ML20085E495

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Monthly Operating Repts for May 1995 for LaSalle County Nuclear Power Station
ML20085E495
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 05/31/1995
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9506160552
Download: ML20085E495 (16)
v • d • e


Text

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. Gimmonwralth rAhum O)mpany

,s . 12%alle Generating Matson j

' Rol North 21st Road l

  • I Marwilles. It. 613 t l4757 Tel HI5 35N,761 June 13,1995 1 l

U.S. Nuclear Regulatory Commission Document Control Desk l Washington, D.C. 20555 l Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for May,1995.

D. . Ray Station Manager LaSalle County Station i

DJR/mkl l Enclosure ,

cc: John B. Martin, Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle l 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 oft-Site Safety Review Senior Participant - Downers Grove l INPO Records Center l Central File 9506160552 950531 ,

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LASALLE NUCLEAR poler STATION 5

UNIT 1 ,

r MONTHLY PERFORMANCE REPORT May 1995 CCheONNEALTH EDISON CCMPANY NRC DOCKET NO. 050-373 i

LICENSE NO. NPF-11 i i

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TABLE OF CONTENTS +

(UNIT 1)

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

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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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-made cooling '

pond using the Illinois river for make-up and blowdown. The architect-engineer was sargent and Lundy and the contractor was Cosunonwealth Edison Company.

Unit one was issued operating license number NPF-11 on April 17,  ;

1982. Initial criticality was achieved on June 21, 1982 and t commercial power operation was comunenced on January 1, 1984.

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

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II. ICHTMLY REPORT L:

A. SUbeGLRT OF OPERATING EXPERIENCE (Unit 1)

Dy Tisas Event-

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1 0000 Reactor critical, Generator on-line at 1130 Nwe. ,

10 2100 Reduced power level to 740 Mwe for the performance of a red set.

12 2000 Increased power level to 1130 Nwe.

I 16 2200 Reduced power level to 1070 Mwe for the performance of a i rod set. }

2300 Increased power level to 1125 Mwe.

l 23 2100 Reduced power level to 750 Mwe for the perforsmance of a l rod set and to place the 'B' Turbine Driven Reactor Feed Pump off-line for maintenance activities.

24 1400 Increased power level to 1020 Mwe. I 25 0300 Reduced power level to 950 due to system load. ,

0530 Increased power level to 1015 Mwe.

t 2200 Reduced power level to 830 Nwe to place the 'B' Turbine Driven Reactor Feed Puay on-line and the 'A' Turbine .

Driven Reactor Feed Pung off-line for mainter.ance i activities.

26 0600 Increased power level to 1020 Mwe.

2300 Reduced power level to 830 Mwe to place the 'A' Turbine  ;

Driven Reactor Feed Pung on-line.

27 1300 Increased power level to 1020 Nwe.  !

r 28 1400 Increased power level to 1125 Mwe. f 1900 Reduced power level to 1100 Mwe due to Low Power Range  ;

Monitor high alarms.

31 0300 Reduced power level to 1050 Mwe for the performance of a i rod set.

0700 Increased power level to 1125 Nwe. I 2400 Reactor critical, Generator on-line at 1120 Nwe. I

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D. AbSMDb83fTS TO TSE FACILITY OR TECENICAL CPECIFICATION (None)  :

C. sum (ITTED LICENSEE EVENT REPORTS (Unit 1) r r

Occurence '

LER No. Date Description [

95-010 04/15/95 During performance of surveillance LES-PC-209, l Unit 2 PCCN and RBCCN Group 2 Isolation Logic i System Functional Test an electrical maintenance j technician pulled the wrong fuse at panel ,

2E13-P611 causing an ESF actuation.

D. DATA TABULATIONS (Unit 1) ,

1. i Operating Data Report (See Table 1) '
2. Average Daily Unit Power Level (See Table 2)

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3. Unit Shutdowns and Significant Power Reductions (See Table 3) I E. UNIQUE REPORTING REQUIREMENTS (IDIIT 1) i
1. Safety Relief Valve Operat:,.pns (None) 6
2. Major Changes to Radioactive Naste Treatment Systems (None)
3. Static O-Ring Failures ,

(None)  :

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4. Changes to the off-Site Dose Calculation Manual I (None)
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. TABLE 9 D.1 OPERATING DATA REPORT DOCKET No. 050-373 UNIT LASALLE ONE DATE June 9, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 OPERATING STATUS

