Text

Monthly Operating Rept for Feb 1983
	ML20073E718
Person / Time
Site:	LaSalle
Issue date:	03/07/1983
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20073E670	List: ML20073E663; ML20073E718;
References
	NUDOCS 8304150288
	Download: ML20073E718 (14)
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LASALLE NUCLEAR POWER STATION UNIT I MONTHLY PERFORMANCE REPORT FEBRUARY, 1983 i

i COMMONWEALTH EDIS0N COMPANY i

i NRC DOCKET NO. 050-373 l

l LICENSE NO. NPF-11 i

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TABLE OF CONTENTS

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INTRODUCTIONi i

11.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE lli. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY. RELATED MAINTENANCE

' mendments to Facility License or Technical Specifications A.

A 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 4

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions VI.

UNIQUE REPORTING REQUIREMENTS i

A.

Main Steam Relief Valve Operations B.

ECCS System Outages i

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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INTRODUCTION i

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

- with a designed electrical output of 1078 MWe net, located in Marseilles, l

Illinois. The Station is owned by Commonwealth Edison Company.

The l

l 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 com-nercial generation of power.

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

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SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE l

February 1.

The unit was shutdown due to the "B" RHR Pump being declared Inoperative due to excessive pump vibration.

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'4 February 2-5.

The reactor went critical at 1113 hours0.0129 days 0.309 hours 0.00184 weeks 4.234965e-4 months on February 2, 1983 4

At 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months a steam leak was observed on a Main Steam Line Drain.

At 2150 the reactor was shutdown. The reactor was critical for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and i

37 ninutes.

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February 6-18.

The reactor went critical at 1047 hours0.0121 days 0.291 hours 0.00173 weeks 3.983835e-4 months on February 6.

1 At 0909 hours0.0105 days 0.253 hours 0.0015 weeks 3.458745e-4 months on February 7, 1983 the reactor was shutdwon due to a steam leak on B inboard Main Steam Line drain pipe. The reactor was critical for 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months and 22 minutes.

February 19-28.

The reactor went critical at 0035 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months on February 19 t

At 2110 the main generator was synchronized to the grid and load increased to 100 MWe. At 1035 hours0.012 days 0.288 hours 0.00171 weeks 3.938175e-4 months on February 20, 1983 the main turbine was i

unloaded for, LOS-TG-SA2, Turbine Valve Leak Tightness Surveillance. At i

l 1810 hours0.0209 days 0.503 hours 0.00299 weeks 6.88705e-4 months the main generator was synchronized to the grid and loaded to 130 MWe.

At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on February 21, 1983 load was increased to 355 MWE.

i At 1545 hours0.0179 days 0.429 hours 0.00255 weeks 5.878725e-4 months on February 25, 1983 load was reduced to 200 MWe due to being unable to regenerate the condensate polishers. The reactor was crit ical 'for 239 hours0.00277 days 0.0664 hours 3.95172e-4 weeks 9.09395e-5 months and 25 minutes.

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Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED i

j MAINTENANCE l

A.

Amendments to Facility License or Technical Specifications.

f There were no amendment to facility license-or technical specifica-l tion during the reporting period.

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Facility or Procedure Changes Requiring NRC Approval.

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There were no facility or procedure changes requiring NRC approval f

during the reporting period.

j C.

Tests and Experiments Requiring NRC Approval.

3 There were no tests or experiments requiring NRC approval during the j

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reporting period.

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Corrective Maintenance of Safety Related Equipment.

I The following tables present a summary of safety-related maintenance j

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completed on Unit One during the reported period. The headings i.

indicated in this summary include: Work Request Numbers, LER Numbers, i

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Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.

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WORK REQUEST LER C0flP0flEllT CAUSE OF MALFUllCT10tl RESULTS A!1D EFFECTS C0llRECTIVE ACTI0il ON SAFE OPERATI0li l

L20993

'B' RHR Outboard Broken torque switch Indicates full closed when Replaced torque Drain Valve valve is about 1 turn from switch full closed.

