ML20036B277
| ML20036B277 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/30/1993 |
| From: | Cialkowski M, Spedl G COMMONWEALTH EDISON CO. |
| To: | NRC |
| References | |
| NUDOCS 9305180438 | |
| Download: ML20036B277 (19) | |
Text
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- i C:mm2nw:cith Edison LaSalle County Nuclear Station Rural Route #1, Box 220
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i Marseilles, Illinois 61341 Telephone 815/357-6761 l
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May 10, 1993 t
Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-137 Washington, D.C.
20555 ATIN: Document Control Desk Gentlemen i
Enclosed for your infonaation is tbc monthly performance report covering _
LaSalle County Nuclear Power Station for April 1993.
r Very truly yours f
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Gary F. Spe 1 Station Manager LaSalle County Station Enclosure xc:
A. D. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety B. Stransky, NRR Project Manager i
M. J. Wallace, CECO 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
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W. P. Pietryga, OA/NS Off Site Review Station File
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9305180438 930430 PDR ADOCK 05000373
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LASALLE NUCLEAR IOIER STATICN UNIT 1 MCETHLY PERFORMANCE REPORT APRIL 1993 CCMMCMWEALTH EDISCM C(MPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 5
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TABLE OF CGITENTS (UNIT 1) f I.
INTRODUCTIGt l
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REPORT h
A.
SUBMARY OF OPERATING EEPERIENCE i
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ADMENDBERTS TO FACILITY LICENSE OR TECINICAL SPECIFICATIGIS l
I C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPBG3tT i
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LICENSEE EVENT REPORTS i
E.
DATA TABULATIGtS 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 Operat2ons' j
2.
ECCS System Outages j
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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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INTRODUCTICM (UNIT 1) ne LaSalle County Nuclear Power Station is a two-Unit facility owned ~
by Commonwealth Edison Company and located near Marsellies, Illinois.
Each unit is a Bolling Mater Reactor with a designed met electrical output of 1078 Megawatts. Maste heat is rejected to a man-made j
cooling pond using the Illinois river for make-up and blowdown. The j
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 commmenced on January 1, 1984.
I This report was complied by Michael J. Cialkowski, telephone number j
(815)357-6761, extension 2427.
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f II. MONTELI REPORT L
s SUDMARY OF OFERATICG EKFERIENCE (Unit 1)
A.
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Day IiMM EYR t 1
0000 Reactor critical, Generator on-line at 1000 Mwe, j
main turbine testing in progress.
i 0600 Increased power level to 1135 Mwe.
2400 Reduced power level to 1000 Mwe to perform main turbine testing.
2 0130 Increased power level to 1100 Mwe.
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0200 Reduced power level to 750 Mwe to perform rod set.
1200 Increased power level to 1130 Mwe.
11 0100 Reduced power level to 990 Mwe due to system load.
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1100 Increased power level to 1135 Mwe.
13 0200 Reduced power level to 995 Mwe to perform weekly surveillances.
I 2000 Increased power level to 1130 Mwe.
14 0500 Reduced power level to 1000 Mwe due to low condensate pump suction pressure.
15 0100 Reduced power level to 600 Mwe to transfer the condensate pumps.
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16 2200 Increased power level to 1130 Mwe.
i 18 0230 Reduced power level to 900 Mwe due to system load.
i 1200 Increased power level to 1135 Mwe.
i 20 0100 Reduced power level to 900 Mwe due to system Joad,
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performed weekly surveillances.
1300 Increased power level to 1130 Mwe.
21 0400 Reduced power level to 960 Mwe due to system load.
f 1100 Increased power level to 1130 Mwe.
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t 22 0030 Reduced power level to 950 Mwe due to system load.
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1100 Increased power level to 1130 Mwe.
i 1600 Reduced power level to 1070 Mwe due to system load.
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,4 II. DOITELY REPORT 3
A.
SUBMARY OF OFERATICG EEPERIENCE (Unit 1) l 1
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day Time Rygst j
22 22'20 Increased power level to 1130 Mwe.
I 23 0200 Reduced power level to 850 Mwe due to system load.
0600 Increased power level to 1120 Mwe.
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0840 Manual reactor scrasa due to a feedwater transient.
24 1245 Reactor critical.
2000 Generator on-line at 100 Mwe.
f 2300 Increased power level to 200 Mwe.
1 25 0900 Increased power level to 800 Mwe.
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26 0800 Increased power level to 1000 Mwe.
i 1130 Reduced power level to 850 Mwe, performed rod set.
l 2000 Increased power level to 1125 Mwe.
