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LASALLE-NUCLEAR POWER STATION

- UN I T ''1 '\

MONTHLY. PERFORMANCE REPORT-

. AUGUST 1983

'

. COMMONWEALTH EDISON COMPANY

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NRC DOCKET N0~. 050-373

LICENSE NO. NPF-11

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" . 83091'40077 830907>; PDR ADOCK 05000373- R PDR ,

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TABLE OF CONTENTS

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-!.. fl'NTRODUCTION

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|: 11. : SUMMARY-.0F OPERATING EXPERIENCE.FOR UNIT ONE

- 111. PLANT ~ 0R PROCEDURE. CHANGES,1 TESTS, EXPERIMENTS, AND SAFETY RELATED

} MAINTENANCE

A. Amendments to' Facility Liccnse-or Technical-Specifications-Facility or. Procedure Changes Requiring NRC ApprovalB. :

CL - Tests.and' Experiments Requiring NRC Approval~"

D. Corrective Maintenance of Safety Related Equipment

E - lV. LICENSEE EVENT REPORTSu

-V. DATA 1TABULAT10NS

- A. Operating Data ReportB.- Average Daily Unit Power ~ Level~

. C. Unit Shutdowns and' Power Reductions

-VI. UNiquELREPORTING REQUIREMENTS-.

A. ' Main' Steam Relief Valve.0perations-B. . ECCS System Outages

- C. ; . 0f f-Si te Dose : Calculation Manual- Change:LD. Major Changes to. Radioactive Waste Treatment System. E .3 Changes ~to the Process Control ~ Program

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- 1. -lNTRODUCTION

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

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

'lllinois.' 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~

oftinitial criticality.was June 21,'1982. The unit has not commenced.

commercial generation of power.x

1This 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

August 1-12 The unit started the reporting period at approximately 54%reactor power. At 0221 hours on August 4 reactor power was reduced torestart the RR pumps. Reactor power was 36%. At 0700 hours on August 4reactor power was increased to 63%. At 0445 hours on August 7 reactorpower was 83%. At 0200 hours on August 8 the reactor was at 100% power.On August 9 at 0250 hours reactor power was reduced from 95% to 64%. At2212 on' August 9 reactor power was 92%. On August 11 at 1728 hoursreactor power was decreased to approximately 70% for reactor recirc testing.At 0945 hours on August 12 reactor power was increased to 90% via reactorrecirc system. On August 12 at 1250 hours the reactor scrammed whileperforming LIS-NR-04 the section on APRM Channel C, flow bias referenceset point. Received a downscale trip which caused the RR FCV to open andthe unit to scram. The reactor was critical for 276 hours and 50 minutes.

August 13-31 The reactor went critical at 0600 hours on August 13 At1413 hours on August 13 the main generator was synchronized to the grid andloaded. At 2300 hours on August 13 reactor power was 47%. At 1500 hours onAugust 14 reactor power was 71%. On August 16 at 2100 hocrs reactor powerwas 95%. At 1705 hours on August 18 reactor power was redJced due to aGSEP alert initiated because of the 'A' VE Charcoal bed getting wet. At 2323hours on August 18 reactor power was 52%. At 1700 hours on August 19 reactorpower was 80%. On August 20 at 0932 the reactor scrammed due to low feedwaterflow. On August 22 this outage was continued to replace the "B" recirc pumpseals, heater drain system modifications and local leak rate testing. Alsothe main control valves were converted from partial arc to full arc steam

admission. The reactor was critical for 171 hours and 32 minutes.

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Iilli. PLANT 0R PROCEDURE. CHANGES, TESTS, EXPERIMENTS AND' SAFETY RELATED

rMAINTENANCE- |~

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- . A. Amendments. to Facility | License or. Technical Specifications. l.

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5There were.no amendments to the: facility. license.or technical -|1

:6 specifications during the. reporting period. |'1.

B. Fac'ility'or Procedure Changes' Requiring NRC Approval.

,There were no| facility orfprocedure changes' requiring NRC approval."

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during'the reporting period.

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C '. . Tests and' Experiments Requiring'NRC. Approval.*

11ere were no tests or experiments requiring NRC approval during

the: reporting' period.,

D. : Corrective Maintenance of Safety Related Equipment.

The following tablesipresent.-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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W0llK REQUEST LER C0llP0llEllT CAUSE GF MAlfullCT10ll RESULTS All0 effec 1S LOnL i 1.1 wp viii

ON SAFE OPERATIO!!-

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--- - D/G Air Receiver Bad Valve Valve leaks Replaced valveL23265' Pressure Indicator

Isolation Valve.

Battery.

