ML20079C205
| ML20079C205 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/31/1991 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9106190064 | |
| Download: ML20079C205 (28) | |
Text
- , Cnmmonw:nith Edisca
'*- c LaSaue County Nuclear Station
- RuralRoute #1, Box 220 V' Marseilles, lilinois 61341 Te!ephone 815/357-6761 June 10, 1991 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-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 Hay, 1991.
Very truly yours, o
r G. J. Diedericli b (Station Hanager LaSalle County Station GJD/MJC/djf Enclosure xt: A. B. Davis, NRC, Region III T. H. Tongue, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety J. B. Hickman, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing H. F. Naughton, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor M. M. Servoss, OA/NS Off Site Review Station File 9106190064 010531 F
ADOCK 05000.3D
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8 LASALLE NUCLEAR POWER STATION UNIT 1 HONTHLY PERFORMANCE REPORT MAY 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-il I
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TABLE OF CONTENTS (UNIT 1)
I. INTRODUCTION II. REPORT A. SUMARY OF OPERATING EXPERIENCE B. AMENDNENTS TO FACILI1Y LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE-TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS
- 1. Operating Data Report
- 7. 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. 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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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 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 primary construction 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 commenced on January 1, 1984.
This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.
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s II. MONTHLY REPORT
- A. SLM4ARY OF OPERATING EXPERIENCE (Unit 1)
D3y Time Event 1 0000 Reactor subcritical, generator off line, LIR04 in progress.
6 0921 Reactor critical.
9 1733 Generator on line.
11 2049 Generator on line at 730 M4E.
13 0300 Increased power to 810 MHE (holding power level due to air leakage on the "B" main steam isolation valve).
19 0426 Reactor shutdown (scram) due to low reactor water level. ,
21 0057 Reactor critical.
1833 Generator on line.
2300 Generator on line at 130 MNE.
22 0425 Turbine-generator trip for over-speed test.
0456 Generator on line.
1800 Generator on line at 900 MHE.
24 0100 Reduced power to 640 MNE for rod set.
1800 Increased power to 1109 MHE.
l: 27 0400 Reduced power to 995 MHE for system load.
l-i 1200 Increased power to 1115 MNE. t 31 0015 Reduced power to 998 MHE due to loss of 15A heater due to level controller problems.
0500 Increased power to 1106 MHE.
2400 Reactor critical, generator on line at 1106 MHE.
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B. AMENDMENTS TO THE FACILITY LICENSE 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 1)
LER Number Qalg Descriotion 91-006-00 05/19/91 Unit 1 Reactor Scram caused by feedwater >
controller malfunction.
91-007-00 05/28/91 Unit 1 Reactor Water Clean Up Isolution due to leaky valve.
E. DATA TABULATIONS (Unit 1)
, 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) l l-l l
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C. ' TABLE 1 (Unit 1) -
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMFMT ,
HORK REQUEST RESULTS AND EFFECTS '
NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LO1433 Safety Relief Valve Valve seat leakage. Valve leakage at temperatures Replaced valve.
1B21-F013F above 200*F.
LO1434 Safety Relief Valve Valve seat leakage. Valve leakage at temperatures Replaced valve.
1821-F013S above 200*F.
LO1437 Hydraulic Control Drive water supply Degraded control rod operation. Replaced filter.
Unit 14-15 filter.
LO1438 Hydraulic Control Drive water supply Degraded control rod operation. Replaced filter.
Unit 14-51 fil ter.
LO2041 Hydraulic Control Nitrogen accumulator Nitroger. accumulator Replaced fitting.
Unit 54-47 charging fitting. leaking.
LO2122 Hydraulic Control Water accumulator Excessive alarms. Replaced water accumulator.
Unit 54-47 leakage.
LO2123 Hydraulic Control Hater accumulator Excessive alarms. Replaced water accumulator.
Unit 06-27 1eakage.
LO2124 Hydraulic Control Hater accumulator Excessive alarms Replaced water accumulator.
( Unit 38-07 leakage.
i LO2125 Hydraulic Control Hater accumulator Excessive alarms Replaced water accumulator.
t Unit 42-07 leakage.
l l LO2126 Hydraulic Control Hater accumulator Excessive alarms Replaced water accumulator.
