ML20107D930

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Monthly Operating Repts for March 1996 for LSCS
ML20107D930
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 03/31/1996
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9604190093
Download: ML20107D930 (16)
v • d • e


Text

1 Commonwealth I:dison Comp.iny

  • 12Salle Generating Station 2601 North Jlst Road Marseilles, II,613 I i-9757 g Tel 815-35'4C6I i

April 11,1996 l United States Nuclear Regulatory Commission

Washington, D.C. 20555 Attention: Document Control Desk i

)

Subject:

LaSalle County Statior Units 1 and 2 j Monthly Performance hvort a NRC Docket Numbers 50 373 and 50-374.

Enclosed is the LaSalle County Station Monthly Performance Report for the j month of Ma ch,1996.

Respectfully, i

I D.J. Ray'07 Station Manager LaSalle County Station Enclosure cc: H. J. Miller, NRC Region lli Administrator P. G. Brochman, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager, NRR - LaSalle C. H. Matthews, IDNS Resident Inspector - LaSalle D. Deppa, IDNS Reactor Safety Springfield P. Doverspike, GE Representative - LaSalle D. L. Farrar, Nuclear Regulatory Services Manager INPO - Records Center Central file I

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9604190093 960331

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t i IASALLE NUCLEAR PotMR STATION 1

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' UNIT 1 )

J ndONTMLY PERFOItMANCE REPORT 1 l

i March 1996

! CObedONNEALTH EDISON CCMPANY f

1 i NRC DOCKET No. 050-373 i

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! LICENSE No. NPF-11 4

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  • l TABLE OF CONTENTS  !

(UNIT 1) )

I. INTRODUCTION II. REPORT A. SIEtihRY OF OPERATING EXPERIENCE B. A N S TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TABUIATIONS

1. Operating Data Report l
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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'I . INTRODUCTION (UNIT 1)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Comanonwealth 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-snado cooling pond using the Illinois river for snake-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was Comanonwealth Edison Company.

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

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, This report was compiled by Michael J. Cialkowski, telephone l nuamber (815)357-6761, extension 2056.

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II. MONTELY 2EPORT i A. SthedARY OF OPERATING EXPERIENCE (Unit 1) y D Time Event 1 0000 Reactor sub-critical, Generator off-line, refuel outage (L1R07) in progress.

31 2400 Reactor sub-critical, Generator off-line, refuel outage (L1R07) in progress.

B. mnenTS TO TEE FACILITY OR TECENICAL SPECIFICATION On March 11, 1996, Aamendsment 110 was issued to license NPF-11 (Unit 1). This asmendsment allows the implesmentation of the new 10 CFR 50 Appendix J leak testing requirements.  ;

C. SUB(ITTED LICENSEE EVENT REPORTS (Unit 1) l l

Occurrence  ;

LER No. Date Description 96-001 02/13/96 Four fire protection systeen valves were not verified to be in the correct -

position as required by the Tecimical Specification.

l D. DATA TABULATIONS (Unit 1) l

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 l (See Attachment A) j l
2. Major Changes to Radioactive Waste Treatment Systeam (None)
3. Static O-Ring Failures (None)
4. Changes to the Off-Site Dose Calculation Manual (None)

TABLE 1 1 D.1 OPERATING DATA REPORT DOCKET NO. 050-373 '

UNIT LASALLE ONE DATE April 10, 1996 COMPLETED BY M.J. CIALK0WSKI l TELEPHONE (815) 357 6761 OPERATlWG STATUS

1. REPORTING PERIOD: March 1996 GROSS HOURS IN REPORTING PERIOD 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 DEslGN ELECTRICAL RATING (MWe N 1,078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Wet): N/A
4. REASONS FOR RESTRICTION (!F ANY): N/A REPORTING PERIOD DATA THl$ MONTH YEAR TO-DATE CUMULATIVE
5. REACTOR CRITICAL TIME (HOURS) 0.0 585.5 75,527.5
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2
7. GENERATOR ON LINE TIME (HOURS) 0.0 582.3 73,922.4
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWHt) 0 1,411,768 219,S66,585
10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 0 470,404 73,514,256
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) *8,246 432,896 70,571,324
12. REACTOR SERVICE FACTOR (%) 0.0 26.8 70.3
13. REACTOR AVAILABILITY FACTOR (%) 0.0 26.8 71.9
16. UNIT SERVICE FACTOR (%) 0.0 26.7 68.8
15. UNIT AVAILIBILITY FACTOR (%) 0.0 26.7 68.8
16. UNIT CAPACITY FACTOR (USING MDC) (%) 1.1 19.1 63.4
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 1.0 18.4 61.0
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 7.8
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): Refuel, 01/25/96, 10 Weeks
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 04/09/96

