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Monthly Operating Rept for June 1983
	ML20077H720
Person / Time
Site:	LaSalle
Issue date:	07/12/1983
From:	Diederich G, Lin D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8308110241
	Download: ML20077H720 (16)
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l LASALLE NUCLEAR POWER STATION I

UNIT 1 i

MONTHLY PERFORMANCE REPORT 4

I JUNE 1983 I

COMMONWEALTH EDISON COMPANY i

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NRC DOCKET NO. 050-373-1

-LICENSE NO. NPF-11 i

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TABLE OF CONTENTS I.

IhTRODUCTION

II.

SUlefARY OF OPERATING EXPERIENCE FOR UNIT ONE f.

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATEb MAINTENANCE A.

Amendnents 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 Reductiot:s VI.

UNIQUE REPORTING REQUIREMENTS A.

Main Steam Relief Valve Operations B.

ECCS System Outages C.

Off-Site Dose Calculation Mandal Changes D.

Major Changes to Radioactive Waste Treatment System E.

Changes to the Process Control Program l

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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.

i 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,

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II.

SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE June 1 The unit starYed the reporting period at approximately 29%

reactor power. At 0220 hours0.00255 days 0.0611 hours 3.637566e-4 weeks 8.371e-5 months on June 1 the reactor scrammed due to low level while performing LOS-TG-SA1.

The reactor was critical for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 20 minutes.

June 2-6 The reactor went critical at 0930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months on June 2.

At 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months on June 3 the main generator was syncnconized to the grid and loaded. At 1811 hours0.021 days 0.503 hours 0.00299 weeks 6.890855e-4 months on June 6 the reactor scrammed due to a turbine trip caused by high vibration.

The reactor was critical for 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months and 41 minutes.

June 7-8 The reactor went critical at 2350 hours0.0272 days 0.653 hours 0.00389 weeks 8.94175e-4 months on June 7 At 0008 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months June 8 the reactor scrammed due to ranging from 6 to 7 during LGP-3-2.

The reactor was critical for 18 minutes.

June 8-14 The reactor went critical at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months on June 8.

At 0920 the main generator was synchronized to the grid and loaded to 20% power.

On June 10 at 0800 reactor power was increased to 40%.

On June 12 at 1225 reactor power was 69%. At 0719 hours0.00832 days 0.2 hours 0.00119 weeks 2.735795e-4 months on June 14 the reactor scrammed due to a turbine trip caused by high vibration on bearing #8.

The reactor was critical for 142 hours0.00164 days 0.0394 hours 2.347884e-4 weeks 5.4031e-5 months and 4 minutes.

June 14-30 The reactor went critical at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months on June 14.

At 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months on June 15 the main generator was synchronized to the grid and loaded.

At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 15 reactor power was increased to 42%.

At 1835 on June 15 reactor power was increased to 71%.

On June 16 at 0347 load was reduced to 52% per the load dispatcher. At 0820 on June 16 reactor power was 67%. At 0800 on June 17 reactor power was increased to 62%. On June 26 at 0117 power was reduced to 40% for a rod sequence change. At 0135 on June 25 reactor power was 64%.

On June 27 at 2350 reactor power was reduced to 30% for Reactor Recirculation testing. At 1530 on June 28 reactor power was 65%. At 2221 hours0.0257 days 0.617 hours 0.00367 weeks 8.450905e-4 months on June 30 the reactor scrammed due to startup testing, STP-27 The reactor was critical for 384 hours0.00444 days 0.107 hours 6.349206e-4 weeks 1.46112e-4 months and 51 minutes.

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SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE (Cont'd.)

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0347 load was reduced to 52% per the load dispatcher. At 0820 on June 16 reactor power was 67%. At 0800 on June 17 reactor power was increased to 62%. On June 26 at 0117 power was reduced to 40% for a rod sequence change. At 0135 on June 25 reactor power was 64%.