Unit One 250 V Charger Bad breaker Breaker is weak Replaced b_reakerL23828 ---

L25831 83-080/03L-0 LPCS Water Leg Pump Locked bearing Pump frozen with the Replaced bearings,outboard bearing locked. , oil seals,

mechanical seal,

(j shaft, shaft sleeve#.

L25902 4 83-082/03L-0 Rx Bldg. Vent Exhaust Bad GM tube Spurious upscale trip Replaced GM tube

{ P1enum Rad Monitor Ob, served.

L26033 83-077/03L-0 Ammonia Dectecor Bad master fault bulb Optical unit not working Replaced master*

fault bulb

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L26044 83-083/03L-0 SBGT WRGM Blown fuse Pump didn't start in || Replaced forsemanual

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L26101 83-078/03L-0 LPCS Injection Valve Switch out-of-adjustment Alarm is up when pressurd Recalibrated switchLow Pressure Switch is not low

Unit 1 Fuel Pool Vent Bad detector tube Background response Replaced detectorL26118 ---

L26119 PRM A & B increasing over time tube.

RHR Service Water Bad fuse Cubicle has high Replaced fuseL26207 ---

Pump A-B Cubicle ?. Temperature

Temperature Hi Alarm

L26576 - - , HPCS Discharge Air trapped on high Gauge reads lower than Vented airPressure Gauge side of gauge local gauge'

L26617 --- Division i Post Loca Motor drive out-of Recorder readsu2% Realigned motorHydrogen Monitor alignment. Pen drive Hydrogen with the unit . drive. Tightened

& spring loose. S/D pen drive andspring

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ORK REQUEST LE C0lth0ilEllT CAUSECFllAlFblCTIO!! RESULTS AllD EFFECTS CORRI.C l IVL f. sci 10li

ON SAFE OPERATION.

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OPL58JA Pen #1 Problem'due to heat ' Pen is stuck downsca'le Fixed cooling' fansL26654 ---*

Chlorine Detecter Bad Felt wick Electronic drip rate Replaced felt wick026657 ---,

L26658 A&B exceeds 4 minutes as'

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specified in vendor manua..

L26707 --- Leak Detector AT Bad amplifier Recorder pegs high and/or Replaced amplifierRecorder low when it is pulled out

and. pushed in4y

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Standby Gas Treatment Bad chart drive motor Paper does not advance ' Replaced chartL26878 ---

f system Effluent and drive motorlodine Recorder .

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L27036 --- "1B" LPCI Testable Appears Spring tension Valve binds requiring Cleaned andCheck was set too, tight wrench assist to open relubricated

*and close bearing. Reset. . .

! timing. Adj usted. spring tension.

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"lC" LPCI Testable Limit Switch dirty Valve did not cycle / Cleaned limitL27037 ---

Check properly switch

L27181 --- 250 VDC Battery Blown fuse Keeps tripping both AC Replaced fuseCharger feeds and DC output

hreakers

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N IV.-| LICENSEE EVENTEREPORTS.

1The following:Is a tabular summary of all'llcensee event' reports

, _ ifor LaSalle Nuclear Power Station, Unit One, occurring during' the

f reportingiperiod, August 11 through August - 31,1983. ; This information -

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.-Is L provided pursuant i to the reportable ~ occurrence reporting ' require .t

'ments;as set forth in section 6.6.B.1_and-6.6.B.2 of.the Technical.

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(Specifications.- ""

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' TLicensee Event Report Number Da te Title of Occurrence

83-076/03L-0 7-09-83 RCIC Steam Line High Flow .

Isolation

83-077/03L-0$ 7-16-83 B System Ammonia Detector'

t.83-078/03L-0 7-19-83' Reactor Vessel Low Pressure' '

. LPCS Injec' tion Valve Permissive,

'83-079/03L-0 7-08-83 -; Reactor Low. Pressure-RCIC' Isolation

83-080/03L-0- 7-07-83 LPCS Water Leg Pump

f 83-081/03L-0 17-18-83 Hole in FW Pipe. .

83-082/03L-0 7-11-83 Stack WRGH.

:.83-083/03L-0 7-17-83 SBGT WRGH--

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83-084/03L-0 7-18-83- PCIS Valve 1CM027 Failed:- to '. I sol a te

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83-085/03L-0 7-22-83- Failure of a RHR SW PRM Sample Pump

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183-086/03L-0: .7-24-83: . Unit 2 Division:1 Battery. Charger .

, .83-087/03L-0 7-18-83. Bypass. Valves Failed Open/ECCS Initiation

* 83-088/03L-0. . 7-27-83' i11Inois : Dept. of Nuclear . Safety'

_Uncontrolled Release.

