ML20111A975

Monthly Operating Repts for April 1996 for LaSalle County Station Units 1 & 2

ML20111A975
Person / Time
Site:	LaSalle
Issue date:	04/30/1996
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9605140115
Download: ML20111A975 (16)

Text

- - _ _ _ _ .-

. Commonw calth bliwn Comguny l

. 125alle Generating Station 2N)1 North 21st Road Marwilles, 11314 4 l >F57 Tri H I 5 .4 5'45"6 I l

l May 8,1996 l United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

LaSalle County Station Units 1 and 2 Monthly Performance Report NRC Docket Numbers 50-373 and 50-374.

Enclosed is the LaSalle County Station Monthly Performance Report for the l month of April,1996.

Respectfully, l

I

! D.J. Ray Station Manager l LaSalle County Station I

Enclosure j cc: H. J. Miller, NRC Region ill 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

4 9605140115 960430 4 PDR ADOCK 05000373 R PDR

\,

uno,m o miun>

f

l 1.

1 ~

i l

l l

l l

l 1ASALLE NUCLEAR POWER STATIcet UNIT 1 MotfTELY PI3tJORMANCE REPORT April 1996

, CCaedOIRfEALTE EDISott COMPANY I

i NRC DOCEET Mo. 050-373

\

LICENSE No. NPF-11 l

\

l l

l l

1 I

l l

i l

i

(

TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. StaedARY OF OPERATING EEPERIENCE

3. N S TO FACILITY LICENSE OR TECENICAL 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 1

I. INTRODUCTION (UNIT 1)

The Lasalle County Nuclear Power station is a two-Unit facility owned by Commonwealth Edison Cospany and located near Marseilles, Illinois. Each unit is a Boiling Mater Reactor with a designed not electrical output of 1078 Megawatts. Waste heat is rejaoted to a man-snade cooling pond using the Illinois river for snake-up and blowdown. The architeot-engineer was sargent and Lundy and the contractor was cossmonwealth Edison Company.

Unit one was issued operating license number NPF-11 on April 17, 1982. Initial criticality was achieved on June 21, 1902 and commmercial power operation was ocemenced on January 1, 1984.

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

i

l

. II. MONTELY REPORT A. StBedARY OF OPERATING EEPERIENCE (Unit 1)

Dy Time Event 1 0000 Reactor sub-critical, Generator off-line, refuel outage (L1R07) in progress.

30 2400 Reactor sub-critical, Generator off-line, refuel outage (L1A07) in progress.

B. AMENDMENTS TO TEE FACILITY OR TECENICAL SPECIFICATION On April 4, 1996, Amendment 111 was issued to license NPF-11 (Unit 1). This amenchment removes / changes temperature and differential temperature from the isolation logic for the main steam tunnel trips.

On April 5, 1996, Amendment 112 was issued to license NPF-11 l (Unit 1) . This amendment deletes the main steam isolation valve l 1eakage control system and increases main steam isolation valve total l allowed leakage from 100 sofh to 400 sofh, with 100 scfh allowed l 1eakage per main steam line.

C. SUndITTED LICENSEE EVENT REPORTS (Unit 1)

Occurrence LER No. Date Description

96-002 03/23/96 Ecurly fire watch was not performed as l required per the Station Technical Specification.96-003 03/26/96 Reactor scram due to spurious spike of I the 'B' intermediate range monitor.

l D. DATA TABULATIONS (Unit 1) l 1. Operating Data Report (See Table 1) l

2. Average Daily Unit Power Level (See Table 2)

I i 3. Unit Shutdowns and Significant Power Reductions (See Table 3) l 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 l (None) i j 4. Changes to the Off-site Dose Calculation Manual

(None)

I l .

l l TABLE 1 l D.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ONE l DATE May 10, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 OPERATING STATUS

1. REPORTING PERIOD: Aprl( 1996 GROSS HOURS IN REPORTING PERIOD 719 l 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe N 1,078 l l

