ML20045H037
| ML20045H037 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/30/1993 |
| From: | Cialkowski M, Schmeltz J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9307160271 | |
| Download: ML20045H037 (20) | |
Text
. _ _ - - _ _
Commonwe:lth Edison LaSalle County Nuclear Station j.*
r 2601 N. 21st. Rd.
Marseilles, Illinois 61341
- Telephone 815/357-6761 July 9, 1993 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission
. Mail Station Pl-137 Washington, D.C.
20555 ATTN: Document Control Desk Gentlemen:
Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for June 1993.
Very truly yours i
b we, ' -
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sJoseph V.
Schmeltz Station Manager LaSalle County Station
)
Enclosure xc:
A.
B.
Davis, NRC, Region III D.
E.
Hills, NRC Resident Inspector LaSalle J.
L.
Roman, IL Dept. of Nuclaar Fafety B.
Stransky, NRR Project Manager M.
J.
Wallace, CECO i
D.
L.
Farrar, CECO INPO Records Center D.
R.
Eggett, NED P,
D.
Doverspike, GE Resident T.
K.
Schuster, Manager of Nuclear Licensing T.
A.
Rieck, Nuclear Fuel Services Manager J.
E, Lockwood, Regulatory Assurance Supervisor l
W.
P.
Pietryga, QA/NS Off Site Review i
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Station File 9307160271 930630 Uh d k I
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JUNE 1993 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 i
LICENSE NO. NPF-11 I
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TABLE OF CONTENTS j
(UNIT 1).
1 I.
INTRODUCTION
.]
II, REPORT
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A.
SU144ARY OF OPERATING EXPERIENCE B.
AMEND!ENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D.
LICENSEE EVENT REPORTS E.
DATA TABULATIONS I
1.
Operating Data Report 2.
Average Daily Unit Power Level
]
3.
Unit Shutdowns and Power Reductions F.
UNIQUE REPORTING REQUIREMENTS 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 i
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INTRODUCTION (UNIT 1)
The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison Company and located near NMrseilles, 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 1
pond using the Illinois river for make-up and blowdown. The J
architect-engineer was Sargent and Lundy and the contractor was
'l 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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II. MONTHLY REPORT-A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
Day Time Event 1
0000 Reactor critical, Generator on-line at 1050 Mwe.
0200 Reduced power level to 850 Mwe due to > stem load.
0900 Increased power level to 1125 Mwe.
2 0200 Reduced power level to 900 Mwe due to system load.
1300 Increased power level to 1125 Mwe.
3 0200 Reduced power level to 850 Mwe due to system load.
1100 Increased power level to 1125 Mwe.
4 0100 Reduced power level to 1000 Mwe due to system load.
1100 Increased power level to 1125 Mwe.
6 0700 Reduced power level to 850 Mwe due to system load.
1500 Increased power level to 1120 Mwe.
7 0130 Reduced power level to 900 Mwe due to system load.
1400 Increased power level to 1120 Mwe.
8 0000 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1120 Mwe.
9 0300 Reduced power level to 900 Mwe due to system load.
1000 Increased power level to 1120 Mwe.
12 0030 Reduced power level to 850 Mwe due to system load.
1200 Increased power level to 1110 Mwe.
13 0100 Reduced power level to 850 Mwe due to system load.
1130
-Increased power level to 1110 Mwe.
14 0000 Reduced power level to 950 Mwe due to system load.
1000 Increased power level to 1110 Mwe.
16 0030 Reduced power level to 850 Mwe due to system load.
1100 Increased power level to 1115 Mwe.
17 0400 Reduced power level to 950 Mwe due to system load.
1000 Increased power level to 1115 Mwe.
19 0300 Reduced power level to 895 Mwe due to system load.
1000 Increased power level to 1115 Mwe.
20 0400 Reduced power level to 850 Mwe due to system load.
1200 Increased' power level to 1115 Mwe.
21 0100 Reduced power level to 850 Mwe due to system load.
5 II. MONTULY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
Day Time Event 21.
0900 Increased power level to 1105 Mwe.
22' 0200 Reduced power level to 850 Mwe due to system load.
l 1000 Increased power level to 1110 Mwe.
23 0200 Reduced power level to 850 Mwe due to system load.
1000 increased power level to 1105 Mwe.
26 0000 Reduced power level to 850 Mwe due to system load.
1100 Increased power level to 1105 Mwe.
27 0000 Reduced power level to 850 Mwe due to system load.
1100 Increased power level to 1105 Mwe.
28 0300 Reduced power level to 1025 Mwe due to system load.
0700 Increased power level to 1110 Mwe.
29 0030 Reduced power level to 850 Mwe due to system load.
1100 Increased power level to 1110 Mwe.
30 0030 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1110 Mwe.
2400 Reactor critical, Generator on-line at 900 Mwe, power level being reduced due to system load.
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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)
(None)
{
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 I
(None)
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2.
ECCS System Outages Note: The year and unit data has been removed from the outage number.
OUTAGE NO.
EQUIPMENT PURPOSE 0429 lE51-C003 Replace motor contactor at f
MCC.