,' 83-089/03L-0- .7-25-83.: . Failure of Unit-2 SBGT Heaters toEnergize'

183-090/03L-0 '7-26-83 -Leakiin Line Designed to Contain'

Radioactive Liquid

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Licensee' Event' Report Number . Date - Title of Occurrence ' i

83-091/03L-0 .8-04-83 Reactor Vessel Lo Lo Water' Level-

~83-092/03L-0 8-01-83 . Control Rod 34-43 Accumulator inop'<

183-093/03L-0 8-01-83 Control Rod 34-47 Full.In Light inop-

83-094/03L-0 8-05-83 Radwaste Discharge Sample Pump Seal"

Failure

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,. V. - . DATA TABULATIONS-

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e - The following: data tabulations are presented in this report: ,

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_ _ .c A.- (Operating Data Report.

- - B'. -Average Daily ~ Unit Power Level'

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nVI. . Unique? REPORTING REQUIREMENTS

cA. Main-Steam' Relief Valve Operations for Unit 1,

ThereLwere 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-'-

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period:

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Outage No. -Equipment Purpose =of Outage' -

1-777-83 HPCS Water Repair Oil Leak'

Leg Pump

1-796-83 .HPCS Water Replace PumpLeg Pump

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C. 'Off-Site Dose Calculation Manual

:There were no changes to the Off-Site Dose Calculations

-Manual during this' reporting period.

-D.- 1 Radioactive. Waste Treatnent System

There were no changes to the Radioactive Waste Treatment

. System during this reporting period.

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E. Process Control Program

There were no changes to the' Process Control Program during this,

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ATTACIDfENT D Revisich 2'*. . ;

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OPERATING DATA REPORT,

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D'OCKET NO. 040-173. .

. UNIT LaSalle One*

Sept. 7, 1983-

DATE* ' Diane L. Lin*

,. COMPLETED BY.

. - TEl.EPHONE (815) 357 .6761.

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OPER ATING STATUS . .:

Au'aust 1983 GROSS. HOURS IN REPORTING PERICO: 7kk' *

1. REPORTING PERIOD.

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 100% MAX. OEPEND. CAPACITY (MWe. Net): 0. I

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DESIGN ELECTRICAL RATING (MWo. Net): 1076 I

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe. Net):* **

. 4. REASONS FOR RESTRICTION flF ANY1:'

THIS MONTH YR TO DATE ',CUMULATIV E* *,

448.4 1029.0 6457.6- 5. NUM8ER OF HOURS REACTOR WAS CRITICAL . . . . . . . . . . . . . . .

0 0 06. R EACTOR RESERVE SHUTOCWN HOURS . . . . . . . . . . . . . . . . . . .

440.1 2557.98- 4h15.687. HOURS GEN ER ATOR ON LIN E . . . . . . . . . . . . . . . . . . . . . . . . . .

0 08. UNIT RESERVE SHUTOQWN HOURS ......................

............. 1131742 4567722 ' 6708301. . S. GROSS THERMAL ENERGY GENER ATED (MWM)

361365 1383413 1743503_so. GROSS ELECTRICAL ENERGY CENERATED (MWH) . . .~ . . . . . . . . . .

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............. 342556 1268919 172969411. NET ELECTRICAL ENERGY GENERATED (MWH)

NA NA NA12 R EACTOR SE RVICE F ACTOR . . . . . . . . . _. . . . . . . . . . . . . . . . .

NA NA NA13. REACTOR AVAILASILITY F ACTOR . . . . . . . . . . . . . . .'. . . . . . . .

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NA NA NA.*

14. UNIT SERVICE F ACTO R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .NA' NA NA

15. UNIT AVAI LAs t uTY F ACTO R . . . . . . . . . . . . . . . . . . . . . . . . . .NA NA NA |'

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

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

NA NA NA14. UNIT F O R CE D OUTAG E R ATE . . . . . . . . . . . . . . . . . . . . . . . . . . ,

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,19. ,SHUTOOWNS SCHEDULEO OVER NEXT 6 MONTHS (TYPE. DATE. AND OURATION OF EACHl:

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9/11/8320. OF SHUT DOWN AT END OF REPCRT PERICO. ESTIMATED DATE OF STARTUP:.

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

6/21/82INITIAL CRITICAUTY ;

9/4/82 -*

INITIAL ELECTRICITY .

!COMMERCIAL OPERATION !'

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OPERATING DATA REPORT~

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docket NO. 050-373-

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LaSalle One.

NIT.

} DATE Auaust 8. 1983.

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Diane L. Lin'

.COMPLETED BY

|TELEPHONE (815)357-6:761.

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OPERATING STATUS .* '

744 .Ju'ly 1983 GROSS. HOURS IN REPORTING PERIOD:.