L21351 IB Diesel Generator Bendix was bad Would no start Replaced bendix Air Compressor L21913 CSCS Equipment Love controller out-of-Damper did not cycle Recalibrated love Cooling and Ventila-adj ustmen t controller tion Duct

fl IN Solenoid Valve Bad tape on lug conne.c-Sparked when bumped Retaped lug connec-L22023 tion tion 1

L22145 f

RCIC/LPCS Watert ight Mechanism disconnected Interfers with proper door Reconnected Door operation mechanism L22270 83- 008/03 L-0 Mechanical Snubber Missing pin in rear Snuboer not pinned to Installed pin bracket building Repaired crack L22331 83-007/03L-0

'C' Inboard MSIV Crack in weld Lines leaked prain Line L22338

'D' Main Steam Line No lathern ring Valve leaks s'

Repacked valve Drain Valve L22420 83-010/03L-0 Piping Restraint Extra restraint No effect Removed restraint L22453 1 A MSIV Outboard Bent line No effect Replaced bent pipe Drain Line t

L22454 83-001/0lT-0 RHR Inj ect ion Valve Bad switch Switch leaked Replaced switch Pressure Switch

'B' L22455 83-001/0lT-0 RHR Injection Valve Bad switch Nd effect Replaced switch Pressure Switch 'D' e'

L22478 VC B Train Radia-Bad amphenol connector Monitor will not stay Replaced amphenol tion Monitor energized connector L22489 83-001/0lT-0 1821-N413C Pressure Bad switch Switch leaked Replaced switch Switch

V0llK IlEQUEST LER C0llP0llEllT CAUSE OF MALFullCTI0li RESULTS AllD EFFECTS C0!lRECilVI. ACIl0lb O!! SAFE OPERATIO!!

L22490 Shutdown Cooling Packing was loose Val.ve leaked Adj usted packing Inboard Isolation Valve L22552 s

Bus 111Y Breaker #17 Water in junction box Received ~30 V ground Retaped leads L22578 1A Diesel Generator Defective diode No effect Replaced dio~de Re lay K-11 Main Steam Line Defective K-56 relay Valve does not close on a Replaced relay L22595 Inboard Drain isola-group one isolation signal (1

d tion Valve L22433 J 1A Inb'oard MSIV Bad weld Leaking Rewelded line L22438f Drain Line IB Inboard MSIV Bad weld Leaking Rewelded line L22385 -

L22386 Drain Line Rewelded line ID Inboard MSIV Bad weld Leaking L22434 L22439 Drain Line l

fA Outboard MSIV Bad weld Leaking Rewelded line L22411 Drain Line j e L22430 IB Outboard MSIV Bad weld Leaking Rewelded line L22435 Drain Line L22431 IC Outboard MSIV Bad weld Leaking Rewelded line L22436 Drain Line L22432 1D Outboard MSIV

, Bad weld Leaking Rewelded line L22437 Drain Line

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4 IV.

LICENSEE EVENT REPORTS The followlog is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the i

reporting period, February 1 to February 28, 1983 This information is provided pursuant to the reportable occurrence reporting require-l ments as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

't Licensee Event Report Number Date Title of Occurrence 83-001/01T-0 2/11/83 Reactor Vessel Low Pressure LPCS/

LPCI Injection Valve Pressure 83-005/01T-0 2/7/83 Leak Detection Temperature Switches Out of Calibration 83-006/03L-0 2/2/83 Cracked Weld on MSL Drain 83-007/03L-0 2/7/83 Primary Containment Pressure Boundary Leakage j

83-008/03L-0

/3/83 Inoperable Mechanical Snubber i

83-009/03L-0 2/8/83 Inoperable Mechanical Snubber

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83-010/03L-0 2/9/83 Piping Restraint Installed in Violation of Design i

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1 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 r

ATIAC' HEC D Revision 2 3

_ NOver5ber 13,.197 9

l OPERATING DATA REPORT 050-373 DOCKET NO. LaSalle UNIT nne March 3, 1983 DATE Diane L. Lire COMPLETED BY TELEPHONE (815)357-6761 x499 l OPERATING STATUS e

ay $3 GROSS. HOURS IN REPORTING PERIOD: b72

1. REPORTING PERIOD:

1002:

M AX. OEPEND. CAPACITY (MWo. Net): 0

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):

DESIGN ELECTR6 CAL RATING (MWeNet):

