ML20071H459

Monthly Operating Repts for June 1994 for LaSalle County Nuclear Power Station

ML20071H459
Person / Time
Site:	LaSalle
Issue date:	06/30/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9407150175
Download: ML20071H459 (16)

Text

. .

4 Commonw=lth Edison LaSalle County Nuclear Station 2601 N. 21st. Rd.

• Marseilles,!!linois 61341 1 Telephone 815/357-6761 July 11,1994 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 June 1994.

_- s D. Ray Station Manager LaSalle County Station DJR/tmb Enclosure cc: John B. Martin, Regional Administrator - Region Ill NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project Manager - LaSalle GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Manager of Nuclear Licensing - Downers Grove Nuclear Fuel Services Manager - General Office QA/NS Off-Site Review - General Office INPO Records Center Station File

/

9407150175 940630 QV PDR ADOCK 05000373 U

,I R PDR

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JUNE 1994 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF 11

TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A.

SUMMARY

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

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

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

e e

I. INTRODUCTION (UNIT 1)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison Company and located near Narseilles, Illinois.

Each unit is a Boiling Nater Reactor with a designed not electrical output of 1078 Negawatts. 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-ll on April 17, 1982. Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984. ,

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6763, extension 2427.

k i

h r

i

(

+ ,

a II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

EAZ Time Event 1 0000 Reactor sub-critical, Generator of f-line, refuel outage (L1R06) in progress.

23 0018 Reactor critical.

27 2047 Generator on-line at 50 Mwe.

2200 Power level at 151 Mwe.

28 1141 Generator off-line for turbine overspeed trip test.

i 1245 Generator on-line at 50 Mwe. l 29 1900 Power level at 200 Mwe.

2108 Power level at 156 Mwe.

30 2400 Reactor critical, Generator on-line at 160 Mwe.

B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Deletion of the Primary Containment structural integrity tendon testing from the Technical Specifications.

C. LICENSEE EVENT REPORTS (Unit 1)

LER Number Date Description l 94-008 06/07/94 Testing of standby liquid control system discharge safety relief valve.94-009 06/03/94 Shutdown cooling isolation due to high suction flow.

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 (None)

TABLE 1 D.1 OPERATING DATA REPORT DOCKET No. 050-373 UNIT LASALLE ONE DATE July 8,1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 OPERAVING STATUS

1. REPORTING PER100: June 1994 CROSS HOURS IN REPORTING PERIOD 720

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe Net): 1,036 DESIGN ELECTRICAL RATING (MWe-N 1,078

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

6. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

5. . REACTOR CRITICAL TIME (HOURS) 191.7 1,150.0 62,476.9

6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2

7. GENERATOR ON-LINE TIME (HOURS) 74.2 1,020.5 61,034.2

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

9. THERMAL ENERGY GENERATED (MWHt) 53,191 3,012,603 180,338,240

10. ELECTRICAL ENERGY CENERATED (MWHe-Gross) 11,282 1,011,308 60,265,679

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 1,934 936,907 57,785,661

'S3. REACTOR SERVICE FACTOR (%) 26.6 26.5 67.9

13. REACTOR AVAILABILITY FACTOR (%) 26.6 26.5 69.7

14. UNIT SERVICE FACTCR (%) 10.3 23.5 66.3

15. UNIT AVAltlBILITY F ACTOR (%) 10.3 23.5 66.3

16. UNIT CAPACITY FACTOR (USING MDC) (%) 0.3 20.8 60.6

~ 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 0.2 20.0 58.2

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 39.6 8.3

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

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

DOCKET NO. 050-373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE July 8, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PER100: June 1994 DAY POWER DAY POWER 1 -12 17 -12 2 -12 18 -12 3 -12 19 -12 4 -12 20 -12 5 -12 21 -12 6 -12 22 -16 7 -12 23 -16 8 -12 24 -15 9 -12 25 -14 10 -12 26 -14 11 -12 27 6 12 -12 28 124 1 13 12 29 127 14 -12 30 151 15 -12 31 16 -12 l

l

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

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER fYYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable) 4 940318 5 645.8 C 4 Refuel outage (LlR06).

5 940628 5 1.0 B 4 Manual turbine trip for performance of overspeed test.

GUMMARY OF OPERATION:

The unit entered the sonth in a scheduled refuel outage. The unit was returned to service on 06/27/94.

