ML20080H038

Monthly Operating Repts for Jan 1995 for LaSalle County Nuclear Power Station

ML20080H038
Person / Time
Site:	LaSalle
Issue date:	01/31/1995
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9502140383
Download: ML20080H038 (17)

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. , Omimonwealth Illison Company laNtile Generatmg Nation i  ; 2601 North 21st Road

,- Marw:illes. II 613 4 I-9'57

.. , TelHI535'676i February 10,1995 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 January,1995.

%q 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.

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

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f*rQQt 4as a ue r) 9502140383 950131 PDR ADDCK 05000373 ji R PDR e,e_ o,,a,

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f.amat T 2 NUCLEAR POlmR STATION UNIT 1 MONTHLY PERFORMANCE REPORT January 1995 COMMONWEALTH EDISON CONPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 k

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l. TABLE OF CONTENTS l (UNIT 1) l I. INTRODUCTION II. REPORT A. SISSIARY OF OPERATING EXPERIENCE l B. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS l D. DATA TABULATIONS l 1. Operating Data Report

2. Average Daily Unit Power Level ,

3. Unit shutdowns and Power Reductions  !

l E. UNIQUE REPORTING REQUIREMENTS

1. Main Steaan Safety Relief Valve Operations ,

2. Major Changes to Radioactive Waste Treatment System- !

l 3. Static O-Ring Failures j

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 Ccamoraealth Edison Company and located near Marseilles, Illinois. Each unit is a BoiliLg Water Reactor with a designed not electrical output of 1078 Megesatts. Waste heat is rejected to a '

man-made cooling pond using ti,e Illinois river for make-up and blowdown. The architect-engiv s was Sargent and Lundy and the contractor was Coasmonwealth E!t n Company.

Unit one was issued operating linense number NPF-11 on April 17, 1982. Initial criticality was achieved on June 21, 1982 and commercial power operation was comumenced on January 1,1984.

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

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1 II.

• MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

Day Tinte Event 1 0000 Reactor critical, Generator on-line at 1130 Mwe.

4 0300 Reduced power level to 1000 Mwe to perform a rod set.

1000 Increased power level to 1145 Mwe.

12 2300 Reduced power level to 930 Mwe to perform a rod set.

13 0500 Increased power level to 1120 Mwe.

0600 Reduced power level to 990 Mwe to perform a rod set. }

1100 Increased power level to 1100 Mwe.

21 0500 Reduced power level to 1070 Mwe to changeover Condensate / Condensate Booster pumps.

0900 Increased power level to 1135 Mwe.

31 2400 Reactor critical, Generator on-line at 1140 Mwe.

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AMENDNENTJ TO THE FACILITY OR TECHNICAL CPECIFICATION )

. (Non3) ,

e t C. LICENSEE EVENT REPORTS (Unit 1)

LER No. Dat., Descrintion 95-001 01/06/95 Instrument stop valve for Residual Heat Removal (RER) Pump 1A high pressure switch found closed.

This instrument provides for an alarm in the Control Room.95-003 01/27/95 TIP Ball Valves will re-open upon reset of a Group 7 isolation if the valve control switch is left in the open position.95-004 01/31/95 Determination that a Senior Reector Operator was absent from the Control Room for 3 minutes 32 seconds on May 26, 1994.

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)

I i' TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ONE DATE February 10, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 DPERATING STATUS I

' 1. REPORTING PEW 100: January 1995 GROSS HOURS IN REPORTING PERIOD 744 i

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 (IF ANY) (MWe-Net):

6. REASONS FOR RESTRICTION (IF ANY): ,s REPORTING PERIDO DATA

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THIS MONTH YEAR-TO-DATE CUMULATIVE ,

5. REACTOR CRITICAL TIME (HOURS) 744.0 744.0 67,383.9

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

7 GENERATOR ON LINE TIME (HOURS) 744.0 744.0 65,855.2

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

9. THERMAL ENERGY GENERATED (MWHt) 2,457,885 2,457,885 195,144,710

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 839,182 839,182 65.230,073 l z