Unit 10-23 leakage.
- LO2127 Hydraulic Control Water accumulator Excessive alarms Replaced water accumulator.
Unit 14-23 leakage.
(No SOR failures this :::enth)
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C. TABLE 1 (Unit 1)
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MAJOR CORRECTIVE MAINTEkANCE TO ,
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SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS l HORK REQUEST CORRECTIVE ACTION
' CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION NUMBER COMPONENT Excessive alarms Replaced water accumulator.
LO2128 Hydraulic Control Water accumulator Unit 26-27 leakage.
Excessive alarms Replaced water accumulator.
LO3118 liydraulic Contrri Hater accumulator Unit 10-47 leakage.
Degraded operation. Replaced control rod Control Rod Drive Seal damage. drive module.
LO3549 Module 46-35 Degraded operation. Replaced control rod Control Rod Drive Seal damage. drive module.
LO3550 Module 38-35 Degraded operation. Replaced control rod Control Rod Drive Seal damage. drive module.
LO3551 Module 34-55 Degraded operation. Replaced control rod Control Rod Drive Seal damage. drive module.
LO3552 Module 30-47 Degraded operation. Replaced control rod Control Rod Drive Seal damage. drive module.
LO3553 Module 30-43 Excessive alarms. Replaced water accumulator.
LO3616 Ilydraulic Control Hater accumulator Unit 02-35 leakage.
Excessive alarms. Replaced water accumulator.
LO4232 Hydraulic Control Hater accumulator Unit 30-59 leakage.
Excessive alarms. Replaced water accumulator.
LO4233 Hydraulic Control Water accumulator Unit 22-03 leakage.
Excessive alarms. Replaced water accumulator.
LO4477 ilydraulic Control Hater accumulator Unit 50-11 leakage.
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C. TABLE I (Unit 1)
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIFHENT RESULTS AND EFFECTS .
HORK REQUEST CORRECTIVE ACTION COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CMBER Excessive alarms. Replaced water accumulator.
LO4478 Hydraulic Control Hater accumulator Unit 38-11 leakage.
Excessive alarms. Replaced water accumulator.
LO4479 Hydraulic Control Hater accumulator Unit 10-27 leakage.
Excessive alarms. Replaced water accumulator.
LO4480 Hydraulic Control Hater accumulator Unit 54-15 leakage.
Excessive alarms. Replaced water accur'1ator.
LO4481 Hydraulic Control Hater accumulator Unit 34-39 leakige.
Excessive alarms. Replaced water accumulator.
LO4482 Hydraulic Control Hater accumulator Unit 22-11 TeaKage.
Excessive alarms. Replaced water accumulator.
LO4483 Hydraulic Control Hater accumulator Unit 10-51 leakage.
Excessive alarms. Eeplaced water accumulator.
LO4484 Hydraulic Control Hater accumulator Unit 42-35 leakage.
Excessive alarms. Replaced water accumulator.
LO4485 Hydraulic Control Hater accumulator Unit 18-27 leakage.
Seal damage. Degraded operation. Replaced control rod drive LO4976 Control Rod Drive module.
Module 34-23 ZCA0TS/5+
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C. TABLE 1 (Unit 1) -
MAJOR CORRECTIVE MAINTENANCE TO -
SAFETY-RELATED EQUIPMENT .
HORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLMT OPERATION CORPECTIVE ACTION LO4977 Control Rod Drive Seal damage. Degraded operation. Replaced control rori drive Module 46-31 module.
LO4978 Control Rod Drive Seal damage. Degraded operation. Replaced control rod drive Module 54-35 module.
LO5379 Control Room HVAC Flow switch. Switch failed calibration. Replaced flow switch.
Mixing Damper LO5553 Control Rod Drive Seal damage. Degraded operation.. Replaced control rod drive Module 02-43 module.
LO5703 Turbine Building Damper actuator Degraded operation. Replaced actuator.
HVAC Check 1FZ-VT070A.
Damper IVT79YA LO5704 Turbine Building Damper actuator Degraded operation. Replaced actuator.