1. REPORTING PERIOD: May 1995 GROSS HOURS IN REPORT!rG PERIOD 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe Net): 1,036 DE$1GN ELECTRICAL RATING (MWe-N 1,078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net):

O. REASONS FOR RESTRICTION (IF ANY):

REPORT!Nr PERICO DATA THIS MONTH YEAR-10-DAT'i CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 744.0 3,492.7 70,132.6
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 F. GENER4 TOR ON LINE TIME (HOURS) 744.0 3,482.7 68,593.9 f 8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWHt) 2,396,025 11,309,091 203,995,916
10. ELECTRICAL ENERCT GENERATED (MWHe Gross) 808,877 3,842,854 68,233,745
11. ELECTRICAL ENERGT GENERATED (MWHe Wet) 782,478 3,730,068 65 499,212
12. REACTOR SERVICE FACTOR (%) 100.0  %.4 70.1
13. REACTOR AVAILABILITY FACTOR (%) 100.0 96.4 71.7
10. UNIT SERVICE FACTOR (%) 100.0 96.1 68.5
15. UNIT AVAILIBILITY F4CTOR '%) 100.0 96.1 68.5
16. UNIT CAPACITY FACTOR (USING W C) (%) 101.5 99.4 63.2
17. UNIT eAPACITY FACTOR (USING DESIGN MWe) (%) 97.6 95.5 60.7 i

l 18. UNIT FfACED OUTAGE FACTOR (%) 0.0 3.9 8.1 l ..............................................

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19. SHUTDOWNS SCHEDULED DVER THE NCXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
30. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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, DOCKET NO. 050 373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWEli LEVEL (MWe Net) DATE June 9, 1995 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815)-357-6761 REPORT PERIOD: May 1995 DAY POWER DAY POWER 1 1,091 17 1,084 2 1,089 18 1,083 3 1,088 19 1,081 l

4 1,089 20 1,081 5 1,091 21 1,077 6 1,091 22 1,077 7 1,087 23 1,,056 3 1,086 24 928 9 1,089 25 950 '

10 1,065 26 945 11 847 27 924 12 1,034 28 1,031 13 1,081 29 1,070 14 1,084 30 1,070 l 15 1,083 31 1,072 16 1,080 t l

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IASAT.t2 NUCLEAR POWER STATION UNIT 2 '

t MONTELY PERFOstMANCE REPORT May 1995 ,

CatedDNWEALTH EDISON COMPANY r

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NRC DOCKET NO. 050-374 LICENSE NO. NPF-19 ,

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l TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION ,

II. REPORT A. 3140thRY OF OPERATING EXPERIENCE g i B. AMENDMENTS TO FACILITY LICENSE OR TECSNICAL SPECIFICATIONS i C. LICENSEE EVENT REPORTS i

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. Rjor Changer to Radioactive Waste Treatment System '
3. Static O-Ring Failures
4. Off-Site Dose Calculation Manual Changes 6

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I. INTRODUCTION (UNIT 2) i The Lasalle County Nuclear Power station is a two-Unit facility owned by Consnonwealth Edison Company and located near Marseilles, i Illinois. Each unit is a Boiling Water Reactor with a designed not '

electrical output of o?S Megawatts, Waste heat is rejected to a man-made cooling pone,using the Illinois river for make-up and  !

blowdown. The architect-engineer was sargent and Lundy and the i contractor was Comunonwealth Edison Company. j Unit two was issued operating license number NPF-18 on December 16, ,

1993. Initial criticality was achieved on March 10, 1984 and commeercial power operation was comumenced on October 19, 1984.

t This report was compiled by Michael J. Cialkowski, telephone number (015)357-6761, extension 2056.

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II. MONTELY REPORT A. StsedhRY OF OPERATING EXPERIENCE (Unit 2) ,

Dy Time Event 1 0000 Reactor sub-critical, Generator off-line. Refuel outage ,

(L2R06) in progress.

l 16 2203 Reactor critical. i 22 0141 Manual reactor scram to perform maintenance on the l 2E12F000 and 2E12F009 Residual Beat Removal system i shutdown cooling valves and to repair the Main condenser

'C' hood boot seal.

