ML20059J425

Monthly Operating Rept for Oct 1993 for LaSalle County Nuclear Power Station

ML20059J425
Person / Time
Site:	LaSalle
Issue date:	10/31/1993
From:	Cialkowski M, Schmeltz J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9311120200
Download: ML20059J425 (18)

Text

O Telephone 815/357-0761 Commonwealth Edison LaSatie County Nuclear Station 2601 N. 21st. Rd.

Marseilles, Illinois 61341 November 3,1993 t

i U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 i

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for October 1993.

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Joseph V. Schmeltz Acting Station Manager LaSalle County Station JVS/tmb Enclosure cc:

Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear. Safety - LaSalle NRR Project Manager - LaSalle l

GE Representative - LaSalle i

Regulatory Assurance Supervisor - LaSalle

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Manager of Nuclear Licensing - Downers Grove Nuclear Fuel Services Manager - General Office QA/NS Off-Site Review - General Office INPO Records Center Station File t

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LASALLE NUCLEAR POWER STATION UNIT 1 5

MONTHLY PERFORMANCE REPORT l

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COMMONWEALTH EDISON COMPANY t

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NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i

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l TABLE OF CONTENTS f

(UNIT I)

I.

INTRODUCTION II.

REPORT f

A.

SUMMARY

OF OPERATING EXPERIENCE B.

AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D.

LICENSEE EVENT REPORTS i

E.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions F.

UNIQUE REPORTING REQUIREMENTS 1.

Main Steam Safety Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System 5.

Indications of Failed Fuel Elements i

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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 net 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 i

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 commenced on January 1, 1984.

I This repost was compiled by Michael J.

Cialkowski, telephone number (815)357-(,761, extension 2427.

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MONTHLY REPORT i

A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

Day Time Event i

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1 0000 Reactor sub-critical, Generator off-line, forced outage

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in progress.

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0045 Reactor critical.

7 0328 cenerator on-line at 38 Mwe.

2200 Power level at 735 Mwe.

8 1700 Power level at 1100 Mwe.

l 10 0100 Reduced power level to 700 Mwe to perform a ' rod set.

I 2400 Increased power level to 1125 Mwe.

19 0100 Reduced power level to 1000 Mwe to perform monthly 5

surveillance s.

l 0800 Increased power level to 1135 Mwe.

I 31 2400 Reactor critical, Generator on-line at 1135 Mwe.

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AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION l

(None) l C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports ).

(See Table 1)

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D.

LICENSEE EVENT REPORTS (Unit 1) t i

LER Number Date Description 93-016 10/22/93.

Reactor Core Isolation Cooling system high pressure suction alarm.93-017 10/27/93 Missed Technical Specification surveillance.

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DATA TABULATIONS (Unit 1) l 1.

Operating Data Report (See Table 2) l 2.

Average Daily Unit Power Level (See Table 3) 3.

Unit Shutdowns and Significant Power Reductions (See Table 4)

F.

UNIQUE REPORTING REQUIREMENTS (UNIT 1) 1.

Safety Relief Valve Operations l

(None) 1 2.

ECCS System Outages s

Note: The year and unit data have been removed from the outage number.

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OUTAGE NO.

EOUIPMENT PURPOSE (U-0) i 0493 ODG0lP Pump repair.

0502 ODG006 Repack valve.

i 0518 ODG034B Valve repair.

l 0519 1

(U-1) i 0777 1DG0lP Pump motor repair.

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-i 0784 IE22-C302A Air compressor repair.

0789 IE51-F360 Replaced relay.

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3.

Changes to the Off-Site Dose Calculation Manual l

(None) 4.

Major Changes to Radioactive Waste Treatment Systems (None) 4 S.

Indications of Failed Fuel Elements l

(None)

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,b C. TABLE 1 (Unit 1)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REOUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L21009 Primary containment Regulator pressure Unable to monitor Replaced presssure gauge.

instrument nitrogen gauge pressure isolation valve IIN017 L22424 Reactor Recirc Valve actuator leakage None Replaced actuator, flow control valve IB33-F060B L24708 safety relief.

Solenoid valve 0-rings valve failed to cycle Replaced 0-rings.

valve IB21-F013D L24709 Safety relief Indicating switch Dual indication when Replaced switch valve IB21-F013U assembly valve was closed assembly.

L24756 Reactor recirc Pump seal leaking Pump seal pressure Replaced pump seal.

pump 1B33-C001 decreasing L24839 safety relief Indicating switch Dual indication when Replaced switch valve 1B21-F013D assembly valve was closed assembly.

L24999 Diesel generator Valve packing leakage None Repacked valve.

cooler autlet stop valve ODG006 L25130 Diesel generator Valve leakage None Replaced valve.

air start motor inlet valve ODG034B L25160 Diesel generator Pump bearing degraded None Replaced pump bearing.

cooling water pump IDG01P L25330 Reactor core 74 relay faulty Alarm inoperable Replaced relay.

isolation cooling trip valve l,

IE51-F360 (No SOR failures this month.)

