ML20024E678

Monthly Operating Rept for Jul 1983.W/830808 Ltr

ML20024E678
Person / Time
Site:	LaSalle
Issue date:	08/08/1983
From:	Diederich G, Lin D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8308160383
Download: ML20024E678 (16)

Text

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LASALLE NUCLEAR POWER STATl011 4

UltiT 1 MONTHLY PERFORMAllCE REPORT 4

July 1983.

COMMONWEALTH EDISON COMPANY 4

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- NRC DOCKET NO. 050-373 2

LICENSE NO. NPF-11 a

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r TABLE OF CONTENTS

l. INTRODUCTION 1

II.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE lil. 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 4

IV. LICENSEE EVENT REPORTS U. DATA TABULATIONS

, A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. UlllquE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations

8. 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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.i 1- - 1. . INTRODUCTION -

l The LaSalle Nuclear Power Station Unit One is a Boiling Water Reactor 2

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

l contractor was Commonwealth Edison Company.

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g The condenser cooling method is~ a closed cycle cooling pond. - The plant-i t- is subject to License Number NPF-11, issued on April 17, 1982. Th'e 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 numberi(815)357-6761, .

extension 499.

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II.

SUMMARY

OF OPERATING EXPERIENCE'FOR UNIT ONE l

July 1-2 The unit was shutdown from the reactor scram for STP-27 which occured at 22A1 on June 30.

July 3-16 The reactor went critical at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> on July 3. At 1247 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.744835e-4 months <br /> on July 4 the main generator was synchronized to the grid and loaded, Reactor power was then gradually raised to 68% on July 8, reaching 25% on July 4 at~1445 hours and 48% on July 5 at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. On July 8 at 1432 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.44876e-4 months <br />, reactor power was reduced to 41% for STP-29 Reactor power was r .aised to 66% at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on July 10.

On July 16 at 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> the reactor scrammed due to Turbine '

Control Valve fast closure due to STE/GE working on 22VDC house power supply to EHC. The reactor was critical for 316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br /> and 50 minutes.

July 17-18 The reactor went critical at 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br /> on July 17. On July 18 at 1133 hours0.0131 days <br />0.315 hours <br />0.00187 weeks <br />4.311065e-4 months <br /> the reactor scrammed from level 3 due to loss of EHC power supply while the Instrument Maintenance Department was troubleshooting the system. The reactor was critical for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> and 58 minutes.

July 19-27 The reactor went critical at 2035 hours0.0236 days <br />0.565 hours <br />0.00336 weeks <br />7.743175e-4 months <br /> on July 19 At 1607 hours0.0186 days <br />0.446 hours <br />0.00266 weeks <br />6.114635e-4 months <br /> on July 20 the main generator was sychronized to the grid and loaded to 28% power. On July 21 at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> reactor power was 50%. From July 21 at 1640 hour0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br />st.

0422 hours0.00488 days <br />0.117 hours <br />6.977513e-4 weeks <br />1.60571e-4 months <br /> on July 27, the reactor power was 70%. At 0422 hours0.00488 days <br />0.117 hours <br />6.977513e-4 weeks <br />1.60571e-4 months <br /> the reactor scrammed due to a spurious low pressure signal which resulted with MSIV closures. The reactor was critical for 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> and 47 minutes.

July 28-29 The reactor went critical at 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br /> on July 28. At 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> the main generator was sychronized to the grid and loaded. On July 29 at 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br /> reactor power was 58%;

at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> on July 29 the reactor scrammed due to spurious low pressure signal resulting in MSlV closure.

The reactor was critical for 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> and 5 minutes.

July 30-31 The reactor went critical at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> on July 30. At 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> on July 30 the main generator was synchronized to the grid and loaded. From July 30 at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> to 2400 on July 31 reactor power. was 23%. The reactor was critical'for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 55 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.

STP FSAR Table 14.2-123 has been revised for STP-26, Relief Valve Startup Test. This change deletes measurement of SRV capacity.

Based on FSAR Table 5.2-12 and Figure 5.2-3, Unit 1 safety relief valves have the required capacity. There was no unreviewed safety question.

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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VI. . UNIQUE REPORTING REQUIREMENTS 4

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-reIIef valves was actuated, how it was activated and the circumstances resulting in its actuation.

Valves No & Type Plant Description Date Actuated Actuations Conditions of Events

' 7-27-83 1821-F013E 4 Automatic 965 psig Group l-isola tionJ SRV 1 Manual lifted for Reactor..

pressure control 7-29-83 IB21-F013R 5 Automatic 965 psig Main Steam isolation caused j the scram i

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l VI. UNIQUE REPORTING REQUIREMENTS l (Con't.)

