ML20072E025
| ML20072E025 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/31/1994 |
| From: | Cialkowski M, Ray D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9408220080 | |
| Download: ML20072E025 (16) | |
Text
'.
O 2601 N.21st. Rd.
Commonwrith Edison LaSa!!e County Nuclear Station j
Marseilles. lilinois 61341 Telephone 815/357-6761 August 11,1994 U.S. Nuclear Regulatory Commission Document Control Desk Wah.inuton, D.C. 20555 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for July 'l994.
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D. J. ' Ray Station hianager LaSalle County Station DJR/tmb Enclosure cc:
John B. hfartin, Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project hianager - Washington, D.C.
GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Licensing Operations Director - Downers Grove Nuclear Fuel Services hianager - General Office Off Site Safety Review Senior Participant - Downers Grove INPO Records Center Station File i
l 100CED 940822coso 94o731
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PDR ADOCK 05000373 i
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i LASALLE NUCLEAR POWER STATION l
UNIT 1 MONTHLY PERFORMANCE REPORT JULY 1994 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11
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1 TABLE OF CONTENTS (UNIT 1)
I.
INTRODUCTION II.
REPORT A.
SUMMARY
OF C'ERATINO ZIPERIENCE B.
AMENDHENi; 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 REPORTINO 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.
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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II.
MONTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
Egg Time Event
'l 0000 Reactor critical, Generator on-line at 160 Mwe.
3 1445 Power level at 320 Mwe.
5 0250 Power level at 480 Mwe.
0336 Reactor scram due to reactor water level control signal loss to the
'1B' turbine driven reactor feed pump.
6 0320 Reactor critical.
7 0645 Generator on-line at 77 Mwe.
1655 Power level at 340 Mwe.
2141 Power level at 540 Nwe.
8 1000 Reactor scram due to a feedwater signal spike.
10 1835 Reactor critical.
11 2116 Generator on-line at 34 Mwe.
12 0200 Power level at 340 Mwe.
25 0500 Power level at 860 Mwe.
26 0300 Power level at 1118 Mwe.
27 0200 Reduced power level to 890 Nwe to perform a rod set.
j 1100 Increased power level to 1120 Nwe.
31 0600 Reduced power level to 995 Mwe due to system load.
2400 Reactor critical, generator on-line at 1118 Mwe.
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1 B.,
ANENDNENT3 TO THE FACILITY OR TECHNICAL EPECIFICATION (None) j C.
LICENSEE EVENT REPORTS (Unit 1) 1 LER Number Date Descriction 94-010 07/05/94 Reactor scram due to reactor water level i
control signal loss to the '1B' turbine l
driven reactor feed pump.
]
94-011 07/08/>4 Reactor scram due to a feedwater signal spike.
l 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 REQUIRENENTS (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) l i
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TABLE 1 0.1 OPERATING DATA REPORT DOCKET NO. 050 373 UNIT LA$ALLE ONE DATE August 10, 1994 COMPLETED 8Y M.J. CIALK0WSKI TELEPHONE (815) 357-6761 OPESATING STATUS 1.
DEPORTING PERIOD:
July 1994 GROS $ HOURS IN REPORTING PERIOD 744 3.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323 MAX DEPEND CAPACITY (MWe Net):
1,036 DESIGN ELECTRICAL RATING (MWe-N 1,078 i
3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
4.
REASONS FOR RESTRICTION (IF ANY):
REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE 5.
REACTOR CRITICAL TIME (HOURS) 663.7 1,813.7 63,140.6 6.
DEACTOR RESERVE $HUTDOWN TIME (HOURS) 0.0 0.0 1,641.2'
- 7.'
GENERATOR DN LINE TIME (POURS) 609.6 1,630.1 61,643.8 8.
UNIT RESERVE $HUTDOWN TIME (HOUR $)
0.0 0.0 1.0 9.