Gn 06/28/94 the main turbine was tripped for the performance of an overspeed test. The unit finished the month at low power.

t IJLSALLE NUCLEAR POWER STATION UNIT 2 [

NONTHLY PERFORNANCE REPORT ,

JUNE 1994 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 t

c F

t h

a f

TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION "

II. REPORT A. SUNMARY 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

2. 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

l m

4 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 met  ;

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 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 October 19, 1984. i This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.

l t

i i

B n

r h

I t

-i i

h 6

l t

i

II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Time Event 1 0000 Reactor critical, Generator on-line at 1130 Mwe.

4 0330 Reduced power level to 1040 Mwe due to system load.

0530 Increased power level to 1130 Mwe.

21 2230 Automatic reactor scram due to loss of bus 231A and 231B.

25 2055 Reactor critical.

26 1450 Generator on-line at 60 Mwe.

1608 Power level at 160 Mwe.

27 0600 Power level at 362 Mwe, reactor recirculation pumps upshifted.

0800 Power level at 610 Mwe.

1430 Increased power level to 1085 Mwe.

29 0100 Reduced power level to 700 Mwe to perform rod set.

0900 Increased power level to 1130 Mwe.

30 2400 Reactor critical, Generator on-line at 1130 Mwe.

B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Deletion of the Primary Containment structural integrity tendon testing from the Technical Specifications.

C. LICENSEE EVENT REPORTS (Unit 2)

LER Number Date Descrintion 94-003 06/16/94 Request for notice of enforcement discretion for critical surveillances.

?94-004 06/21/94 Loss of DC power to bus 231A and 231B resulting in an automatic reactor scram.94-005 06/22/94 Reactor recirculation system piping snubber support deformed.94-006 06/27/94 Hydraulic control unit low pressure switch out of tolerance exceeding a limiting condition of operation.

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 O-Ring Failures (None)

4. Changes to the Off-site Dose Calculation Manual (None) 1 l

1 1

1

TABLE 1 3.1 OPERATING DATA REPORT DOCKET No. 050-374 UNIT LASALLE TWO DATE July 8, 1994 COMPLETED BY M.J. CIALK0WSKI 4 TELEPHONE (815) 357-6761 I OPERATING STATUS

1. REPORTING PERIOD: June 1994 GROSS HOURS IN REPORTING PERIOD: 720

3. CURRENTLY AUTHORIZE 0 POWER LEVEL (MWt): 3,3 23 MAX DEPEND CAPACITY (MWe-Met): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078

3. POWER LEVEL TO WHICH RESTRICTED (!F ANY) (MWe-Net):

4. DEA 30NS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 625.6 4,034.1 60,959.7

6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 F. GENERATOR ON-LINE TIME (HOURS) 607.7 3,948.4 59,830.7

8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 ;

l

9. THERMAL ENERGY GENERATED (MWHt) 1,957,800 12,600,003 180,700,456

10. ELECTRICAL ENF'sY GENERATED (MWHe-Gross) 658,782 4,290,617 60,275,257

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 636,157 4,161,211 57,917,102

12. REACTOR SERVICE FACTOR (%) 86.9 92.9 71.7

13. REACTOR AVAILABILITY FACTOR (%) 86.9 92.9 73.7

.14. UNIT SERVICE FACTOR (%) 84.4 90.9 70.4

15. UNIT AVAILIBILITY FACTOR (%) 84.4 90.9 70.4

16. UNIT CAPACITY FACTOR (USING MDC) (%) 85.3 92.5 65.7 1F. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 82.0 88.9 63.2

18. UNIT FORCED DUTAGE FACTOR (%) 15.6 2.8 10.9

10. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

20. IF $NUTDOWN AT END OF REPORT PERIDO, ESTIMATED DATE OF STARTUP:

- 00CKET NO. 050-374 TABLE 2 UNIT LASALLE TWO D.2 AVERACE DAILY UNIT POWER LEVEL (MWe Wet) DATE July 8, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PERIOD: June 1994 DAY POWER DAY POWER 1 1,093 17 1,079 2 1,095 18 1,071 3 1,095 19 1,072 4 1,078 20 1,073 5 1,091 21 1,006 6 1,090 22 -16 7 1,088 23 -16 8 1,095 24 -14 9 1,096 25 -14 10 1,094 26 38 11 1,091 27 689 12 1,091 28 989 13 1,091 29 1,017 14 1,090 30 1,084 15 1,089 31 16 1,083 J

TABLE 3 ,

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COBOtENTS SEQUENTIAL DATE Ft FORCED DURATION THE REACTOR OR (LER # if NUNBER (YYMNDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable) 4 940621 F 112.3 A 3 Reactor scram due to the loss of buss 231A and the 2318.

EUMMARY OF OPERATION:

l The unit remained on-line at high power throughout most of the month. The unit experienced a automatic reactor j scram on 06/21/94. The unit was returned to service 06/26/94.

l

- .,