ML20099G106
| ML20099G106 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/31/1992 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9208140107 | |
| Download: ML20099G106 (26) | |
Text
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Comm:nw lth Edi:on i' LaSalle County Nuclear Station 2001 N. 21st. Rd.
MarSullies, Hlinois 61341 Telephone 815/357-6761 August 10, 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hall Station PI-137 Washington, D.C. 20555 ATIN: Document Control Desk Gentlemen:
Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for July 1992.
Very truly yours, G /f! ~ i -
G. J. Dieder ch fo/ Station Manager LaSalle County Station GJD/HJC/dj f Enclosure xt: A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Roman, Il Dept. of Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO D. L. Farrar. CECO INPO Records Center L. R. Eggett, NED P. D. Doverspike, GE Ruident T. J. Kovach, Hanager of Nuclear Licensing T. A. Ricck, Nuclear fuel Services Ma'iager J. E. Lockwood, Regulatory Assurance Supervisor H. P. Pietryga, QA/NS Off Site Review Station File
/ i ZCADTS/S [@8%O$goho0 3
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lASALLE HUCLEAR POWER STATION ,
UNIT 1 MONTHLY PERFORMANCE REPORT JULY 1992 COMMONHEALTH EDIS0N COMPANY NRC DOCKET NO. %)-373 LICENSE NO. NPF-11 r f.
I ZCADTS/5-
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TABLE Of CONTENTS (UNIT 1)
I. INTRODUCTION i
II. REPORT A.
SUMMARY
OF OPERATING EXPERIENCE B. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. RAJOR CORRECTIVE HAINTENANCE 10 SAFETY-RELATED EQUIPHENT D. LICENSEE EVENT REPORTS E. DATA TABULATION 3 1, Operating.0ata Report
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS
- 1. Main Steam Relief Valve Operations
- 2. ECCS System Outages
- 3. Of f-Site Dose Calculation Haraudi Changes
- 4. Major Changes to Radioactiva Haste Treatment System S. Indications of failed fuel Elements I
i ZCADTS/5- ,
I. INTRODUCTION (Unit 1)
The LaSalle County Muclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste 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 g,rimary construction contractor was Commonwealth Edison Company.
Unit One was issued operating license number NPF-11 on April 17, 1982. S Initial criticality was achieved on June 21, 1982 and connercial power operation was connenced on January 1.1984.
This report was compiled by !tichael J. Cialkowski, telephone number (815)357-6761, extension 2427.
I o
ZCADTS/5
l .' II. HONTHl.Y REPORT I
A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
DJuf lime Event . _ _ _
1 0000 Reactor critical, Generator on-line at 850 Hwe.
1100 Increased power level to 1095 Hwe (Unit in coastdown).
3 0100 Reduced power level to 850 Hwe due to system load.
12L5 Increased power level to 1100 Hwe.
1900 Reduced power level to 1000 Hwe due to system load.
2300 Reduced power level to 850 Hwe due to system load.
4 1300 Increased power level to 1090 Hwe.
2000 Reduced power level to 850 Hwe due to system load.
5 1100 Increased power level to 1060 Hwe.
2330 Reduced power level to 850 Hwe due to system load.
6 1400 Increased or>wer level to 1090 Hwe. .
2000 Reduced power icvel to 850 Hwe due to system load.
7 1200 Increased power level to 1075 Hwe.
1430 Reduceo power level to 975 Hwe due to trip of the 'IC' Circulating Hater Pump. Pump trip was caused by high differential pressure across the suction screen.
1630 Increased power level to 1070 Hwe.
8 0100 Reduced power level to 840 Hwe due to system load.
1200 Increased power level to 1090 Hwe.
2100 Reduced power level to 840 Hwe due to system load, placed the '1A' Turbine Driven Reactor Feed Pump out of service for maintenance.
9 0800 Increased power level to 1010 Hwe.
2330 Reduced power level te 850 Hwe due to system load.
10 0630 Increased power level to 990 Hve.
1900 Increased powcr level to 1080 Hwe, placed the '1A' Turbine Driven Reactor feed Putup back in service.
11 0430 Reduced power level to 900 Hwe due to system load.
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ZCADTS/5
II. HDNilltY REPORT (CONTINUED)
A.