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E.1 OPERATING DATA REPORT l

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DOCKET NO. 050-373 UNIT LASALLE ONE DATE November ' 3, 1993 l

COMPLETED BY M.J.CIALKOWSKI j

' OPERATING STATUS TELEPHONE (815) 357-6761

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1.

REPORTING PERIOD:

October 1993 GROSS HOURS IN REPORTING PERIOD:

745 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):

3,323 l

' MAX DEPENDABLE CAPACITY (MWe-Net):

1,036 DESIGN ELECTRICAL RATING (MWe_ Net):

1,078 3.

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

N/A

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4 REASON FOR RESTRICTION (IF ANY):

. ji THIS MONTH YEAR TO DATE CUMULATIVE 5.

REACTOR CRITICAL TIME (HOURS) 624.3 5,938.2 59,862.9 1

6.

REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 7

GDiERATOR ON-LINE TIME (HOURS) 597.5 5,642.1 58,549.7 I

8.

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

THERMAL DiERGY GENERATED (MWHt) 1,912,121 17,587,525 172,647,683 1

10. ELECTRICAL DIERGY GENERATED (MWHe-Gross) 651,144 5,867,562 57,659,911

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31. ELECTRICAL ENERGY GENERATED (MWHe_ Net) 633,610 5,654,329 55,302,419 l

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12. REACTOR SERVICE FACTOR (%)

83.8 81.4 69.4 i

13. REACTOR AVAILABILITY FACTOR (%)

83.8 81.4 71.3

14. UNIT SERVICE FACTOR (%)

80.2 77.3 67.9

15. UNIT AVAILIBILITY FACTOR (%)

80.2 77.3 67.9

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

82.1 74.8 61.9-

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17.. UNIT CAPACITY FACTOR (USING DESIGN MWe) 78.9 71.9 59.5

18. UNIT FORCED OUTAGE FACTOR (%)

19.8 17.5 8.0 19.-SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

No Outages Scheduled

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

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TABLE 3 E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)

DOCKET NO. 050-373 l

UNIT LASALLE ONE j

DATE November 3, 1993 _

COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)_357-6761 j

l REPORT PERIOD: October 1993 i

DAY POWER DAY POWER l

1

-10 17 1,104 1

1 2

_10 18 1,100 3

-11 19 1,073 4

_11 20 1,104 5

_11 21 1,103 6

-12 22 1,086 7

344 23 1,104 8

983 24 1,103 9

1,008 25 1,100 10 985 26 1,102 11 1,104 27 1,102 12 1,104 28 1,101 13 1,104 29 1,103 14 1,100 30 1,102 15 1,098 31 1,150 16 1,101

TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD)

S: SCHEDULED (HOURS)

REASON REDUCING POWER applicable) 10 930914 F

147.5 A

3 Automatic Reactor scram due to loss of the System Aux.

Transformer.

(LER# 93-015) i

SUMMARY

OF OPERATION:

The. unit started the month off-line due to a loss'of the System Auxiliary Transformer. The unit was returned to service on 10/07/93. The unit remained on-line at high power for the remainder of the month. Several micor power reductions were required < luring the month due to <outine surveillance activities.

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IASALLE NUCLEAR POWER STATION I

i UNIT 2 MONTHLY PERFORMANCE REPORT OCTOBER 1993 COMMONWEALTH EDISON COMPANY I

NRC DOCKET NO. 050-374 LICENSE NO..N.'F.

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TABLE OF CONTENTS (UNIT 2)

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INTRODUCTION I

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REPORT l

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SUMMARY

OF OPERATING EXPERIENCE t

B.

AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS' j

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C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT' t

D.

LICENSEE EVENT REPORTS E.

DATA TABULATIONS

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Operating Data Report j

2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions l

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'CNIQUE REPORTING REQUIREMENTS 1

Main Steam Safety Relief Valve Operations

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ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System 5.

Indications of Failed Fuel Elements

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INTRODUCTION (UNIT 2) i 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 designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois river for make-up and l

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

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Unit two was issued operating license number NPP-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on October 19, 1984, a

This report was compiled by Michael J.

Cialkowski, telephone number (815)357-6761, extension 2427.

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MONTHLY "' PORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

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Day Time Event 1

0000 Reactor sub-critical, Generator off-line.

31 2400 Reactor sub-critical, Generator off-line, refuel outage in progress.

B.

AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports )

j (See Table 1) j i

D.

LICENSEE EVENT REPORTS (Unit 2)

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t LER Number Date Description I

I 93-008*

10/22/93 ESF actuation'due to maintenance being performed on incorrect valve.

