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Monthly Operating Rept for Dec 1994 for LaSalle County Nuclear Station Units 1 & 2
	ML20077R312
Person / Time
Site:	LaSalle
Issue date:	12/31/1994
From:	Cialkowski M, Ray D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9501200142
	Download: ML20077R312 (18)
	v • d • e

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Commonwealth Edison

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

Marseilles, Illinois 61341 Telephone 815/357-6761 January 12,1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 l

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for December,1994.

D. J. Ray Station Manager LaSalle County Station DJR/tmb Enclosure l

cc: John B. Martin, Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle l IL Department of Nuclear Safety - LaSalle IL Department of Nuclear Safety - Springfield, IL NRR Project Manager - Washington, D.C. !

l 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 l l

INPO Records Center Central File l l

l 100053 ;j 9501200142 DR 941231 ADOCK 05000373 / p/; ,

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LASALLE NUCLEAR PONER STATION UNIT 1 NONTELY PERFORNANCE REPORT December 1994 COMMONNEALTE EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l

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) TABLE OF CONTENTS l (UNIT 1) 4 1 I. INTRODUCTION i II. REPORT t

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SUMMARY

OF OPERATING EXPERIENCE

{ B. AMENDMENTS TO FACILITY LICENSE OR TECENICAL SPECIFICATIONS i

C. LICENSEE EVENT REPORTS

$ D. DATA TABULATIONS 1 1. Operating Data Report *

2. Average Daily Unit Power Level

3. Unit shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS j 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 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 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 comunenced on January 1, 1984.

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

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II. MONTHLY REPORT A. SUNNARY OF OPERATING EXPERIENCE (Unit 1)

Dar Time Einna 1 0000 Reactor critical, Generator on-line at 1140 Nwo.

9 0100 Reduced power level to 1070 Nwe to changeover the Condensate / Condensate Booster pumps.

0500 Increased power level to 1140 12we.

11 2100 Reduced power level to 890 Nwe to place the 'A' Turbine Driven Reactor Feed pump out of service for maintenance activities. Placed the Notor Driven Reactor Food pump on-line.

12 0400 Increased power level to 1060 Nwe.

2133 Reactor scras due to group I isolation during Nain Steam high flow switch surveillance. Cause was attributed to a failed flow switch.

17 1123 Reactor critical.

18 0420 Generator on-line at 88 Nwe.

0430 Power level at 180 Nwe.

19 1840 Nanual Reactor shutdown due to problems with the Rod Position Indication system.

l 22 1031 Reactor cricical.

23 0130 Generator on-line at 80 Nwe.

1400 Power level at 200 Nwe.

2200 Power level at 700 Nwe.

24 0100 Power level at 900 Nwo.

25 1300 Reduced power level to 850 Nwe due to system load.

26 0500 Increased power level to 900 Nwe.

27 0100 Reduced power level to 630 Nwe to perform a rod set.

0700 Increased power level to 1000 Nwo.

28 0600 Increased power level to 1130 Nwe.

30 2200 Reduced power level to 990 Nwe due to system load.

31 1300 Increased power level to 1140 Nwe.

2400 Reactor critical, Generator on-line at 1130 Nwe.

i i Q. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATIO3 (None)

C, LICENSEE EVENT REPORTS (Unit 1)

LER No. Dats pescriction 94-015 12/12/94 Received group 1 isolation causing a reactor

scram.

l D. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 1) j 2. Average Daily Unit Power Level (See Table 2) l

3. Unit Shutdowns and Significant Power Reductions (See Table 3) j E. UNIQUE REPORTING REQUIREMENTS (UNIT 1) l 1. Safety Relief Valve Operations l

l Date of Type of

Actuation valve Actuating Boason 12/12/94 1B21-F013D Automatic Reactor Scram LER# 94-015

i. 12/12/94 1B21-F0138 Automatic Reactor Scram LERS94-015

12/12/94 1B21-F013U Automatic Reactor Scram LER$ 94-015

, 12/12/94 1B21-F013B Manual Reactor Scram LER# 94-015 l 12/12/94 1B21-F013C Manual Reactor Scram LERS94-015 ,

2. Major Changes to Radioactive Waste Treatment Systems

(None) l 3. Static O-Ring Failures (See Attachment A)

4. Changes to the Off-site Dose Calculation Manual (None) l i

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TABLE 1

, D.1 OPERATING DATA REPORT DOCKET NO. 050-373 1 UNIT LASALLE ONE j DATE January 11,1995

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COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 OPERATING STATUS