SUMMARY
OF OPERATING EXPERIENCE'(Unit 1)
Day J3E Lunt 0800 Increased power level to 1080 Hwe.
12 0030 Reduced power level to 850 Hwn due to system load.
1100 Increased power level to 1075 Hwe.
13 0330 Reduced power level to 850 Hwe due to system load.
14 1100 Increased power level to 1070 Hwe.
15 2330 Reduced power level to 850 Hwe due to system load.
16 0700 Increased power level to 1075 Hwe.
17 0030 Reduced power Icvel to 8C Mwe due to system load.
18 0100 Reduced power level to 830 Hwe due to system load.
0700 Increased power level to 1050 Hwe.
2300 Reduced power level to 850 Hwe due to system load.
19 0730 Increased power level to 1050 Hwe.
20 0100 Reduced power level to 950 Hwe due to system load.
0530 Increased power level to .045 Nwe.
22 0400 Reduced power level to 1030 Hwe and held for TIP set.
2335 Reduced power level to 850 Hwe due to system load.
23 0530 Increased power level to 1030 Hwe.
2130 Reduced power level to 760 Hwe due to system load.
24 0600 Increased power level to 1030 Hwe.
2300 Reduced power level to 850 b . due to system load.
25 0730 Increased power level to 1030 Hwe.
26 0100 Reduced power level to 750 Hwe due to system load.
1600 Increased power level to 850 Hwe, 2130 Reduced power level to 780 Hwe due to system load, i-ZCADTS/S
- . . _ .-. - . _ = - . _ . - .- . _ .
l .' II. HON 111LY REPORT (CONTINUED)
A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1) ,
I DaX ling Event __
i 27 0430 Increased power level to 1030 Hwe.
2130 Reduced power level to 750 Hwe due to system load, ,
performed monthly surveillances. l l
28 0700 Increased power level to 1030 Hwn. ;
2300 Reduced power level to 770 Hwe due to system load.
29 0610 Iacreased power level to 1020 Hve.
2100 Reduced power level to 850 Hwe due to system load.
30 0630 Increased power level to 1020 Hve.
1700 Reduced power level to 890 Hwe due to system load.
2130 Reduced power level to 760 Hwe due to system load.
31 0700 Increased power level to 1010 Hwe.
1230 Increased power level to 1025 Hwe.
2300 Reduced power level to 850 Hwe due to system load.
- 2400 Reactor critical, Generator on-line at 780 Hwe, l continuing coastdown. Power level reduced due to system load, p
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ZCADTS/5
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[ [ .B. AMEHDHENTS TO Tile FACILITY LICENSE OR TECHNICA'. SPECIFICATION
^
(None.)
C. MAJOR CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQUIPHENT (including SOR differential pressure switch failure reports).
(See Table 1)
D. LICENSEE EVENT REPORTS (Unit 1)
(None.)
E. DATA TABULATIONS (Unit 1)
- 1. Operating Data Report (See Table 2)
Average Daily Unit Power Level (See Table 3) 2.
- 3. Unit Shutdowns and Significar.t Power Reductions (See Table 4)
I i
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. _ _ _ _ _ - _ _ _ - _ _ _ _ -_ l
C. TABLE.1 (Unit 1)
MAJOR CORRECTIVE MAINTENANCE TO ,' -'
SAFETY-RELATED EQUIPMENT-WJRK REQUEST .
RESULTS AND EFFECTS ,
NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L16309 Control Room HVAC Holsture in flow meter. No indication. Purged sensing lines and Anunonia Detector . replaced flow meter.
OXY-VC165A L16401 Control Room HVAC. Grounded motor windings. Fan tripped on thermal overload. Replaced motor.
Return Fan OVCO2CB i L16474 Switchgear Heat Fan supply breaker.
Fan supply treaker tripped on Replaced breaker.
Removal Vent Fan magnetics.
.! IVXO4C.
- L16815 Hydraulic Control Nitrogen charging nipple Degraded operation. Replaced charging cipple.
Unit 50-35 leaking.
(No SOR Failures this month.)
