ML20078H497

Monthly Operating Repts for LaSalle County Nuclear Power Station Units 1 & 2

ML20078H497
Person / Time
Site:	LaSalle
Issue date:	10/31/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9411170314
Download: ML20078H497 (17)

Text

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Commonwstith Edison

• LaSalle County Nuclear Station 2601 N. 21st. Rd.

' Marseities, lilinois 61341 Telephone 815/357-6761 l

l Novernber 11,1994 l U.S. Nuclear Regulato;y Commission Document Control Desk Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for October,1994.

cy D. J. Ray -

Station Manager LaSalle County Station  :

DJR/tmb Enclosure l cc: John B. Martin, Regional Administrator - Region III l NRC Senior Resident Inspector - LaSalle l IL Department of Nuclear Safety - LaSalle l IL Department of Nuclear Safety - Springfield, IL NRR Project Manager - Washington, D.C. l 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 GO C F;l g.

! i 9411170314 941031 '

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT october 1994 CCMMONWEALTH EDISON COMPANY -

I NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l

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. . 1 TABLE OF CONTENTS .

(UNIT 1) I I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICEilSEE 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

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2. INTRODUCTION (UNIT 1)

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-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-11 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 (015)357-6761, extension 2427.

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I II. MONTHLY REPORT

.A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

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

8 0300 Reduced power level to 1050 Mwe due to system load. '

0900 Increased power level to 1135 Mwe.

15 0100 Reduced power level to 900 Mwe to perform testing on the Motor Driven Reactor Feed Pump and control card changeout on the 'A' Turbine Driven Reactor Feed Pump.

0400 Increased power level to 1135 Mwe.  ;

20 0400 Reduced power level to 630 Mwe to perform scram time testing.

1000 Increased power level to 1140 Mwe. l 30 1500 Reduced power level to 1054 Mwe to perform a rod set.

1600 Increased power level to 1140 Mwe.  ;

31 2400 Reactor critical, Generator on-line at 1140 Mwh. f t

B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION i (None)

C. LICENSEE EVENT REPORTS (Unit 1) l (None)

D. DATA TABULATIONS (Unit 1) ,

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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 ,

0.1 OPERATING DATA REPORT DOCKET No. 050 373 UNIT LASALLE ONE DATE November 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 ,

1 OPERATING STATUS

1. REPORTING PERIOD: October 1994 GROSS HOURS IN REPORTING PERIOD 745 [

2. CE2RENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 1,078 '

DES!CN ELECTRICAL RATING (MWe-N

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

P

4. REASONS FOR RESTRICTION (IF ANY):  ;

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (NOURS) 745.0 4,022.7 65,349.6

- 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 F. GENERATOR ON LINE TIME (HOURS) 745.0 3,839.1 63,852.8 i

8. EJIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 [

9. THERMAL ENERGY GENERATED (MWHt) 2,454,696 11,381,568 188,707,205

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 835,880 3,799,813 63,054,184

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 809,102 3,627,132 60,475,886

12. REACTOR SERVICE FACTOR (%) 100.0 55.1 68.8

13. REACTOR AVAILABILITY FACTOR (%) 100.0 55.1 70.5

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14. UNIT SERVICE FACTOR (%) 100.0 52.6 67.2

15. UNIT AVAILISILITY FACTOR (%) 100.0 52.6 67.2 .

10. UNii CAPACITY FACTOR (USING MOC) (%) 104.8 48.0 61.5  !

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17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 100.7 46.1 59.1 ,

10. UNIT FORCED OUTAGE FACTOR (%) 0.0 17.3- 8.2

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

20. 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 AVERACE DAILY UN!1 POWER LEVEL (MWe-Net) DATE November 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 REPORT PERIOD: October 1994 DAY POWER DAY POWER 1 1,090 17 1,090 2 1,092 18 1,093 3 1,091 19 1,093 4 1,090 20 1,094 5 1,089 21 1,092 ,

6 1,089 22 1,093 7 1,089 23 1,094 8 1,083 24 1,091 9 1,088 25 1,095 10 1,086 26 1,095 11 1,089 27 1,084 12 1,091 28 1,021 13 1,091 29 1,088 14 1,0 79 30 1,131 15 1,039 31 1,096 16 1,089 l

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TABLE 3 D.3 UNIT SEUTDOWNS AND POWER REDUCTION 8 > 20%

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER $ if NUMAER (YYMMDD) St SCREDULED LILOURS ) BEASO_N REDUCING POE a neolicable)

(None)

SUMMARY

OF OPERATION:

The unit remained on line at high power throughout the month. Several minor power reductions were required due to system load maintenance and surveillance activities.