> l l

3. POWER LEVEL TO WHICH RESTRICTED (!F ANY) (MWe Net): N/A j 1

6. REASONS FOR RESTRICTION (IF ANY): N/A  !

REPORTING PERIOD DATA

.............................................. i THIS MONTH YEAR TO DATE CUMULATIVE

)

l 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 j

9. THERMAL ENERGY GENERATED (MWHt) 0 1,411,768 219,866,585

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 0 470,404 73,514,256

11. ELECTRICAL ENERGY GENERATED (MWHe Net) -8,593 424,303 70,562,731

12. REACTOR SERVICE FACTOR (%) 0.0 20.2 69.9

13. REACTOR AVAILABILITY FACTOR (%) 0.0 20.2 71.4 I l

E UNIT SERVICE FACTOR (%) 0.0 20.1 68.4 i

15. UNIT AVAILIBILITY FACTOR (%) 0.0 20.1 68.4 i

16. UNIT CAPACITY FACTOR (USING MDC) (%) 1.2 14.1 63.0

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) -1.1 13.6 60.5

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 7.8 l

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)2 N/A

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 05/07/96 i

I

\

DOCKET NO. 050-373 TA8LE 2 UNIT LABALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE May 10, 1996 l

COMPLETED BY M.J. CIALKDWSKI TELEPHONE (815)-357 6761 REPORT PERIOD: April 1996 DAY POWER DAY POWER 1 12 17 12 2 11 18 -12 f

3 11 19 12 1

l 4 12 20 12 5 -12 21 -12 i

6 -12 22 12

! 7 -12 23 12 l 8 12 24 -12 l 9 -12 25 -12 10 12 26 -12 11 -12 27 12 12 -12 28 12 l 13 -12 29 -12 i

l 14 12 30 12 15 -12 31 16 12 l

l i

R i

e l

i I I . - - - - . -

)

4 TABLE 3 ,

D.3 CNIT SHUTDOWNS AND POWER REDUCTIottS > 204 (UNIT 1) -

METHoo oF coautEcTIVE YEARLY TYPE SHUTTING DOWN ACTICIES/CMSERITS SEQUENTIAL DATE F: EORCED DURATIott THE REACTOR OR (LER S if NUMBER (YYledDD) 5: SCHEDULED (HOOFj)_ REASOtt REDUCING POWER applicable) 01 960125 S 719.0 C 2 Refuel outage (L1R07) i i

l EUteEARY OF OPERATION: The unit renaained in a scheduled refueling outage for the entire month.

1 a

I LASALLE NUCLEAR POWER STATIODT DEIT 2 N LY PERFONdANCE REPORT

! April 1996 N TE EDIS00T COMPANY NRC DOCKET NO. 050-374 l

LICENSE NO. NPF-18 1

4 l

t l

i

TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A. StBedkRY OF OPERATING EXPERIENCE

3. NS TO FACILITY LICENSE OR TECENICAL SPECIFICATIONS l

l C. LICENSEE EVENT REPORTS l l

l D. DATA TABULATIONS l l 1. Operating Data Report

! 2. Average Daily Unit Power Level ]

1

3. Unit Shutdowns and Power Reductions l l

1 l E. UNIQUE REPORTING REQUIREMENTS

( 1. Main Steam Safety Relief Valve operations

2. Major Changes to Radioactive Waste Treatment System

3. Static O-Ring Failures l 4. Off-Site Dose Calculation Manual Changes l

l l

l l

l l

i l

t

._...__. - ..-.. .. .. - -~ - - . - . . . - - . - -

l

• l l

I. I8rrscOUCTIott (UttIT 2)

The Lasalle County Nuclear Power Station is a two-Unit facility <

owned by Commmonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed not l electrical output of 1078 Megawatts. Waste heat is rejected to a l 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 two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and oceansreial power operation was commenced on October 19, 1984.

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

l l

l

.. . . ~ - . . . - - - - . . . - . - _ - . _ . .. - . _ _ - . . . - . - - - - - _ - . - _ . - - - - . ._ - - - . - - - . - - - - .

~ '

i

. II. MutlTELY REPORT i .

I A. SCDMARY OF OPIMATING EXPERIENCE (Unit 2)

I y

D Time Event 1 0000 Reactor critical, Generator on-line at 1020 Mwe, i power level held due to core limits.

l j 0400 Increased power level to 1135 Mwe.

i 3 0310 Reduced power level to 1090 Mwe to perform control rod cycling.

0630 Increased power level to 1130 Mwe.

4 7 0300 Reduced power level to 1035 Mwe due to control rod 46-11 drifting.

0900 Reduced power level to 850 Mwe to perform control

! rod positioning.

i i 2230 Increased power level to 1135 Mwe.

10 0300 Reduced power level to 1090 Mwe for performance of l control rod cycling.

0530 Increased power level to 1135 Mwe.

17 0115 Reduced power level to 1000 Mwe for performance of

- control rod cycling and to take the 'B' Eeater Drain pump off-line and place the 'D' Beater Drain pump on-line.

l 0330 Increased power level to 1110 Mwe.

j 19 2225 Reducing power level to perform surveillance

testing and control rod moves. Power level held at i 1 930 Mwe due to Low Power Range Monitor high alarm. l l

20 0850 Increased power level to 1020 Mwe. )

1800 Increased power level to 1000 Mwe.

24 0110 Reduced power level to 765 Mwe to perform a rod set.