7HERMAL ENERGY GENERATED (MWHt) 1,099,117 4,111,720 181,437,357
.10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 334,093 1,345,401 60,599,772
- 11. 2LECTRICAL ENERGY GENERATED (MWHe Net) 317,969 1,254,876 58,103,630
-12. DEACTOR $ERVICE FACTOR (%)
89.2 35.7 68.1
- 13. REACTOR AVAILABILITY FACTOR (%)
89.2 35.7-69.8
-14. UNIT SERVICE FACTOR (%)
81.9 32.0
.66.4 15.- UNIT AVAILIBILITY FACTOR (%)
81.9 32.0 66.4
- 16. UNIT CAPACITY FACTOR (U$ LNG MDC) (%)
41.3 23.8 60.4
.17. UNii CAPACITY FACTOR (USING DESIGN MWe) (%)
39.6 22.9 58.1 1
- 18. UNIT f 0RCED OUTAGE FACTOR (%)
18.1 33.0 8.4
)
- 19. $HUTDOWNS $CHEDULED DVER THE NEXT 6 MONTH $ (TYPE, DATE, AND DURATION OF EACH):
20.. !F $HUTDOWN AT END OF REPORT PER100, ESTIMATED DATE OF STARTUP:
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DOCKET NO. 050-373 TABLE 2 UNIT LASALLE ONE D2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)
DATE August 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 l
REPORT PER100:
July 1994 DAY POWER DAY POWER 1
142 17 302
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2 220 18 307 3
286 19 305 4
280 20 302 5
43 21 302 6
-12 22 309 j
7 197 23 497 8
219 24 861 9
12 25 846 10
-12 26 1,069 11 1
27 1,034 12 267 28 1,0 75 13 298 29 1, 0 73 14 312 30 1,068 15 306 31 1,059 16 306
TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS >'20%
(UNIT 1)
NETHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COBSENTS EEQUENTIAL DATE
.F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYleEDD)
S: SCHEDULED (HOURS)
REASON REDUCING POWER applicable) 6 940705 F
23.7 A
3 Reactor scram due to loss of the reactor water level control.
(LER # 94-010)
-7 940708 F
56.6 H
3 Reactor scram due to a feedwater signal spike.
(LER # 94-011)
SUNNARY OF OPERATION:-
The unit. entered the month at low power following a return to service from a scheduled refueling outage.
The unit was ramping up in power when on 07/05/95 a reactor scram occurred due to reactor water level control nignal loss. The unit was returned to service on 07/07/94. The unit was again ramping up in power when a second reactor ceram occurred on 07/08/94 due to a feedwater signal spike. The unit was returned to service on 07/11/94.
The unit ramped up in power and remained at high power for the remainder of the month.
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l LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT JULY 1994 j
COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 f
1 I
k TABLE OF CONTENTS I
(UNIT 2) l l
I.
INTRODUCTION II.
REPORT i
A.
SUNNARY OF OPERATING EXPERIENCE B.
ANENDNENTS 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 REQUIRENENTS 1.
Nain Steam Safety Relief Valve Operations 2.
Najor Changes to Radioactive Maste Treatment System 3.
Static O-Ring Failures 4.
Off-Site Dose Calculation Nanual changes i
i
=
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 Wegawatts. Waste heat is rejected to a l
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 complied by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.
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1 II.
MONTHLY REPORT
+
A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 2)
Day Z13e Event i
1 0000 Reactor critical, Generator on-line at 1130 Nwe.
10 0600 Reduced power level to 890 Mwe due to system load.
1200 Increased power level to 1125 Mwe.
11 0300 Reduced power level to 970 Nwe due to system load.
0900 Increased power level to 1125 Nwe.
18 0400 Reduced power level to 1000 Mwe due to system load.
1000 Inreased power level to 1118 Mwe.
24 0700 Reduced power level to 860 Mwe due to system load.
1100 Increased power level to 1118 Nwe.
31 2400 Reactor critical, Oenerator on-line at 1118 Nwe.
