ML20080U164

Monthly Operating Repts for Feb 1995 for LaSalle County Station

ML20080U164
Person / Time
Site:	LaSalle
Issue date:	02/28/1995
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9503140256
Download: ML20080U164 (19)

Text

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- (bmmonw;ealth hiivm O>mpany laSalle Generating 5tation

/;7 2001 North 2Ist Road

, Marvilk s, IL 61.4419757 l

Tel H15-357C61 i

Match 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 February,1995.

I D. J. Ray Station Manager LaSalle County Station DJR/mkl 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 1

Licensing Operations Director - Downers Grove Nuclear Fuel Services Manager - General Office Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Central File r

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9503140256 950228 PDR ADOCK 05000373 R

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T.1 R E T.T.T NUCLEAR POWER STATIN t

UNIT 1 MONTELY PERFOSIMANCE REPORT

' February 1995 CCD6000fMEALTE EDIsot! CCMPANY i

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NRC DOCKET NO. 050-373 i

LICENSE No. NPF-11 l

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TABLE OF CONTENTS (UNIT 1)

I.

INTRODUCTICIf II.-

REPORT A.

StaedhRY OF OVERATING EXPERIENCE B.

- MS 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 REQUIRENENTS 1.

Main Steaua safety Relief valve Operations 2.

Major Changes to Radioactive Waste Treatseent Systeun 3.

Static O-Ring Failures 4.

Off-site Dose calculation Manual Changes

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INTRODUCTICtt (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 1?,

r 1982. Initial criticality was achieved on June 21, 1982 and cossmarcial power operation was commenced on January 1, 1994.

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

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MONTELY REPORT l

A.

stmesLRY OF OPERATING EXPERIENCE (Unit 1)

'g Time Event l

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0000 Reactor critical, Generator on-line at 1140 Mwe.

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2 0100 Reduced power 1evel to 1070 Mwe to changeover Condensate / Condensate Booster pumps.

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0600 Increased power level to 1140 Mwe.

3 0500 Reduced power level to 1075 Mwe for scram pilot valve inspections.

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0530 Increased power level to 1105 Mwe.

i 2100 Reduced power level to 620 Mwe to perfrom a rod set.

4 0100 Increased power level to 850 Mwe for performance of

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scram timing and scram pilot valve inspections.

1600 Increased power level to 1140 Mwe.

2200 Reduced power level to 1030 Hwe for performance of scram timing.

5 0200 Increased power level to 1140 Mwe.

9 0230 Commenced shutdown for repair of the 1E51F357 valve.

0942 Reactor manually scrammed.

14 1958 Reactor critical.

i 15 0558 Generator on-line at 60 Mwe.

2300 Power level at 330 Mwe.

17 0200 Power level at 1115 Mwe.

i 18 1000 Reduced power level to 900 Mwe to perform a rod set.

1400 Increased power level to 1095 Mwe.

2100 Reduced power level to 800 Mwe to perform a rod set.

l 19 1800 Increased power level to 1140 Mwe.

22 0100 Reduced power level to 1075 Mwe to changeover Condensate / Condensate Booster pumps.

0600 Increased power level to 1140 Mwe.

23 1900 Reduced power level to 1040 Mwe to perform a rod set.

24 0200 Increased power level to 1140 Mwe.

1 28 0100 Reduced power level to 1050 Mwe to changeover l

Foodwater Beater Drain pumps.

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0800 Increased power level to 1140 Mwe.

2400 Reactoi critical, Generator on-line at 1140 Mwe, i

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JWSIEBENTS.TO TEE FACILITE OR TECENICAL CFECIFICATION

.~(None)

C.

lit'N 888 EVENT REPORTS (Unit 1)

'LER No.

Date Description ~

95-002 02/07/95 The Reactor Core Isolation Cooling systeen was out of service for snaintmenance. With the snaintenance completed the 1E51-F063 valve'was closed for depressurising of the steam line.

h line failed to depressurise, h 1E51-F063 valve was declared inoperable and the 1E51-F008 was taken out of service closed to oemply with Technical Specification 3.6.3.

