ML20094H099

Monthly Operating Repts for Oct 1995 for LaSalle County Nuclear Station

ML20094H099
Person / Time
Site:	LaSalle
Issue date:	10/31/1995
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9511140001
Download: ML20094H099 (18)

Text

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, Commonwealth Edi3on O>mpany I.aSalle Generat:r.g Station l 2601 North 21st Road Stardales, il.613 t i-9757 Tel 815-3576761 November 10,1995 U.S. Nuclear Regulatory Commission Document Control Desk i Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for October,1995, 1

D. J. Ray l Station Manager LaSalle County Station i DJR/mkl Enclosure cc: H. J. Miller, 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 i Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Central File

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9511140001 951031 PDR ADOCK 05000373

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LABALLE NUCLEAR Poller STATION f UNIT 1

MONTELY PERFCSNhNCE REPORT y October 1995 CCDedDNNEALTE EDISON CCMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11

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TABLE OF CONTENTS (UNIT 1)

I. INTRODUCifION II. REPORT I

A. SUteRRY OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL 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 Valve 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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. 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 net electrical output of 1078 Megawatts. Waste heat is rejected to a man-inada cooling j pond using the Illinois river for make-up and blowdown. The 1 architect-engineer was Sargent and Lundy and the contractor was Conunonwealth 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. j This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2056.

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II . . MONTELY REPORT t

! A. SUl@SRY OF OPERATING EXPERIENCE (Unit 1) i y

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

1200 Reduced power level to 740 Mwe for performance of a rod set.

1630 Increased power level to 1015 Mwe.

4 1900 Reduced power level to 880 Mwe to place the Turbine Driven Reactor Feed Pump on-line.

5 0400 Increased power level to 1125 Mwe.

15 1600 Reduced power level to 850 Mwe for performance of a rod set.

16 0200 Increased power level to 1125 Mwe.

19 0500 Reduced power level to 1060 Mwe to place the "1D" Condensate / Condensate Booster Pung on-line.

0545 Increased power level to 1110 Mwe.

0600 Reduced power level to 1060 Mae to take the "1D" Condensate / Condensate Booster Pump off-line.

0730 Increased power level to 1110 Mwe.

20 0430 Reduced power level to 1040 Mwe to swap the Heater Drain Pumps.

0600 Increased power level to 1110 Mwe.

27 2100 Reduced power level to 830 Mwe for performance of Turbine Generator and Main Steam Isolation Valve testing.

28 0515 Reduced power level to 800 Mwe.

1700 Increased power level to 1080 Mwe.

29 0000 Reduced power level to 785 Mwe for performance of scram time testing.

2400 Power level at 1100 Mwe.

31 2400 Reactor critical, Generator on-line at 1030 Mwe.

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3. AMENDMENT 3 TO THE FACILITY OF. TECENICAL CPECIFICATION

! +- On October 10, 1995, Amendment 107 was issued to license NPF-11

(Unit 1). This amendment updated the changes in responsibility and reporting relationships to reflect the present station and corporate 1 organizations.

C. SUBMITTED LICENSEE EVENT REPORTS (Unit 1) -

Occurence LER No. Date Description 95-013 08/25/95 Missed calibration of the "1B" Diesel Generator low lube oil pressure shutdown switch.

l 95-016 10/24/95 A manual Reactor scram due to increasing Reactor water level which was caused by the Emergency Governor Lockout Valve sticking.

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) 1 l

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- E.- UNIQUE REPORTIN3 REQUIREMENT 3-(UNIT 1)

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{ 4. Changes to the off-site Dose Calculation Manual 4

The following is a susumary of the changes to the Offsite Dose i calculation Manual, Revision 1.7 (September 1995) for LaSalle site

' specific sections: Chapters 10, 11, 12 and Appendix F. A

determination has been made that these changes will not reduce the accuracy nor reliability of the dose calculations and setpoint determinations.

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j -Added text regarding potential waste oil incineration and j potential exfiltration of Turbine Building air.

-Inglement Uniform Radiological Environmental Monitoring Program

with appropriate updates.

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-state 25% frequency definition clarification to chapter 12 for 1 OD N surveillances.

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t -Inserted Technical specification requirement for liquid holdup

} tanks and maine condenser release rate.

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-Inserted summaary table of effluent and environmental susunary of

regulations.

-Revised the definition of Member of the Public and occupationally Exposed according to the 8-14 95 10CFR20 Revision.

