ML20079E718
| ML20079E718 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/31/1983 |
| From: | Diederich G, Lin D COMMONWEALTH EDISON CO. |
| To: | NRC |
| References | |
| NUDOCS 8401170402 | |
| Download: ML20079E718 (15) | |
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4 LASALLE NUCLEAR POWER STATION l
UNIT 1 MONTHLY PERFORMANCE REPORT j DECEMBER 1983 L
COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11
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TABLE OF CONTENTS
- 1. INTRODUCTION
- 11.
SUMMARY
OF OPERATING EXPERIENCE ~FOR UNIT ONE Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. LICENSEE EVENT REPORTS V. DATA' TABULATIONS A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations B. ECCS System Outages C. Off-Site Dose Calculation Manual Changes
! D. Major Changes to Radioactive Waste Treatment System l
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- l. INTRODUCTION The LaSalle Nuclear Power Station Unit One is a Boiling Water Reactor with a designed electrical output of 1078 MWe net, located in Marseilles, Illinois. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Commonwealth Edison Company.
The condenser cooling method is a closed cycle cooling pond. The plant is subject to License Number NPF-11, issued on April 17, 1982. The date of initial criticality was June 21, 1982. The unit has not commenced commercial generation of power.
This report was complied by Diane L. Lin, telephone number (815)357-6761, extension 499.
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- 11.
SUMMARY
OF CPERATING EXPERIENCE FOR UNIT ONE December 1-31 The unit was shutdcwn due to a ventilation problem in the drywell and.the replacement of cables which were damaged by excessive heat in the drywell.
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111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications.
There were no amendments to the facility license or technical specifications during the reporting period.
B. Facility or Procedure Changes Requiring NRC Approval.
There were no facility or procedure changes requiring NRC approval during the reporting period.
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C. Tests and Experiments Requiring NRC Approval.
I' There were no tests or experiments requiring NRC approval during the reporting period.
D. Corrective Maintenance of Safety Related Equipment.
l The following tables present a summary of safety-related maintenance l
completed on Unit One during the reported period. The headings in-dicated-In this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action, l
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ATTACllllEllT 'A L il'-JUO- /
Revision 3
- CORRECTIVE HAINTENANCE OF .
Horch 1, 1983 SAFETY RELATED EQUIPMENT 5 RESULTS All0 EFFECTS C0111100IiVI. AC f1011 UOl!1; REfltJESI . 1.ER C0111'0111.l!I CAUSE DF llAl.FUllCT1011 Off SAFE OPEftATI0li <
I L26104 --- Damper OVE09YA Faulty actuator Damper would not move Rebuild actuator MSIV Leakage Stem plating and stem / bonnet Valves broken Replaced stem and L26920 ---
Control Main threads galled. stem / bonnet.
L27753 Steam Pressure ;
1 and Instrument Stop Valves Defective meter Meter damaged when D/G 2A Repl'ac'ed meter L27531 D/G Wattmeter was paralleled out of phase with the grid
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--- DW Air /Supp Pool Defective range card Recorder not driving Replaced range card L27682 Water Temperature properly ar,d indicating Recorder irratically Bottom seat ring sealing Valve would not pass local Machined bottom L28423 33-152/03L-0 RHR Shutdown seat ring isolation Valve surface"was not flat leak rate test Valve was closed when hot and Valve would not open Opened valve L29339 83-142/03L-0 RHR Suction Cooling Inboard when cooled stuck Isolation Valve Snubber was inoperable Replaced snubber 3 L29581 83-145/03L-0 Mechanical Snubber High temperature in drywell
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When bus 142Y was de-energ- Freed up welded L29744 83-148/03L-0 Switchgear 136X Contact welded on relay Undervoltage Relay l327-AP107A ized, equipment on 136x did contact i
not load shed e
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ATTACilllElst A Lil'-Jou-/
Revision 3
- CORRECTIVE HAINTENAllCE OF Kgrch 1, 1983 SAFETY RELATED EQUIPMENT 5 RESULTS AllD EFFECTS - 00ltilECIIVL AC T10!!
UO!!K !!I'.qtJESI LER C0lll'0!!!.fli CAUSE OF llAl.! UllCT1011 Oil SAFE OPERATl0ll _
RHR 'C' LPCI High temperature in drywell Possible damage to cable Repulled cable L29889 '
Testable Check insulation and. bypass Valve Cables L29953 ---
RCIC Testable High temperature in drywell Possible damage to cable Repulled cables Check Valve Cable. insulation l
HPCS Testable High temperature in drywell Possible damage to cable Replaced cable
) L29971 ---
Check Valve insulation IE22-F005 L29978 ---
RHR 'B' Heat Limits out-of-adjustment To stop valve travel Adjusted limits Exchanger Outlet Valve .