N Reactor Core Isolation Cooling system was declared inoperable per Technical Specification 3.7.3 an a 14 day time clock was entered.95-005 02/09/95 New Diesel Fuel. coming onsite at LaSalle is'not tested per AS'ad 02276 as specified in Technical

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Specification 4.7.1.1.2.C.2.

l 95-006 02/10/95 Technical Specification 3.3.6 requires a control i

Rod withdrawal block for the Reactor Recirculation system flow unit upscale, in operating and comparator trip. h current procedure which functionally tests these on a monthly basis per Technical Specification does not. ensure the relays enforcing the rod blocks change state.95-007 02/16/95 Quarterly surveillance for the Division III DC system not perforsnod as required by Technical

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Specification 4.9.2.3.1.E.1.

l 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 see attached letter from D. Scott, Director Emergency Preparedness, comed to J.Nartin, Regional Administrator, Nuclear Regulatory Comunission, Region III dated 02/23/95.

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TABLE 1 D.1 OPERATING DATA REPORT DOCKET No. 050-373 I

WIT LASALLE ONE DATE March 10, 1995 COMPLETED BY M.J. CIALK0WSKI a

TELEPHONE (815)-357-6761 i

CPERATING STATUS 1,

REPORTING PERIOD:

February 1995 GROSS HOURS IN REPORTING PERIOD 672 2.' CURRENTLY AUTHORIZED POWER fEVEL (MWt):

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

1,036-DESIGN ELECTRICAL RATING (MWe-N 1,078 f

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

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REASONS FOR RESTRICTION (IF ANY):

1 REPORTING PERIts DATA i

THIS MONTH YEAR TO-DATE CUNULATIVE 5.' REACTOR CRITICAL TIME (NOURS) 541.7 1,285.7 67,925.6 6.

REACTOR RESERVE SMUTDOW TIME (HOURS) 0.0 -

0.0 1,641.2 7,

GENERATOR ON LINE TIME (HOURS) 531.7 1,275.7 66,386.9 s

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WIT RESERVE SHUTDOW TIME (HOURS) 0.0 0.0 1.0 9.

T:2RMAL ENERGY GENERATED (MWHt) 1,627,218 4,085,103 196,771,928

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 549,748 1,388,930 65,779,821

11. ELEC1RICAL ENERGY GENERATED (MWHe Net) 531,418 1,345,227 63,114,371 l

12. REACTOR SERVICE FACTOR (X) 80.6 90.8 69.4 i

13. REACTOR AVAILABILITY FACTOR (%)

80.6 90.8 71.1

14. WIT SERVICE FACTOR (%)

79.1 90.1 67.8

15. WIT AVAILIRILITY FACTOR (%)

79.1 90.1 67.8 l

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

76.3 91.7 62.2 i

17. WIT CAPACITY FACTOP. (USING DESIGN MWe) (%)

73.4 88.1 59.8 t

18. Wif FORCED OUTAGE FACTOR (%)

20.9 9.9 8.3 i

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

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

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DOCKET No. 050-373

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UNIT LAGALLE (INE D.2 - AVERAGE DAILY UNIT MadER LEVEL (NWe-Net)'

'DATE March 10,-1995

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COMPLETED BY N.J. CIALK0WOKI.

TELEPMONE (815)*357-6761

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' REPORT PERIOD:

Fetruary 1995 f

DAY:

POWER DAY POWER 1

1,099 17 1,017.