0345 Increased power level to 900 Mwe to perform surveillance testing. Turbine control valve #3 failed to reopen during testing.

0500 Increased power level to 965 Mwe, power level held due to Turbine control Valve #3 remaining in a closed position.

1 26 2040 Reduced power level to 875 Mwe to perform l surveillance testing. l 2240 Reduced power level to 780 Mwe to perform rod l sequencing.

A. StaemRY OF @PERATING EXPERIENCE (Unit 2)

. (continued) y D Time Event 27 1310 Increased power level to 950 Mwe, power level held due to Turbine Control Valve #3 remaining in a closed position.

30 2400 Reactor critical, Generator on-line at 950 Mwe.

E. N r8 TO TER FACILITY OR TECENICAL SPECIFICATION on April 4, 1996, Amendment 96 was issued to license NPF-18 (Unit 2). This amendment removes / changes teeperature and differential temperature from the isolation logic for the main steam tunnel trips.

On April 5, 1996, Amendment 97 was issued to license NPF-18 (Unit 2). This amendment deletes the main steam isolation valve leakage control system and increases main steam isolation valve total allowed leakage from 100 sofh to 400 sofh, with 100 sofh allowed leakage per main steam line.

Note: The implementation and issuanoe of amendments 96 and 97 is dependent upon the installation of the associated modifications during the L2R07 refuel outage.

C. SUENITTED 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 Naste Treatment Systems (None)

3. Static O-Ring Failures (None)

4. Changes to the Off-Site Dose Calculation Manual (None)

I l

l

i i

TABLE 1 0.1 OPERATING DATA REPORT DOCKET No. 050-374 l UNIT LASALLE TWO DATE May 10, 1996 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815) 357-6761 j OPERATING STATUS

1. REPORTING PERIOD: April 1996 GROSS HOURS IN REPORTING PERIOD: 719

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPENO CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,0 78 i 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): N/A l 6. REASONS FOR RESTRICTION (IF ANY): N/A l REPORTING PERIOD DATA THl3 MONTH YEAR-T0-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 719.0 2,808.3 74,097.9

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

l

7. GENERATOR ON-LINE TIME (HOURS) 719.0 2, 73 9.2 72,580.7

8. UNIV RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 l

9. THERMAL ENERGY GENERATED (MWHt) 2,236,799 8,609,058 220,578,313

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 769,003 2,942,162 73,840,018

11. ELECTRICAL ENERGY GENERATED (MWHe Net) 741,773 2,845,278 70,997,950

12. REACTOR SERVICE FACTOR (%) 100.0 96.7 73.3

13. REACTOR AVAILABILITY FACTOR (%) 100.0 96.7 75.0

10. UNIT SERVICE FACTOR (%) 100.0 94.4 71.8

15. UNIT AVAILIBILITY FACTOR (%) 100.0 94.4 71.8

16. UNIT CAPACITY FACTOR (USING MDC) (%) 99.6 94.6 67.8 l

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 95.7 90.9 65.1

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 5.6 9.9

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): Refuel, 09/0//%,10 Weeks

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

l l

DOCKET NO. 050 374 TA8LE 2 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE May 10, 1996 COMPLETED 8Y M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PERIOD: April 1996 DAY POWER DAY POWER 1 1,062 17 1,063 2 1,102 18 1,063 3 1,100 19 1,042 4 1,103 20 983 5 1,102 21 1,040 6 1,100 22 1,036 7 977 23 1,028 8 1,098 24 886 9 1,096 25 905 10 1,099 26 891 11 1,098 27 875 12 1,094 28 908 13 1,094 29 906 14 1,096 30 905 15 1,085 11 16 1,067

b TABLE 3 D.3 UNIT SHUTDOIRIS AND POWER REDUCTIcers > 20%

(UNIT 2)

METsoD oF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTICIIS/CCheerTS SEQUENTIAL DATE F: FORCED DURATICBI THE REACTOR OR (LER S if yman (YYtedDD) 3: SCHEDULED (HOURS) REASott REDUCING POWER applicable)

(None)

EUtedARY OF OPERATIOti: The unit remained on-line at high power throughout the month. Several minor power reductions were required throughout the month for routine maintenance activities.

_ - _ - _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ . - _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ .