ML20087F991

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Jul 1995 for LaSalle County Nuclear Power Station
ML20087F991
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 07/31/1995
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9508160164
Download: ML20087F991 (18)
v • d • e


Text

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

F Commonwealth filiwn Osmpany

).*

Lahlle Generating Station

~

g .

. ' 2601 North 21st Roa<J

~

Marseilles. IL 61341-9757 Tel'H1435N>T61 August 11,1995 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 July,1995.

(. .

7 D. . Ray )

Station Manager '

LaSalle County Station i

DJR/mkl Enclosure cc: H. J. Miller, 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 Licensing Operations Director - Downers Grove Nuclear Fuel Services Manager - General Office Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Central File 9508160164 950731 PDR ADOCK 05000373 / /

R PDR 6 A Unia,m company Ig

i l

b f

I I

i I

1 i

I LABALLE NUCLEAR POWER STATION ,

UNIT 1 l DONTHLY PERFORMANCE REPORT 1

July 1995 l CCDGONNEALTH EDISON COMPANY NRC DOCKET NO. 050-373 ,

LICENSE NO. NPF-11  !

I t

t J

l I

l I

I l.

h l

5 I

i i

TABLE OF CONTENTS (UNIT 1) ,

I. INTRODUCTION II. REPORT A. Sthe4ARY OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS 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. Major Changes to Radioactive Waste Treatment System
3. Static O-Ring Failures
4. Off-site Dose calculatioa Manual Changes l

l l

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 sian-made cooling pond using the Illinois river for make-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 comunercial power operation was commenced on January 1, 1984.

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

1 s '-

]

1

-+' l ZZ.- lONTELY REPORT ,

A. StRedhRY OF OPERATING EXPERIENCE-(Unit 1)

Dy - Time ~ Event J l

-1 0000 Reactor critical, Generator on-line at 1120 Mwe.

]

5 0240 Reduced power level to.1070 Mwe due to control rod drive scram solenoid pilot valve replacements. j 2345 Reduced power level to 850 Mwe to perform scram time I testing. .j 6 0050 Increased power level to 1070 Mwe.

.. . I 7 0220 Reduced power level to 1000 Mwe due to system load, q 1030 Increased power level to 1120 Mwe.  !

8 0545 Reduced power level to 900 Mwe due to system load.

0840 Increased power level-1050 Mwe.

1 9 0530 Reduced power level to 960 Mwe due to system load.  !

0745 Increased power. level to 1095 Mwe.

10 0210 Reduced power level to 890 Mwe due to system load.

0645 Increased power level to 1000 Mwe. -

2300 Reduced power level to B50 Mwe to perform scram time testing.  !

11 0315 Increased power level to 925 Mwe.

i 2335 Reduced power level to 800 Mwe to perform scram time testing. ,

-1 12 0200 Increased power level to 1000 Mwe. )

1 2345 Reduced power level to 800 Mwe to perform scram time j testing.

13 0230 Increased power level to 1000 Mwe.

14 0010 Reduced power level to 800 Mwe to perform scram time testing.

0215 Increased power level to 970 Mwe.

15 0345 Increased power level to 1000 Mwe.

16 2350 Reduced power level to 970 Mwe due to control rod drive scram solenoid pilot valve replacements.  !

17 2315 Reduced power level to 790 Mwe to perform scram time testing.

'- 18 0715 Increased power level to 1030 Mwe. j i

2345 Reduced power level to 820 Mwe due to control rod drive I scram solenoid pilot valve replacements.

19 0800 Increased power level to 1060 Mwe.

2300 Reduced power level to 770 Mwe to perform scram time testing.

I

u. , ., ~ , <

I 4

4

- A. SUltiARY OF OPERATING EXPERIENCE (Unit 1)

(continued) g Time Event 20 1400 Increased power level to 1110 Mwe.

21 2200 Reduced power level to 840 Mwe to perform scram time testing and main steam isolation valve testing.

22 1000 Increased power level to 1110 Mwe.

23 0200 Reduced power level to 890 Mwe due to system load.

1100 Increased power level to 1110 Mwe.

25 0300 Reduced power level to 1040 Mwe for performance of a rod set.

0500 Increased power level to 1110 Mwe.

31 2400 Reactor critical, Generator on-line at 1090 Mwe.

i 1

I i

5. AMENDNENTS TO THE FACILITY OR TECHNICAL SPECIFICATION 1

,(None)- l

. l C.- SUBMITTED LICENSEE EVENT REPORTS-(Unit 1)

-l occurence l LER No. Date Description ,95-011 UT((>W During a routine inspection of the Fire l Protection Program, . it was noted that the Firewatch/ Compensatory Neasure Logs indicated that hourly fire watches required by Technical Specifications were frequently performed at-intervals exceeding one hour.