SRV Solenoid High temperature in drywell Cable insulation cracked Replaced cabics L30120 ---
Cable and brittle L30292 ---
itechanical Llig temperature in drywell snubbers inoperable -
Replaced snubbers Snubbe rs L30293 Mechanical Snubber sHigh temperature in drywell 'ossible damage to snubbers Replaced snubb*ers L30383 ---
L30387 .
L30389 i L30392-6 L30637 L30617 - ---
SRV Cables tigh temperature in drywell : ables were damaged Reoleced cables Cable to SRV Cable was damaged during Cable was damaged Replaced cable
'L30879 ---
L30880
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IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, Decernber 1 through December 31, 1983 This information is provided pursuant to the reportable occurrence reporting reouirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.
Licensee Event Report Number Date Title of Occurrence 83-143/olT-0 11/23/83 Heat Damaged Cables 83-144/03L-0 11/13/83 Unit 1 RHR Service Water Pump 'D' Failure to Start 83-145/03L-0 11/08/83 Inoperable Mechanical Snubber 83-146/03L-0 11/09/83 Containment Leakage Limit Exceeded 83-147/03L-0 11/12/83 Loss of RHR 'B' Shutdown Cooling 83-148/03L-0 11/18/83 Absence of Load Shedding on Switchgear 136X 83-149/03L-0 12/07/83 Rx Vessel Low Water Level Scran /
PC isolation 83-150/01T-0 12/12/83 Incomplete Performance of SRM/lRM Functional Tests ,
83-151/03L-0 11/28/83 Functional Test of IRM's 83-152/03L-0 11/30/83 Shutdown Cooling Inboard Isolation Valve Leakage (1E12-F009) l
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-V. DATA TABULAT10NS The'following data tabulations are presented in this report:
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'A. Operating Data Report B. . Ave rage Dal ly ' Un i t - Pc.we r Leve l
.t C. Unit Shutdowns and Power Reductions
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LTP-300-7
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- ATTACicfEIC C .- Revision 3 March 1, 1983 7 .
- OPERATING DATA REPORT .
CCCKETNO. 050-373 UNIT LaSalle One CATE january 6, 1984 COMPT.ETED BY' D.]ane L. Iin (815)357-6761 TELEPHONE l f,
r OPERATING STATUS 744 I 1. REPORTING PERICO:
December 1983 GROSS. HOURS IN REPORTING PERICO:
1002 MAX. CEPEND. CAPACITY (MWo.Nett: 0
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): In79 ,
t DESIGN ELECTRICAL RATING (MWe. Net):
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- 3. POWER LEVELTO WHICH RESTRICTED (IF ANY) IMWo. Net):
. 4. REASCUS FOR RESTRICTICN llF ANY):
THis MONTH YR TO DATE ' CUM'uLATiv E 0 3617.4 6364.8 L NUMSER OF HCURS REACTOR WAS CRmCAL ...............
O O O E. REACTOR RESERVE SHUTCOWN HOURS . . . . . . . . . .'. . . . . . . . . 4945,18 0 3086.8 f . 7. HOURS G EN E M ATdON LIN E . . . . . . . . . . . . . . . . . . . . . . . . . .
E, UNIT RESERVE SHUTDOWN HOURS .,....................
0 0 n
0 5R6464R ,,8_0,05227
- 9. GROSS THENMAL ENERGY GCNERATED (MWH1 ..............
0 1782781 2't0 horn l 10. GROSS ELECTRICAL ENERGY GENERATED (MWM) . . . . . . . . . . . . .
i 0 1639809 2100dRL'
- 11. NET ELECTRICAt. ENEplGY GENERATED (MWH) .............. .
MA NA NA _
- 12. R EACTOR SE RVICE F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . -
NA NA NA
- 13. REACTOR AVAIL. ABILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . .
. NA NA NA
- 14. UNIT SERVICE FACTOR ..............................
NA NA NA I 15. UNIT AV AILABILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .
NA NA NA
- 16. UNIT CAPACITY FACTOR tussag MOC1 . . . . . . . . . . . . . . . . . . . . .
NA NA NA
- 17. UNIT CAP ACITY F ACTOR (Using Design MWel . . . . . . . . . . . . . . . . . ~l
- NA NA NA .