- 19. ELECTRICAL ENERGY GENERATED (MWHe-Net) 813,809 813,809 62,582,953

12. REACTOR SERVICE FACTOR (%) 100.0 100.0 69.3

'13. REACTOR AVAILABILITY FACTOR (%) 100.0 100.0 71.0

16. UNIT SERVICE FACTOR (%) 100.0 100.0 67.8 1$. UNIT AVAILIBILITY FACTOR (%) 100.0 100.0 67.8 f

16. UNIT CAPACITT FACTOR (USING MDC) (%) 105.6 105.6 62.1 i

97. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 101.5 101.5 59.7 i i

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 8.2

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

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

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. DOCKET Wo. 050-373-t TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE February 10,'1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 i l

REPORT PERIOD: January 1995 l

DAY POWER DAY POWER j j

1 1,081- 17 1,095 j 2 1,088 18 1,098 3- 1,076 19 1,097 f 1

4 1,087 20 1,097 I

5 1,099 21 1,093 6 1,097 22 1,099  ;

i 7 1,098 23 1,098 8 1,098 24 1,099 l 9 1,098 25 1,098

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10 1,0% 26 1,098 f

11 1,099 27 1,099  ;

12 1,0% 28 . 1,099 i i

15 1,042 29 1,100 -

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14 1,094 30 1,101 j 15 1,094 31 1,100 I

16 1,095 i

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TABLE 3 D.3 UNIT SHUTDOWMS AND POWER REDDCTIONS > 20%

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COOSENTS CEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER 9 if NUBEBER (YDSEDD) S SCHEDULED 1BOURS) REASON BEDUCING POWER applicable)

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SUMMARY

OF OPERATION:

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

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Ta m LE NUCLEAR PONER STATION.  !

UNIT 2 MONTHLY PERFORMANCE REPORT f

January 1995 C0000010fEALTH EDISON COMPANY NRC DOCIWT NO. 050-374 ,

i LICENSE NO. NPF-18 5

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't TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A. SUsetARY OF OPERATING EXPERIENCE B. AMENDHENTS TO FACILITY LICENSE OR TECENICAL BPECIFICATIONS 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

3. Static O-Ring Failures

4. Off-site Dose calculation Manual Changes 1

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I. INTRODUCTION (UNIT 2)

The Lasalle County Nuclear Power station is a two-Unit facility owned by Casumonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Nater Reactor with a designed not .

electrical output of 1078 Megawatts. Waste heat is rejected to a l man-made cooling pond using the Illinois river for make-up and blowdown. The architect-engineer was sargent and Lundy and the contractor was cosanonwealth Edison Ccapany.

Unit two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and ,

cessnercial power operation was coasmenced on October 19, 1984.

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

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. II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Time Erent 1 0000 Reactor critical, Generator on-line at 1130 Mwe.

0300 Reduced power to 930 Mwe due to system load requirements.

2 0400 Increased power level to 1140 Mwe.

5 0300 Reduced power level to 1000 Mwe to perform a rod set.

0600 Increased power level to 1140 Mwe.

9 0100 Reduced power level to 1100 Mwe for control rod drive hydraulic control unit accumulator replacements.

10 0100 Reduced power level to 900 Mwe to perform scram time testing.

1000 Increased power level to 1135 Mwe.

11 0000 Reduced power level to 830 Mwe to perform scram cimo testing.

2200 Increased power level to 1130 Mwe.

12 0200 Reduced power level to 900 Ewe to perform scram time testing.

1000 Increased power level to 1140 Mwe.

13 0300 Reduced power level to 900 Mwe to perform a rod set and scram time testing.

0900 Increased power level to 1140 Mwe.

16 2000 Reduced power level to 1100 Mwe due to changeover the Feedwater Heater Drain pumps.