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l LASALLE NUCLEAR POWER STASION  ;

UNIT 2 MONTHLY PERFORMANCE REPORT October 1994 COMMONWEALTH EDISON COMPANY l

NRC DOCKET NO. 050-374 LICENSE NO. NPF-10 i

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l TABLE OF CONTENTS (UNIT 2)

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 i

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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-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.

This report was compiled by Michael J. Ciclkowski, telephone number (815)357-6761, extension 2427.

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4 II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Time Enni 1 0000 Reactor critical, Generator on-line at 840 Nwe due to Condensate pump limitations.

3 1600 Reduced power level to 640 Nwe due to a '25A' Feedwater Heater isolation.

2100 Increased power level to 830 Nwe.

6 0000 Reduced power level to 735 Nwe to place the *25A' '

Feedwater Heater on-line.

0200 Increased power level to 830 Nwo.

0900 Reduced power level to 810 Nwe to perform scram time testing.

0930 Increased power level to 835 Nwe. ,

7 0100 Reduced power level to 810 Nwe to perform scram time testing.

0130 Increased power level to 840 Nwe.

9 0030 Reduced power level to 800 Nwe to perform scram time testing.

1800 Increased power level to 835 Nwe.

11 0300 Reduced power level to 740 Nwe to perform scram time testing.

0700 Increased power level to 830 Nwe.

1300 Reduced power level to 730 Nwe to perform scram time l testing.

1830 Increased power level to 820 Nwe.

12 0300 Reduced power level to 730 Nwe to perform scram time testing.

0600 Increased power level to 835 Nwe.

1400 Reduced power level to 715 Mwe to perform scram time testing.

1700 Increased power level to 840 Nwe.

13 0200 Reduced power level to 740 Nwe to perform scram time testing.

0000 Increased power level to 830 Nwo.

1530 Reduced power level to 725 Nwe to perform scram time testing.

1800 Increased power level to 825 Mwe.

14 0230 Reduced power level to 680 Nwe to perform scram time testing.

4 A. CUMMARY OF OPERATIN3 EXPERIENCE (Unit 2)

, (continued)

DAZ Tiam Krant 14 0600 Increased power level to 835 Nwe.

1300 Reduced power level to 700 Nwe to place the 'A' Condensate / Condensate Rooster pump on-line.

2200 Increased power Aevel to 1100 Nwe.

16 0300 Reduced power level ts 845 Nwe to perform scram time testing.

1300 Increased power level to 1135 Nwe.

17 0300 Reduced power level to 900 Nwe to perform replacement of' scram pilot solenoid valves.

0500 Increased power level to 1060 Nwe.

1930 Reduced power level to 850 Nwe to perform scram time testing.

18 0100 Increased power level to 1100 Nwe.

2200 Reduced power level to 845 Mwe to perform scram time testing.

19 0300 Increased power level to 1125 Nwe.

1057 Reactor scram due to Electro Hydraulic Control system oscillations.

24 0126 Reactor critical.

2015 Generator on-line at 60 Nwe.

25 1900 Power level at 1065 Nwe.

26 0800 Reduced power level to 740 Nwe due to loss of the 'C' Condensate / Condensate Booster pump.

1600 Increased power level to 810 Nwe.

27 0230 Reduced power level to 740 Nwe to perform replacement of a scram solenoid pilot valves. )

0300 Increased power level to 800 Nwo.

28 0300 Reduced power level to 730 Nwe to perform replacement of a scram solenoid pilot valves.

0400 Increased power level to 800 Nwe.

2200 Reduced power level to 700 Nwe to place the 'C' Condensate / Condensate Booster pump on-line. '

29 1900 Increased power level to 1035 Nws.