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) I E. UNIQUE REPORTING REQUIREMENTS (UNIT 1)
1. Safety Relief Valve Operations I (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 (None)

E i

l l

L,,

' TABLE 1 D.1: OPERATING DATA REPORT DOCKET No. 050 373 i

UNIT LASALLE ONE j DATE August 10, 1995

. COMPLETED BY M.J. CIALK0WSKI. .

TELEPHONE (815) 357 6761

]

OPERATING STATUS l t

1.. REPORTING PERIOD: July 1995 GROSS NOURS IN REPORTING PERIOD -744. ;j 4

. 2.

. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITV'(MWe-Met):- 1,036 DESIGN ELECTRICAL RATING (MWe N 1,078 3.-' P0bER LEVE6 TO WN!CN RESTRICTED (IF ANY) (MWe-Net):'  :

'4.. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTN YEAR TO-DATE CUNULATIVE i

{

5 .' REACTOR CRITICAL TIME (NOURS) 744.0 4,827.0 71,466.9 :  !

6. REACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 - 1,641.2 f 1
7. GENERATOR ON LINE TIME (NOURS) 744.0 4,788.5 69,899.6 ,

'8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 .

9. THERMAL ENERGY GENERATED (MWNt) 2,398,719 15,460,630 208,147,455
10. ELECTRICAL ENERGY GENERATED (MWNo Gross) 777,476 5,204,402 69,595,293 ~l l
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 750,639 5,042,638 66,811,782  ;
12. REACTOR SERVICE FACTOR (%) 100.0 94.9 70.4 l

~

13.' REACTOR AVAILABILITY FACTOR (%) 100.0 94.9 - 72.0

.'16. UNIT SERVICE FACTOR (%) 100.0 94.1 68.8 l

'i

15. UNIT AVAIL 181LITY FACTOR (%) 100.0 94.1 68.8 j
16. UNIT CAPACITY FACTOR (USING MDC) (%) 97.4 95.7 - 63.5 i t

17.' UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 93.6 92.0 ' 61.0

]

18. UNIT FORCED OUTAGE FACTOR (1) 0.0 2.8 7.9 . -l
19. SNUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACN): 01/27/96

'20. IF SNUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF. STAR'UPt T N/A I l

I i

'l '

(

DOCKET 100. 050-373 I

. TABLE 2 .

WIT LASALLE ONE .

D.2 AVERAGE DAILY WIT POWER LEVEL'(MWe-Net) DATE August 10, 1995 COMPLETED BY M.J. CIALK0WIKI ,

TELEPHONE (815) 357-6761.

.i July 1995 REPOR1 PERIOD: .

DAY POWER DAY POWER j 1 1,071 .17 - 926 l

2. 1,066 18 933 3 1,065 19 874 4 1,065 20 979 ,

5 1,022 21 1,050  ;

6 974 22 976 7 1,057. 23 ' ~ 1,020 i 8 1,014 24 1,058 9 1,040 25 1,056 ,

10 938 ', 26 1,059 11 882 27 1,056 t

12 948 28 1,061 13 915 29 1,057 14 932 30 1,046 15 1,010 31 1,041 l 16 1,037 i

)

l I

-m TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20% -

(UNIT 1)

METHOD or CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCR4ENTS CEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYbHDD) S* SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None)

CtheRRY OF OPERATION:

The unit remained on-line at high power throughout the month. The unit experienced several minor power reductions due to maintenance and surveillance activities and systesa load.

s',

1

\

?

i i

f IASALLE NUCLEAR POWER STATION }

r UNIT 2  !

MONTHLY PERFORMANCE REPORT- j i

July 1995 .

COMMONWEALTH EDISOM COMPANY  !

i t

NRC DOCKET No. 050-374 i

LICENSE No. NPF-10 -

?

t t

b t

f

-! t t

1 l

I i

h

?

s t

TABLE OF CONTENTS

-!. (UNIT 2)

I. INTRODUCTION' II. REPORT A. SLSe&RY OF OPERATING EXPERIENCE B. AMENDMDITS 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

!- UNIQUE REPORTING REQUIREMENTS

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

L h

t i

)

l l

)

I. INTRODUCTION (UNIT 2)

The LaSalle County Nuclear Power station is a two-Unit facility owned by comanonwealth Edison company and located near Marseilles, i Illinois. Each unit is a Boiling Water Reactor with a designed not -  !

electrical output of 1078 Megawatts. waste heat is rejected to a  ;

man-snade cooling pond using the Illinois river for snake-up and blowdown. The architect-engineer was sargent and Lundy and the contractor was Cor.unonwealth Edison company.

Unit two was issued operating license number NPF-19 on December 16, 1993. Initial criticality was achieved on March 10, 1984 and comunercial power operation was commenced on october 19, 1994.

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

P r

I

?

