ML20086K048

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Monthly Operating Repts for June 1995 for LaSalle Generating Station Units 1 & 2
ML20086K048
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 06/30/1995
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9507190349
Download: ML20086K048 (17)
v • d • e


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  • [. Commonwealth IMiwn Compan3 laSa!!c Generating Station

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  • 2 Nil North 21st Road plarwilles,11613419757

. Tel H15-357K61 July 12,1995 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Enclosed for your information is the nionthly performance report covering LaSalle County Nuclear Power Station for June,1995.

.i D. J. Ray Station Manager LaSalle County Station DIR/mkl Enclosure cc: H. J. Miiler, 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.

GE 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 20 0 U.'.% ,

9507190349 950630 PDR ADDCK 05000373 I R PDR 1 l.

A Unicom Company

LABALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT June 1995 cceedONNEALTE EDISCH COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i

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TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. SIDGERY OF OPERATING EXPERIENCE

,. B. AMENDNENTS TO FACILITI LICENSE OR TECHNICAL SPECIFICATIONS f

C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

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

l 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 l

I. INTRODUCTION (UNIT 1)

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 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 consnercial power operation was consnenced on January 1, 1984.

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, exte:.sion 2056.

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.II . M3NTELY REPORT A. StH4hRY OF OPERATING EXPERIENCE (Unit 1)

Day Time Event 1 0000 Reactor critical, Generator on-line at 1120 Mwe.

11 0045 Reduced power level to 740 Mwe for the performance of a rod set, scram time testing, and Main steam Line Isolation valve testing.

0515 Increased power level to 820 Mwe.

1300 Reduced power level to 475 Mwe.

1415 Reduced power level to 200 Mwe.

2154 Generator off-line, forced outage (L1F30) for replacement of Main steam Isolation valve solenoids.

2203 Manual Reactor scram.

17 0749 Reactor critical.

18 1200 Generator on-line at 60 Mwe.

1325 Power level at 160 Mwe.

2130 Power level at 200 Mwe.

19 0145 Upshifted Reactor Recirculation pumps.

0215 Power level at 500 Mwe.

0545 Power level at 700 Mwe.

1445 Power level at 1000 Mwe.

20 0900 Power level at 1070 Mwe.

21 0015 Reduced power level to 700 Mwe for performance of a rod set.

0515 Increased power level to 900 Mwe.

2100 Increased power level to 1110 Mwe.

28 0220 Reduced power level to 1000 Mwe due to control rod 30-39 insert drift.

0400 Increased power level to 1070 Mwe.

30 0115 Reduced power level to S10 Mwe for scram time testing of control rod 30-39.

0415 Increased power level to 1010 Mwe.

1900 Increased power level to 1110 Mwe.

2400 Reactor critical, Generator on-line at 1120 Mwe.

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AMENDNENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

C. SUB(ITTED LICENSEE EVENT REPORTS (Unit 1) 4 (None)

D. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 1) >

) 2. Average Daily Unit Power Level (See Table 2) i j 3. Unit Shutdowns and Significant Power Reductions (See Table 3) 1 I

j E. UNIQUE REPORTING REQUIREMENTS (UNIT 1)

I 1. Safety Relief valve operations i i (None)

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2. Major Changes to Radioactive Waste Treatment Systems (Nono)
3. Static O-Ring Failures (None)
4. Changes to the Off-Site Dose Calculation Manual 1

(None) 1 4

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- . TABLE 1

  • - D.1 OPERATING DATA REPORT DOCKET No. 050-373
  • UNIT LASALLE ONE DATE July 10, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 OPERATING STATUS
1. REPORTING PERIODS June 1995 GROSS NOURS IN REPORTING PERIOD 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 CISIGN ELECTRICAL RATING (MWe N 1,078
3. POWER LEVEL TO WICH RESTRICTED (IF ANY) (MWe-Net):
6. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-To-DATE CUMULATIVE

5. EEACTOR CRITICAL TIME (HOURS) 590.3 4,083.0 70,722.9
6. 6EACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1,641.2
7. GENERATOR ON-LINE TIME (NOURS) 561.8 4,044.5 69,155.6
8. UNIT RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWNt) 1,752,820 13,061,911 205,748,736
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 584,072 4,426,926 68,817,817
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 561,931 4,291,999 66,061,143
12. REACTOR SERVICE FACTOR (X) 82.0 94.0 70.2 1
13. REACTOR AVAILABILITY FACTOR (1) 82.0 94.0 71.8
15. UNIT SERVICE FACTOR (1) 78.0 93.1 68.6
15. UNIT AVAILIBILITY FACTOR (1) 78.0 93.1 68.6
16. UNIT CAPACITY FACTOR (USING MDCs (%) 75.3 95.4 63.3
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (1) 72.4 91.7 60.8
18. UNIT FORCE 0 OUTAGE FACTOR (1) 0.0 3.4 8.0
19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACN): ,

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20. IF SNUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP I

DOCKET NO. 050-373

, TABLE 2 UNIT LASALLE ONE i D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Wet) DATE July 10, 1995 l COMPLETED 8Y M.J. CIALK0WSKI TELEPHONE (815) 357-6761 i

REPORT PERIOD: June 1995 DAY poler DAY POWER I

l l 1 1,076 17 12 I

l 2 1,072 18 78 i

3 1,073 19 771 4 1,073 20 909

$ 1,070 21 967 t

6 1,069 22 1,067 I

! 7 1,079 23 1,062 l

8 1,085 24 1,060 l

9 1,086 25 1,062 10 1,070 26 1,061 11 484 27 1,064 12 -12 28 1,034 13 -12 29 1,033 l 14 -12 30 1,002 15 -12 31 16 -12 l

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TABLE 3 ,

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 1) .

I MTHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CobeENTS CQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER S if NUMBER (YY>eOD) 5: SCHEDULED (HOURS) REASON REDUCING POWER applicable) l I 3 950611 F 158.2 A 2 Forced outage for replacement of Main Steam Isolation 4 Valve solenoids.

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4 simesARY OF OPERATION:

4 The unit remained on-line at high power throughout most of the month. The unit expirenced a forced outage on j 06/11/94 to replace a Main Steam Line Isolation valve solenoids. The unit was returned to service on 06/10/95.

During the remainder of the month there were several minor power reductions due to maintenance and surveillance cetivities.

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LASALLE NUCLEAR PolmR STATION UNIT 2 DONTELY PERFORMANCE REPORT June 1995 CCteeDNNEALTE EDISON COMPANY NRC DOCKET No. 050-374  :

LICENSE NO. NPF-18 I

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i TABLE OF CONTENTS (UNIT 2)

1. INTRODUCTION II. REPORT A. StBeGGLY OF OPERATING EXPERIENCE
3. AMENDMENTS TO FACILITY LICENSE OR TECENICAL SPECIFICATIONS j C. LICENSEE EVENT REPORTS f 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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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 net i 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, 1994 and commercial power operation was comunenced on october 19, 1984.

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

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II. MONTHLY REPORT A. 31264ARY OF OPERATING EXPERIENCE (Unit 2)

Day Time Event 1 0000 Reactor sub-critical, Generator off-line. Refuel outage (L2R06) in progress.

7 1035 Reactor critical.

11 0220 Generator on-line at 60 MWo.

0345 Power level at 125 MWo.

1130 Power level at 185 kwe.

12 0335 Turbine Generator trip for overspeed testing.

0505 Generator on-line at 60 MWe.

1315 Power level at 180 MWe.

14 0015 Power level at 315 NWo.

16 1024 Upshifted Reactor Recirculation pumps.

1135 Power level at 700 NWo.

17 1530 Power level at 900 Nke.

19 0400 Power level at 1040 NWo.

30 2400 Reactor critical, Generator on-line at 1040 MWe.

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.. B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION l

. (None) ,

l C. SUBMITTED LICENSEE EVENT REPORTS (Unit 2)

Occurence l LER No. Date Description 95-009 05/03/95 During the performance of a reactor vessel water level reference leg continuous backfill at panel 2Cll-P002 an instrument rack spike occurred.

This resulted in a low reactor water level 1/2 scram, a 1/2 isolation signal to Primary containment Isolation groups 1,2,3,4,5,6,7 & 10, a 1/2 initiation signal to Alternate Rod Insertion and a High Pressure Core Spray Diesel Generator and pump initiation.

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) j 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) l

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. TABLE 1

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

. UNIT LASALLE TWO DATE July 10, 1995 COMPLETED SY M.J. CIALK0WSKI TELCPHONE (815)-357-6761 OPERATING STATUS 1

1. REPORTING PERIOD: June 1995 GROSS HOURS IN REPORTING PERIOD: 720 '
2. CURRENTLY AUTHORIZED P0bER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Wet): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078 l
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

4 REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS **TH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (NouRS) 565.4 1,841.7 67,049.6
6. REACTOR RESERVE SNUTDOWN TIME (HOURS) 0.0 0.0 1,716.9
7. GENERATOR ON-LINE TIME (NOURS) 476.2 1,628.5 65,614.0 ,

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8. UNIT RESERVE SNUTDobal TIME (NOURS) 0.0 0.0 0.0
9. THERMAL Eue:RGY GENERATED OGJMt) 1,130,246 4,861,253 196,613,181
10. ELECTRICAL ENERGY GENERATED (MWNo-Gross) 394,337 1,675,464 66,364,033
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 375,943 1,589,882 63,774,644
12. REACTOR SERVICE FACTOR (1) 78.5 42.4 71.5
13. REACTOR AVAILABILITY FACTOR (1) 78.5 42.4 73.3
14. UNIT SERVICE FACTOR (1) 66.1 37.5 70.0 l l
15. UNIT AVAILis!LITY FACTOR (E) 66.1 37.5 70.0
16. UNIT CAPACITY FACTOR (USING MDC) (%) 50.4 35.3 65.6
17. UNIT CAPACITY FAL &J (USING DESIGN MWe) (1) 48.4 34.0 63.1
18. UNIT FORCED OUTAGE FACTOR (1) 0.0 0.0 10.4 l
19. SNUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACN):
20. IF SNUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
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DOCKET Mo. 050 374

    • - TABLE 2 UNIT LASALLE TWO

, 'D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE July 10, 1995 COMPLETED 8Y M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PERIOD: June 1995 s

DAY POWER DAY POWER

....... ......... ....... ......... j 1 -12 17 730 2 -12 18 838 3 -12 19 1,037 4 -12 20 1,081 5 -12 21 1,070 6 -12 22 1,069 e 7 12 23 1,054 8 -12 24 994 ,

9 -12 25 1,069 to 12 26 1,066  ;

11 129 27 1,073 12 126 28 1,077 13 176 29 1,075 ,

l 14 280 30 1,075 15 276 31 16 489 1 i

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

(UNIT 2) l METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCDOENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YDOOD) 5: SCHEDULED (BOURS) REASON REDUCING POWER applicable)

< 1 950218 5 242.3 C 2 Refuel outage (L2R06) 2 950612 s 1.5 B 4 Main Turbine overspeed trip test (the Reactor remained critical).

5themRY OF OPERATION:

, The unit started the month in a scheduled refuel outage. The unit was returned to service on 06/11/95. The

! Main Turbine was taken off-line for a brief period on 06/12/95 for routine overspeed testing. Upon the return l ts service and subsequent rasip up in power the unit remained on line for the remainder of the month.

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