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1,094 18 979 3

1,043 19' 1,010 4

976 20 1,096 l

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5 1,092 21 1,096 l

6 1,095 22 1,097 t

7 1,096 23 1,093 f

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1,012 24 1,092

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9 100 25 1,094 1

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+12 26 1,097 t

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+12 27 1,096 f

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-12 28 1,087 13

+12 29 14 12 30 15 109 31 i

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TABIA 3 D.3 UNIT SEUTDOINIS JWW POIIER REDUCTICMS > 204 (UNIT 1)

DETHOD OF COIUtECTIVE YEARLY TYPE SEUTTI1OG DOHN ACTIONS /CCBGENTS SEQUENTIAL DATE F: FORCED DURATION TEE REACTOR OR (LER # if NUISER (YYleeD) 8: SCHEDULED (BOURS)

REASON REDUCING POWER applicable) 1 950209 F

140.3 A

2 Demnual reactor scram for the repair of the 1E51F357. valve.

i StmethRY OF OPERATION

• The unit remained on-line at high power throughout most of the month. Several minor power reductions were required due to maintenance and surveillance activities.-The unit emperienced a forced outage on 02/09/95 for repair of the 1E51F357 valve. The unit was returned to service on 02/15/95.

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UNIT 2 M00fT3LY PERPoetsutCE REPORT February 1995 CONM00fMEALTE EDISON COMPANY i

NRC DOCEET NO. 050-374 f

LICENSE NO. NPF-18 l

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j TABLE OF CONTENTS i

(UNIT 2)'

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INTRODUCTION 1

i II.

REPORT

. A.

StBedhRY OF OPERATING EXPERIENCE

'. 1 3.

• • - #TS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

LICENSEE EVENT REPORTS 1

D.

DATA TABULATIONS

.1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions E.

IfMIQUE R1, PORTING REQUIRENENTS 1.

Ma'.n Steam Safety Relief Valve operations

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2.

sesjor Changes to Radioactive Waste Treatment System 3.

Static O-Ring Failures j

4.

Off-site Dose Calculation Manual Changes i

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INTRODUCTION (UNIT 2)

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The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison coupany 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 connonwealth Edison conpany.

l 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 Oc';ober 19, 1984.

This report was compiled by Michael J.

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

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MONTELY REPORT

. A.

St2MhRY OF CPERATING EXPERIENCE (Unit 2)

= nag Time.

Event I

1 0000 Reactor critical, Generator on-line at 1140 Mwe.

4 2300 Reduced power level to 1000 Mwe to perform a rod set.

5 0140 Increased power level to 1140 Mwe.

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12 2300 paduced power level to 1000 Mwe to perform a rod set.

i 13 0700 Increased power level to 1140 Mwe.

i 17 0900 co n nood shutdown for refuel cutage (12R06).

18 0020 Main turbine trip.

i 0033 Manual reactor scram.

l 28 2400 Reactor sub-critical, Generator off-line. Refuel outage (L2R06) in progress.

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D.., N.TO TER FACILITY OR TECENICAL fFECIFICATION (None)'

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LICENSEE EVENT REPORTS (Unit 2)

LER No.

Date-Description-95-002-

' 02/03/95 An out of service'was placed which affected fire detection sones 2-34 and 35.Per Technical-Specification 3.3.7.9, an hourly firewatch sust be in affect within one hour of declaring..the componerts out of service. The designated -

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firewat h became effective outside of.the:

allotted time frame. The operations department was able to verify that a-Radiation Protection tocht.tician was in area prior to.t.he designated firewatch becoming effective..He verified that there were no fires in the area.95-003 02/21/95 A full reactor scram occurred as a. result of.

high water level in the south scram discharge volume header-while performing a planned refuel outage hydrolasing activity. A Nigh level alarm annunciated and was followed by a scram signal.

The high level condition in the scram discharge volume cleared af ter approwi==tely 2 minutes.. '

since the vents and drain valves are maintained in a full open position to allow the discharge volume to continually drain during performance-of the hydrolasing.95-004 02/23/95 Fire detection zone 2-30 activated when water was introduced into the system from a clean condensate storage system hose break..An hourly fire watch which was enacted but.was unable to tour the entire affected zone. The stations-fire marshall was contacted and..a proper fire watch for the entire zone was then established.95-005 02/10/95 2821F029A Outboard Main Steam Isolation Valve failed to close when control switch was taken to close position. Valve later closed on its own on 02/19/95.