4 ZCADIS/5
- TABLE 2 E.1 OPERATING DATA REPORT DOCEET 110. 050-373 UllIT LASALLE OllE DATE August 10,1992 COMPLETED BY M.J.CIALEOWSKI OPERATING STATUS TELEPl!ONE (815) 357-6761 1 REPORTING PERIODt July 1992 GROSS HOURS TN REPORTING PERIOD: 744
- 2. CURREliTLY Af'"110RIZED POWER LEVEL (MWL): 3,323 MAX DEPEllDAL.2 C..PACITY (MWo-Het): 1,036 DESIGl3 ELECTRICAL RAT 1!1G (MWe-Net): 1,076
- 3. POWER LEVEL TO WilICll RESTRICTED (IF ANY) (MWe-Net): N/A
- 4. REASOt3 FOR RESTRICTIOri (IF ANY): -
TilIS MONTil YEAR TO DATE CUMULATIVE
- 5. REACTOR CRITICAL TIME (llOURS) 744.0 5,049.5 52,406.0 r
- 6. REACTOR RESERVE SHUTDOWN TIME (IIOU PS) 0.0 0.0 1,641.2
- 7. GENERATOR OH-LINE TIME (IIOURS) 744.0 5,016.8 51,395.1
- 8. UNIT RESERVE SlIUTDOWN TIVE tilOURS) 0.0 0.0 1.0
- 9. TilERMAL ENERGY GENERATED (MWilt) 2,204,697 15,930,868 151,087,347
- 10. ELECTRICAL ENERGY GENERATED (MWile-G ro s s ) 732,090 5,382,09'. 50,471,865
- 11. ELECTRICAL ENERGY GENERATED (MWile-Net) 705,907 5,208,836 48,403,981
- 12. REACTOR SERVICE FACTOR (%) 100.0 98.8 69.6
- 13. REACTOR AVAILABILITY FACTOR (%) 100.0 98.8 71 8 I4. UNIT SERVICE FACTOR (%) 100.0 93.2 08.3
- 15. UNIT AVAIL 1BILITY FACTOR (%) 100.0 98.2 68.3
- 16. UNIT CAPACITY FACTOR (USING MDC) (%) 91.6 98.4 62.1 17 UNIT CAPACITY FACTOR (USING DESIGN MWe) 88.0 94.5 59.7
- 18. UNIT FORCED OUTAGE FACTOR (%) 0.0 1.8 7.1
- 19. S!!UTDOWNS SCllEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACN):
Refuel Or' age, 09/26/92, 13 Weeks
- 20. IF SIIUTDOWN 1 ND OF REPORT PERIOD, ESTIMATED D1TE OF STARTUP:
M
. - . .. - . _ -- . ..-. - - . .-~ - .- - .. - .- ~ . _ -
a y ., .l TABLE 3 l E.3 .-AVERAGE DAILY UllIT POWER LEVEL (MWe-Mot.)
DOCKET NO. 050-073
. UNIT LASALLE ONE ,
DATE August 10,1992 !
CCt4PLETED BY H.J. CI ALKOWSKI !
TELEPilONE (815) 357-6761 i
l REPORT PERIOD: July 1992
, DAY POWER DAY POWER 1 991 17 961 i 2 1,072 18 963 l.. 3 954 19 951 -
4 925 20 997 j .
5' 928 21 1,004 r
. 6. 936 22 1,002 7 973 23 951 ,
8 .945 24 922 i
. 9 ,. 931-. 25 941-
, .10 941 26 790 11 1,002:- 27 925 ;
'h . 12 970 .28 894 13 994 29 903 14 989- 30 896 15 961 31 875
.16' 942 1
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4 b 1 5 d -
.b 9em y- , - - me>4-r gv- & 4hpo= ., w e y- 'wy-ay.mgn ge-9p n g w- c g 3 g gyw g- ie- #y 3 m w -3
TABLE 4.
~-
E.3 UNIT SH'JTDONNS AND PONER REDUCTIONS > 207.
(Unit 1) t i
METHOD OF CDP.RECTIVE YEARLY . TYPE SHUTTING 00HN ACTIONSKDNENTS SEQUENTIAL DATE f: FORCED DURATION THE REACTOR OR (LER/DVR # 1f ,
NUMBER (YY)MDD) 5: SCHEDULED (HOURS) REASON REDUCING P0HER applicable) 4 f
(None.)
t
SUMMARY
OF OPERATION:
i i The unit remained on line at high power throughout the month. Several minor power reductions were required due to system loading and maintenance activities.
t ZCADTS/5
,.i .