9. REPORTING PERIOD: December 1994 GROSS HOURS IN REPORTING PERIOD 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-N 1,078

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

4. REASONS FOR RESTRICTION (IF ANY): l REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 570.3 5,313.0 66,639.9

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

7. GENERATOR ON-LINE TIME (HOURS) 538.4 5,D97.5 65,111.2

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

9. THERMAL ENERGY GENERATED (MWHt) 1,603,693 15,361,188 192,686,825 l 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 525,061 5,136,520 64,390,891

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 505,918 4,920,390 61,769,144

12. REACTOR SERVICE FACTOR (%) 76.7 60.7 69.1 1

13. REACTOR AVAILABILITY FACTOR (%) 76.7 60.7 70.8 l

l 14. UNIT SERVICE FACTOR (%) 72.4 58.2 67.5

15. UNIT AVAILIBILITY FACTOR (%) 72.4 58.2 67.5

16. UNIT CAPACITY FACTOR (USING MDC) (%) 65.6 54.2 61.8

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 63.1 52.1 59.4 ,

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18. UNIT FORCED OUTAGE FACTOR (%) 27.6 16.5 8.3

99. SNUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

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

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,. DOCKET Wo. 050-373

. . TABLE 2 UNIT LASALLE ONE

j D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) .DATE January 11,1995 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815) 357-6761 1

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. REPORT PERIOD: December 1994 DAY POWER DAY POWER l

1 1,099 17 -12 ;

2 1,101 18 91

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4 1,098 20 -12 I

5 1,097 21 12 6 1,096 22 12 7 1,097 23 269 8 1,099 24 856 9 1,098 25 838 i

10 1,102 26 857 j t

11 1,079 27 922

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p 12 892 28 1,087 i l

13 12 29 1,095 14 -12 30 1,085 15 12 31 1,042 ,

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

(UNIT 1) t I

l METHOD OF CORRECTIVE YEARLl TYPE SHUTTING DOWN ACTIONS / COMMENTS CEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (I2R 9 if NUMBER (YYBOEDD) S_: SCHEDULRQ 1BOURS) ERA _S9H REDUCING POWER a_policablel 8 941212 F 126.8 A 3 Reactor scram due to group I isolation during a Main Steam high flow switch surveillance.

LERG 94-015.

9 941219 F 78.8 A 1 Manual Reactor shutdown due to problems with the Rod Position Indication system.

CUBOEARY OF OPERATION:

The unit started the month on line at high power. The unit experienced an automatic reactor scram on 12/12/94 and was returned to service on 12/18/94. The unit was then manually shutdown on 12/19/94 due problems with the rod position indication system. The unit was returned to service on 12/23/94. Following a ramp to power several minor power reductions were required due to system requirements.

. ATTACEMENT A SOR do SWITCH FAILI[RE DATA SHEET Equipment Piece Number: 1E31-N009C Model Number: 102-As-B403-NX-JJTTX6 Serial Number: 86-10-558 Application: Main steam Line Einh Flow Date and Time of Discovery: 12/13/94 0000 hours0 days 0 hours 0 weeks 0 months L

Reactor Mode: 3 fEot shutdown) Power Levels _ph r

Calibration Tolerance: 102.0 - 104.0 PSID Nominal Setpoints 103.0 PSID ,

Action Limits: < 98.2 or >107.8 PSID Reject Limits: < 94.8 or >111.2 PSID Technical Specification T Limits: ._115_ PSID As Found Setpoints N/A PSID Date and Time of Return to Service: 12/14/94 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months ,

Model Number of Replacement Switch: _1}l-AS-B403-NX-JJTTX6 Serial Number of Replacement Switch: 93-3-7111 PIF Numbers 373-180-94-02588 Causes Switch was found to be not reneatahle.

Corrective Action: The switch was taken out of service and replaced.

LASALLE NUCLEAR POWER STATION UNIT 2 NONTELY PERFORMANCE REPoitT December 1994 ColetOWtEALTE EDISON COMPANY l

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

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TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EEPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECEMICAL 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 Yalve 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 I. INTRODUCTION (UNIT 2) l l

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison Company and located near Marseilles, j Illinois. Each unit is a Boiling Water Reactor with a designad not ,

electrical output of 1078 Megawatts. Waste heat is rejecteA ta a ,

man-made cooling pond using the Illinois river for make-up &nd '

blowdown. The architect-engineer was sargent and Lundy and the l 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, 1904.