9VAC Check 1FZ-VT0708.
Damper IVT79YA LO5705 Torbine Building Damper actuator Degraded operation. Replaced actuator.
HVAC Check 1FZ-VT071A.
Damper IVT79YB LO5706 Turbine Building Damper actuator Degraded operation. Replaced actuator.
HVAC Check 1FZ-VT0718.
Damper IVT79YB LO5707 Turbine Building Damper actuator. Degraded operation. Replaced actuator. .
HVAC Check 1FZ-VT072A. l Damper IVT79YC ZCADTS/5+
C. TABLE 1 (Unit 1)
MAJOR CORRECTIVE MAINTENANCE TO ,
SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PULNT OPERATION CORRECTIVE ACTION LO5708 Turbine Building Damper actuator. Degraded operation. Replaced actuator.
HVAC Check 1FZ-VT0728.
Damper IVT79YC LO5848 Main Steam Isolation Solenoid valves. Degraded operation. Replaced solenoid valves.
Valves 1821-F032A and 1821-F0328 LO6148 Hydraulic Control Diaphragm on scram Degraded operation. Replaced diaphragm.
Unit 22-15 inlet valve.
LO6333 Hydraulic Control Insert supply Control rod drive inoperable. Replaced directional Unit 38-23 directional control control valve.
valve.
LO6938 Main Steam Line Flow Flow switch IE31-N009C. Degraded operation. Replaced switch.
LO7069 Control Room HFA relay Relay inoperable. Replaced relay.
Ventilation 0FSY-VC004X.
LO7087 High Pressure Core Pump bearings. None. Replaced pump.
Spray Hater Leg Pump IE22-C003 LO7266 Reactor Core Solenoid valve coll. Soleisold inoperable. Replaced coll.
Isolation Cooling Trip and Throttle Valve IE51-C002 LO7582 Main Steam Isolation 4-way air valve. Valve inoperable - Replaced valve.
Valve 1821-F0228. limited power level operation.
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C. TABLE 1 (Unit 1) -
MAJOR CORRECTIVE MAINTENANCE TO -
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SAFETY-RELATED EQUIPMENT .
MORK REQUEST . RESULTS AND EFFECTS IpsER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LO7634 Hydraulic Control Scram pilot solenoid Degraded operation. Replaced solenoid valves.
Unit 10-39 valves. ;
LO7642 Hydraulic Control Scram pilot solenoid Degraded operation. Replaced solenoid valves. !
, Unit 22-35 valves. '
l LO7653 Aux. Electric Crepressor OVE-04CA. None. Replaced compressor.
Equipment Toom
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HVAC LO6177 Control Room HVAC Damper. Damper inoperable. Replaced damper.
1 Air Damper OVCOSYA !
l L97735 Hydraulic Control Mater accumulator Excessive alarms. Replaced water accumulator. [
- Unit 46-47 leakage. l
! L98475 Hydraulic Control Mater accumulator Excessive alarus. Replaced water accumulator. !
Unit 58-39 leakage. l L99842 Control Rod Drive Seal damage. Degraded operation. Replaced control rod i Module 34-59 drive module.
! L99843 Control Rod Drive Seal damage. Degraded operation. Replaced control rod Module 22-51 drive module.