F. UNIQUE REPORTING REQUIREMENTS (Unit 1)
- 1. Safety / Relief valve operations (None.)
- 2. ECCS System Outages (See Table 5)
- 3. Changes to the Off-Site Dose Calculation Manual (None.)
- 4. Major changes to Radioactlye Wasta Treatment Systems.
(None.)
- 5. Indications of Failed fuel Elements.
(None.)
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p ZCADTS/S
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l,- (Unit 1)
Table 5 f.2 ECCS System Outages dote: The year and unit data has been removed from the outage number.
OUTAGE NQ,. [QWfMMI PURPOSE (U-0) 0550 ODG01K Replace fuel filter.
0552. ODG0lK Replace soakback oil filter and clean oil strainer.
0557 ODG023B Disassemble and inspect check valve.
(U-1) 0536 1E22-5001 Inspect HACR relay test switches.
0537 IE22-C302B Air compressor inspection.
0556 1E12-C003 Hegger motor.
0557 1E12-C003 Coupling lubrication.
0560 lE12-f006B Inspection, refurbishment, and 0561 VOTES test.
0562 0566 0573 lE12-F051B Administrative control.
IE12-F0658 0596 IDG035 Administrative control.
ZCADTS/5+
LASALLE NUCLEAR POWER STATION UNIT 2 HONTHLY PERf0RMANCE' REPORT JULY 1992 COMMONHEALTH EDISON COMPANY
-NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7
l TABLE OF CONTENTS (Unit 2)
I. INTRODUCTION II. REPORT A. SUKliARY OF OPERATING EXPERIENCE B. AHENDHENTS TO FACILITY LICENSE OR TELHNICAL SPECIFICA1 IONS C. HAJOR CORRECTIVE KAINTENANCE TO SAFETY-RELATED EQUIPHENT 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
- 1. Safety / Relief Valyc Operations
- 2. ECCS System Outages
- 3. Of f-Site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Haste Treati.ent System
- 5. Indications of failed fuel Elements ZCADTS/7
t-
- 1. INTR 000CTION (Unit 2)
The LaSalle County Nuclear Power Station is a two-unit facility owned by
-Commonwealth Edison Company and located near Marsellies. Illinois. rach
-unit is a Bolling Water Reactor with'a designed net electrical output of 1078 Megawatts. - Haste-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 primary construction 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.
3
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1
i II. t90NTHLY REPORT A. SUfNARY OF OPERATING EXPERIENCE (Unit 2) day limft EvfAt 1 0000 Reactor critical, Generator on line at 900 Hwe.
i 3 2300 Reduced power ' 1.el to 850 Hwe due to system load.
4 070 Increased power level to 1080 Hve.
1900 Reduced p s er level to 850 Hwe due to systera load.
5 1500 Increased power level to 1075 Hwe.
2400 Reduced power level to 875 Hwe due to system load.
6 1130 Increased power level to 1100 Hwe.
1400 Reduced power levei to 1065 Hwe due *.o APRH high alarms.
- z00
. Reduced power level to 850 Hwe due to system load.
1400 Increased power level to 1105 Hwe.
2330 Reduced power level to 850 Hwe due to system It 8 1300 Increased power level to 1125 Hwe.
10 0100 Reduced pcwer level to 850 Hwe due to system load.
1200 Increased power level to 1125 Hwe.
11 0130 Reduced power level to 990 Hwe dat te system load.
1100 Increased power level to 1115 Hwn.
12 0?30 Reduced power le"el to 850 Hwe due to system load.
1300 Increased power level to 1115 Hwe.
15 0200 Reduced power level to 850 Hwe due to system load.
1200 Increased power level to 1100 Hwe.
2300 Reduced power 1 el to 850 Hwe due to systen. load.
16 1300 Increased power level to 1090 Mwe.
-17 1300 Reduced power level to 990 Hwe due to loss of the Hain Power le ansformer fans.
1320 Increased power level to 1100 Hwe.
1S 2300 Reduced powcr level to 850 Hwe due to system load.
ZCADTSl'
II. HONTHLY REPORT
' .* A. SUHMARY OF OPERATING EXPERIENCE (Unit 2) (CONTINUED)
On lin Lv3aL 19 0900 Increased power level to 1090 Hwe.
2000_ Reduced power level to 990 Hwe due to system load.
