ML20078R400

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Monthly Operating Rept for Oct 1983
ML20078R400
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 10/31/1983
From: Diederich G, Lin D
COMMONWEALTH EDISON CO.
To:
NRC
References
NUDOCS 8311150011
Download: ML20078R400 (14)
v • d • e


Text

1 LASALLE NUCLEAR POWER STATl.0N UNIT 1 i

MONTHLY PERFORMANCE REPORT

! October 1983

[ COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i

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F TABLE OF CONTENTS

. l. lHTRODUCTION ll.

SUMMARY

OF OPERATING EXPERn. 'CE FOR UNIT ONE

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lil. PLANT 0R PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

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A. Amendments to Facility License or Technical Specifications B. Facility.or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval

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D. Corrective Maintenance of Safety Related Equipment IV. LICENSEE EVENT REPORTS V. ' DATA TABULATIONS' A. Operating Data Report

., B. Average Daily thilt 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 I

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1. 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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SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE October 1-6 The unit started the reporting period at approximately 10% power. At '0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br /> on October 2 the main generator was syn-chronized to the grid and loaded. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on October 2 the reactor was manually scrammed due to the generator tripping on neutral ground. The reactor was critical for 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br />.

October 7-24 The reactor went critical at 0655 hours0.00758 days <br />0.182 hours <br />0.00108 weeks <br />2.492275e-4 months <br /> on Octcber 7 On 0ctober 8 at 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br /> the main generator was synchronized to the grid and loaded. At. 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br /> on October 8 reactor power was 24%.

On October 10 at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> reactor power was increased to 44%. On October 11 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> reactor power was 70%. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on October 17 reactor power was 92%. On October 22 at 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br /> reactor power was reduced to 39% due to the shad running, which caused the circ.

water traveling screen shear pins to shear. At 2249 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.557445e-4 months <br /> on October 22 reactor power was 85%. On October 23 at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> the reactor was manually scrammed due to a group I isolation during STP-25 The reactor was critical for 396 hours0.00458 days <br />0.11 hours <br />6.547619e-4 weeks <br />1.50678e-4 months <br /> and 5 minutes.

October 25 The reactor went critical at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on October 25 At 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> the reactor was manually scrammed due to the loss of Unit 1 instrument air pressure, which was being fed from Unit 2 service air comp assors. The System Aux Transformer feed to Bus 252 tripped which caused a loss of TBCCW, subsequently causing the loss of the service air compressor. The reactor was critical for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 35 minutes.

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October 26-31 The reactor went critical at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> on October 26.

At 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> on October 27 the main generator was synchronized to the grid and loaded. At 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br /> on October 27 reactor power was 21%. On October 28 at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> the turbine was manually tripped to repair #1 control valve. At 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br /> on October 28 the main generator was syn-chronized to the grid and loaded. At 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> on October 28 reactor power was 24%. At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on October 29 reactor power was 47%. On October 29 at 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br /> reactor power was 73%. The reactor was cri tical for 139 hours0.00161 days <br />0.0386 hours <br />2.29828e-4 weeks <br />5.28895e-5 months <br /> and 10 minutes.

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lli. 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.

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B. Facility or Procedure Changes Requiring NRC Approval.

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

l C. Tests and Experiments Requiring NRC Approval.

There were no tests or experiments requiring NRC approval during the reporting period.

D. Corrective Maintenance of Safety Related Equipment.

The following tables present a summary of safety-related maintenance 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.

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LER C0HP0llEllT CAUSE OF MALFullCTI0li RESULTS A110 EFFECTS CORRECIIVI. ECT lul0 WORK REQUEST Ott SAFE OPERATl0tl L25948 -

'A' RHR Service Loose' wires on High dP alarm up with Tightened loose Water Strainer agastat timer pumps shutdown and wires on agastat dP Switch indicating timer zero.

L26408

'0A' VC Ammonia Tubing and fibre Detector trips at 2 ppm Cleaned tubing Detector optic dirty. Instead of 25 ppm. and fibre opEic L26660 83-097/03L-0 Chlorine Detector Bad felt wick Drip rate greater than Replaced felt 4 minutes as specified wick in vendor manua1.

Division i Post LOCA- Defective servoamplifier Recorder reading Replaced servo-L267'd0h Hydrogen Analyzer board -

different from local amplifier board

, Recorder reading.

