Text

Monthly Operating Rept for Aug 1983
	ML20080E781
Person / Time
Site:	LaSalle
Issue date:	09/07/1983
From:	Diederich G, Lin D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8309140077
	Download: ML20080E781 (16)
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LASALLE-NUCLEAR POWER STATION

- UN I T 1 '

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MONTHLY. PERFORMANCE REPORT-

. AUGUST 1983

. COMMONWEALTH EDISON COMPANY NRC DOCKET N0~. 050-373 LICENSE NO. NPF-11

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TABLE OF CONTENTS o

-!.. fl'NTRODUCTION

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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-B. : Facility or. Procedure Changes Requiring NRC Approval

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CL - Tests.and' Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment E - lV. LICENSEE EVENT REPORTS u

-V. DATA 1TABULAT10NS

- A. Operating Data Report B.- Average Daily Unit Power ~ Level

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. C. Unit Shutdowns and' Power Reductions

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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 r-

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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

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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

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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 x commercial generation of power.

1This report was ' complied by Diane L. Lin,; telephone number (815)357-6761, Jextension 499 -

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SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE August 1-12 The unit started the reporting period at approximately 54%

reactor power. At 0221 hours0.00256 days 0.0614 hours 3.654101e-4 weeks 8.40905e-5 months on August 4 reactor power was reduced to restart the RR pumps. Reactor power was 36%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on August 4 reactor power was increased to 63%. At 0445 hours0.00515 days 0.124 hours 7.357804e-4 weeks 1.693225e-4 months on August 7 reactor power was 83%. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on August 8 the reactor was at 100% power.

On August 9 at 0250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months reactor power was reduced from 95% to 64%. At 2212 on' August 9 reactor power was 92%. On August 11 at 1728 hours0.02 days 0.48 hours 0.00286 weeks 6.57504e-4 months reactor power was decreased to approximately 70% for reactor recirc testing.

At 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months on August 12 reactor power was increased to 90% via reactor recirc system. On August 12 at 1250 hours0.0145 days 0.347 hours 0.00207 weeks 4.75625e-4 months the reactor scrammed while performing LIS-NR-04 the section on APRM Channel C, flow bias reference set point. Received a downscale trip which caused the RR FCV to open and the unit to scram. The reactor was critical for 276 hours0.00319 days 0.0767 hours 4.563492e-4 weeks 1.05018e-4 months and 50 minutes.

August 13-31 The reactor went critical at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on August 13 At 1413 hours0.0164 days 0.393 hours 0.00234 weeks 5.376465e-4 months on August 13 the main generator was synchronized to the grid and loaded. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on August 13 reactor power was 47%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on August 14 reactor power was 71%. On August 16 at 2100 hocrs reactor power was 95%. At 1705 hours0.0197 days 0.474 hours 0.00282 weeks 6.487525e-4 months on August 18 reactor power was redJced due to a GSEP alert initiated because of the 'A' VE Charcoal bed getting wet. At 2323 hours0.0269 days 0.645 hours 0.00384 weeks 8.839015e-4 months on August 18 reactor power was 52%. At 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on August 19 reactor power was 80%. On August 20 at 0932 the reactor scrammed due to low feedwater flow. On August 22 this outage was continued to replace the "B" recirc pump seals, heater drain system modifications and local leak rate testing. Also the main control valves were converted from partial arc to full arc steam admission. The reactor was critical for 171 hours0.00198 days 0.0475 hours 2.827381e-4 weeks 6.50655e-5 months and 32 minutes.

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illi. PLANT 0R PROCEDURE. CHANGES, TESTS, EXPERIMENTS AND' SAFETY RELATED rMAINTENANCE-

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

l I 5There were.no amendments to the: facility. license.or technical

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6 specifications during the. reporting period. l

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

,There were nol facility orfprocedure changes' requiring NRC approval.

during'the reporting period.

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

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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 i vii ON SAFE OPERATIO!!

