Text

Monthly Operating Rept for Mar 1983
	ML20073D542
Person / Time
Site:	LaSalle
Issue date:	04/07/1983
From:	Lin D; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20073D531	List: ML20073D526; ML20073D542;
References
	NUDOCS 8304140011
	Download: ML20073D542 (14)
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-i i LASALLE NUCLEAR POWER STATION UNIT 1

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MONTilLY PERFORMANCE REPORT

$ MARCII, 1983 ,

COMMONWEALTil EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l

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4 TABLE OF CONTENTS

1. INTRODUCTION II.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE III. PLANT OR PROCEDURE CllANGES, 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 E. Changes to the Process Control Program

1. INTRODUCTION The LaSalle Nuclear Power Station' Unit One is a Boiling Water J Reactor with a designed electrical output of 1078 MWe net, located i

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 I

plant is subject to License Number NPF-11, issued on April 17, 4

1982. The date of initial criticality was June 21, 1982. The unit has not commenced commercial. generation of power. ;

1 This report was complied by Diane L. Lin, telephone number (815)357-6761, extension 499.

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II.

SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE i

l March 1-12 The unit started the reporting period at approximately i

190 MWe. At 1043 hours0.0121 days 0.29 hours 0.00172 weeks 3.968615e-4 months on March 12, 1983 the reactor scrammed on 111 Steam Tunnel A T MSIV Isolation due to VR being off and VQ on.

] The reactor was critical for 274 hours0.00317 days 0.0761 hours 4.530423e-4 weeks 1.04257e-4 months and 43 minutes.

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, March 12-17 The reactor went critical at 1905 hours0.022 days 0.529 hours 0.00315 weeks 7.248525e-4 months on March 12, i

1983. At 0250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months on March 13, 1983 the main generator was j synchronized to the grid and load increased to 12 MWe. At 1600 on 4

March 14, 1983, load was increased to 637 MWe. At 0300 on March i

j 17, 1983, power was decreased to 10%. At 0326 the turbine tripped on high vibrations due to low load. At 0750 the reactor scrammed

-1 due to a spurious signal from TSV fast closure. The reactor was t

critical for'108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months and 45 minutes.

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March 18-23 The reactor went critical at 1248 hours0.0144 days 0.347 hours 0.00206 weeks 4.74864e-4 months on March'18, l

I 1983. At 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months the main generator was synchronized to the l gird and load increased to 200 MWe. At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on March 19,

, 1983, load was increased to 400 MWe. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on March.20, 1983 load was increased to 710 MWe. The' reactor scrammed on low

! level on March.22, 1983 at 0506 hours0.00586 days 0.141 hours 8.366402e-4 weeks 1.92533e-4 months ., The reactor was cr'itical for 88 hours0.00102 days 0.0244 hours 1.455026e-4 weeks 3.3484e-5 months and 18 minutes.

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March 24-31 The reactor went critical at 2012 hours0.0233 days 0.559 hours 0.00333 weeks 7.65566e-4 months on March 24, 1983. On March 25,1983 at 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months the main generetor was

synchronized to the grid and lo'ad increased. At 0000 hours0 days 0 hours 0 weeks 0 months on March 26, 1983 load was increased to 577 MWe. At 0350 load was decreased to 184 MWe. At 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months on March 28, 1983 load was increased to 750 MWe. At 0830 on March 30, 1983~1oad was decreased to 477 MWe. At 2200 the reactor scrammed due to IRM B Hi alarm.

The reactor was critical for 145 hours0.00168 days 0.0403 hours 2.397487e-4 weeks 5.51725e-5 months and 48 minutes.

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l III. PLANT OR PROCEDURE CllANGES, TESTS, EXPERIMENTS AND SAFETY RELATED I MAINTENANCE A. Amendments to Facility License or Technical Specifications.

4 There were no amendment to facility license or technical specification during the reporting period.

B. Facility or Procedure Changes Requiring NRC Approval.

Thera were no facility or procedure changes requiring NRC l approval during the reporting period.

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1 C. Tests and Experiments Requiring NRC Approval.

I There were no tests or experiments requiring NRC approval i

during the reporting period.

j D. Corrective Maintenance of Safety Related Equipment.

5 The following tables present a summary of safety-related maintenance completed on Unit One during the reported period.

- The headings indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe. Operation, and Corrective Action.

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LER C0llPO!1EllT CAUSE OF MALFullCTI0li RESULTS AtlD EFFECTS CORRECTIVE ACTI0li VORK REQUEST Oil SAFE OPERATIO!!