This r6 port was compiled by Michael J. Cialkowski, telephone number I (015)357-6761, extension 2427.

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II. MONTELY REPORT l

A. '8UMMARY OF OPERATING EXPERIENCE (Unit 2) l l

Day Time Event '

l 1 0000 Reactor critical, Generator on-line at 950 Nwe. Power level being reduced due to Feedwater system testing.

9 0000 Increased power level to 1140 Nwe.

11 0800 Reduced power to 1100 Nwe due to system load.

1100 Increased power level to 1140 Nwe.

15 0300 Reduced power level to 1000 Nwe to perform a rod set.

1700 Increased power level to 1140 Nwe. !

19 0300 Reiuced power level to 1050 Nwe to changeover the Condensate / Condensate Booster pumps.

0600 Increased power level to 1140 Nwe. I 1

24 0400 Reduced power level-to 1030 Nwe due to system load.

25 0200 Reduced power level to 850 Nwe due to system load.

26 1200 Increased power level to 1140 Nwe.

l 30 0200 Reduced power level to 1000 Nwe due to system load.

31 0400 Reduced power level to 1000 Nwe due to system load.

l 1200 Increased power level to 1140 Nwe.

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l 2400 Reactor critical, Generator on-line at 1140 Nwe. l l

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, B. AMENDMENTS TO TEE FACILITY OR TECENICAL SPECIFICATION (None)

C. LICENSEE EVENT REPORTS (Unit 2)

LER No. Date Descrintion ,94-010 12/14/94 During ,._!_------- a' surveillance testing a low level initiation of the Emergency Core Cooling System and Reactor Core Isolation Cooling System was received.94-011 12/20/94 Diesel Generator cooling water pump trip.94-012 12/21/94 Eigh Pressure Core System declared inoperable due to the 'B' diesel generator 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months timeclock expiring.

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. Najor Changes to Radioactive Waste Treatment systems (None)

3. Static O-Ring Failures (None)

4. Changes to the Off-site Dose Calculation Nanual (None)

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

UNIT LASALLE TWO i i

DATE January 11,1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 OPERATING STATUS

1. REPORT!NG PERIOD: December 1994 GROSS HOURS IN REPORTING PERIOD: 744 l 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 mar DEPEND CAPACITY (MWe-Net): 1,036 D?. SIGN ELECTRICAL RATING (MWe-Net): 1,078 l

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): ;

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4. REASONS FOR RESTRICTION (lF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE l

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! 5. REACTOR CRITICAL TIME (HOURS) 744.0 8,282.4 65,208.0 l l l l 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 l t i F. GENERATOR ON-LINE TIME (HOURS) 744.0 8,103.2 63,985.5 Q. CIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0

9. THERMAL ENERGY GENERATED (MWHt) 2,417,108 25,651,475 193,751,928 l

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 826,694 8,703,929 64,688,569

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 801,611 8,428,871 62,184,762

12. REACTOR SERVICE FACTOR (%) 100.0 94.5 72.9

13. REACTOR AVAILABILITY FACTOR (%) 100.0 94.5 74.8

94. UNIT SERVICE FACTOR (%) 100.0 92.5 71.5 i

15. UNIT AVAILIBILITY FACTOR (%) 100.0 92.5 71.5 1

16. UNIT CAPACITY FACTOR (USING MDC) (%) 104.0 92.9 67.1 l

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17. CIT CAPACITY FACTOR (USING DESIGN MWe) (%) 99.9 89.3 64.5

18. C IT FORCED OUTAGE FACTOR (%) 0.0 4.4 10.6 l

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

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

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-Net) DATE January 11,1995 CJMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 REPORT PERIOD: December 1994 DAY POWER DAY POWER l

1 1,032 17 1,100 1

2 1,103 18 1,095 3 1,102 19 1,094 4 1,102 20 1,095 5 1,098 21 1,102 6 1,097 22 1,098 7 1,098 23 1,098 I

8 1,099 24 1,017 9 1,100 25 849 10 1,100 26 1,026 l

l 11 1,006 27 1,094 i

12 1,097 28 1,101 1

13 1,0% 29 1,103 14 1,095 30 985 15 1,086 31 1,042 16 1,100 l

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t I TABLE 3 .

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COBetRNTS CEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER $ if NUMBER _LIIMLEQD_). S SCHEDULED (HOURS.l _ REASON REDUCING POWER applicable)

(None) t CUMBIARY 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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ML20077R312

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