31 2400 Reactor sub-critical, Generator off-line Refuel outage j (L2R06) in progress. s B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

C. SUBMITTED LICENSEE EVENT REPORTS (Unit 2) I Occurence *

, LER No.'"" Date Description I

95-007 04/11/95 A Division 2 ESF actuation occured during the performance of an instrument surveillance due to ,

a reference line pressure spike. The pressure (

spike was caused by the incorrect positioning of ,

an instrument stop valve.  !95-005 04/15/95 During testing of the ATNS/ARI power supplies I trip signals were received from the reactor water level and pressure channels 'A' and 'C'.

This actuation resulted in the scram air header dy ressurizing with a full scram signal received ,

from the high scram discharge volume level. '

D. DATA TABULATIONS (Unit ?) .

1. Operating Data Report (See Table 1) t r
2. Average Daily Unit Power Level (See Table 2)
3. Unit shutdowns c.nd significant Power Reductions (See Table 3)

E. UNIQUE REPORTING REQUIREMENTS (UNIT 2)

1. Safety Relief Valve operations (See Atachment A) '
2. Major Changes to Radioactive Waste Treatment Systems I (None)
3. Static O-Ring Feilures (None) i
4. Changes to the off-site Dose Calculation Manual $

(None) i 1

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s .;- , a , , TABLE 9 0.1 OPERATING DATA REFORT DOCKET NO. 050 374 UNIT LASALLE TWO [ DATE June 9, 1995 

                                                                                                                                                     .l COWLETED BY.M.J.        Cl*'"* 4KI                                     j TELEPHONE (815) '           '61 CPERATING STATUS
 - 1. REPORTING PERIOD:          May 1995                                  GROSS HOURS IN REPORTING PERIOD:                               744        r
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 f DE7!GN ELECTRICAL RATING (MWe Net): 1,078 i i

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3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): --
6. REASONS FOR RESTRICTION (!F ANY):  ;

REPORTING PERIOD DATA l 

                                                                                 ..............................................                         j THIS MONTH           YEAR-TO-DATE           CUMULATIVE               'l
5. REACTOR CRITit.AL TIME (HOURS) 123.6 1,276.2 66,484.2
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 i
7. GENERATOR ON LINE TIME (HOURS) 0.0 1,152.3 65,137.8
8. UNIT RESERVE SHUTDOWN TISC (HOURS) 0.0 0.0 0.0 E

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9. THERMAL ENERGY GENERATED (MWHt) 0 3,731,007 197,482,935
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0 1,281,127 65,%9,6%
11. ELECTRICAL ENERGY GENERATED (MWHe Net) -8,927 1,213,939 . 63,398,701
12. REACTOR SERVICE FACTOR (%) 16.6 35.2 71.4 i v
13. REACTOR AVAILABILITY FACTOR (%) 16.6 35.2 73.3  !

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14. UNIT SERVICE FACTOR (%) 0.0 31.8 70.0 i
15. UNIT AV71LIBILITY FACTOR (%) 0.0 31.8 70.0 f
16. UNIT CAPACITY FACTOR (USING MDC) (%) -1.2 32.3 65.8 i
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) -1.1 31.1 63.2.

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18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 10.4 [
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19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): i k
20. IF SHUTDOWN AT END OF PEPORT PERIOD, ESTIMATED DATE OF STARTUP:

06/09/95

DOCKET NO. 050-374 TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DA!LY UNIT POWER LEVEL (MWe-Net) DATE June 9, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PERIOD: May 1995 DAY POWER DAY POWER r ....... ......... ....... ......... 1 -12 17 -12 2 -12 18 12 3 12 19 -12 4 -12 20 12 5 -12 21 -12 6 -12 22 -12 7 -12 23 -12 8 12 24 -12 9 -12 25 12 10 -12 26 -12 11 12 27 12 12 -12 28 -12 13 12 29 12 14 12 30 12 15 -12 31 -12 16 12

TABLE 3 9 D.3 UNIT SEUTDOWNS AND PotIER REDUCTIONS > 20% (UNIT 2) ISTHFs OF CORRECTIVE YEARLY TYPE 8%fTING DOWN ACTIONS /CCteeDETS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUDGBER (YYtteD) S: SCHEDULED (BOURS) REASON REDUCING PoIIER applicable) 1 950218 S 744.0 c 2 Refuel outage (L2R06) SUtteRY OF OPERATION: The unit was in a scheduled refuel outage for the entire month. - _ - -- - _ -__- _ -____--_ _ .. .-}}

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