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28 0030 Reduced power level to 750 Mwe, performed rod set.
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1200 Increased power level to 1125 Mwe.
30 2400 Reactor critical, Generator on-line at 1125 Mwe.
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AIGENDNElfTS 70 THE FACILITY OR TECIREICAL SPECIFICATIN l
(None)-
C.
MAJOR CORRECTIVE MAINTENANCE 'ID SAFETY-RELATED EQUII9ENT (None)
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SOR differential pressure switch failure reports (None) i D.
LICENSEE EVENT REPORTS (Unit 1) t LER Numiber DALc Dnscription 1
93-010-00 04/14/93 Diesel generator cooling water pump automatic l
trap.
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f 93-011-00 04/23/93 Manual reactor scram due to a loss of feedwater feedwater during a feedwater heater transient.
L E.
DATA TABULATIGIS (Unit 1) i 1.
Operating Data Report (See Table 1) j 2.
Average Daily Unit Power Level (See Table 2) j l
3.
Unit Shutdowns and Significant Power Reductions (See Table 3)
F.
UNIQUE REPORTING REQUIREMENTS (UNIT 1) t
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Safety Relief Valve Operations j
(None)
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2.
ECCS System Outages T
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Note: The year and unit data has been removed from the outage number.
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.QUIAGE MQ1 SQQHIElfT PURPDSB 0374 1E51--C003 Pump replacement 3.
Changes to the Off-Site Dose Calculation Manual (None) i 4.
Major Changes to Radioactive Naste Treatment Systems
.j (None) f S.
Indications of railed Fuel Elements (None) 1 b
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TABLE 1 E.1 OPERATING DATA REPORT l
h DOCRET NO. 050_373 l
UNIT LASALLE ONE
.l DATE May 10, 1993 COMPLETED BY M.J.CIALROWSRI-OPERATING STATUS TELEPHONE (815) 357-6761
'1.. REPORTING PERIOD:
April 1993 l
GROSS HOITRS IN REPORTING PERIOD:
719 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323 l
MAX DEPENDABLE CAPACITY (MWe_ Net):
1,036
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DESIGN ELECTRICAL RATING (MWe-Net):
1,078 I
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3.
POWER L3 VEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
N/A I
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REASON FOR RESTRICTION (IF ANY):
THIS MONTH YEAR TO DATE CUMULATIVE
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REACTOR CRITICAL TIME (HOURS) 690.9 2,038.2 55,962.9 t
6 REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 f
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GENERATOR ON-LINE TIME (HOURS) 683.7 1,768.8 54,676.4 i
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UNIT RE5trTOE SHUTDGCI TIME (HOURS) 0.0 0.0 1.0 i
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THERMAL ENERGY GENERATED (MWHt) 2,166,637 5,267,075 160,327,233
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 734,676 1,755,630 53,547,'979-
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 710,167 1,682,537-51,330,627 i
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-12. REACTOR SERVICE FACTOR (%)
96.1 70.8 68.4 1
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- 13. REACTOR AVAILABILITY FACTOR (%)
96.1 70.8 70.4 i
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- 14. UNIT SERVICE FACTOR (%)
95.1 61.4 66.8 "15. 1MIT AVAILIBILITT FACTOR (%)
95.1 61.4 66.8
- 16. UNIT CAPACITY FACTOR (USING MDC) (%)
95.3 56.4 60.0 I
- 17. UNIT CAPACITY TACTOR (USING DESIGN MWe) 91.6 54.2 58.2 l
IB. UNIT FORCED OUTAGE FACTOR (%)
4.9-18.4 7.3
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- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
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No Outages Schedu: N I
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE Or STARIUP:'
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TABLE 2 E.2 AVERAGE DAILY ITAIT POWER LEVEL (MWe-Net)
DOCKET NO. 050-373-UNIT LASALLE ONE DATE May 10, 1993.
COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761 l
REPORT PERIOD: April 1993 DAY POWER DAY PONER 1
1,085 17 1,092 i
2 1,081 18 1,038 l
3 1,089
-19 1,089 4
1,024 20 1,042 i
5 1,095 21 1,065
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1,091 22 1,042 l
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1,002 23 344
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U 1,091 24 14 t
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1,089 25 659 10 1,089 26 958 11 1,056 27 1,050 i
1.2 1,091 28 1,014
'l 13 1,056 29 1,089 14 985 30 1,088 15 989 31 16 1,094 I
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TABLE 3 E.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 20%
(UNIT 1) e i
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METHOD OF CORRECTIVE j
YEARLY-TYPE SHUTTING DONN ACTIONS /COBGENTS SEQUENTIAL DATE F: FORCED DORATIOt THE REACIDR OR (LER/DVR S if l
NUMBER
_LIIMMDD1
!i d CHEDELED LHQURS1.