{

r i

i i

t 9

1 I

v~- .- .

j i

II . -. MONTELY REPORT ~

A. StSedhRY OF OPERATING EXPERIENCE (Unit 2) i f

Day Time Event 1 0000 Reactor critical, Generator on-line at 1040 MWe. l t

3 0130 Reduced power level to 850 NWe due to system load. j 1300- Increased power level to 1110 MWo.

4 0645 Reduced power level to 1010 Mwe due to system load.  !

1000 Increased power level to 1120 MWo.  ;

15 0430 Reduced power' 1evel to 900 Nke due to feedwater heater second s tage . leakage. ,

16 1345 Increased power level to 1095 Mwe '

  • 21 0200 Reduced power level to 850 MWe for performance of a rod [

set.

1200 Increased power level to 1110 NWe.

20 0115 Reduced power level to 910 NWe due to oscillations of ,

the 'A' Reactor Recirculation flow control valve. [

0415 Increased power level to 1090 Mwe. j 29 0345 Reduced power level to 900 NWe due to oscillations of the 'A' Reactor Recirculation flow control valve.  !

0445 Increased power level to 940 NWe. .

31 2400 Reactor critical, Generator on-line at 960 Mwe.

i e

f e

6 T

b l

l i

1 1

, S. Aw w*8NTS TO THE FACILITY OR TECHNICAL SPECIFICATION

.(None)

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.

j . ".

.*' -TABLE 1 ,

' D.1 OPERATING DATA REPORT DOCKET No. 050 374 i

  • UNIT LASALLE TWO DATE August 10, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 ,

OPERATING STATUS

1. REPORTING PERIOD: July 1995 GROSS NOURS IN REPORTING PERIOD: 744 l i

b

2. CUkRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEhD CAPACITY (MWe Net): 1,036
  • DESIGN ELECTRICAL RATING (MWe-Net): 1,078 -;
3. POWER LEVEL TO WHICN RESTRICTED (IF ANY) (MWe Net):
4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA  ;

.............................................. 4 THIS MONTN YEAR TO-DATE CLMILATIVE ,

...e........ ............ ............

67,793.6 '

L 5. REACTOR CRITICAL TIME (HOURS) 744.0 2,585.7

6. REACTOR RESERVE $NUTDOWN TIME (HOURS) 0.0 0.0 1,716.9
7. GENERATOR ON LINE TIME (HOURS) 744.0 2,3 72.5 66,358.0
8. UNIT RESERVE SNUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHt) 2,349,253 7,210,506 200,962,434 801,100 2,476,564 67,165,133 f
10. ELECTRICAL ENERGY GENERATED (MWHe-Cross)
11. ELECTRICAL ENERGY GENERATED (MWHe Net) 773,928 2,363,810 64,548,572
12. REACTOR SERVICE FACTOR (1) 100.0 50.8 71.7
13. REACTOR AVAILABILITY FACTOR (%) 1UO.0 50.8 73.5
14. UNIT SERVICE FACTOR (%) 100.0 46.6 70.2 '
15. UNIT AVAILIBILITY FACTOR (%) 100.0 46.6 70.2
16. UNIT CAPACITY FACTOR (USING IOC) (%) 100.4 44.9 - 65.9
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 96.5 43.1 63.3
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 10.3 i
19. SNUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): N/A
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A i

DOCKET NO. 050-374

-TABLE 2 WIT LASALLE TWO '

D.2 AVERAGE DAILY WIT POWER LEVEL (MWe-Net) DATE August 10, 1995 )

COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761' i

?

REPORT PERIOD: July 1995 l DAY POWER DAY POWER j 1' 1,075 17 - 1,064 l 2 915 18 1,073  ;

3 1,022 19 1,074 f

4 1,074 20 1,072 5 1,083 21 1,024

{

6 1,085 22 1,069 ,

7 1,089 '23 ~ ~ T1,071 8 1,00 24 1,068 (

9 1,079 25 1,067 l 10 1,0 73 26 1,064 l 11 1,069 27 1,062 l t

12 1,065 28 1,038 13 1,067 29 931 14 1,063 30 929 l

15 900 31 931 16 967 l t

e t

i i

l 1

1 l

~ . _ _

.. .o.

TABLE 3 D.3 UNIT SRUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

ME;THOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCM 6MTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER S if NUMBER (YYM4DD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None)

StaemRY OF OPERATION:

The unit remained on-line at high power throughout the month. The unit experienced several minor power reductions due to system load.

_ _ _ _ _ _ _ _______ __ - . . _ - - . - - - ~ - _ - . __ - _ . . _ - . _ - - -_ . . - . . ,

. __ _ _ . . _ _ _ . _ _ . . . _ _ . . . . . _ . . . _ . .

Retrieved from "https://kanterella.com/w/index.php?title=ML20087F991&oldid=2736914"