On June 27 at 2350 reactor power was reduced to 30% for Reactor Recir-culation testing. At-1530 on June 28 reactor power was 65%. At 2221 hours0.0257 days 0.617 hours 0.00367 weeks 8.450905e-4 months on June 30 the reactor was scrammed as per startup test STP-27 The reactor was critical for 384 hours0.00444 days 0.107 hours 6.349206e-4 weeks 1.46112e-4 months and 51 minutes.

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Ill. 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.

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, Resul ts and Ef fects on Safe Operation, and Corrective Action.

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VORK REQUEST LER C0llP0llEllT CAUSE 0F llALFullCTI0li RESULTS All0 EFFECTS CORRCCilVL ACil0l(

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19883 LPRM 08-41A Failed Downscale None Replaced connector 24206 Startrec isolators Out of calibration None Recalibrate,d_ points 24623 83-04-8/03L-0 Mechanical Snubber Bad Snubber Locked in place Snubber replaced 5

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83-051/03L-0 B VC Chlorine Loose circuit board Trip will not reset Tightened circuit Detector board.

24864 RHR IC System Miscalibration incorrect pressure Calibrated Gage Pressure Gage readings 24866 VG Effluent Bad chart dkive motor No continous recordings Replaced chart Radiation Monitor e

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24947 83-055/03L-0 MS Leakage Control None Required for startup Lifted leads and Temperature verified upscale indication 25046 SBGT Radiation Bad filter Low Vacuum Pomp Alarms, Filter changed Monitor OPLS8JA Clears and repeats cycl.

8 25081 Narrow Range Level Out of Calibration Level Indicator does not Calibrated logs Transmitter & Level track in the band indicator OPL58JA SBG7 Bad chart drive motor, Monitor cycles from Replaced chart drive 25145 Radiation Monitor bad vacuum transducer.

operate to fail mode motor and vacuum transducer

UORK REQUEST LER C0llP0llEllT CAUSE Of 11AlfullCT10ll RESULTS AllD EFFECTS CORRECilyi ACYL 0ll Oil SAFE OPERATI0li 25158 83-060/0ll-0 RR Pump Breaker 4B Unknown ilone, since redundant Troubleshooting 3B breaker performed logic test performed. No problem discovered, t

25215 Div II Post Loca D.cfective regulator, Div 1 available for Changed Regulator H2 /02 bad pump diaphram post Loca Monitoring "R0" installed new diaphrams in pump new flow control valves or reagent g'j gases l

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l U-l HPCS AC Air Bad head gasket lodged Over pressure resulted Replaced head and 25250 Loading Relief over discharge valve and relief valve lifted spacer gaskets

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Valve Changed H2 + C2 25324 Div I Post Loca H2 Bad H 2 + O2 reagent Drifts Upscale Reagent gas' flow-Recorder / Monitor Gas Flowmeter Control meter control j

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l 25382 Div I Post Loca 02 Leak in 'O' ring on Drifts Downscafe Replaced pump 02 cell.

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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, accuring durin1 the reporting period, June 1 to June 30, 1983 ibis information is provided pursuant to the reportable occurence reporting require-i ments as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

1 Licensee Event Report Number Date Title of Occurrence 83-047/03L-0 5-07-83 Radwaste Discharge Process Radiation Monitor 83-048/03L-0 5-10-83 Hechanical Snubber inoperable 83-049/03L-0 5-18-83 Mechanical Snubbers not deleted from Technical Specifications 83-051/03L-0 5-15-83 B VC chlorine Detector 83-052/03L-0 5-16-83 1821-FD28C MSIV RPS Limit switch out of Tolerance 83-053/03L-0 5-22-83 Radwaste Discharge vith inoperable Process Radiation j

Monitor 83-054/03L-0 5-20-83 Missed monthly functional or suppression Pool Water Temperature l

83-055/03L-0 5-25-83 MS Leakage control Temperature Indication Functional 83-056/03L-0 5-29-83 Uncoupled Rod.30-19 l

83-057/03L-0 6- 01-83 Coldown Rate Exceeded 83-058/01T-0 6-21-83 Primary Containnent Vacuum Breaker Closed 83-059/01L-0 5-31-83

. Failure of Radwaste Discharge.