L17534 -----

Reactor Water Instru- Bad 3-Way Manifold Valve will not seat when Replaced 3-way mani-ment Stop Valve reactor pressure is -v200 fold PSI L18545 --

SBGT WRGM Bad switch Cannot operate switch Replaced switch L20289 -

Channel A Turbine Switches out-of-tolerance Turbine trip gives s Recalibrated switches Control & Stop Valve scram Trip Bypass L22333 h 83-001/01T-0 Division I 125 Vdc Bad switch Ground to 1E12-N009A Replaced switch Bus 111Y J

L22347 l 83-013/03L-0 Leak Detection Bad switches Ambient temperature switch Replaced 6 switches Temperature Switch and recorder have a 10

. difference L22379 83-009/03L-0 Mechanical Snubber Bad snubber ,

Snubber hard to stroke Replaced snubber L22579 83-015/03L-0 Diesel Generator 1B Lead separated from coil Oscillates on start-up ! Resoldered lead to Governor Control coil L22730 LPCS/LPCI Injection Bad switch No effect / Replaced switch Valve Permissive L22742 Core 6P Recorder Gear meshing and clutch Recorder does not change Adjusted gear meshing out-of-adjustment with changes in core flow and clutch L22777 'A' VC Charcoal Limit switch out-of- Dual indication in Control Adjusted limit switch Train Outlet Damper adjustment Room L22893 -

Jet Pump #19 Flow Isolation valve leaking Water leak on flow trans- Tightened nut on Transmitter ,

mi'qter isolation valve L22979 --- 7 Jet Pump Flow Wrong head correction Flow indicator indicated Recalculated head Indicator less than zero PSID correction O

LER C0llP0llEllT CAUSE OF mal.FUllCTI0li RESULTS AllD EFFECTS CORRECTIVE ACTI0li WORVs REQUEST 011 SAFE OPERATIO!!

L23016 Alarm A106 Bad annunciator input Alarm initiated erroneously Replaced input card card L23310 ,

IRM F Connector pin loose IRM will not insert Adjusted connector Pn i __

L23359 OPL58JB SEGT Bad PC b ard and vacuum Skid won't auto start Repaired PC board Analyzer transducer and replaced vacuum transducer

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- IV. LICENSEE EVENT REPORTS N

The following is a tabular-summary of all licensee event reports' for LaSalle Nuclear Power Station, Unit One, occurring during the i

reporting period, March 1 to March 31, 1983. This information is provided pursuant to the reportable occurrence reporting require-(

ments as set forth in section 6.6.B.1 and.6.6.B.2 of the Technical 7

Specifications.

j Licensee Event Report Number Date Title of Occurrence i

83-011/03L-0 08-83 Rx. Vessel Low Water Level '

. Scram and Primary Contain -

] ment Isolation Instrumenta-tion 83-012/03L-0 2-10-83 RCIC Pipe Routing Area-High Temperature j 83-013/03L-0 2-10-83 RWCU Area High Isolation 83-014/03L-0 2-15-83 Steam Line High Flow RCIC Isolation Instrument j 83-015/03L-0 2-17-83 IB Diesel Generator-Failure i

I 83-016/03L-0 3-08-83 'O' and 'IB' DG Room Ventila-

, tion Damper Electro-Thermal FP Links i

83-017/03L-0 2-22 Failure of Lake Blowdown Flow Element 0FT-WL001 i

83-018/03L-0 2-26-83 RCIC Pump Suction Line.High j Pressure >

c 83-019/03L-0 3-02-83 Lake Blowdown Flow Indication Broken

] .83-020/03L-O 3-05 -Reactor Low Pressure RCIC

. Isolation l

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V. DATA TABULATIONS The following data tabulations are presented in this report:

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions

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. '. - LTP-300-7

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- . , November 13, 1979 ll 5 (

ATTACHMENT A u

' l AVERAGE DAILY' UNIT POWER LEVEL .

DOCKET N0. 050-373 4

t/ NIT LaSalle One {

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DATE Apri1*7", 1983 t

- COMPLETED BY Diane L. 'Lin

} TELEPHONE (815') 357-6761 X499

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. MONTH March 1983 ,

DAY AVERAGE DAILY POWER LEVEL '

. DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t) (MWe-Net)

I . 1. 168 .

17. ~ 10 I

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2. 162 3 '159 19 464 . l 1 !

4. 276 20. 64~8 q 5 171 21. 663

6. 173 22. 127 7 172 23 0

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8. 169 24. O I

9 170 ,

25 311

10. 16'2 26, 322 l \l. 167 27 627

! 12. 65 . 28. 684 I3 201 '29 678

- ' 14.. s2s 30. 274

15. 614 31. 0

16. 600

Revision 2 1

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ilovember 13, 1979 6 .

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. ATTACilHF.NT H '- 1 UNIT SIIUTDOW!!S Af10 POWER REDUCTIO!1s '

DOCKET HO. 050-373 UNIT NAtiE LaSalle'One DATE April 7. 1983

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REPORT H0HTil March 1983 ,

COMPLETED BY Diane L. Lin'.

