ML20046D235
| ML20046D235 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/31/1993 |
| From: | Cialkowski M, Schmeltz J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9308160380 | |
| Download: ML20046D235 (20) | |
Text
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C:mmonwe:.Ith Ediron LaSalle County Nuclear Station ,
2601 N. 21st. Rd.
fAarseilles, Illinois 61341 Telephone 815/357-6761 August 9,1993 United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for July 1993. ,
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\ Joseph V. Schmeltz Acting Station Manager LaSalle County Station Enclosure cc: Regional Administrator - Region III NRC Senior Resident Inspecor - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project Manager - LaSalle GE Resident - 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 i
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i LASALLE NUCLEAR POWER STATION ,
UNIT 1 [
t MONTHLY PERFORMANCE REPORT JULY 1993 ;
i cot 440NWEALTH EDISON COMPANY '
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NRC DOCKET No. 050-373 LICENSE No. NPF-11 '
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. i TABLE OF CONTENTS (UNIT 1)
I. INTRODUCTION j II. REPORT A. SU24GRY OF OPERATING EXPERIENCE r
B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS l l
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS
- 1. Operating Data Report
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS i
- 1. Main Steam Safety Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indications of Failed Fuel Elements t
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I. 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 net 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-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)357-6761, extension 2427.
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l II. HONTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
Day Time Event 1 0000 Reactor critical, Generator on-line at 900 Mwe due to a system load.
1100 Increased power level to 1115 Mwe.
2 0100 Reduced power level to 850 Mwe due to system load. l 1200 Increased power level to 1110 Mwe.
t 3 0300 Reduced power level to 850 HNe due to system load. !
1300 Increased power level to 1110 Mwe. .
I 4 0630 Reduced power level to 1000 MMe due to system load.
1100 Increased power level to 1105 MMe.
6 0230 Reduced power level to 1000 NNe due to system load. ;
1100 Increased power level to 1110 Mwe. .
7 0230 Reduced power level to 850 NNe due to system load.
1230 Increased power level to 1115 Mwe.
8 0300 Reduced power level to 1000 Mwe due to system load.
1000 Increased power level to 1110 Mwe.
9 0500 Reduced power level to 1050 Mwe due to system load.
B 0900 Increased power level to 1105 Mwe.
10 0400 Reduced power level to 1050 Mwe due to system load. ,
1200 Increased power level to 1110 Mwe.
11 0400 Reduced power level to 1000 Mwe due to system load.
1200 Increased power level to 1110 Mwe.
12 1500 Reduced power level to 840 Mwe due to feedwater heater drain valve control problems.
13 2000 Increased power level to 1085 Mwe.
15 0030 Reduced power level to 850 NNe due to system load.
1300 Increased power level to 1105 Mwe. ,
16 0230 Reduced power level to 900 MWe due to system load.
1000 Increased power level to 1110 Mwe.
18 0600 Reduced power level to 640 Mwe due to loss of the
'A' Turbine Driven Reactor Feed pump.
l 1700 Increased power level to 1110 Hwe. :
22 0100 Reduced power level to 850 Mwe due to system load.
0900 Increased power level to 1115 Mwe. !
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1 II . . MotiTHLY REPORT l A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1) ,
Day Time Event 29 0300 Reduced power level to 900 Nwe due to system load, placed the 'A' Turbine Driven Reactor Feed Pump !
off-line. ,
0700 Increased power level to 1000 Mwe.
30 0100 Reduced power level to 850 Mwe due to system load, .,
placed the 'A' Turbine Driven Reactor Feed Pump !
on-line. .
1300 Increased power level to 1100 Nke. ,
31 0330 Reduced power level to 950 Mwe due to system load.
1030 Increased power level to 1100 Mwe.
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2400 Reactor critical, Generator on-line at 1100 Mwe.
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r B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (None) ,
SOR differential pressure switch failure reports (None)
D. LICENSEE EVENT REPORTS (Unit 1)
LER Number Date Description 93-0I2-00 07/02/93 Reactor Core Isolation Cooling System ,
inoperable due to 250 VDC battery a charger.