Valve to Close 83-060/01L-0 6-06-83 RR Breaker.4B did not open on RPT i

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IV.

UNIQUE REPORTING REQUIREMENTS (Con ' t. )

B.

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

Outage No.

Equipment Purpose of Outage 1-605-83 "A"

RHR Pump Lube motor 1-608-83 "C"

RHR Pump Change oil 1E12-C002C 1-647-83' HPCS Pump Change motor bearing oil 1-668-83 HPCS Minimum Rewire digital computer point Flow Valve 1E22-F012 1-671-83 HPCS Switchgear Breaker inspection 143 1-672-83 HPCS Diesel Replace contacts on Generators relay K-18 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.

E.

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

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DATA TAEULATIONS The following data tabulations are presented in this report:

A.

Operating Data Report 3.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 4

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',LTP-300-7 MTACIDENT D RaviSlost 2

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NOver5ber L3,.1979 9

OPERATING DATA REPORT 050-373 OOCKET NO.

UNIT LaSa1le One July 12, 1983 DATE Diane L.- Lin COMPLETED BY (815) 357-6761 l

TELEPHONE OPERATING STATUS 720

1. REPORTINC PERIGO:

June 14Wt

' GROSS. HOUR $ lN REPORTING PERICO:_

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 1009 M AX. DEP END. CAPACITY (MWeNeti:

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DESIGN ELECTRICAL RATING (MWeNet):

1078

3. POWER LEVELTO WHICH RESTRICTED (IF ANY) (MWeNet):

4. REASONS FOR RESTRICTION (IF ANY1:

- TMi$ MONTH YM TO DATE ' CUMULATIVE b3k 2 I791 2 Sk28 6 ~

5. NUMSER OF HOURS REACTOR WAS CRITICAL...............

0 0

0 E. REACTOR RESERVE SMUTDOWN HOURS...................

688 9 I616 38 3k70 08

7. HOURS GEN ER ATOR ON LiflE..........................

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

S. GROSS THERMAL ENERGY GENER ATED (MWH1........... 1140747 d 24071A1 0 4567467 o

10. GROSS ELECTRICAL ENERGY GENERATED (MWHI.......... 352 622 701930 1222329

11. NET ELECTRICAL ENERGY GENER ATED (MWH)........... 3315756'262k1 1087016 NA NA NA

12. R EACTOR SE RVICE F ACTOR..........................

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NA NA NA

13. REACTOR AVAILASILITY F ACTOR....~..................

NA NA NA

14. UNIT SERVICE F ACTOR..............................

NA' NA NA

15. UNIT AVAILASIUTY F ACTOR..........................

f NA NA NA 1 46 UNIT CAPACITY FACTOR tusing MDC).....................

NA NA NA

17. UNIT CAPAC17Y FACTOR (Usics Osen MWel.................

NA NA NA

18. UNIT FORCED OUTAGE M ATE.........................

19. SMUTDOWNS SCHEDULED OVER NEXT 4 MONTHS (TYPE DATE. AND OURATION OF EACH):

7/3/83

20. ir SuuT OOWN AT ENo OF REPORT PERico. ESTiMATEo oATE Or STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL QPERATIONI:

PORECAST ACHIEVED t

6/2I/82 i

INmAL CRmCAUTY 9/k/82 iNmAL ELECTRICITY 7/83 COMMERCIAL OPERATION i

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ATTACHMENT A

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AVERAGE DAILY' UNIT POWER LEVEL DOCKET NO.

050-171 UNIT LaSalle One DATE July 12. 1983 COMPLETED BY Diane L. Lin TELEPHONE (815) 157-6761 MONTH June 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t)

(MWe-Net)

I 17 524

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526 2.