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, TARE 2 l' E.1 0F'EPAi!G DATA HPORT 10CKE1 ND 050-373 l UNIT LASALLE ONE Mit JUNE 10,1991 l COMPLETEL TY M.J. CI Att0 Gl :
1ELEPHDNE (015)-:57 6761 0FEFAllNGSTATU$
- 1, REPORT!NS PERIODi APRIL 1991 09059 H00FS IN PEPORi!6 PERIOD
- 744
- 2. CURRENTLY AUTHChilED PDWT.R LEVEL (MWt): 3.323 MAX IDEhD CAPAtili (MWe-Neth 1,036 1 K5!M ELECTEICAL RAllE (MJe-Neth 1.070 t
- 3. - POWER LEVEL 10 UHICH RCSTRICIED (If ANY) (MWe-Neth N/A
- 4. - FEASONS FDP RE51RICT10N (If ANf h FEPORi!NG FERIOD IATA TEIS MONiii YEAR-TD-MTE CUMULATIVE 5, REACIDX CRITICAL 11ME (H]URS) 570.1 1,670.9 42,288.3
- 6. REAtlGR RESERVE SHUTDOWN TIME (HOURS) 0,0 0.0 1,641.2
- 7. f{NERATOR OW-LINE TIME (H3URS) 471,8 1,579.7 41,329.5 ,
B. UNIT RISEPVE SHUIDOWN TlHE ! HOURS) 0.0 0.0 1.0 9, THERMAL ENERGY GENERATED (tiUHt) 1,238,328 4,904,20 119 A07,801
' L10i ELECTRICAL ENERCY GENERATED (MWHe-Gross) 402,900 1,633,441 39,636,729
- 11.- ELECTRICAL' EN[R5Y SENERATED (MUHe-Net) 394,969 -1,556,576 37,926,659 12, SEACIOR SEkVitE FACTOR (Il 76.6 46.3 65.0
- 13. REACTOR AVAILABILITY TACTOR (%) 76.6 46.3 67.6 1
,- 14. UNII SERVIEE FACTOR (%) 63.4 43.6- 63.6
- 15. UNIT A'/AILIBILITV FACIDR (%) 63.4 43.6 63.6-
- 16. UNii CAFACITY FACTOR (USING M K! (%) 4?.9 41.5 56,3 i
, 17. UN!i CAPACITY TACTOR (US! E KSIGN fWe) .(1) 43.0 39.9- 54.1 L 18,UNITTORCEDOUTAGEFACTOR(1) 11.7 3.8 8.3 p . . . . . . . _ . _ . . . . . . . . . . . . . . . . . . . . . -
j 19. SHUIDOWN3 SCHEDJLED OVER THE NEXT 6 a3NTHS (IffE, MIE, AND MATION DF EACH):
!. 20 IF SHUTDCWN Al END Of REPORT fER10D, ES11 MATED MIE OF STARTUP:
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I 10CtEl NO, 0 %-373 1A!LE 3 L'N11 LAMLLE %E E.? AVERGE M]tY UN17 FDL'ER LEVEL Owe Net) MIE JUNE 10,1991 CDP.PLElf D EY .t) ElkitNS/l TELEFHDNE G15)-357-4761 REFORT pef:10D: APRIL 1991 :
NY FOUER Mi POL'El 1 -12 17 836 2 -12 18 B45 3 -12 19 146 4 -12 20 12 5 -12 21 13 6 -12 22 467 7 -12 23 956 8 -12 24 973 9 22 25 1,078-
-10 136 26 1,030 11 301 27 1,062 12 741 28 1,074 13 782 29 1,069 14 772 30 1,068 I
'15 013 31 1,059 16 8%
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TABLE 4 E.3 UNIT SHUTDOHNS AND P0HER REDUCTIONS > 207. '
(Unit 1)
METHOD OF CORRECTIVE SHUTTING DOM ACTIONS /C0fMENTS YEARLY TYPE DURATION THE REACTOR OR (LER/DVR # if SEQUENTIAL DATE F: FORCED applicable)
(HOURS) REASON REDUCING POWER l NUHBER (YY)NDD) S: SCHEDULED 209.6 C 1 Refueling outage LIRO4.
01 910216 S F 62.1 A 3 Control failure of the 02 910519 1A turbine driven reactor feed pump (DVR #1-1-91-0062).
4 Turbine overspeed trip 03 910522 S 0.5 8 test (no reactor trip).
SU N RY OF OPERATION:
Refueling Outage L1R04 ended on 05/09/91. A reactor scram occurred on 05/19/91 due to low reactor water level. The unit cas returned to service 05/22/91. The Unit remained at high power for the duration of the month.
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. f. UNIQUE REPORTING REQUIRTHENTS (Unit 1)
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- 1. Safety / Relief valve operations l VALVES NO & TYPE PLANT DESCRIPTION DAlf &CTUATED 6CIVAl10!i CONDITION OF EVENT (None)
- 2. ECCS System Outages (See Table S)
- 3. Changes to the Off-Site Dose Calculation Manual (None)
- 4. Major changes to Radioactive Haste Treatment Systems.