93-013-00 07/27/93 Spurious group 6 and 7 isolation.
E. 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)
F. UNIQUE REPORTING REQUIREMENTS (UNIT 1)
- 1. Safety Relief Valve Operations (None)
- 2. ECCS System Outages )
(None)
- 3. Changes to the Off-site Dose calculation Manual '
(None)
- 4. Major Changes to Radioactive Waste Treatment Systems (None)
- 5. Indications of Failed Puel Elements (None) '
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, . TABLE 1 ;
. - E.1 OPERATING DATA REPORT _
- DOCKET NO. 050-373 ,
UNIT LASALLE ONE :
DATE' August 30, 1993 !
COMPLETED BY M.J.CIALKOWSKI
- OPERATING' STATUS TELEPHONE (815) 357-6761 .;
-1. REPORTING PERIOD: ' July 1993 I GROSS-HOURS IN REPORTING PERIOD: 744 ,
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- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 '!
MAX DEPENDABLE CAPACITY (MWe-Net): 1,036
. DESIGN' ELECTRICAL RATING- (MWe_ Net): 1,078 l h
- 3. POWER' LEVEL TO WHICH' RESTRICTED (IF ANY) (MWe-Net): ,
- 4. REASON FOR RESTRICTION (IF ANY):
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THIS MONTH YEAR TO DATE CUMULATIVE :
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REACTOR CRITICAL TIME (HOURS) 744.0 4,246.2 -58,170.9
- 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2
- 7. GENERATOR ON-LINE TIME (HOURS) 744.0 3,976.8 56,884.4 i
- 8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 ,
- 9. THERMAL ENERGY' GENERATED (MWHt) 2,'384,381 12,275,499 167,335,657 f
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 789,426 4,093,019. 55,885,368 .;
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net). 761,700 3,940,465 53,588,555 l
- 12. REACTOR SERVICE FACTOR (%) 100.0 183.5 69.2' {
- 13. REACTOR AVAILABILITY FACTOR (%) 100.0- 83.5 71.2 ;
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I4, UNIT SERVICE FACTOR (%) 100.0- 78.2 67.7 !
- 15. UNIT AVAILIBILITY FACTOR (%) '100.0 78.2 67.7
-16. UNIT CAPACITY FACTOR (USING MDC) (%) 98.8 74.8 61.6 l
- 17. UNIT CAPACI7Y FACTOR (USING DESIGN MWe) 95.0 71.9 .59.2
-l f18. UNIT FORCED OUTAGE FACTOR (%) 0.0 9.1 7 . 11 I
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF.EACH): ;
No Outages Scheduled
" 20. 1F SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: '
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- -'. - E.2 AVERAGE DAILY UNIT POWER LEVEL- (MWe-Net) !
DOCKET NO. 050-373 i UNIT LASALLE ONE I
DATE AugustL10,- 1993 -
COMPLETED BY M.J. CIALKOWSKI- 'l TELEPHONE (815)-357-6761'
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. . I REPORT PERIOD: July 1993 [
t DAY POWER DAY POWER i
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I 1,011 17 -1,061 '!
2 1,002 18 972 [
a 3 991 19 1,056 1,053 !
4 1,044 20
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5 1,051 21 1,051'
..q 6 1,049. 22 998 .
7 1,025 23 1,043' 1 8 1,052 .24 1,007 e i
9 1,063 25 1,050 ,
10 1,052 26 1,060 'j 11 1,033 27- II,059 :
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- 12. 968 28 1,058 l 13 903 29 952 ,
14 1,043 30 989 q 5
15 986 31 3,027 .
16 1,030 -
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a TABLE 3 .
E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%
(UNIT 1)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCH4ENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYt4CD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)
(None)-
SUbt4ARY OF OPERATION:
The unit remained on-line at high power throughout the month. Several minor power reductions were required during the month due to system loading, maintenance and surveillance activities.
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-v LASALLE NUCLEAR POWER STATION .