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TELEPliONE (815) 357-6761 . ,

x499 HETiiOD OF SilUTTiliG DOWN TYPE DURATION Tile REACTOR OR

. F: FORCED REDUCING POWER (2) CORRECTIVE ACT10tlS/ COMME!!TS DATE 5: SCllEDULED (il0URS) REAS0li (1) 71 0 .

G 3 Rx Scram due to Hi Steam 5 3/12/83. F 16.1 # Tunnel AT MSIV Isolation

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due to ,VR,off and VQ on.

B 5 To troubleshoot / repair

-6 .3/17/83 F 0 B RR Flow Control Valve.

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9 Turbine trip on high F 4.4 A 7 3/17/83 .

vibrations due to low load.

3 Rx Scram due to spurious F 36.2 A 8 3/17/83 *

- . signal from TSV fast closure A 3 Rx Scram on' low level.

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3/22/83 F- 70.1 0 A 5 Due to IC71-N006C not Id 3/26/83 F functioning properly.

0 B 5 . To remove CP's.froal line 11 3/30/83 F

and to' isolate 1/2 of the 1

condenser to look for leaks.

A 3 Rx Scraht due to IRM B 12 3/30/83- F 26.8 -

Hi Alarm.' .

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.LTP-300-7 ATTAC10fENT D Revision 2 HOvedber 13:,.1979 9

' OPERATING DATA REPORT 050-373 DOCKET NO.

i UNIT LaSalle One April 7, 1983

. DATE

. COMPLETED BY Diane L. fin

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I. TELEPHONE (815) 357-6761 X499

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OPER ATING STATUS ..

March 1983

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1. REPORTING PERIOO: GROSS. HOURS IN REPORTING PERIOD:

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2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 1007u MAX. DEPEND. CAPACITY (MWe Neti: ,

DESIGN ELECTRICAL MATING (MWo. Net): 107R l j 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe. Net):

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. A REASONS FOR RESTRICTION (IF ANY1: .

1 - THl3 MONTH YR TO DATE ',CUMULATIV E 890 4527.4 I

5. NUMBER OF HOURS REACTOR WAS CRITICAL .............. 617.6 0 0 0 j S. REACTOR RESERVE SHUTDCWN HOURS . . . . . . . . . . . . . . . . . . .

802.68 2660.38 1 7. HOURS GENER ATOR ON LIN E . . . . . . . . . . . . . . . . . . . . . . . . . 590. 5 0 0 O

s. UNIT RESERVE SHUTOOWN HOURS ...................... ,

1018841 3159420

s. GROSS THERMAL ENERGY GENER ATED (MWM) ............. 794333 226534 285052 805451 4 10. GROSS ELECTRICAL ENERGY GENERATED IMWH) . . . . . . . . . . . . .

' 254967 715742

) 11. NET ELECTRICAL ENERGY GENERATEO IMWH) ............. 209033 NA 2

NA NA

12. R EACT O R SE RVICE F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . .

NA NA _NA i 13. REACTOR AVAILABILITY F ACTOR . . . . . . . . . . . . . . .'. . . . . . . .

NA NA NA I 14 UNIT S E RVIC E F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

NA- NA NA

11. UNIT AVAILABILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

' NA l

16. UNIT CAPAC17Y FACTOR (Using MDC) .....................

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17. UNIT CAPACITY FACTOR (Unieg Design MWel . . . . . . . . . . . . . . . . .

NA NA NA l 14. UNIT F OR CED OUTAG E M AT E . . . . . . . . . . . .. . . . . . . . . . . . . . . 9

! 19. , SHUTDOWNS SCHEDULED OVER NEXT S MONTHS (TYPE. DATE. AND OURATION OF EACH1:

4-6-83

20. IF SHUT DOWN AT END OF REPORT PERIOO ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL CPER ATION): FORECAST ACHIEVED

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6-2I-82 .

INITIAL CRITICALITY i

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9.-91 .02.

j COMMERCIAL OPERATION 6-01-81 ;

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VI. UNIQUE REPORTING REQUIREMENTS i

i A. Main Steam Relief Valve Operations for Unit 1 There were no main steam relief valve operations for the reporting period.

l B. ECCS Systems Outages There were no ECCS System Outages during this reporting period.

C. Off-Site Dose Calculation Manual There were no changes to the Off-Site Dose Calculations ,

Manual during this reporting period.

r I. D. Radioactive Waste Treatment System l-There were no changes to the Radioactive baste Treatment System during this reporting period.

E. Process Control Program There were no changes to the Process: Control Program during this reporting period.-

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ML20073D542

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SUMMARY

SUMMARY

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