(None) .
I Indications of failed fuel Elements.
5.
(None) l l
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(Unit 1)
Table 5
. F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
OUTAGE NO. EOUIPMENI PURPOSE (U-0) 179 ODG01K Hiring inspection.
180 ODG01K Lubrication.
183 ODG01P Maintenance.
185 ODG01K Calibration of speed sensor.
(0-1) 1248 IE22-S001 Maintenance and inspection.
1249 1267 IE51-f008 Repair oil leak.
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LASALLE NUCLEAR P0HER STATION UNIT 2 HONTHLY PERFORMANCE REPORT MAY 1991 COMMONHEALTH EDIS0N COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 t
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1 TABLE OF CONTENTS (Unit 2)
I i I. INTRODUCTION II. REPORT A. SUMARY OF OPERATING EXPERIENCE B. AMENDMFNTS 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 n0VIREMENTS
- 1. Safety / Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Maste Treatment System
- 5. Indications of Failed Fuel Elements r
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I. INTRODUCTION (Unit 2)
The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marect!!as, Illinois. Each unit is a Boiling Nater Reactor with a designed net electrical output of 1078 Megawatts. Haste heat is rejected to a man-made coeling 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 NPT-18 on Decerber 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.
This report was complied by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.
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_. . _ . -_ .. _ . . _ . _ ~ . . _ _ . . _ _ _ . . _ _ . _ _ _ _ _ . . _ . . __ _ . _ . _ _ . _ . . . _ _ . _ _ _ . _ . . _ . . . . , ...
', o II. MONTHLY REPORT
- A. SLM4ARY Of OPERATING EXPERIENCE (Unit 2)
Day Time _ Event 1 0000 Reactor critical, generator on line at 1060 MHE to perform weekly surveillances.
1000 Increased power to 1132 MHE.
7 2330 Reduced power to 1046 MWE for weekly surveillances.
8 1000 Increased power to 1130 MHE. l 10 0100 Reduced power to 1070 MNE for condensate booster pump transfer.
0600 Increased power to 1130 MNE.
12 1500 Reduceo power 10 1060 MHE for condensate booster pump transfer.
1900 Increased power to 1115 MHE.
15 0100 Reduced power to 1070 MNE for weekly surveillances.
0600 Increased power to 1120 MHE.
17 2300 Reduced power to 900 MHE to place 2B turbine driven reactor feed pump off-line for lubrication, place the '
motor driven reactor feed pump on-line and to perform monthly surveillances.
19 1500 Increased power to 1125 MHE.
22 0100 Reduced power to 1070_MHE to perform weekly surveillances.
0330 Increased power to 1122 MNE.
31 2400 Reactor critical, generator on-line at 1120 MHE.
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, - , - - - . - . . , , , . , . . - . - ~ _ - . . . _ ,. . . . . -
- . _ , , , ~ - , , . . . , . .. ..,,e .. . , - - - _ - . . - . - . . ,- - m , ,,-. , .m ,
_ . - . - - - . - - - - - . - - . _ - - . - . . - = - - - _ - _ -
E 8. AMENDNENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIf! CATION (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 (None) i 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)
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C. TABLE 1 (Unit 2)
MAJOR CORRECTIVE MAINTENANCE TO ,
SAFET(-RELATED EQUIPMENT - ,
J MORK REGUEST RESULTS AND EFFECTS
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NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION t LO7667 Control Room Chemical tape Detector inoperable - Replaced chemical Ammonia Detector casette carrier. chemical tape would not casette carrier.
0XY-VC165A advance.
LO8194 Residual Heat Removal 74 relay contacts. Improper light Replaced 74 relay.
Pump 1A Cubicle indication.
Cooler LO8195 Low Pressure Core 74 relay contacts. Improper light Replaced 74 relay.
! Spray Pump Cooling indication.
t Fan l
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i, (No SOR Failures this month)
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l 1A!!E 2 E.1 DIEFATING IATA FEFCF1 10DET NO. 05H74 Ut,1T LAIA;tE TUO 14iE JuhE 1(, 19?1 CC*FLETED ?Y a.J. CIALL N it!