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DOCKET NO. 050 373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE April 10, 1996 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815) 357 6761

! REPORT PERIOD: March 1996  ;

l DAY POWER DAY POWER

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1 11 17 11 2 11 18 -11 3 11 19 -11 i 4 -11 20 11 I

5 -11 21 -11 6 11 22 11 7 -11 23 11 i 8 11 24 11

9 11 25 -11 i

10 11 26 11 11 -11 27 11 12 11 28 11 l 13 11 29 11 14 -11 30 12 15 11 31 12 16 -11 i

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TABIE 3 ,

D.3 UNIT SHUTDOOntS AND POOKR REDUCTIOgIS > 204 (UNIT 1) j I

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mTBoD or conREcTIVE  !

YEARLY TYPE SRUTTING DOORf ACTICOfS/CobSENTS  !

SEQUENTIAL DATE F: FORCED DURATIcet THE REACTOR OR (LER I if  !

NUMBER (YYledDD) S: SCHEDULED (HOURS) REASott REDUCING PotfER applicable) 01 960125 S 744.0 C 2 Refuel outage (L1R07) i I

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I EImetARY OF OPERATION: The unit renmained in a scheduled refueling outage for the entire amonth.

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LASALLE NUCLEAR Poller STATIcht UNIT 2 MONTHLY PERFOIIMANCE REPORT March 1996 l

CC2000NWEALTH EDISON COMPANY NRC DOCEET No. 050-374 LICENSE NO. NPF-18 l

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4 TABLE OF CONTENTS (UNIT 2)~

I. INTRODUCTION II. REPORT l

A. SimedARY 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 l 1. Main Steam Safety Relief Valve Operations l l 2. Major Changes to Radioactive Waste Treatment System
3. Static O-Ring Failures
4. Off-Site Dose Calculation Manual Changes l 1 l

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'I . INTRODUCTION (UNIT 2)

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-snada 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 two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and j commercial power operation was commenced on October 19, 1984. l l

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

number (015)357-6761, extension 2056. i i

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i II. MONTELY REPORT

, A. StBetARY OF OPERATING EXPERIENCE (Unit 2) y D Time Event i

1 0000 Reactor critical, Generator on-line at 1135 Mwe.

1 2320 Reduoed power level to 1020 Mwe to transfer the Circulating Water system pumps and the Condensate / Condensate Booster pumps.

10 0130 Reduced power level to 850 Mwe for performance of a rod set.

1600 Incremsad power level to 1130 Mwe.

30 2100 Reduced power level to '750 Mwe for performance of a rod set.

31 1100 Increased power level to 1030 Mwe, power level held due to core limits.

2400 Reactor critical, Generator on-line at 1020 Mwe.

B. W N umNTS TO THE FACILITY OR TECHNICAL SPECIFICATION ,

on March 11, 1996, Amenchment 95 was issued to license NPF-10 )

(Unit 2). This amendment allows the implementation of the new ]

10 CFR 50 Appendix J 1eak testing requirements.

C. SUEMITTED LICENSEE EVENT REPORTS (Unit 2)

Occurrence LER No. Date Description )96-002 02/04/96 Manual Reactor scram due to loss of cooling on the '2E' Main Power Transformer.