UNIT 2 140NTHLY PERFORMANCE REPORT JULY 1993- ,
t Col 4CNWEALTH EDISON COMPANY NRC DOCKET No. 050-374 LICENSE NO. NPF-18 i
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I TABLE OF CONTENTS (UNIT 2) l I. INTRODUCTION f II. REPORT l A. SU}4aRY OF OPERATING EXPERIENCE '
B. AME:NDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS
-t C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS ;
E. DATA TABULATIONS i I. Operating Data Report ;
- 2. Average Daily Unit Power Level i
- 3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS
- 1. Main Steam Safety Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-Sice Dose calculation Manual Changes
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indicstions of Failed Fuel Elements ;
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I. INTRODUCTION (UNIT 2) if The LaSalle County Nuclear Power Station is'a two-Unit facility. j 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 j nan-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. j i
Unit two was issued operating license number NFF-18 on December 16, j 1983. Initial criticality was achieved on March 10,.1984 and .i commercial power operation was commenced on October 19, 1984. ,
This report was compiled by Michael J. Cialkowski, telephone number l (815)357-6761, extension 2427.
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I II. MONTHLY REPORT i
A. SUMtGRY OF OPERATING EXPERIENCE (Unit 2)
L g Time Event 1 0000 Reactor critical, Generator on-line at 1045 Mwe, power level being reduced to 900 Mwe due to system load.
1000 Increased power level to 1115 Mwe. l 2 0300 Reduced power level to 940 Mwe due to system load. '
1300 Increased power level to 1115 Mwe. ,
3 0630 Reduced power level to 1000 Mwe due to system load.
1200 Increased power level to 1115 Mwe.
5 0530 Reduced power level to 750 Mwe due to system load.
1300 Increased power level to 1110 Mwe.
6 0230 Reduced power level to 1000 Mwe due to system load.
1200 Increased power level to 1115 Mwe. -
7 0300 Reduced power level to 1000 NMe due to system load.
1200 Increased power level to 1115 Mwe.
2000 Reduced power level to 1000 Mwe to place the 'C' circulating Water pump out of service.
8 0230 Reduced power J avel to 950 Mwe due to system load.
1200 Increased power level to 1110 Mwe. {
9 0600 Reduced power level to 1000 Mwe due to control rod 18-39 drifting. ,
0800 Increased power level to 1080 Mwe.
10 0200 Reduced power level to 850 Mwe to perform scram time testing on control rod 18-39.
1400 Increased power level to 1110 Mwe.
2330 Reduced power level to 700 Mwe due to feed water heater drain pump problenus.
11 1600 Increased power level to 1105 Mwe, 13 0200 Reduced power level to 850 Mwe due to system load.
1300 Increased power level to 1100 Mwe.
14 0300 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1100 Mwe.
17 0200 Reduced power level to 850 Mwe Due to system load.
1000 Increased power level to 1080 Mwe, 18 0430 Reduced power level to 1000 Mwe due to system load.
II, 2ONTHLY REPORT A'. SUteaRY OF OPERATING EXPERIENCE (Unit 2)
Day Time Event 18 0700 Increased power level to 1060 Hve.
20 0300 Reduced power level to 950 Mwe due to system load.
1100 Increased power level to 1050 Hwe.
21 0300 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1050 Mwe.
22 0100 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1050 Mwe.
24 0100 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1040 Mwe.
26 0330 Reduced power level to 850 Mwe due to system load.
r 1000 Increased power level to 1050 Mwe.
27 0400 Reduced power level to 950 Mwe due to system load.
1000 Increased power level to 1040 Mwe.
29 0300 Reduced power level to 850 Mwe due to system load.
1200 Increased power level to 1040 Mwe. i 30 0400 Reduced power level to 950 Mwe due to system load.
1000 Increased power level to 1040 Mwe.
P 2300 Reduced power level to 850 Mwe due to system load.
31 1000 Increased power level to 1035 Mwe. I 2400 Reactor critical, Generator on-line at 1025 Mwe.