L27021f 83-111/03L-0 'A' RHR Pump Suction Defective motor and Tri PPi ng on thermal Replaced motor Valve. torque switch ovbrioad during valve and torque switch

. operation.

L27321 -

ESF Status Panel Defective lamp drive Window is dimly lit Replaced lamp Window 28 circuit *

. continuoulsy drive circuit L27508 83-110/03L-0 Bus 141Y Undervaltage Defective undervoltage Relay operates Replaced under-

  • Relay Relay erratically voltage Relay ,
  1. ' None L27763 83-117/03L-0 'B' RHR Heat Unknown Valve stuck Exchanger Valve Lg8071 -

SBGT PRM 'A' Defective Transducer Noble gas channel is Replaced transducer erradic causing repeated

'a l a rms .

L48191 83-120/Q3L-0 Piping Restraints . Water hammer No effect Replaced restraints L28374 -

CRD 30-39 Loose connector 'jRodwhen locally Replaced connector scrammed does not

. produce initiation signal.

LR8571 -

1E41-FQ11 Limit Defect in casting at OiI drippi_ng from Replaced Iimit Switch gasket area. limit switch. switch cartridge 3, ,

IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event repo r t s for LaSalle Nuclear Power Station, Unit One, occurring during the l

reporting period, October 1 through October 31, 1983 This i n fo rma t i on is provided pursuant to the reportable occurrence reporting requi rements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Ti tie of Occurrence 83-108/03L-0 9/01/83 A RHR Minimum Flow Valve Failure to Cycle 83-109/03L-0 9/06/83 Radwaste Discharge Isolation Valve Failure 83-110/03L-0 9/08/83 Non Repeatable Calibration Trip of 4KV UV Relay 83-111/03L-0 8/21/83 LPCI 'A' Suction Valve F004A 83-112/03L-0 9/14/83 OVC13YA Damper Failed Closed 83-114/03L-0 9/21/83 Reactor Vessel Low Water Level Scram Switch 81-115/03L-0 9/27/83 Reactor Vessel Low Water Level RCIC, LPCS, RHR, init. & ADS Perm 83-116/03L-0 9/26/83 Uncoupled Rod 30-19 83-117/03L-0 9/13/83 Failure of 1E12-F003B Valve to Open 83-118/03L-0 9/26/83 'D' MSL Radiation Monitor 83-119/03L-0 10/17/83 1E51-F066 and 1E51-F065 83-120/03L-0 10/03/83 Damaged Mechanical Snubbers 83-121/03L-0 10/14/83 Control Rod 30-14 Uncoupled

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I i ,V. DATA TABULATIONS i

h The"following ~ data tabulations are presented in this report: "

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'A . Operating Data Report i

B. Average Daily Unit Power Level

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j. C. Unit Shutdowns and Power Reductions I

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-ATTACHMENT D .Rcvis,Ic'n 2 1 -.Novembar %, .1979

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' OPERATING DATA REPORT OOCKET NO. 050-373 4

UNIT LaSaIIe One

  • DATE November 8. 1983

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COMPLETED BY Diane L. Lin TELEPHONE (815)357-6761 X499. l OPERATING STATUS . .

' October 1983 gross _HoVRS IN REPORTING PER100: 745

1. REPORTING PERIOD: e 100% uAx, ospguo, capacity guw u,,3: 0
2. CURRENTLY AUTHORIZED POWER LEVEL (Mytti:/d 'U DESIGN ELECTRICAL RATING (MWo. Net):
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): -
4. REASONS FOR RESTRICTION (IF ANY1:

THIS MONTH YR TO DATE ' CUMULATIVE 588.8 3549.6* 6297.0*

5. NUM8ER OF HOURS REACTOR WAS CRmCAL 0 0 0
8. REACTOR RESERVE SHUTDOWN HOURS . . . . . . . . . . . . . . . . . . .

462.0 3019.0 4877.58

7. HOURS C E N E R ATOR ON LIN E . . . . . . . . . . . . . . . . . . . . . . . . .

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8. UNIT RESERVE SHUTDOWN HOURS . ..................... '

...... ...... 1085561 5677283 7817862

9. GROSS T'HERMAL ENERGY GENER ATED (MWH) 1721709 2243008
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) . . . . . . . . . . . . 338296

............. 32 7 033 1589652 2050427

11. NET ELECTRICAL ENERGY GENERATED (MWH) ,

NA NA NA

12. R EACTO R $E RVIC E F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . .

NA NA NA

13. R E ACTOR AVAILAglLITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . .
  • NA NA NA
14. UNIT SERVICE FACTOR . . . . . . . . ........... ..........