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 0-Ring Failures (None)
4. Changes to the off-site Dose calculation Manual (None)

TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LASALLE TWO DATE April 10, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 l DPERATING STATUS

1. REPORTING PERIOD: March 1996 GROSS ROURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe Net): 1,036 DESIGN ELECTRICAL RATING (MWe Net): 1,0 78
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): N/A 4 REASONS FOR RESTRICTION (!F ANY): N/A REPORTING PERIOD DATA THIS MONTH YEAR To-DATE CUMULATIVE
5. REACTOR CRITICAL TIME (HOURS) 744.0 2,089.3 73,378.9
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 F. GENERATOR ON LINE TIME (HOURS) 744.0 2,020.2 71,861.7
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. T:ERMAL ENERGY GENERATED (MWHt) 2,442,127 6,372,259 218,341,514
10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 839,556 2,173,159 73,071,015
11. ELECTRICAL ENERGY GENERATED (MWHe Net) 816,216 2,103,505 70,256,177
12. REACTOR SERVICE FACTOR (%) 100.0 95.7 73.1
13. REACTOR AVAILABILITY FACTOR (%) 100.0 95.7 74.8
14. UNIT SERVICE FACTOR (%) 100.0 92.5 71.6
15. UNIT AVAIL!BILITY FACTOR (%) 100.0 92.5 71.6
16. UNil CAPACITY FACTOR (USING MDC) (%) 105.9 93.0 67.6
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 101.8 89.3 64.9
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 7.5 10.0
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, ANO DURATION OF EACH): Refuel, 09/07/96, 10 Weeks
20. IF SHUTDOWN AT END OF REPORT PER100, ESTIMATED DATE OF STARTUP: N/A

DOCKET No. 050 374 TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DA!LY UNIT POWER LEVEL (MWe Net) DATE April 10, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 REPORT PERIOD: March 1996 DAY POWER DAY POWER 1 1,105 17 1,107 i l

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3 1,103 19 1,105  !

4 1,103 20 1,104 1 1

5 1,101 21 1,105 l 6 1,101 22 1,107 7 1,100 23 1,110 8 1,099 24 1,110

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9 1,096 25 1,105 10 1,045 26 1,105 11 1,107 27 1,106 12 1,108 28 1,106 13 1,108 29 1,105 14 1,107 30 1,079 15 1,106 31 949 16 1,106 l

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TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 206 (UNIT 2) .

METHOD OF CORRECTIVE YEARLY TYPE SEUTTING DOWN ACTIONS /CCBGdENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER f if NUMBER (YYBOOD) 5: SCHEDULED (BOURS) REASON REDUCING POWER applicable)

(None)

SIDE 4ARY OF OPERATION: The unit reannined on-line at high power throughout the month. Several minor power reductions were required throughout the month for routine maintenance activities.

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, Attachment A Safety Relief Valve operations The following operations took place with the unit shutdown and with the reactor depressurised as part of routine intentional operability testing.

Date of Type of Eleason for Valve Actuation Actuation Actuation 1521F013A 03/19/96 Manual operability Testing 1521F0135 03/19/96 Manual operability Testing 1521F013c 03/19/96 Manual operability Testing

, 1521F013D 03/19/96 Manual operability Testing 1521F013E 03/19/96 Manual operability Testing 1521F013F 03/19/96 Manual operability Testing 1521F013G 03/19/96 Manual operability Testing 1521F0135 03/19/96 Manual operability Testing 1521F013J 03/19/96 Manual operability Testing J

1521F013K 03/19/96 Manual operability Testing '

1521F013L 03/19/96 Manual operability Testing 1521F013M 03/19/96 Manual operability Testing 9

1521F013N 03/19/96 Manual operability Testing 1521F013P 03/19/96 Manual operability Testing 1521F013R 03/19/96 Manual operability Testing l 1521F0138 03/19/96 Manual operability Testing i 1321F0130 03/19/96 Manual operability Testing 1521F013V 03/19/96 Manual operability Testing i

1521F013A 03/28/96 Manual operability Testing 1521F0135 03/28/96 Manual operability Testing 1521F013C 03/28/96 Manual operability Testing 1521F013D 03/28/96 Manual operability Testing 1521F013E 03/28/96 Manual operability Testing 1321F013F 03/28/96 Manual operability Testing 1321F0135 03/28/96 Manual operability Testing 1521F013J 03/28/96 Manual operability Testing 1321F013K 03/28/96 Manual operability Testing 1521F013L 03/28/96 Manual operability Testing 1821F013N 03/28/96 Manual operability Testing 1521F013R 03/28/96 Manual operability Testing 1321F0138 03/28/96 Manual operability Testing 1521F013v 03/28/96 Manual operability Testing 1521F0130 03/29/96 Manual operability Testing 1

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