D.

DATA TABULATIONS (Unit 2) 1.

Operating Data Report (See Table 1) 2.

Average Daily Unit Power Level (See Table 2)

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Unit Shutdowns and Significant Power Reductions (See Table 3)

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E.

UNIQUE REPORTING REQUIREMENTS (UNIT 2) 1.

Safety Relief Valve Operations (None) 2.

Major Changes to Radioactive Maste Treatment Systems (None) 3.

Static O-Ring Failures (None) 4.

Changes to the off-Site Dose Calculation Manual See attached letter from D. Scott, Director Emergency Preparedness, Comed to J. Martin,' Regional Administrator, Nuclear Regulatory Commission, Region III dated 02/23/95.

e, TABLE 1 a

D.1 OPERATING DATA REPORT DOCKET NO. 050 374 UNIT LASALLE TWO DATE March 10, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 1l

OPERATING STATUS i-

1. ' REPORTING PERIOD:

February 1995 GROSS HOURS IN REPORTING PERIOD:

672:

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CURRENTLY AUTHORI2ED POWER LEVEL (MWt):

3,323 MAX DEPEND CAPACITY (MWe Net):

1,036 l

DESIGN ELECTRICAL RATING (MWe-Net):

1,078 3.

POWER LEVEL TO WICN RESTRICTED (IF ANY) (MWe Net):

4.

REASONS FOR RESTRICTION (IF ANf):

REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE

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REACTOR CRITICAL TIME (HOURS) 408.6 1,152.6 66,360.6

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REACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1,716.9 7.

GENERATOR ON LINE TIME (HOURS) 408.3 1,152.3 65,137.8

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UNIT RESERVE SMUTDOWN TIME (HOURS) 0.0 0.0 0.0 9.

THERMAL ENERGY 4ENERATED (MWHt) 1,305,813 3,731,007 197,482,935

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 450,530 1,281,127 65,969,696

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 433,271 1,239,066 63,423,828 1

12. REACTOR SERVICE FACTOR (%)

60.8 81.4 73.0

13. REACTOR AVAILABILITY FACTOR (%)

60.8 81.4 74.9

14. UNIT SERVICE FACTOR (%)

60.8 81.4 71.7

15. UNIT AVAILIBILITY FACTOR (%)

60.8 81.4 71.7

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

62.2 84.5 67.4

17. UNIT CAPACITT FACTOR (USING DESIGN MWe) (X) 59.8 81.2 64.8

18. UNIT FORCED OUTAGE FACTOR (%)

0.0 0.0 10.4 l

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION 0F EACH):

20. IF A'TDOWN AT END 0F REPORT PERIOD, ESTIMATCD DATE OF STARTU 04/21/95 i

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DOCKET NO. 050 374

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. TABLE 2 UNIT LASALLE TWO Fi D.2 AVERAGE DAILY UNIT P0hEk LEVEL (NWe Net).

DATE March 10, 1995 COMPLETED BY N.J. CIALEDWIKI

.,."'r TELEPMONE (815) 357-6761 b

REPORT PERIOD:

February 1995 DAY PohER DAY POWER 1

1,102 17 655-2 1,101 18

-11 3

1,099 19

-12 4

1,094 20 -

-11 5

1,096.'

21

-11 6

1,102 22

-11 7

?,103 23

-11' 8

1,099 24

-11 9

1,098 25 11 10 1,008

'26

-11 11 1.093 27

-11 l

1 12 1,090 28 11 13 1,065-29 14 1,093 30 15 1,092 31 16 1,097

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a TABLE 3 D.3 UNIT SEUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

ISTROD OF COIUWCTIVE YEARLY TYPE SEUTTIP8G DOY2 ACTIONS /CCDeSNTS SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YY)eOD)

S*

SCHEDULED (HOURS)

REASON REDUCING POWER applicable) 1 950219 8

263.7 C

2 Refuel outage (L2R06)

St294ARY OF OPERATION:

The unit started the month on line at high power. Unit shutdown c-nced on 02/17/95 and the unit was manually scramened on 02/18/95 to enter into a scheduled refuel outage.