- 18. UNIT F O RCED OUTAG E R ATE . . . . . . . . . . . . . . . . . . . . . . . . . . _ i
- 19. ,$HUTDOWNS SCHEDULED OVER NEXT S MONTHS (T'tPE DATE. AND DURATION CF EACHl:
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- 20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
FOR Ei".AST ACHIEVED
- 21. UNITS IN TEST STATUS (PRICR TO COMMERCIAL CPERATION):
6/91/R9 IWflAL CRITICALITY
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INIT1AL ELECTRICITY t
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COMMERCI AL CPERATION :
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- LTP-300-7 RLvision 3 ATTACHMENT S herch 1, 1983 6
i AVERAGE D AILY UNIT POWER LEVEL 050-373 I DOCKET NO.
UNIT Lasalle 'One
- b. DATE January 6.1984 p .
COMPLETLD BY Diane L. Lin TELEPHONE (815)357-6761
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MOhTri _ December 1983 c.
DAY AVERAGE DAILY POWER LEVEL
$~ DAY AVERAGE DAILY POWF.R LEVEL (MWe-Net)
(MWe-Net) g7 o 0
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0 O 21 5
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0 25 9 0 0 26 to 0
0 27 '
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14 0
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15 0
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h-L INSTRUCTIONS On this form. !!s: :he sversge dsdy unit power loci in MW:. Net for each dsy in the reporting
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. cesics: wheie mepw..tt. ,
i -- The.c fi;urce wi!! be used to plot s paph for caeh reporti. h g mon:h. Nute that when maximum a ed :er 't.e net ette::tesi r:t:ng oi the unit. (nc:e may be oce:siens when t e!n seeh enes. :he sc f-~~ .O S: e tv .'.e :o:r .*ed pes er iew! !;ne) 7- :.ernote.' .o n;.a tr.e : pren: sr..nu.y m.
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LTP-300-7 "' '
- _R vision 3 March 1, 1913
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9 (Final) ~
- ATTACllHENT -E
- j UNIT SiluTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 .
- UNIT NAitE LaSalle'One ___
DATE January 6,84
. REPORT HONTil December 1981 COMPLETED BY Diane L. Lin y
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TELEPI10NE (815)357-6761 _l IlElllCD OF TYPE SilUTTING DOWN i j l
- F: FORCED DURATION Tile REACTOR OR REASON (1) REDUCING POWER (2) ' CORRECTIVE ACTIONS /C0ttitENISl l
NO. DATE 5: SCllEDULED (ll0URS)
- 42 11/3/83* S 744.0 B 4 Opened oil ci'rcuit i breakers 9-10 and 10-11 for STP-27 i
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- Refer to the November 1983 report.
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VI. UNIQUE. REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations for Unit 1 Relief valve operations during the reporting period are summarized l In the following Table. The table included information as to l
which relief valve was actuated, how it was activated and the l
circumstances resulting in its actuation.
L Valves No & Type ' Plant Description Date Actuated Actuations Conditions of Events 12/2/83 IB21-F013E 10 Manual 0 psig LIS-NB-14 B. ECCS Systems Outages
' The following outages were taken on ECCS System during the reporting period:
Outage No. Equi pnen t Purpose of Outage 1-1395-83 'B' RHR Heat Hydro 1E12-F003B Exchanger Outlet Valve 1-1396-83 'B' and 'C' Lube Coupling RHR Water Leg Pump IE12-C003
.C. Off-Site Dose Calculation Manual There were no changes to the Off-Si te Dose Calculations Manual during this reporting period.
D. Radioactive Waste Treatment System There were no changes to the Radioactive Waste Treatment System during this reporting period.
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Commonwealth Edison LaSa!!e Ccunty Nuclear Station Rural Route #1, Box P20 !
Marseilles, Illinois 61341 1 Telephone 815/957 6761 l
January 5, 1984 Director, Of fice of flanagement Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:
Enclosed for your information is the monthly performar.cc report covering LaSalle County Nuclear Power Station, Unit One, for the period covering December 1 through December 31, 1983 Very truly yours,
, A G. J. Diederich Station Superintendent L6talle County Station GJD/DLL/bej Enclosure xc: J. G. Keppler NRC, Region lII NRC Resident inspector LaSalle Gary Wright 111. Dept. of Nuclear Safety D. P. G lle CECO D. L. Farrar CECO IllP0 Records Center Ron A. Johnson, P/P Coordinator Si4ED iIi i