C. SUEMITTED LICENSEE EVENT REPORTS (Unit 2) j (None)

. l D. DATA TABUIATIONS (Unit 2)

l. Operating Data Report (See Table 1) 4
2. Average Daily Unit Power Level (See Table 2) l l 1 3. Unit Shutdowns and Significant Power Reductions (see Table 3) l

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E. UNIQUE REPORTING REQUIREMENTS (UNIT 2)

1. Safety Relief Valve operations I (None) ,

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2. Major Changes to Radioactive Waste Treatment Systems  ;

(None) l

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

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,. I TAELE 1 0.1 OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LASALLE TWO DATE Jure 10, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 OPERATING STATUS

1. REPORTING PERIOD: May 1996 GROSS HOURS IN REPORTING PERIOD: 744
3. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 I DESIGN ELECTRICAL RATING (MWe-Net): 1,078 j l
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): N/A -
6. REASONS FOR RESTRICTION (!F ANY): N/A J

REPORTING PERIOD DATA THIS MONTH YEAR-TO DATE CUMULATIVE ,

5. REACTOR CRITICAL TIME (HOURS) 675.9 3,484.2 74,773.8 j i
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9

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7. GTNERATOR ON-LINE TIME (HOURS) 658.9 3,398.1 73,239.6 l l
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHt) 1,810,408 10,419,466 222,388,721
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 622,117 3,564,279 74,462,135
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 601,184 3,446,462 71,599,134
13. REACTOR SERVICE FACTOR (%) 90.8 95.5 73.4
13. REACTOR AVAILABILITY FACTOR (%) 90.8 95.5 75.1
16. UNIT SERVICE FACTOR (%) P8.6 93.2 71.9
15. UNIT AVAILIBILITY FACTOR (%) 88.6 93.2 71.9 l
16. UNIT CAPACITY FACTOR (USING MDC) (%) 78.0 91.2 67.9 l l
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 75.0 87.7 65.2
18. UNIT FORCED OUTAGE FACTOR (%) 11.6 6.9 9.9 I
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EAC1): Refuel, 09/07/96, 10 Weeks
20. ;F SHUTDOWN AT END OF REPOCT PERIOD, ESTIMATED DATE OF STARTUP: N/A i

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DOCKET NO. 050-374 TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE June 10, 1996 COMPLETED BY M.J. CIALK0W5KI TELEPHONE (815) 357 6761 l REPORT PERIOD: May 1996 l

DAY POWER DAY POWER

....... ......... ....... ......... l 1 907 17 917  !

2 904 18 925 f

3 915 19 925 4 913 20 898 5 913 21 107 6 910 22 -11 1 7 919 23 11 I 8 918 24 3 9 923 25 498 10 921 26 885  !

11 930 27 949 12 918 28 1,032 13 922 29 1,103 14 924 30 1,103 15 907 31 1,100 16 888 i

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TABLE 3 , ,

D.3 UNIT SHUTDOWNS AMD POWER REDUCTI0ess > 20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /C(BedENTS SEQUENTIAL DATE F: FORCED DURATIOtt THE REACTOR OR (LER # if NUMBER (YYledDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 04 960521 F 85.1 A 2 Unit shutdown due to problemas with the Electro-Hydraulic Control systesa.

Stme(ARY OF OPERATION: The unit remained on-line at high power throughout most of the month. The unit experienced a forced outage on 05/20/96 to correct problesas with the Electro-Hydraulic Control system.

The unit was returned to service on 05/24/96.

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