REASON REDUCJNG_L9fER applicable.)
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930423 F
35.3 A
2 Manual reactor scram due to a feedwater heater transient.
(LERl93-011-00 DVR 501-01-93-0032)
SUtemRY OF OPERATION:
The unit entered the month on line at high power. The unit experienced a forced outage due to a feedwater heater transient. The unit was returned to service on 04/24/93, ror the remainder of the month the unit remained on-line at. high power. Several minor power reductions were, required during the month due to system loading, maintenance and surveillance activities.
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r LASATLE NUCLEAR POKER STATIQt i
UNIT 2 MNTHLY PERFORMANCE REPORT APRIL 1993 CDe4GfWEALTH EDISQt CCMPANY NEC DOCKET NO. 050-374 LICENSE NO. NPF-18
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j TABLE OF CNTENTS (UNIT 2) f I.
INTRODUCTIN l
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II.
REPORT j
f A.
SUleULEY OF OPERATING EKPERIENCE j
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B.
AMENDMENTS TO FACILITY LICENSE OR TECNICAL SPECIFICATINS l
l C.
MAJOR CORRECTIVE MAINTENANCE M SAFETY-RELATED EQUIPMENT h
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t D.
LICENSEE EVENT REPORTS t
E.
DATA TAIKILATIONS f
1.
Operating Data Report 2.
Average Daily Unit Power Level l
3.
Unit Shutdowns and Power Reductions l
i F.
UNIQUE REPORTING REQUIREMENTS f
1.
Main Steaun Safety Relief Valve Operations 2.
ECCS Systesa Outages f
3.
Off-Site Dose Calculation Manual Changes j
4.
Major Changes to Radioactive Maste. Treatment System i
5.
Indications of Failed Fuel Elements I
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INTRODUCTIGt (UNIT 2).
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The LaSalle County Nuclear Power Station is a two-Unit facility owned by Comunonwealth Edison Company and located near Marseilles, Illinois.
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Each unit is a Boiling Water Reactor with a designed net electrical
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output of 1078 Megawatts. Maste heat is rejected to a man-made l
cooling pond using the Illinois river for make-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was Comenonwealth Edison Company.
t Unit two was issued operating license number NPF-18 on Deces.aber 16, j
1983. Initial criticelity was achieved on March 10, 1984 and l
comunercial power operation was comumenced on October 19, 1984.
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This report was compiled by Michael J. Cialkowski, telephone number j
(815)357-6761, extension 2427.
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II. MGtrTrLY REPORT 1
A.
SUPMARY OF C?ERATICG EKPERIENCE (Unit 2)
Day Time EYnnt 1
0000 Reactor critical, Generator on-line at 1130 Mwe.
8 0030 Reduced power level to 900 Mwe, performed monthly surveillances and rod set.
10 2330 Reduced power level to 755 Mwe to perform a rod set.
12 1630 Increased power level to 1135 Mwe.
14 0030 Reduced power level to 995 Mwo to perform monthly surveillances.
1100 Increased power level to 1135 Mwe.
17 0245 Reduced power level to 1090 Mwe due to system load.
0800 Increased power level to 1135 Mwe.
21 0200 Reduced power level to 995 Mwe to perform monthly surveillances.
1200 Increased power level to 1135 Mwe.
25 0630 Reduced power level to 930 Mwe due to system load.
2330 Reduced power level to 900 Mwe due to system load.
26 1200 Increased power level to 1135 Mwe.
30 2400 Reactor critical, Generator on-line at 1127 Mwe.
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AMMENDMENTS *IO THE FACILITY OR TECHNICAL SPECIFICATICM -
(None)
C.
MAJOR CORRECTIVE MAINTENANCE *IO SAFETf-RELATED EQUII9ENT (including SOR differential pressure switch failure reports ).
(See Table 1)
D.
LICENSEE EVENT REPORTS (Unit 2)
(None)
E.
DATA TABULATICMS (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.-
QLTIAGE_NQ2 EOUIPRENT HIRPOSE 0304 2E22-S001 Repair / replace lockout relays 0327 2E12-D300A Repair line leak and megger motors 3.
Changes to the Off-Site Dose Calculation Manual (None) 4.