3 328 19 633 4.

344 20.

7s4 5.

389 21.

733 6.

305 22.

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516 9

74 25 693 10.

333 26.

701 11.

572 27 671 12.

663 28.

qAR 13 733

'29 481 14.

255 30.

'645 15 403 31.

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UNIT SiluTDOWNS AllD POWER RsDUCTIONS D'0CKET NO.

050-373 UNIT NAME LaSalle One DATE July 12, 1983 REPORT HONTH

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Diane L. Lin.

COMPLETED BY TELEPil0NE (815) 357-6761 HETl100 0F SilUTTING DOWN TYPE Tile REACTOR OR F: FORCED DURATION NO.

DATE S: SCllEDULED (if00RS)

REASON (I)

REDUCING POWER.(2)

CORRECTIVE ACTIONS / COMMENTS Rx. scram due'to low level 16 6-01-83' F

31,. 2' A

3 while conducting LOS-TG-SA)

Rx. scram caused by a 17 6-06-83 F

29.6 A

3 turbine. trip on high vibration 18 6-08-83 F

9.1 A

3 Rx. scram due to ranging from 6 to.7 during LGP-3-2

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Due to turbine, trip from 19 6-14-83 F

14.2 A.

3 high vibration on breaking

8 20 6-16-83 F

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5 Per idad dispatcher 21 6-24-83 F

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5 For sequence change Tu r b i ne t'r i p arid Rx,

22 6-30-83 F'

1.6 B

3 scran for STP-27 I

j V I.* Unique REPORTING REQUIREMENTS i

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A.

Main Steam Relief Valve Operations for Unit 1 Relief valve operations during the reporting period are summarized in the following table. The table included information as to which relief valve was actuated, how it was activated and the circumstances resulting in its actuation.

Valves ~

No. & Type Plant Description Date Actuated Actuations Conditions of Events 6-29-83 IB21-F013B 1 Manual 965 psig STP-26 6-29-83 IB21-F013F 1 Manual 965 psig STP-26 6-29-83 1821-F013G 2 Manual 965 psig STP-26 6-29-83 1821-F013H 1 Manual 965 psig STP-26 6-29-83 1B21-F013J 1 Manual 965 psig STP-26 l

6-29-83 1821-F013K 1 Manual 965 psig STP-26 3

6-29-83 IB21-F013L 1 Manual 965 psig STP-26 6-29-83 1821-F013M 1 Manual 965 psig STP-26 6-29-83 1821-F013N 1 Manual 965 psig STP-26 6-29-83 1821-F013P 1 Manual 965 psig STP-26 6-29-83 1821-F013C 1 Manual 965 psig STP-26 6-29-83 1821-F013D 1 Manual 965 psig STP-26 l

6-29-83 1821-F013E 1 Manual 965 psig STP-26 l

6-29-83 IB21-F013R 1 Manual 965 psig STP-26 6-29-83 1821-F013S 1 Manual 965 psig STP-26 6-29-83 IB21-F013U 1 Manual 965 psig STP-26 6-29-83 1821-F013v 1 Manual 965 psig STP-26 i

6-29-83 1821-F013A 1 Hanual 965 psig STP-26 l

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x Commonwealth Edison i) Ruraj Routa #1, Box 220 LaSalle County Nucitar Station c

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'V Marseilles, Illinois 61341 Telephone 815/357-6761 July 12, 1983 Di rector, Of fice of Management 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 performance report covering LaSalle County Nuclear Power Station, Unit One, for the period covering June 1.through June 30, 1983.

Very truly yours, G. J. Diederich Station Superintendent GJD/DLL/bej Enclosure xc:

J.G. Keppler NRC, Region lII NRC Resident inspector LaSalle Gary Wright ll1.

Dept. of Nuclear Safety D.P. Galle CECO D.L. Farrar Ceco INPO Records Center d

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ML20077H720

Text

SUMMARY

SUMMARY

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