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• LER 93-008, High radiation door left open and LER 93-009, High I

radiation barrier removed, as reported in the September 1993 report were, upon further investigation, determined to be non-reportable items. LER number 93-008 was reissued.

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DATA TABULATIONS (Unit 2) 1.

Operating Data Report (See Table 2) l t

2.

Average Daily Unit Power Level (See Table 3) i 3.

Unit Shutdowns and Significant Power Reductions (See Table 4) l F.

UNIQUE REPORTING REQUIREMENTS (UNIT 2) 1.

Safety Relief Valve Operations 5

(None)

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2.

ECCS System Outages j

Note: The year and unit data has been removed from the outage

'l number.

l OUTAGE NO.

EOUIPMENT PURPOSE 1332 2DG0lP Replace pump bearings.

i 3.

Changes to the Off-site Dose Calculation Manual I

(None) j l

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Major Changes to Radioactive Waste Treatment Systems (None) 5.

Indications of Failed Fuel Elements (None)

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C. TABLE 1.(Unit 2)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT I

WORK RESULTS AND EFFECTS REQUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L13644 Diesel generator Thermocouple Low temperature reading Replaced thermocouple.

2E22-S001 cylinder

1. 20 temperature L17656 Nuclear boiler Vent valve leaking None Replaced valve.

system pressure switch 2B21-N413C t

L22168 Reactor building Damper positioner Positioner failed to Replaced actuator.

ventilation supply move flow damper 2VR06Y' L24888 Hydraulic control Scram discharge Valve failed to operate Replaced valve dise unit 54-43 isolation valve and bonnet assembly.

L25237 Residual heat Pressure switch Switch out of tolerance Replaced switch.

removal minimum 2E12-N010AA flow bypass L25254 Hydraulic control Charging water Valve failed to operate Replaced valve.

unit 30-47 isolation valve t

(No SOR failures this month) 1

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TABLE 2-E.1 OPERATING DATA REPORT t

DOCKET NO. ~050-373

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UNIT LASALLE TWO l

DATE November'3, 1993 COMPLETED BY M.J.CIALKOWSKI

-OPERATING STATUS TELEPHONE (815) 357-6761

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1 REPORTING PERIOD:

October 1993 GROSS HOURS IN REPORTING PERIOD:

745' l

f 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):

3,323 MAX DEPENDABLE CAPACITY (MWe-Net):

1,036 l

DESIGN ELECTRICAL RATING (MWe-Net):

1,078 i

3.

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

N/A 4

REASON FOR RESTRICTION (IF ANY):

THIS MONTH YEAR TO DATE CUMULATIVE 5.

REACTOR CRITICAL TIME (HOURS) 0.0 5,719.8 56,733.3 f

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REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 7.

GENERATOR ON-LINE TIME (HOURS) 0.0 5,697.4 55,753.8 D.

UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 i

i 9.

THERMAL ENERGY GENERATED (MWHt) 0 17,910,531 167,925,418

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0 6,030,629 55,931,938

11. ELECTRICAL ENERGY GENERATED (MWHe-Net)

-8,200 5,808,417 53,721,350

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12. REACTOR SERVICE FACTOR (%)

0.0 78.4 71.6'

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13. REACTOR AVAILABILITY FACTOR (%)

0.0 78.4 73.8

14. UNIT SERVICE FACTOR (%)

0.0 78.1 70.4 i

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15. UNIT AVAILIBILITY FACTOR (%)

u.9 78.1 70.4

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

-1.1 76.8 65.5 j

17. UNIT CAPACITT FACTOR (USING DESIGN MWe)

-1.0 73.9 62.9 i

18 UNIT FORCED OUTAGE FACTOR (%)

0.0 0.0 11.5-i

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

.i Refuel, 09/04/93, 12 Weeks l

l 2U. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

11/30/93 l

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l TABLE 3 E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)

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'j DOCKET NO. 050-373' UNIT LASALLE TWO DATE November 3, 1993'"\\

CP4PLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761 l

.. l REPORT PERIOD: October 1993 i

DAY POWER DAY POWER

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1

-10 17

-11 2

-13 18

-11 3

-11 19

-11 f

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-11 20

-11

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5

-11 21

-11 i

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-12 22

-11 l

7

-12 23

-11 8

-11 24

-11 i

9

-11 25

-11 I

r 10

-11 26

-11

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11

-11 27

-11 l

i 12

-11 28

-11 l

i 13

-11 29

-11 t

14

-11 30

-11 I

IF

-11 31

-11 16

-11 i

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TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2) i METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD)

St SCHEDULED (HOURS)

REASON REDUCING POWER applicable) 2 930904 S

745 C

2 Refueling Outage (L2R05)

SUMMARY

OF OPERATION:

The unit entered a scheduled refueling outage on 09/04/93.

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