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mmmonwealth tiliwn Gmpany ICX10 pus Place oownencme n.unsis February 23,1995 Mr. Jack Martin, Regional Administrator Nuclear Regulatory Commission, Region ill 801 Warrenville Rd.

Lis!s, IL 60532-1357 j

SUBJECT:

Commonwealth Edison Offsite Dose Calculation Manual (ODCM) Revisions 1.1,1.2 and 1.3 i

Dear Mr. Martin:

The following is a summary of the changes made to the Commonwealth Edison Company (Comed) Offsite Dose Calculation Manual (ODCM) during the period of July - December 1994.

Modifications were made to the site specific sections of the Comed ODCM for Byron, Dresden, i

LaSalle and Zion Stations. Braidwood and Quad Cities Stations did not have any revisions during -

this time. The following presents a synopsis of the revisions made.

l Byron Station - Revision 1.2, August 1994 - Chapters 10,11,12 and Appendix F i

I Revision to REMP TLD Locations.

Added compliance matrix to Chapter 12 to summarize and relate regulations, ODCM equations and Technical Specification requirements.

Revised Land Use Census (e.g. nearest resident, dairy and livestock) incorporated in new Appendix F tables.

Revision of Restricted Area Boundary Map to indicate waste storage locations.

Editorial comments to ensure consistency in ODCM and Technical Specification text.

Dresden - Revision 1.1, July 1994 - Chapters 10,11,12 and Appendix F Revised Unit 1 Gaseous Release Diagram to update CFM values.

Revision to REMP Locations.

Revised Land Use Census (e.g. nearest resident, dairy and livestock) incorporated in new Appendix F tables.

Revised Restricted Area Boundary Map to indicate waste storage locations.

1 Editorial comments to ensure consistency in ODCM and the Dresden Updated FSAR.

LaSalle - Revision 1.1, July 1994 - Chapters 10,11,12 and Appendix F j

Revision to REMP Locations.

Added compliance matrix to Chapter 12 to summarize and relate regulations, ODCM equations and Technical Specification requirements.

Revised Land Use Census (e.g. nearest resident, dairy and livestock) incorporated in new Appendix F tables.

Inserted Technical Specification clarifications into Chapter 12.

Editorial comments to ensure consistency in ODCM and Technical Specification text.

EPMISc/chronMP/2

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Ziga - Revision 1.3, December 1994 - Chapter 12 Modifications in gaseous effluent monitor action statements.

Deletion of Offsite Review approval requirement after onsite review and approval of ODCM revisions.

l Changes are submitted to your office as part of the normal controlled document distributions, in lieu of submitting the entire ODCM for each change to the document.

Please contact Mashelle Pavey at 708-663-7589 if you have any questions regarding ODCM.

Sincerely, j

dd l

I Doug Scott t

Director Emergency Preparedness i

cc: Jeff Birkmeier, ODCM - Braidwood Dennis Drawbaugh/ Bill McNeill, ODCM - Byron Kristen Schwab, ODCM - Dresden Tim Greene, ODCM - LaSalle I

Rod Wiebenga - ODCM Quad Cities Rick Laburn, ODCM - Zion Marri Marchionda-Palmer, Lead Technical Health Physicist - Byron i

Pat Quealy, Lead Technical Health Physicist - Dresden Priscilla McCounnaughay, Lead Technical Health Physicist - LaSalle-Greg Kassner, Zion Health Physics Supervisor j

John Golden /Mashelle Pavey EPG-00-M02 I

s EPMISC/chron/MPf3

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