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f B. AMEN 24ENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports)
(See Table 1)
D. LICENSEE EVENT REPORTS (Unit 2)
(None) {
E. DATA TABULATIONS (Unit 2)
- 1. Operating Data Report (See Table 2) ,
- 2. Average Daily Unit Power Level (see Table 3) ,
- 3. Unit shutdowns and significant Power Reductions (See Table 4) ,
F. UNIQUE REPORTING REQUIREMENTS (UNIT 2)
- 1. Safety Relief Valve Operations (None)
- 2. ECCS System Outages Note: The year and unit data has been removed from the outage l number.
OUTAGE NO. EQUIPMENT PURPOSE 0593 2E22-C002 Install interposing relays.
0618 2E51-D003 Repair steam line drain tap valve.
0698 2DG01K Install / remove cylinder testing equipment.
- 3. Changes to the Off-Site Dose Calculation Manual i (None)
- 4. Major Changes to Radioactive Waste Treatment Systems (None)
- 5. Indications of Failed Fuel Elements (None) u I
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. TABLE A (Unit 2)
MAJOR CORRECTIVE MAINTENANCE TO . +-
SAFETY-RELATED EQUIINENT
' NORK RESULTS AND EFFECTS
- REQUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L23299- Control Rod Drive Scram pilot valve Rod drifted from full Replaced diaphragm 1B-39 diaphragm out to full in (No SOR failures this month.)
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. TABLE.2
- E.1 OPERATING DATA REPORT
. DOCKET NO. 050-373 UNIT LASALLE TWO DATE August 10, 1993 COMPLETED BY M.J.CIALKOWSKI
' OPERATING STATUS TELEPHONE (815) 357-6761 1.' . REPORTING PERIOD: July 1993 GROSS HOURS IN REPORTING PERIOD: 744
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPENDABLE CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078
-3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
- 4. REASON FOR RESTRICTION (IF ANY):
THIS MONTH YEAR TO DATE CUMULATIVE-
- 5. REACTOR CRITICAL TIME (HOURS) 744.0 4,901.3 55,914.8
- 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 -1,716.9
- 7. . GENERATOR ON-LINE TIME (HOURS) 744.0 4,879.2 54,935.5
- 8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0'
- 9. THERMAL ENERGY GENERATED (MWHt) 2,341,910 15,597,368 165,612,255
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 776,180 5,269,685 55,-170,994-11.' ELECTRICAL ENERGY GENERATED (MWHe-Net) 748,873: 5,091,160 53,004,093
- 12. REACTOR SERVICE FACTOR (%) 100.0 96.3' 72.6 13 REACTOR AVAILABILITY FACTOR (%) 100.0 96.3 74.8' 14.. UNIT SERVICE FACTOR (%) 100.0 95.9 71.3
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- 15. UNIT AVAILIBILITY FACTOR (%) 100.0 95.9 .71.3
- 16. UNIT' CAPACITY FACTOR (USING MDC) (%) 97.'2 96'.6 66.4
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 93.4 92.8 63.8
'18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 11.6
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- 19. SilUTDOWNS SCHEDULED OVER . THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Refuel, 09/04/93, 11-Weeks
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
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DOCKET NO. 050-373.
. UNIT LASALLE TWO- l I': DATE August 10, 1993 l I
COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761
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REPORT PERIOD: July 1993 j u
DAY POWER DAY POWER i
1 1,020 17 1,006 i l
2 1,042 18 1,026- -f 3 1,057 19 1,026 f
1 4 1,063 20 1,001 'i 5 1,002 21 980 ;
6 1,046 22 977 .;
7 1,042 23 1,016 i 8 1,035 24 966 )
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.t 9 1,036 25 1,010 ;
-f 10 958 26 974 11 935 27 987 '
12 1,057 28 989 13 986 29 948-14 1,018 30 971 f 15 1,045 31 944 -
4 16 1,042
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'f TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%
(UNIT 2) '
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / Cot 4ENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NIMBER (YYMMDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)
(None)
StM4ARY OF OPERATION:
i Th2 unit remained on-line at high power throughout the month. Several minor power reductions were required during the month due to system loading, maintenance and surveillance activities.
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