Major Changes to Radioactive Naste Treatment Systems (None) 5.
Indications of Failed Fuel Elements (None)
m C. TABLE 1 (Unit 2)
MAJC3 CORRECTIVE MAINTENANCE TO.
SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REQUEET
_CCBERONENT CAUSK_DLJEAIZDitC[IDN_
ESAF_E_PILANT_QRERATEIf __CQRRE_CILVE_ACII(35 L21536 High Pressure Core. Loss of sensing module Transmitter exhibited Replaced transmitter Spray Trip level fill oil a shift of 3%
Transmitter
- 2B21-N409A L22301 Diesel Room HVAC Overloat relay Vent fan breaker Replaced relay Supply Fan 2VD03C
' tripping 4
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(No SOR failures this month.)
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TABLE 2 E.1 OPERATING DATA REPORT i
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DOCKET NO. 050-373 4
f UNIT LASALLE TWO DATE May 10,'1993 COMPLETED BY M.J.CIALKOWSKI OPERATING STA7US TELEPHONE (815) 357-6761 t
i 1.
REPORTING PERIOD:
April 1993 i
GROSS HOURS IN REPORTING PERIOD:
719 l
s 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323 j
MAX DEPENDABLE CAPACITY (MWe-Net):
1,036 j
DESIGN ELECTRICAL RATING (MWe-Net):
1,078 l
3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
N/A i
4.
REASGi FOR RESTRICTIQi (IF ANY):
- f THIS MONTH YEAR TO DATE CUMULATIVE j
5.
REACTOR CRITICAL TIME (HOURS) 719.0 2,879.0
.53,892.5
-6.
REACTOR RESERVE SHUTDOWN TIME (HOURS)-
0.0 0.0 1,716.9 i
7.
GENERATOR ON-LINE TIME (HOURS) 719.0 2,879.0 52,935.4
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UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
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THERMAL ENERGY GENERATED (MWHt) 2,309,099 9,275,125 159,290,012
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- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 785,800 3,157,019 53,058,328 i
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- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 760,343 3,052,731 50,965,664 l
'12.' REACTOR SERVICE FACTOR (%)
100.0
.100.0 72.0-
- 13. REACTOR AVAILABILITY FACTOR (%)
100.0-100.0 74.3 14.' UNIT SERVICE FACTOR (%)
100.0 100.0 70.8-i 115. UNIT AVAILIBILITY FACTOR (%)
100.0 100.0
.70.8.
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- 16. UNIT CAPACITY FACTOR (USING MDC) (%)
102.1 102.3 65.8 I
- 17. UNIT CAPACITY TACTOR (USING DESIGN MWe) 98.1 98.4 63.2 i
LIB.' UNIT FORCED OUTAGE FACTOR (%)
- 0. 0 -
0.0 12.0 l
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- 19. SHUTDOWNS SCHEDULED OVER THE'NEXT.6 MONTHS'(TYPE, DATE, AND DURATION OF EACH)
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Refuel, 09/04/93, 11 Weeks
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- 20. IF-SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
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1 TABLE'3; E. 2 -
AVERAGE DAILY UNIT POWER LEVEL.(MWe-Net)
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r DOCKET NO. 050-373 UNIT LASALLE TWO I
DATE May 10, 1993 f
COMPLETED BY M.J. CIALKOWSKI
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TELEPHONE (815)-357-6761 l
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-l REPORT PERIOD: April 1993 l
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DAY POWER DAY POWER f
a 1
1,097 17 1,092 2
1,098
'18 1,096 l
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1,096 19 1,095 j
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1,050 20 1,095
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5 1,093 21 1,080 6
1,096 22 1,092 5
7 1,087 23 1,090 8
898 24 1,088
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9 918 25 950 I
r 10 915 26 1,037 11 903 27 1,091 l
12 1,013 28 1,094 j
f 13 1,091 29 1,093.
I 14 1,058 30 1,089 l
15 1,092 31
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.l 16 1,095 i
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TABLE 4 E.3 UNIT SHUTDONNS AND PONER REDUCTIONS > 20%
(UNIT 2)
METHOD OF CORRECTIVE YEARLT TYPE SHUTTING DONN ACTIONS /CONGDrIS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR S if NUMB.ER IIYMEDDJ E1_SmmDLED 1HQLTRS]_.
REASON REDUCING _EQWER AppliCDhle)
(None)
SusesARY Or OexRATION:
The unit remained on-line at high power throughout the month. Several minor power reductions were required due to system loading, maintenance and surveillance activities.
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