1. REPORTING PERICD:

2. CURRENTLY AUTHCRIZED POWER LEVEt,(MWt): 100% MAX. O EPENO. CAPACITY (MWeNet): O ,

DESIGN ELECTRICAL RATING (MWeNet): 1078.

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3. POWER LEVEL TO WHICH RESTRICTED (lF ANY) (MWeNet): N/A

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. A. REASONS FOR RESTRICTION (IF ANY1:

. THl3 MONTH YR TO DATE ",CUMULATIV E*

580.6 2371.8 6009.25. NUM8ER OF HOURS REACTOR WAS CRITICAL ...............

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s. REACTOR RESERVE SHUTDOWN HOURS . . . . . . . . . . . . . . . . . . .501.5 2117.88 397'5.58

7. HOURS G EN E R ATOR ON LIN E . . . . . . . . . . . . . . . . . . . . . . . . . .0 0 0

s. UNIT RESERVE SHUTDOWN HOURS ......................

S. GROSS THER' MAL ENERGY GENER ATED (MWM) ............. 1028597'4435980 %76549

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........ 421018 1022948 154i'ih7~

10. GR'OSS ELECTRICAL ENERGY GENERATED (MWM) . . ..

11. NET ELECTRICAL ENERGY GENERATEC iMWH1 ............. 300122926363 1387138

NA NA NA12. R EACTOR SE RVICE F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

13. REACTOR AVAILA81LITY FACTOR , . . . .~ . . . . . . . . . .'. . . . . . . . NA NA NA,

NA NA NA.*

14. UNIT SERVICE F ACTO R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..

NA' NA NA15. U NIT AVAILA51UTY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

fNA NA NA'16. UNIT CAPAC17Y FACTOR (Using MDC) .....................

NA NA NA17. UNIT CAPACITY FACTOR (Using Design MWe) . . . . . . . . . . . . . . . . .

NA NA NA18. UNIT FORCED OUTAGE RATE .......................... .

.19. ,$HUTDOWNS SCHEDULED CVER NEXT 6 MCNTHS (TYPE. DATE. AND DURATION OF EACHl:

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

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEV ED

6/21/83 .

INITIAL CRITICAUTY ;

9/4/82 ^*

INITIAL ELECTRICITY .

COMM ERCI AL OPERATION -

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ATTACHMENT A ,z,

AVERAGE DAILY UNIT POWER LEVEL '*-

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DOCKET NO. '050-373 -- --

EdNIT LaSalle Orie'

DATE Septt 7, 1983 .**- .

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COMPLETED BY Diane L.'Lin,

_ . . . TELEPHONE (814T 447-6761-

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' . MONTH August 1983 ,:-

: .v.;. . - .

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- DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

(MWe-Net)-

(MWe-Ne t)=-m . .

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'' ' ' *iRevision 2 .*

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November 13,, 1979. ,

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. ATTACllHENT B ,****

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UNIT SHUTDOWNS AND POWER REDUCTIONS',.

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sDOCKET N0. . oso_173,

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UNIT NAME Lasalle one' '

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DATE sept. 7, 1983.

- REPORT H0'lTH August 1983' ,..

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COMPLETED BY Diane L. Lin -

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. . -TELEPil0NE (815)357-6761*

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| HETl100 0F-

| - SiluTTING DOWN.

TYPE-

F: FORCED DURATION. THE REACTOR OR

H0. DATE S: SCllEDULED (1100RS) REASON (1) REDUCING POWER.(2) CORRECTIVE ACTIONS / COMMENTS.

j Reduced power *from 95% to 64%

i 30 8/09/83 F 0- H 5i'

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, -31 8/11/83 S 0' H 5 . Reduced, power for Reactor,*

Recirc. testing,

Reactor. scram due to APRM

32 8/12/83 F 17.2 B 3*

Hi Hi Alarm,- -

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'A' V6 Charcoal Bed got wet'

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33 8/l8/83 F 0 A'

Reactor sqram due'to low,

34 8/20/83 F 278.5 A 3 Reactor water inlet flow. |

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[ Commonwealth Edison" " . - - - "z

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c ) . LcSallaCountyNuctrerStItion-.'- RuralRoute #1, Box 220 -

'> , Marseilles, Illinois 61341;7N y T6tephone 815/357-6761..

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_ September-7, 1983_ .

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~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.

August I through August 31, 1983'

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.Very trul_y yours,

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$ %E^G. J. Diederich.'

Station Superintendent

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| GJD/DLL/rmp

Enclosure|-..

(; .xc: . J. G. Keppler . NRC, Region l l i:NRC' Resident . inspector LaSalle' '

Gary Wright; 111. Dept. of Nuclear Safety,

D. P.-Galle CECO-D~. : L. - Fa r ra r ' CECO -INPO Records - Center

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