107R

3. POWEA LEVEL TO WHICH RESTRICTED (IF ANY) (MWeNet):

4. REASONS FOR RESTRICTION (IF ANY):

TH13 MONTH YR TO CATE ',CUMULATIV E

5. NUM8ER OF HOURS REACTOR WAS CRITICAL,..............

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8. REACTOR RESERVE SHUTDOWN HOURS

7. HOUR $ G EN E R ATO R ON LIN E..........................

0 0

0

8. UNIT RESERVE SHUTOCWN HOURS

....... 224508 224508 ' 2365087

9. GROSS THERMAL ENERGY GENEP \\TED (MWH1 k

58518 58518 578917 to. Gross ELECTRICAL ENERGY GENERA TED (MWH)..

45934 45934 506709

11. NET ELECTRICAL ENERGY GENER ATED (MWH)

NA NA NA I

12. R EACTCR SERVIC E F ACTO R...........................

NA NA NA

13. REACTOR AVAILA BILITY F ACTOR.......................

NA NA NA b

14. UNIT SERVICE FACTOR NA' NA NA

15. UNIT AVAILA88 tlTY F ACTO R..........................

NA NA NA L

16-UNIT CAPACITY FACTOR (Using MOC)

NA NA NA

17. UNIT CAPACITY F ACTOR (Useat Design MWel.................

18. UNIT FO R CE D CUTAG E R ATE..........................

NA NA PJ A e

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND OURATION OF EACH1:

NA

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

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATICN):

FORECAST ACHIEVED 6/21/82 i

luiTi AL CRITICALITY 9/4/82 INITIAL ELECTRICITY 4/1/83 ComMtRC AL OPERATlON L

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Due to cor rection made in September 1982 report.

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LTP-300-7

~~~.:. Revision 2--

, November 13, 1979

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5 ATTACHMENT A AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

050-373 LaSalle NNIT One DATE Mar'ch 3, 1983 COMPLETED BY Diane L.' Lin i

TELEPHONE (81'5)357-6761 x499 l

' MONTH February 1983

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

4 (MWe-Met)

(MWe-Net) i O

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0 17 i

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0 18.

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3 0

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0 21.

265

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0 22.

360 1

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0 23 391 24.

341

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0 4

9 0

25, 261 1

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0 26.

182 l

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0 27 167 i

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0 28.

177

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0 30.

15; o

31.

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LTP-300-7 Rsvision 2 Novernber 13., 1979 6

ATTACllHENT B UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

050-373 UNIT NAME LaSalle One March 3, 1983 DATE REPORT HONTH Fe'bruary 1983 COMPLETED BY Diane L.

Lin f

TELEPil0NE (815)357-6761 x499 HETif0D OF SilVTTING DOWN TYPE Tile REACTOR OR NO.

DATE S: SCHEDULED (ll0URS)

REASON (I)

REDUCING POWER (2)

CORRECTIVE ACTIONS / COMMENTS l:

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Normal shutdo'wn due to

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12/31/82*

F 45.8

" Unusual Event" due.to l;

"B" RHF} Pump being inop.

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1 Steam leak from "A" Out-li 2

2/2/83 F

107.3 board Main Steam Line

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Drain Pipe due to cracked i

I welds.

I Steam leak on "B'i inboard

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A 1

3 2/7/83 F

300.1

.MSL drain pipe due to cracked weld.

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2/20/83 F

7.'6 B

9 Turbine off loaded to i

perform LOS-TG-SA2 Turbine f

Valve Leak Tightness Test.

Refer to the December 1982 report.

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l VI.

UNIQUE REPORTING REQUIREMENTS A.

Main Steam Relief Valve Operations for Unit 1 Relief valve operations during the reporting period are summarized in the following table. The table includes 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 2/19/83 IB21-F013C 2 Manual 1000 psig To verify proper valve operation af ter a solenoid replacement.

2/19/83 1821-F0135 3 Manual 1000 psig To verify proper posi-tion indication after removing the position indication assembly to gag the valve for a vessel hydro.

I 2/19/83 1821-F013U 3 Manual 1000 psig To verify proper posi-tion indication after removing the position indication assembly to gag the valve for a vessel hydro.

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 j

during this reporting period.

1 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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ML20073E718

Text

SUMMARY

SUMMARY

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