B.
AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)
C.
LICENSEE EVENT REPORTS (Unit 2)
(None)
D.
DATA TABULATIONS (Unit 2) 1.
Operating Data Report (See Table 1)
I 2.
Average Daily Unit Power Level (See Table 2) 3.
Unit Shutdowns and Significant Power Reductions (See Table 3)
E.
UNIQUE REPORTINO REQUIREMENTS (UNIT 2) 1.
Safety Relief Valve Operations (None) 2.
Major Changes to Radioactive Waste Treatment Systems (None) 3.
Static O-Ring Failures l
(None) l 4.
Changes to the Off-site Dose calculation Manual (None) t
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TABLE 1 0.1 OPERATING DATA REPORT DOC %ET No. 050 374 UNIT LASALLE TWO DATE August 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 OPERAllNG STATUS 1.
REPORTING PERl00:
July 1994 GRob$ HOURS IN REPORilNG PERIOD 744 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323 MAX DEPEND CAPACITY (MWe Net):
1,036 DESIGN ELECTRICAL RATING (MWe-Net):
1,078
~ 3.
POWER LEVEL TO WHICH RESTRICTED (If ANY) (MWe Net):
6.
REASONS FOR RESTRICTION (IP ANY):
REPORTING PERICO DATA THIS MONTH YEAR TO DATE CUMULATIVE
-5.
SEACTOR CRITICAL TIME (HOURS) 744.0 4,778.1 61,703.7 6.
DEACTOR RESERVE SHUT 00WN TIME (HOURS) 0.0 0.0 1,716.9 7.
GENERATOR DN LINE i!ME (HOURS) 744.0 4,692.4 60,574.7 8.
UNIT RESERVE SHUT 00WN TIME (HOURS) 0.0 0.0 0.0 9.
THERMAL ENERGY GENERATED (MWHt) 2,460,123 15,060,126 183,160,579
- 10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 826,549 5,117,166 61,101,806
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 799,162 4,960,373 58,716,264
- 12. REACTOR SERVICE FACTOR (%)
100.0 93.9 71.9
- 13. REACTOR AVAILABILITY FACTOR (%)
100.0 93.9 73.9
- 14. UNIT SERVICE FACTOR (%)
100.0 92.2 70.6
- 15. UNIT AVAILIBILITY FACTOR (%)
100.0 92.2 70.6
- 10. UNIT CAPACITY FACTOR (US!NG MDC) (%)
103.7 94.1
-66.1
- 17. UN!i CAPACITY FACTOR (USING DESIGN MWe) (%)
99.6 90.5 63.5
- 18. UNIT FORCED OUTAGE FACTOR (%)
0.0 2.3 10.8
- 19. SMUIDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)2
- 20. IF SHUTDOWN AT END OF REPORT PER100, ESTIMATED DATE OF STARTUP:
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DOCKET NO. 050 374 TABLE 2 UNIT L4SAll8 TWO 0.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Wet)
DATE August 10, 1994 COMPLETED BY M.J. CI ALK0WKI TELEPHONE (815) 357 676) i i
REPORT PERIOD:
July 1994 OAY POWER DAY POWEA J
1 1,083 17 1,074 2
1,086 18 1,057 3
1,085 19 1,074 4
1,084 20 1,075 5
1,081 21 1,074 6
1,074 22 1,079 7
1,072 23 1,077 8
1,075 24 1,050
)
9 1,080 25 1,074 10 1,045 26 1,078 11 1,055 27 1,079 12 1,080 28 1,079 13 1,079 29 1,075 14 1,078 30 1,070 15 1,078 31 1,073 1
16 1,075
3 TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%
(UNIT 2)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS ETEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YY)SEDD)
St SCHEDULED
-(HOURS)
REASON REDUCING POWER applicable)
(None)
SUMMARY
OF OPERATION:
The unit remained on-line at high power throughout the month. Minor reductions in power were required due to system loading.
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