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

Outage No. Equipment Purpose of Outage 1-711-83 Div. I Water Leg Investigate Pump tripping Pump 1-712-83 Div. I Water Leg Repair pump Pump 1E21-C002 1-718-83 Div. I Water Leg Repair pump 3

Pump 1E21-C002 1-728-83 1E22-S001 Clean and Inspect Changes HPCS Battery charger 1-737-83 1E12-F016B Replace switch Contactor Drywell Spray Upstream Stop Valve 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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WORK REQUEST LER C0tlP0llEllT CAUSE OF MALFullCTI0li RESULTS Atl0 EFFECTS CORRECTIVEACT10fll Oil SAFE OPERATl0ll 25968 83-073/01T.0 Div. I Low Low Level incorr'ectly landed leads None, since other ECCS Leads correctly 1 Initiation Switch Division i Systems were landed, lead seals available and operable installed for 30 day; trial period AIR 1-83-67044

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25350 83-064/03L-0 Div i Post Loca Dvst particles in the None, since sediment Recalibration of Monitor metering valve at the monitor operable monitor oxygen analyzer cell 25549 83-061/03L-0 'A' MSIV LCS Pipe Failed breaker installed new Header C/B -

breaker 25631 83-074/03L-0 Contro'i Rod 42-23 Accumulator 25578 RHR Discharge tc Torque switch open, dirt Valve won't seal in Contacts cleaned Radwaste inboard in contacts Torque switch reset Isolation i 1

25755 Exterior Drywell Door out of adjustment Interlock defeated Loss' of Adjusted door I access hatch primary containment I integrity 26013 0XY-VC-165A Ammonia Cassette tape broken No continuous monitoring Replaced cassette Detector tape 26040 HPCS D/G Cooling Defective relay Fan won't run continuously Replaced relay H2O pump & supply Fan - Div lil 26039 'A' RHR Discharge Transmi tter out of cal . Pressure Indication would Recalibrated Pressure Indicator read high transmitter i

HPCS D/G Defective ' switch H! pressure alarm won't Replaced switch 25752 clear P.C. Cam Supp. Cham. 140NE Won't close " Group 2 Lifted lead, to givei 26060 isolation valve isolation signal -50 isolation signal andl ICM027 as required valve closed as l required.

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LER C0llP0llEllT CAUSE OF liAl.FUllCTIO!! RESULTS AllD EFFECTS CORRECTIVE ACT10ll VORK REQUEST Oil SAFE OPERATI0li 26099 Post Loca Gross Bad chart drive motor No continuous monitoring Replaced chart drive Gamma Rad recorder motor 25486 U-1 Div lil Battery Ground lead on R1015 Inoperative diesel fire Relanded lead fire pump 25612 1821-F028D Outboard HONE Required for Startup and Cycled valve itS I V Shutdown 26042 RCIC Testable Check Failed air cylinder Required for shutdown Replaced air d

a cylinder and cycled' 25726 HPCS Min Flow Bypass Internal wiring inside Required for operation Properly installed Valve valve operator. improperly wiring f installed 26316 'B' Diesel Fire Pump Loose Bolts on Exhaust Tightened exhaust Header Exhaust flanges flanges 26309 1821-F022B NONE Required for shutdown ] cycled valve 26310 1821-F028B NONE Required for shutdown cycled valve ,

26166 Main Steam Line Rad Failed relay Nocontinuousmonitoring[ Replaced K-4 relay 25742 Flow pressure switch Switch out of cal. Fan will not run Recal. switch 25876 U-2 Div ll/Div til Broken shear pin None, door was repaired Machined new shaft Water Tight Door promptly i

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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, July 1 thru July 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 Specifications.

Licensee Event Report Number Da te Title of Occurrence i 83-061/03L-0 6-22-83 Inboard HSL LCS Heater Failure (1E32-8001A).

83-062/03L-0 6-12-83 Failure of Hydrogen Analyzer A

! 83-063/03L-0 6-13-83 Failure of Div. I Hydrogen Recorder 83-064/03L-0 6-13-83 Div. I Post Loca.0xygen Monitor 83-06J/03L-0 6-15-83 Post Loca Oxygen 83-066/03L-0 6-17-83 Fall to Indicate Close of HPCS Testable Check'

83-067/03L-0 6-17-83 Fail to Indicate Close of HPCS Testable Check ~ . ,

Bypass 83-068/03L-0 6-11-83 Supp'. Pool Temperature Div. l ,.

83-069/03L-0 6-20-83 Failure of_ Dampers 10VE07YB, OVE08YB, and OVE09YB

83-070/03L-0 .6-24-83 Concerning Waste Transfer Line Leaking 83-071/03L-0 ' 6-25-83 Outboard MSIV 1821-F028D Suspect Limit SW

. Problem 83-072/03L-0 9-83 HPCS Inop 83-073/01T 7-14-83 Div'l Low Low Level Initiation-

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Licensee Event Report Number Date Title of Occurence' 83-074/03L-0 6-27-83 Control' Rod 42-23 Accumulator High Water Level 83-075-03L-0 7-09-83 Div.-1I and Div. III Watcr Tight Dcor (U-2)

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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' - OPERATING DATA REPORT

- DOCKET NO. 050-373 UNIT LaSalle One I ' .

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s DATE Aumme R IgR3

• CCMPLETED BY Diane L. t.in '

, - TELEPHONE (815)357 .6761 l s

t OPER ATING STATUS .