I 30 1300 Reduced power level to 850 Nwe to perform a rod set. I I

2000 Increased power level to 1075 Nwe.

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

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, B. AMENDMEMT3 TO THE FACILITY OR TECHNICAL SPECIFICATION (None)

C. LICENSEE EVENT REPORTS (Unit 2)

LER_11o_ Data n,seriotion 94-007 10/04/94 Division I group 2 and group 4 isolation due to a blown fuse.94-008 10/19/94 Reactor scram due to Electro Hydraulic Control system oscillations.

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 Date of Type of YAlY1 AEtMA119D AEtRILt19B Ditacriotion 2B21-F013K 10/19/94 Automatic Reactor Scram (LER# 94-000) 2B21-F013F 10/19/94 Automatic Reactor Scram (LER# 94-008) 2B21-F013G 10/19/94 Automatic Reactor Scram (LER# 94-008) 2B21-F013S 10/19/94 Automatic Reactor Scram (LER# 94-008) 2B21-F013U 10/19/94 Automatic Reactor Scram (LER# 94-008) 2B21-F013D 10/19/94 Automatic Reactor Scram (LER# 94-000)

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)

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. TABLE 1 D.1 OPERATING DATA REPORT DOCKET No. 050-374 UNIT LASALLE TWO DATE November 10, 1994

. COMPLETED BY M.J. CIALK0WSKI ,

TELEPHONE (815)-357-6761  !

DPERATING STATUS

1. REPORTING PERIOD: October 1994 GROSS HOURS IN REPORTING PERIOD: '745

_2. , CEDRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 1 DESIGN ELECTRICAL RATING (MWe-Net): 1,078-  ;

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

'6. REASONS FOR RESTRICTIDW (IF ANY):

REPORTING PER100 DATA

.............................................. i THis MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 634.5 6,818.4 63,744.0

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

7. GENERATOR ON LINE TIME (HOURS) 615.7 6,639.2 62,521.5

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

9. THERMAL ENERGY GENERATED (MWHt) 1,610,525 20,914,004 189,014,457

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 543,564 7,083,332 63,067,972

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 523,268 6,856,924 60,612,815

12. REACTOR SERVICE FACTOR (%) 85.2 93.5 72.4

13. REACTOR AVAILABILITY FACTOR (%) 85.2 93.5 74.4

14. UNIT SERVICE FACTOR (%) 82.6 91.0 71.1

15. UNIT AVAILIBILITY FACTOR (%) 82.6 91.0 71.1

16. UNIT CAPACITY FACTOR (USING MDC) (%) 67.8 90.7 66.5

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 65.2 87.2 63.9

10. UCIT FORCED OUTAGE FACTOR (%) 17.4 5.3 10.8

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

20. IF SHUTDOWN AT END OF REPCRT PERIOD, ESilMATED DATE OF STARTUP:

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, DOCKET NO. 050-374 TABLE

• UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE Novenber 10, 1994 COMPLETED BY M.J. CIALK0WSKI

. TELEPHONE (815)-357 6761 REPORT PER10D October 1994 DAY POWER DAY POWER 1 801 17 1,013 2 801 18 1,053 3 793 19 472 4 804 20 -12 5 801 21 -12 6 796 22 -12 7 806 23 -12 8 806 24 9 9 803 25 712 10 805 26 819 11 785 27 769 12 792 28 768 13 791 29 863 14 824 30 1,023 15 1,065 31 1,025 16 1,049 l

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b TABLE 3 -

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

METHOD OF C'JRRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) S SCHEDULED LHOURS) REA_S_OH

_ RERECING POWER aoolicablel 6 941019 F 129.3 A 3 Reactor scram due to Elactro Hydraulic Control system oscillations (LER# 94-008)

SUMMARY

OF OPERATION:

The unit remained on-line throughout most of the month. Several minor power reductions were required due to maintenance and surveillance activities. The unit experienced a reactor scram on 10/19/94 due to oscillations in the Electro Hydraulic Control system. The unit was returned to service on 10/24/94.

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