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0506 lE51-C004 Check valve repair.
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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) 4
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-TABLE 1.
E.1 OPERATING DATA REPORT'
..q DOCKET NO. 050-373-
' UNIT LASALLE ONE DATE July 9, 1993
.. COMPLETED BY.M.'J.CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357_6761 June 1993-I.
REPORTING PERIOD:
GROSS HOURS IN REPORTING PERIOD:
720 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) 720.0 3,502.2 57,426.9
-'6.
. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2" 7.
GENERATOR ON-LINE CIME (HOURS) 720.0 3,232.8 56,140.4 8.
UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0'
". THERMAL ENERGY GENERATED-(MWHt) 2,281,520 9,891,118 164,951,276
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 761,052 3,303,593 55,095,942
- 11. ELECTRICAL ENERGY GENERATED-(MWHe_ Net) 735,419 3,178,765 52,826,855
- 12. REACTOR SERVICE FACTOR (%)-
100.0 80.6 69.0
- 13. REACTOR AVAILABILITY FACTOR (%)
100.0.
80.6 70.9
-14. UNIT SERVICE FACTOR (%)
100.0 74.4 67.4
- 15. UNIT AVAILIBILITY FACTOR (%)
100.0 74.4 67.4
- 16. UNIT CAPACITY FACTOR (USING MDC) (%)
98.6 70.6 61.2
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 94.8
'67.9 58.8
- 18. UNIT FORCED OUTAGE FACTOR (%)
0.0 11.0 7.2
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
.No Outages Scheduled
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
TABLE 2 E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)
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DOCKET NO. '050-37 3
-UNIT LASALLE ONE I
DATE July 9, 1993 COMPLETED BY M.J. CIALKOWSKI TELEPHONE ( 815 )-3 57_67 61 REPORT PERIOD: June 1993 DAY POWER DAY POWER 1
1,028 17 1,035 2
1,011 18 1,072 3
1,013 19 1,033
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1,063 20 995 5
1,083 21 996 6
1,009 22 991 7
983 23 993 8
985 24 1,061 9
1,024 25 1,067 f
f 10 1,083 26 997 11 1,065 27 991
-12 977 28 1,052 13 976 29 972 14 1,041 30 992 15 1,061 31 16 993 i
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.s TABLE 3 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%
(UNIT 1)
.. l METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCtedENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD)
S: SCHEDULED MOURS)
REASON REDUCING POWER applicable)
' (None) l SUF24ARY OF OPERATION:
f f-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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k LASALLE NUCLEAR POWER STATION UNIT 2 MONTULY PERFORMANCE REPORT JUNE 1993 ComONWEALTH EDISON COMPANY l
1 NRC DOCKET No. 050-374 i
LICENSE NO. NPF-18 i
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.i TABLE OF CONTENTS (UNIT 2)
I.
INTRODUCTION II.
REPORT A.
SUMMARY
OF OPERATING EXPERIENCE B.
AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS 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 r
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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4 I.
INTRODUCTION (UNIT 2)
The LaSalle County Nuclear Power Station is a two-Unit facility-owned by Commonwealth Edison Company and located near Marsellies, 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 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 Ndchael J.
Cialkowski, telephone number (815)357-6761, extension 2427.
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II. MbNTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 2)
Day Time Event 1
0000 Reactor sub-critical, Generator off-line, maintenance outage in progress.
6 0445 Reactor critical.
2350 Generator on-line.
7 1400 Increased power level to 400 Mwe, upshifted Reactor Recirculation pumps.
1900 Power level held at 610 Mwe due to system load.
8 1300 Increased power level to 1110 Mwe.
9 0300 Reduced power level to 750 Mwe for rod set.
0500 Increased power level to 850 Mwe, power level held due to system load.
2100 Increased power level to 1128 Mwe.
10 0100 Reduced power level to 850 Mwe due to system load.
1400 Increased power level to 1125 Mwe.
11 0200 Reduced power level to 925 Mwe due to system load.
1100 Increased power level to 1110 Mwe.
12 0200 Reduced power level to 950 Mwe due to system load.
1100 Increased power level to' 1120 Mwe.
13 0100 Reduced power level to 850 Mwe due to system load.
1030 Increated power level to 1120 Mwe.
15 0130 Reduced power level to 850 Mwe due to system load.
1230 Increased power level to 1120 Mwe.
16 0200 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1120 Mwe.
17 0400 Reduced power level to 950 Mwe due to system load.
1100 Increased power level to 1120 Mwe.
19 0200 Reduced power level to 900 Mwe due to system load.
0900 Increased power level to 1115 Mwe.
20 0400 Reduced power level to 850 Mwe due to system load.
1200 Increased power level to 1115 Mwe.
21 0230 Reduced power level to 850 Mwe due to system load.
0900 Increased power level to 1115 Mwe.
22 0300 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1115 Mwe.
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II. MONTHLY REPORT A.
SUMt4ARY OF OPERATING EXPERIENCE (Unit 2)
Day Time Event 23 0200 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1110 Mwe.
24 0400 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1115 Mwe.