2350 Reduced power level to 850 Hwc due to system load.
20 0430 Increased power level to 1090 Hwe.
21 0020 Reduce er level to 850 Hwe due to system load.
0640 Increased power level to 1085 Hwe.
2200 Reduced power level to 850 Hwe dL to system load.
22 0520 Increased power level to 1090 Hwe.
2230 Reduced power level to 1040 Hwe due to high Main Turbine bearing vibrations.
25 0220 Reduced power levei to 850 Hwe due to system load.
0600 Increased power level to 1080 Hve.
26 0530 Reduced power level to 840 Hwe due to system load.
1400 Increased power leve, to 1010 Hwe.
27 0000 Reduced power level to 850 Hwe due to system load.
0830 Increased power level to 1070 Pa.
28 0010 Reduced power level to 850 Hwe due to system load. _
29 0600 Increased power level $c 1080 Hwe.
1500 Reduced power level to 8 7 Hwe due to system load.
30 0640 Increased power lesel to 1080 Hve.
31 0100 Reduced power level to 850 Hwe due to system load.
0300 Increase 6 power level to 1080 Hwe.
2400 Reactor critical, Generator on-line at 1080 Hwe.
ZCADTS/7 I
-_ _ _ - _ - -----_----- - - - - - - - - - - ----_ -_-_ _ a
l
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B. AMENDMENTS-TO THE FACILIiY LICENSE OR TECliNICAL SPECIFICATI0h (None.)
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPMENT (including 3 SOR differential pressure switch failure reports).
(See Table 1)
D. LICENSEE EVENT REPORTS (Unit 2)
LERlusher Date Dlur.ipiloja 92-009-N 07/14 Failure of the reactor core isolation cooling isolation vaiva 2E51-F086.
E. DATA TABULATIONS (Unit 2) R
- 1. Oncrating Data Report.
(See Table 2)
- 2. Average Daily Unit Power Level.
(See Table 3)
- 3. Unit Shutdowns and Significant Power Reductions.
(See Table 4)
ZCADTS/7
C. TABLE 1'(Unit 2)
~ '
-MAJOR CORRECTIVE MAINTENANCE TO ,
SAFETY-RELATED EQJIPMENT WORK REQUEST RESULTS AND EFFECTS .
NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L16200 250 Volt DC Battery 250V DC battery discharge' Discharge high alarm indication. Recalibrated unit.
2DC01E' alarm unit.
Ll6639 Residual Heat Removal Motor feed cable insulation MCC feed breaker tri, ped on Replaced feed cable.
Ll6678 Test Return Valve cut by MCC door. magnetics when valve was opened. Replaced anit-rotation 2E12-F024A locking key. ,
L91670 Reactor Building Constant force springs. Damper failed to dose. Replaced springs.
Ventilation Pipe Tunnel Inlet Stop Damper 2VR10Y (No SOR Failures this month.)
ZCAUTS/7
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'[ [ . TABLE 2-
_j -
- E.1 OPERATING DATA REPORT DOCKET NO. 050-373
' UNIT LASALLE TWO '
DATE August 10,1992-
, COMPLETED BY M.J,CIALKOWSKI
- -OPERATING STATUS TELEPHONE (815) 357-6761 z
, 11. . REPORTING PERIOD: July 1992
-l GROSS HOURS;IN-REPORTING PERIOD: 744
- 53. 2 " CURRENTLY AUTHORIZED POWER LEVEL (MWt):' 3,323 MAX DEPENDABLE CAPACITY (MWe-Not): '
1,036
. DESIGN ELECTRICAL RATING (MWe-Net): 1,078
-3, iPOWER LEV 5L TO WHICH RESTRICTED (IT ANY) (MWe-Net): N/A k i
- 4 c REASON FOR RESTRICTION (IF.ANY):
THIS MONTH YEAR TO DATE- CUMULATIVE Q
5.- REACTOR CRITICAL TIME (h00RS) 744.0 2,761.2 47,697.1 16 ~. . REACTOR. RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 [
.'7. -GENERATOM ON-LINE TIME (HOURS) 744.0 2,599.4 46,803.9-
- 8.