J'ly u 1981 744 *

1. REPORTING PERIOD: GROSS HOURS IN R EPORTING PERICO*

M AX. DEPE ND. CAPACITY (MWpNet): 0 l

2. CURRENTLY AUTHORIZED POWER LEVEL (MW : 1007 DESIGN ELECTRICAL RATING (MWe. Net): 075 l

3. POWER LEVEL TO WHICH fitSTRICTED (IF ANY) (MWeNo.): N/A

. 4. REASONS FOR RESTRICTION (IF ANY]:

' ' THl! MONTH YR TO DATE ',CUMULATIV E I

• S. NUM8ER OF HOURS REACTOR WAS CRITICAL ...............p80.6 2371.8 6009.2 0 0 0

. a. REACTOR RESERVE SHUTDCWN HOURS . . . . . . . . . . . . . . . . . . . '

7. HOURS GEN ER ATOR ON LlH E . . . . . . . . . . . . . . . . . . . . .. . . . . 501. 5 2117.88 397s.48 0 0 O S. UNIT RESERVE SHUTOOWN HOURS ...................... ,

S. GROSS THERMAL ENERGY GENER ATED (MWH) ............. 1028s97 141s980 5s76sco

10. GROSS ELECTRICAL ENERGY GENERATED IMWHI 121018 1b22048 198711A i

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N/A N/A - N/A i

11. NET ELECTRICAL ENE81GY GENER ATED (MWH) ..............

N/A N/A N/A

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

N/A N/A 4 13. REACTOR AVAILASILITY FACTOR . . . . .~. . . . . . . . . .'. . . . . . . . N/A '

N/A N/A N/A

< 14. UNI T SE RVlCE F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

N/A N/A

15. UNIT AVAILASILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . N/A'

16. UNIT CAPACITY FA OR tusing MDC) ..................... N/A N/A N/A l

17. UNIT CAPACITY ITACTOR (using Design MWel . . . . . . . . . . . . . . . . . N/A N/A N/A

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,' 18. UNIT FC$ 'l:ED QUhAGE R ATE . . . . . . . . . . . . . . . . . . . . . . . . . N/A 8 f ,

19. ,$HUTDOWNS SCHEDULED OVER NEXT 6 MCNTHS (TYPE. OATE. ANO OURATION OF EACHl:

L' 20..lF SHUT DOWN AT END OF REPORT PERIOO. ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS IPR 10R TO COi.4MERCIAl.OPER ATIONh FORECAST ACHIEVED ,

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6/2I/82 .

INITIA L ELIECTRICITY 9/4/82 x'

- CouuERCIAi. On p.ATiON 9/23/83 .

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-373 dNIT LaS'lle a One

, OATE August'8, 1983

[ COMPLETED By Diane L. Lin TELEPHONE (815)357-6761

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MONTH July 1983

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

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4. i19 20. '61

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5. 517 21. 565

6. 684 22. 726

7. 476 23 660

8. 554 $ 24.

731 9 599 25 708

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10. 603 26. 706

11. 657 27 112

12. 716 -

28. 0

'13 7nt . '29 '475

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~ 731 30. 5 15 731 -31. ~2 66

16. 506

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November i3, 1979 '

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UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET N0. 050-373 UNIT NAME Lasalle one DATE August 8. 1983

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REPORT MONTH July 1983 ,

COMPLETED BY Diane L. Lin'.

TELEPil0NE (815)357-6761 ,

HETHOD OF -

SilUTTING DOWN TYPE DURATION

- THE REACTOR OR REDUCING POWER.(2) CORRECTIVE ACTIONS / COMMENTS DATE '5:F: FORCEO SCllEDULED (HOURS) . REASON (1)

NO.

4 Rx. scram from STP-27

. 23 7-1-83 F 60.2 B

/ 5 For STP-30 24 7-7-83 3 0' H .

H 5 For STP'-29

" 0 25 7-8-83 g A 3 Rx. scram on Turbine Control 26 7-16-83 -

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28.5 .

. Valve fast closure B

3 Rx. scram from level '4 due 27 7-18-83 F . .33.0 ,

to loss of power supply while the Instrument Department was troubishooting the system.

A 3 Rx. scram due to MSIV 28

'7-27-83 F 29.8 ~ closure

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3 ' Rx. scram due to MSIV 7-29-83 'F ' ~ 11.8 , A closure on low steam 29

. line pressure.

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'"N Commonwealth Edison

/ LaSalle County Nuclear Station

) RuralRoute #1, Box 220 i

-' 7 Marseilles, Illinois 61341

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/ Telephone 815/357-6761 August 8, 1983 Director, Of fice of Management Information and Program Control United States Nuclear Regulatory Conunission 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 July 1 through July 31, 1983.

Very truly yours, G. J. Died ch Station Superintendent GJD/DLL/rmp Enclosure xc: J. G. Keppler NRC, Region 111 NRC Resident inspector LaSalle Gary Wright 111. Dept. of Nuclear Safety D. P. Galle Ceco D. L. Farrar CECO INPO Records Center 8/ /