-Reduced distance of Restricted Area Boundary in sectors E and ESE sectors Appendix F.

-Revised Restricted Area Boundary Map to indicate Waste storage locations.

-Editorial comments to ensure consistency in OD N and Technical specification text.

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TABLE 1 0.1 OPERATING DATA REPORT DOCKET No. 050-373 UNIT LASALLE ONE DATE November 10, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 OPERATING STATUS

1. REPORTING PERIOD: October 1995 GROSS NOURS IN REPORTING PERIOD 745

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

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

4 REASONS FOR RESTRICTION (IF ANY): i REPORTING PERIOD DATA l THIS MONYi1 YEAR-TO-DATE tutiLATIVE l

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5. REACTOR CRITICAL TIME (HOURS) 745.0 6,838.1 73,478.0 I l

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

7. GENERATOR ON-LINE TIME (HOURS) 745.0 6,765.0 71,876.1 l

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

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9. THERMAL ENERGY GENERATED (MWHt) 2,358,959 21,692,383 214,379,208

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 798,862 7,278,987 71,669,878

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 773,354 7,043,450 68,812,594 l

12. REACTOR SERVICE FACTOR (%) 100.0 93.7 70.8 j

13. REACTOR AVAILABILITY FACTOR (%) 100.0 93.7 72.4

14. UNIT SERVICE FACTOR (%)- 100.0 92.7 69.3  ;

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15. UNIT AVAIL 1BILITY FACTOR (%) 100.0 92.7 69.3 j

16. UNIT C U ACITY FACTOR (USING MDC) (%) 100.2 93.2 64.0 e 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) M.3 89.6 61.5

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 5.2 8.0

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): 01/27/96

20. IF SHUTDOWN AT END OF REPORT PER100, ESTIMATED DATE OF STARTUP: N/A i

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DOCKET NO. 050 373 TABLE 2 UNIT LASALLE ONE I D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE November 10, 1995  !

COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 l REPORT PERIOD: October 1995 DAY POWER DAY POWER 1 935 17 1,079 2 970 18 1,075 ,

3 960 19 1,064 ,

4 948 20 1,064  ;

5 1,076 21 1,063 ,

6 1,084 22 1,061 i 7 1,088 23 1,058 8 1,083 24 1,053 9 1,078 25 1,048 10 1,072 26 1,043 11 1,064 27 1,021 12 1,060 28 942 13 1,055 29 944 14 1,052 30 1,0!.7 15 1,022 31 1,029 16 1,085 j

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

(UNIT 1) ,-

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( METHOD OF CORRECTIVE

! YEARLY TIPE SHUTTING DOWN ACTIONS /CCl#4ENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YDNDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

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SUDGEhRY OF OPERATION:

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

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LASALLE NUCLEAR PCMER STATION UNIT 2 MONTELY PERFORMANCE REPORT october 1995 CChedONNEALTE EDISON CCMPANY NRC DOCIMT NO. 050-374 l

LICENSE NO. NPF-18 l l

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1 TABLE OF CONTENTS '

(UNIT 2)

I. INTRODUCTION II. REPORT A. SISe&RY OF OPERATING EXPERIENCE i

B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS  ;

C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report 4

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS

1. Main Stean Safety Relief Valve Operations

2. Major Changes to Radioactive Waste Treatment System

3. Static O-Ring Failures

4. Off-site Dose Calculation Manual Changes

I. INTRODUCTION (UNIT 2)

The Lasalle County Nuclear Power station is a two-Unit facility owned by Comenonwealth 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 snake-up and blowdown. The architect-engineer was sargent and Lundy and the contractor was Comenonwealth Edison Company.

l Unit two was issued operating license number NPF-10 on Deea h r 16,

1983. Initial criticality was achieved on March 10, 1994 and j conunercial power operation was comunenced on October 19, 1984.

This report was compiled by Michael J. Cialkowski, telephone number

. (815)35'1-6761, extension 2056.

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d II. - MONTHLY REPORT A. SUtedARY OF OPERATING EXPERIENCE (Unit 2) y D Time Event 1 0000 Reactor critical, Generator on-line at 1125 Hwe.

13 1200 Reduced power level to 1090 Mwe due to Reactor Recirculation Pump Flow Control Valve drifting.

2400 Increased power level to 1125 Mwe.

18 0500 Reduced power level to 1085 Mwe to swap the Heater Drain Punps.

1400 Increased power level to 1130 Mwe.

26 1000 Reduced power level to 1120 Mwe due to Reactor Recirculation Pung Flow Control Valve testing.