- UNIT RESERVE SHUTDOWN. TIME (HOURS). 'O.0 0.0 0,0
.:9( THERMAL ENERGY GENERATED (MWHL) 2,277,885 7[734,657 139,977,056 -
. . . . a
- 10. ELECTOICAL ENERGY GENERATED (MWHe-Gross) 764,308 2,622,632 46,512,382 ~
- 11.; ELECTRICAL ENEEGY GENERATED (MWHe-Net) 737,5o8- P.502,580 44,634,084
- 12.-REACTOR SERVICE FACTOR.(%). 100.0 54.0 .69.9 13.s REACTOR' AVAILABILITY ~9R. (%) 100.0 -54.0 72.4 J14. UNIT SERVICE FACTOR (%) 100.0 50.9 68.6 P
50.9
~15.LUNIT AVAILIBILITY FACTOR (%) 100.0 68.6-
,16.i. UNIT CAPACITY FACTOR (USING MDC) (%)- 95.7 47.3 63.1-il71 UNIT.CAPACIYi FACTOR'(USING DESIGN MNe) 92.0 45.4, 60.7 7
)16.~ UNIT FORCED OUTAGE FACTOR-(%) 0.0 3.8 .- 12 . 7 1
m.
b ^19. SHUTDOWNS' SCHEDULED OVER-THE NEXT 6-MONTHS (TYPE,'DATE, AND DURATION OF EACH)t
- 20. . IF SHUTDGWN - AT END _ OF_' REPORT PERIOD, . ESTIMATED DATE C,F STARTUP:
s 1 .a,.
% --' wrv f - , & w- m y y ey
s<,s.
e-- < , t
.c c.;
e us
[
_..c . L "
TABLE 3
.E.2; .'AVERACE' DAILY UNIT POWER LEVEL-(MWe-Net)-
- f j-
, DOCKET bO.:.050-373
- - UNIT LASALLE 'IWO .
DATE August 10,1992- [
? ", - COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357 6761 REPORT PERIOD: July 1992 DAY ~ -. P NER DAY POWER ,
r s 1 993 17 -975
-2.
' 1,073 :18 1,062 3! - 1,081- 19 948
-4; 951 20 984 5 914- '21 968 4 ;i -
. 6. _947. 22 973
- -7I 966'_ 23- 998
.8 1,000: 24 995:
'9 _ 1,068" 25 996
_ 10l 1,002 _
26 -922
,11 -' 13037:
27 1968 s 12-1 993-. 20-- 947--
=13: --1,071 29 959' 4 14 1,06 30 979 31-15 '- 966 975
- ' 16 ' 954 L ,
w , . . - -,
e af--W-' -, w v -,- s- =r
TABLE 4 , _
E.3 UNIT SHUTDOWNS AND # 4ER REDUCTIONS >20%
(UNIT 2).
l f
METHOD OF CORRECTIVE. l SHUTTING DOWN ACTIONS / COMMENTS YEARLY TYPE l
Ft FORCED DURATION THE REACTOR OR (LER/DVR # if SEQUENTIAL DATE REDUCING POWER applicable)
(YYMMDD) S: SCHEDULED (HOURS) REASON M BER i
l (None.)
SUM 4ARY OF OPERATION:
The unit remained on line at high power throughout the month. Several mir.or power reductions were required : _ co system loading and maintenance activities.
ZCADTS/7
=o : ,
~
-'F. UNIQUE REPORTING REQUIREMENTS (Unit 2)
_1, Saf(ty/ Relief Valve Operations (None.)
- 2. ECCS System Outages )
(See Table 5.) l
- 3. . Changes to the Off-Site Dose Calculation Manual.
(None.)
- 4. Major changes to Radioactive Haste Treatment-Systems.
(None.)
5.- Indications of Failed fuel Elements.
(None.) i ZCADTS/7-
'4 g
.w (Unit 2)
Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
QUlbGE N01 EOUIPMENT PURPOSE
, _1866 2DG02CA Air compressor inspection.
471 -2DG08CA Hotor inspection and repair, l i
1872 2DG090A Repair discharge check valve. I l
1877 2E22-C001 Lubrication.
1881 2E51-C002 Change oli and filters.
1886 2E12-F024A Replace motor and anit-rotation 1887 device.
1893 1889 2E51-F080 Repack 2E51-F086.
1913 2E51-F086 1914 1917-1908 2E12-C002C Install drain lines on oil reservoir.
1909 ZCADTS/7 i _.
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