2400 Increased power level to 1140 Mwe.

18 0200 Reduced power level to 850 Mwe due to changeover the Condensate / Condensate Booster pumps.

0900 Increased power level to 1140 Mwe. ,

22 0000 Reduced power level to 1100 Mwe due to changeover the Feedwater Heater Drain pumps.

0600 Increased power level to 1140 Mwe.

25 2105 Reduced power level to 750 Mwe for surveillance performance and to perform a rod set.

26 0800 Increased power level to 1140 Mwe.

31 2400 Reactor critical, Generator on-line at 1140 Mwe.

. B. AMENDMENTS TO THE FAClILITY OR TECHNICAL CPECIFICATION y' .

(None)

C. LICENSEE EVENT REPORTS (Unit 2)  !

i LER No. Dnip Descriction 1

95-001 01/12/95 During performance of instrumentation  !

surveillance testing a hydraulic transient occurred in a sensing line, resulting in spurious actuaction of Division I Low Pressure ECCS and RCIC. ECCS did not inject into the reactor due to reactor pressure being above the low pressure injection permissive. RCIC injected but no reactor water level change was observed.

D. DATA TABULATIONS (Unit 2)

1. Operating Data Report (See Table 1)

2. Average Daily Unic Power Level (See Table 2)

3. Unit Shutdowns and Significant Power Reductions (See Table 3)

E. UNIQUE REPORTING REQUIREMENTS (UNIT 2) ,

1. Safety Relief Vsive 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) i e

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- TABLE 1 ,

D.1 DPERATING DATA REPORT DOCKET NO. 050-374 t

!~ UNIT LASALLE TWO DATE February 10, 1995 COMPLETED BY M.J. CIALK0WSKI f TELEPHONE (815)-357-6761 OPERATING STATUS

1. REPORTING PERIOD: January 1995 GROSS HOURS IN REPORTING PERIOD: 744 r

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

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

' 4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 744.0 744.0 65,952.0

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

7. GENERATOR ON LINE TIME (HOURS) 744.0 744.0 64,729.5  !

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

9. THERMAL ENERGY GENERATED (MWHt) 2,425,194 2,425,194 196,177,122 .

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 830,597 830,597 65,519,166

11. ELECTRICAL ENERGY CENERATED (MWHe-Net) 805,795 805,795 62,990,557 l

12. REACTOR SERVICE FACTOR (%) 100.0 100.0 73.1

13. REACTOR AVAILABILITY FACTOR (%) 100.0 100.0 75.0 i

14. UNIT SERVICE FACTOR (%) 100.0 100.0 71.8

15. UWIT AVAILIBILITY FACTOR (%) 100.0 100.0 71.8 .

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16. UNIT CAPACITY FACTOR (USING MDC) (%) 104.5 104.5 67.4

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 100.5 100.5 64.8

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 10.5 .

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

Refuel Outage (L2R06), 02/18/95, 8 weeks

20. IF SRUTDOWN 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 February 10,'1995 COMPLETED BY M.J. CIALK0WSKI y: TELEPHONE (815)-357-6761 n.. . ~ <

REPORT PERIOD: January 1995 DAY POWER DAY POWER 1 956 17 1,102 2 1,074 18 1,077 3 1,100 19 1,097 4 1,094 20 1,099 5 1,091 21 1,101 6 1,104 22 1,097 7 1,102 23 1,100 8 1,104 24 1,098 9 1,076 25 1,072 ,

i 10 1,057 26 1,001 11 1,037 27 1,097  !

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12 1,068 28 1,099  !

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13 1,072 29 1,102 4 i

1,099

. 14 30 1,101 15 1,099 31 1,102 1

16 1,097 i

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D.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 20%

(UNIT 2)

NETHOD OF CORRECTIVE YEARLY TYPE SHUTTING DONN ACTIONS /COISEENTS SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER S if NUNBER IIXILE2D1 St SC55 DELE _Q 1HOURSL EgASON REDE NG PONER anolicable)

(None)

SUMEARY 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.