25 0400 Reduced power level to 890 Mwe due to system load.
1200 Increased power level to 1115 Mwe.
26 0400 Reduced power level to 850 Mwe due to system load.
1100 Increased power level to 1110 Mwe.
27 0300 Reduced power level to 850 Mwe due to system load.
1400 Increased power level to 1115 Mwe.
28 0100 Reduced power level to 760 Mwe due to system load.
1200 Increased power level to 1115 Mwe.
29 0100 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1115 Mwe.
30 0100 Reduced power level to 850 Mwe due to system load.
1000 Increased power level to 1115 Mwe.
2400 Reactor critical, generator on-line at 1045 Mwe, power level being reduced due to system load.
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AMENDMENTS 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)
LER Number Date Description 93-004-00 06/04/93 Reactor scram due to low Control Rod Drive charging water header pressure.
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 number.
OUTAGE No.
EQUIPMENT PURPOSE 0475 2E12-F041A Replace Limit switches.
3.
Changes to the Off-site Dose Calculation Manual (None) 4.
Major Changes to Radioactive Waste Treatment Systems (None) 5.
Indications of Failed Fuel Elements (None) i i
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r C. TABLE 1 (Unit 2)
MAJOR CORRECTIVE MAINTENANCE To SAFETY-RELATED EQUIPMENT WOPA RESULTS AND EFFECTS REQUEST CCMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION COPJtECTIVE ACTION L22412 Reactor Recirc Mechanical pump seal Pump seal leakage Replaced pump seal 2B33-C001A L22844 Residual Heat Limit switch Inaccurate indication Replaced limit switch Removal Testable Check Valve
-2E12-F041A L22857 Intermediate Voltage pre-regulator IRM
'H' Failed during Replaced pre-regulator
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. Range Monitor surveillance testing Channel
'H' L22874 Control Rod Transponder card Reactor Manual Control Replaced transponder Drive 34-39 System tripping when card control rod selected t
(No SOR failures this month.)
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TABLE 2-E.1 OPERATING. DATA REPORT DOCKET NO. 050-373 UNIT LASALLE TWO DATE July 9, 1993.
COMPLETED BY M.J.CIALKOWSKI
' OPERATING STATUS TELEPHONE (815) 357-6761 1.
REPORTING PERIOD:
June 1993 GROSS HOURS IN REPORTING PERIOD:
720
'2.
. CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323
- )
MAX DEPENDABLE CAPACITY (MWe-Net):
-1,036 DESIGN ELECTRICAL RATING (MWe-Net):
1,078 t
3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
4.
REASON FOR RESTRICTION (IF ANY):
THIS MONTH YEAR TO DATE
. CUMULATIVE
'51 REACTOR CRITICAL TIME (HOURS) 595.3 4,157.3 55,170.8
-6.
REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 7.
GENERATOR ON-LINE TIME (HOURS) 576.2 4,135.2 54,191.5 8.
UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 9.
TIIERMAL ENERGY GENERATED (MWHt) 1,761,377 13,255,458 163,270,345
- 10. ELECTRICAL ENERGY GENERATED ( W Me-Gross) 585,058 4,493,505 54,394,814
- 11. ELECTRICAL ENERGY GENERATED (MWHe_ Net) 563,314 4,342,287 52,255,220
- 12. REACTOR SERVICE FACTOR (%)
82.7 95.7 72.3
- 13. REACTOR AVAILABILITY FACTOR (%)
82.7 95.7 74.'6 I4. UNIT SERVICE FACTOR (%)
80.0 95.2 71.1
- 15. UNIT AVAILIBILITY FACTOR (%)
80.0 95.2 71.1
- 16. UNIT CAPACITY FACTOR (USING MDC) (%)
75.5 96.5 66.1
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 72.6 92.7 63.6
'18. UNIT FORCED OUTAGE FACTOR (%)
0.0 0.0 11.8
- 19. SHUTDOWNS 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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TABLE 3
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AVERAGE DAILY UNIT POWER LEVEL.(MWe 3et)
E.2 DOCKET NO. 050-373 UNIT LASALLE TWO DATE July 9, 1993 COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761 REPORT PERIOD: June 1993 DAY POWER DAY POWER 1
-11 17 1,039 2
-12 18 1,069 3
-11 19 1,022 4
-12 20 992 5
-12 21 1, 01"/
6
-12 22 1,008 7
349 23 998 8
888 24 1,029 9
982 25 1,026 10 1,016 26 1,015 11 1,037 27 971 12 1,031 28 981 13 995 29 1,005 14 1,075 30 1,002 15 984 31 16 1,010
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TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%
(UNIT 2)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / Cot 44ENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYFNDD)
S: SCHEDULED (HOURS)
. REASON REDUCING POWER applicable) 1 930529 S
143.8 B
2 Maintenance outage SUbt4ARY OF OPERATION:
The unit started the month off-line due to a scheduled maintenance. outage. The unit was returned to service on 06/06/93. The unit remained on-line at high power for the remainder of the month. Several minor power reductions were required due to system leading, maintenance and surveillance activities.
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