1100 Increased power level to 1130 Mwe.

1300 Reduced power level to 1120 Mwe due to Reactor Recirculation Pump Flow Control Valve testing.

1400 Increased power level to 1130 Mwe.

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

B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION On October 10, 1995, Amendment 93 was issued to license NPF-18 (Unit 2). This amendment updated the changes in responsibility and reporting relationships to reflect the present station and corporate organizations.

C. SUBMITTED LICENSEE EVENT REPORTS (Unit 2)

(None)

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 (None)

3. Static O-Ring Failures (None)

E. UNIQUE REPORTING REQUIREMENTD (UNIT 2)

(centinurd)

4. Changes to the Off-site Dose Calculation Manual ,

1 The following is a sumanary of the changes to the Offsite Dose i Calculation Manual, Revision 1.7 (September 1995) for Lasalle site  ;

' Specific Sections: Chapters 10, 11, 12 and Appendiz F. A determination has been made that these changes will not reduce the _

accuracy nor reliability of the dose calculations and setpoint i determinations.

-Added text regarding potential warte oil incineration and potential exfiltration of Turbine Building air.

-Inplement Unifona Radiological Environmental Monitoring Program with appropriate updates.

-state 25% frequency definition clarification to chapter 12'for OD N surveillances.

-Inserted Technical specification requirement for liquid holdup tanks and maine condenser release rate.

-Inserted summaary table of effluent and environmental'summaary of regulations.

-Revised the definition of Member of the Public and Occupationally Exposed according to the 8-14-95 10CFR20 Revision.

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-Reduced distance of Restricted Area Boundary in sectors E and ESE sectors Appendix F.

-Revised Restricted Area Boundary Map to indicate Waste Storage locations.

-Editorial conenents to ensure consistency in ODCM and Technical specification text.

TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LASALLE TWO DATE hovember 10, 1995 COMPLETED 8Y M.J. CIALK0WSKI TELEPHONE (815) 357-6761 CPERATING STATUS

1. REPORTING FERIOD: October 1995 Gross HOURE IN REPORTING PERIOD: 745 )

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):

1 4 REASONS FOR RESTRICTION (IF ANY): l REPORTING PERIOD DATA TNIS MONTH YEAR To-DATE CulRJLATIVE

5. REACTOR CRITICAL TIME (HOURS) 745.0 4,617.6 69,825.6

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

7. 4,392.0 l GENERATOR ON-LINE TIME (HOURS) 745.0 68,377.5

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

9. THERMAL ENERGY GENERATED (MWHt) 2,470,055 13,409,096 207,161,024

10. ELECTRICAL ENERGY GENERATED (HWHe-Gross) 842,831 4,557,955 69,246,524

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 816,638 4,370,974 66,555,736

12. REACTOR SERVICE FACTOR (%) 100.0 63.3 72.2

13. REACTOR AVAILABILITY FACTOR (%) 100.0 63.3 74.0

14. UNIT SERVICE FACTOR (%) 100.0 60.2 70.7

15. UNIT AVAILIBILITY FACTOR (%) 100.0 60.2 70.7 l

16. UNIT CAPACITY FACTOR (USING MDC) (%) 105.8 57.8 66.4

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 101.7 55.6 63.8

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 4.1 10.2 i

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

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTUP: N/A i

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e DOCKET NO. 050 374 TABLE 2 UNIT LASALLE TWO

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D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE November 10, 1995 COMPLETED BY N.J. CIALK0WSKI TELEPHONE (815) 357 6761 REPORT PERIOD: October 1995 DAY POWER DAY POWER 1 1,093 17 1,098 2 1,092 18 1,093 3 1,087 19 1,096 4 1,086 20 1,099 5 1,089 21 1,100 6 1,094 22 1,099-7 1,095 23 1,101 8 1,095 24- 1,103 9 1,093 25 1,103 10 1,090 26 1,102 11 1,089 27 1,103 12 1,089 28 1,102 13 1,090 29 1,147 14 1,097 30 1,103 15 1,098 31 1,102 16 1,100

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

(UNIT 2) ,

METHOD OF CORRECTIVE  !

YEARLY TYPE SHUTTING DOWN . ACTIONS /COMENTS i SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYM4DD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

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stmemRY OF OPERATION:

The unit r - ined on-line at high power throughout the month, several minor power reductions were required during the month due to maintenance and surveillance activities.

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