1ELEPr::NE W 54-357-s?el OrEFAlltG STATUS
- 1. FEFU llW3 fEFIC3: ATFit 1991 Gr~; H U S lh fEF~Fli n fiF1 2 744
- 2. CUTFENTLY A9IGIZED FMk LEVEL (Nt): 3,2:3 nu X fE e CAiACITY W ebeu , 1,03s IGib ELECFICAL EAT!bS We-Net): 1.070
- 3. POLER LEUEL T3 WHICH FESTRICTED (If ANY) We-heU: WA
- 4. FEASONS FOR EESTRICTIDN (If ANf):
FUCETIW FTR!DI IA! A 141E Q iH YEAE-iO-1 ATE CLWLAllVE 5, REACTOR CRITICAL IIME O c)RS) 748,0 3,623 0 40,113.2
- 6. EEAC10R PESEUE SHJIICWN TIME (H035) 0.0 00 1,71!.9
- 7. GENEAATOR ON-LINE 11hE UCRS) 744.0 3,s:3.0 37,4712 0, L: NIT FESENE SOTI AN TIME 010095) 0.0 C.0 0.0
- 9. THERMAL EhERGY GEt!EEATED ( AHt) 2,447,562 11,9L5.2N 117,344,375
- 10. ELECTEICAL ENEFGY GENEPATED W8eGrass) E214% 4,024.915 58 M:-L747
- 11. ELECTk! CAL ENEFG) ED EFATEI (MHe-Net) 7is I?! 3,914,5'8 27.333,6!3 O. EEalci! SERVICE FKTCR (U 100,0 100.0 69.2
- 13. FEACTOR @AILA5!LITY FACICR (1) IM .0 100.0 72 1
- 14. UNIT SERVIEE FACTCP (U IN.0 100.0 68.0
- 15. UNIT AVAILIIIL11Y FACT 0E (U 100 9 iM.0 63.0
- 16. UNIT CAPACITY FA: TOR (U5I@ MX) W 10.3 104.3 62.1
- 17. UNIT CAFACITY FACTOR (U? LNG ((EIGN NE) (D ??.3 1012 57.7
- 18. UNIT FORCEIl 00TAE{ FAC10R m 0.0 0.0 13.7
- 19. SHUTIMS SCHEBJLED OVER THE NEXT 6 M0nTHS (IYPE, DATE, AG ICRATO4 0F Etc:m:
(OE )
- 20. If SHUTDM AT EbD Cf EEPORT FEGICL, ESlIKATE2 IaiE OF c.! AFT 3 h/A
e 4
, 1169[1 h]. (50 '74 14t1 3 Bil lA5:4tE IWS E.2 t,VU AL[ Nil.f 511 F Mk L UR We-H t i Nll JU'i :6, IMI C M LETEI, Fi M.J Citd KOQ I ri. :,e f J vr c_ i t.1.#p m_ . c,,u tL ,u t
!IFORT FEi1 9 MHL 1;il Nt 00)U lui FMF 1 1,077 17 1. 'M 2 1.099 li ils 3 1,071 19 1,029 4 1,076 20 1,;!1 5 1 J'<0 21 1,"7; 6 1,090 22 1/'79 7 1,0H 23 1,077 8 1.076 24 1 179 9 1,031 25 1,076
.4 n, 1,"y,s ac 1. r c Table 5 f.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
OUTAGE NO. EQUIPMENT PURPOSE 134 2DG01K Storage tank cleaning.
135 2DG01X Lubrication and oil change.
136 2DG01K Calibrations.
137 2DG01P Pump coupling lubrication.
138 2DG01K Wiring inspection.
139 2DG01K Replace coolant hose.
144 2E22-C'102A Replaced valve.
148 2E22-5001 Lubrication.
161 2E51-C003 Pump coupling lubrication.
162 2E51-C003 Lubrication.
163 2E51-F004 Performance of LES-EQ-112.
2E51-f005 2E51-F010 2E51-f022 176 2E12-F336A RebutId limitorque.
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