NA NA NA

15. UNIT AV AILABILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

NA NA NA l j

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

NA

17. UNIT CAP ACITY F ACTOR tusing Design MWel . . . . . . . . . . . . . . . . .

NA NA NA

18. U NIT F O R CE D OUTAG E R ATE . . . . . . . . . . . . . . . . . . . . . . . . . . e
19. . SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE.DATE. AND DURATICN OF EACHl:
20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:

FORECAST ACHIEVED

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): - ,

b/21/82 INm AL CRmCAUTY INITI AL ELECTRICITY ,

9/04/82 COMMERCI AL OPE RATION II/I5/83, ,

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LTP-300-7

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. November 13, 1979 5

, ATTACHMENT A AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-373 UNIT LaSalle One DATE November 8, 1983 COMPLETED BY Diane L. Lin TELEPHONE (R14)357-6761 X499 MONTH October 1983 DAY AVERAGE DAILY POWER LEVEL . DAY AVERAGE DAILY POWER LEVEL (MWe-Net) _ (MWe-Net)

. 1. 0 -

17 999

2. 68 18. 1046 3

0 19 1070

4. 0 -
20. 1064 5

0 21. 1062

6. 0 22. 7t4 2 7 0 23 746
8. 9 24. 0 9 191 25 0
10. 427 26. 0
11. gny 27 0
12. 603 28. An 13, 645 '29 495
14. '621 30. 567
15. 799 31. 856 .
16. 903 t*.:..- w. -

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  • 7 LTP-300-7 ' ' '

R;vlalon 2 -

November l'3, 1979' 6 .

. ATTACinfENT B '

UNIT SHUTDOWNS NID POWER RsDUCTIONS .

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D'OCKET NO. 050-373 UNIT NAME LaSalle One

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DATE November 8, 198]

REPORT HONTH November 1983 ,

COMPLETED BY _

Di ane L. Li n -

TEL.EPil0NE (815)357-6761 _,

M99 HETl100 0F SiluTTING DOWN TYPE DURATION Tile REACTOR OR REDUCING POVER.(2) CORRECTIVE ACTIONS /COHHENTS NO. DATE 'S:F: FORCED StilEDULED (ll0URS) REASON (1)

A 2 Generator trip on "Back'Up 10/02/83 F 1,74.6 36 . Ground" caused turbine to

- trip.

0.0 A 5 Power was reduced due to 37 10/22/83 F ,

- the shad running which caused the ci rc water

  • traveling screen shear pins to shear.

80." 2, Group i is'olation per 38 10/23/83 S B, STP-25 18.7 A 2 SAT feed to Bus'252 10/25/83 F 39 t ri pped. Unit 1 instrument and. service air pressure

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  • went down due to Unit 1&2 systems being crosstied.-

9.4 A ~9

' Manually tripped turbine to 40 10/28/83 F repai r #1 control valve.

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{ VI. UNIQUE REPORTING REQUIREMENTS A. . Main Steam Relief Valve Operations for Unit 1 There were no main steam relief valve operations for the reporting period.

B. ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period:

Outage No. Equipment Purpose of Outage 1-1143-83 RCIC/RHR Head Primary Containment Requirement Spray isolation C. Off-Site Dose Calculation Manual There were no changes to the Off-Site 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.

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

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' Commonwealth Edison

  • cm LaSalle County Nuclear Station

- w RuralRoute #1, Box 220 V MarseiHes, Illinois 61341

/ Telephone 815/357-6761 i November 8, 1983 1

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Director, Office of Management information

, and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 l

ATTN: Document Control Desk i

{ Gentlemen:

l Enclosed for your information is the monthly performance report covering

, LaSalle County Nuclear Power Station, Unit One, for the period covering October 1 through October 31, 1983.

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Very truly yours, ,

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j G. J. Diederi

Station Superintendent i LaSalle County Station j

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GJD/DLL/bej l l Enclosure

) xc: J. G. Keppler NRC, Region lII j NRC Resident laspector LaSalle Gary Wright 111. Dept. of Nuclear Safety l D. P. Galle CECO D. L. Farrar CECO

INP0 Records Center

{ Ron A. Johnson, PIP Coordinator SNED l

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