L23265 --- -

D/G Air Receiver Bad Valve Valve leaks Replaced valve Pressure Indicator Isolation Valve

. Battery L23828 Unit One 250 V Charger Bad breaker Breaker is weak Replaced b_reaker 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 L26044 83-083/03L-0 SBGT WRGM Blown fuse Pump didn't start in ll Replaced forse manual L26101 83-078/03L-0 LPCS Injection Valve Switch out-of-adjustment Alarm is up when pressurd Recalibrated switch Low Pressure Switch is not low L26118 ---

Unit 1 Fuel Pool Vent Bad detector tube Background response Replaced detector L26119 PRM A & B increasing over time tube L26207 ---

RHR Service Water Bad fuse Cubicle has high Replaced fuse Pump A-B Cubicle ?. Temperature Temperature Hi Alarm L26576 --, HPCS Discharge Air trapped on high Gauge reads lower than Vented air Pressure Gauge side of gauge local gauge L26617 ---

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

& spring loose. S/D pen drive and spring

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

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L26654 ---

OPL58JA Pen #1 Problem'due to heat ' Pen is stuck downsca'le Fixed cooling' fans 026657 ,

Chlorine Detecter Bad Felt wick Electronic drip rate Replaced felt wick L26658 A&B exceeds 4 minutes as -

.. specified in vendor manua L26707 ---

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

.. , and. pushed in 4y e .

L26878 ---

Standby Gas Treatment Bad chart drive motor Paper does not advance ' Replaced chart system Effluent and drive motor f , lodine Recorder .

L27036 ---

"1B" LPCI Testable Appears Spring tension Valve binds requiring Cleaned and Check was set too,* tight wrench assist to open relubricated and close ... bearing. Reset

! timing. Adj usted

. spring tension.

L27037 ---

"lC" LPCI Testable Limit Switch dirty Valve did not cycle / Cleaned limit Check properly switch L27181 ---

250 VDC Battery Blown fuse Keeps tripping both AC Replaced fuse Charger feeds and DC output hreakers

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N IV.-l 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 .

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

(Specifications.

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 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-83-084/03L-0 7-18 PCIS Valve 1CM027 Failed

- to '. I sol a te

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83-085/03L-0 7-22 Failure of a RHR SW PRM Sample Pump 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 .7-25-83.: . Failure of Unit-2 SBGT Heaters to Energize' 183-090/03L-0

' '7-26-83 -Leakiin Line Designed to Contain Radioactive Liquid a >

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

c A.- (Operating Data Report.

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

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' Unit Shutdowns'and, Power Reductions

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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-period:

Outage No. -Equipment Purpose =of Outage 1-777-83 HPCS Water Repair Oil Leak Leg Pump 1-796-83 .HPCS Water Replace Pump Leg Pump 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

[ reporting period.

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ATTACIDfENT D Revisich 2

.f.-November'l$,.1979

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, OPERATING DATA REPORT

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. D'OCKET NO. 040-173 UNIT LaSalle One DATE Sept. 7, 1983

. COMPLETED BY Diane L. Lin TEl.EPHONE (815) 357 .6761 .

OPER ATING STATUS . .

Au'aust 1983 GROSS. HOURS IN REPORTING PERICO:

7kk *

1. REPORTING PERIOD. . I MAX. OEPEND. CAPACITY (MWe. Net): 0

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 100% i i

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 0

6. R EACTOR RESERVE SHUTOCWN HOURS . . . . . . . . . . . . . . . . . . .

440.1 2557.98- 4h15.68

7. HOURS GEN ER ATOR ON LIN E . . . . . . . . . . . . . . . . . . . . . . . . . .

0 0

8. UNIT RESERVE SHUTOQWN HOURS ......................

............. 1131742 4567722 ' 6708301

. . S. GROSS THERMAL ENERGY GENER ATED (MWM) 361365 1383413 1743503_

so. GROSS ELECTRICAL ENERGY CENERATED (MWH) . . .~ . . . . . . . . . .

............. 342556 1268919 1729694

11. NET ELECTRICAL ENERGY GENERATED (MWH)

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

NA NA NA

13. REACTOR AVAILASILITY F ACTOR . . . . . . . . . . . . . . .'. . . . . . . .

NA NA NA

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

NA' NA NA

15. UNIT AVAI LAs t uTY F ACTO R . . . . . . . . . . . . . . . . . . . . . . . . . .

' NA NA NA l

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

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

NA NA NA

14. 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:

20. OF SHUT DOWN AT END OF REPCRT PERICO. ESTIMATED DATE OF STARTUP:

9/11/83

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICAUTY 6/21/82 INITIAL ELECTRICITY .

9/4/82 -

COMMERCIAL OPERATION !

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. . ATTACIDENT D Revi s,lo'rr 2 November ~1$,.1979

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, OPERATING DATA REPORT

. docket NO. 050-373 NIT LaSalle One

- DATE Auaust 8. 1983

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' COMPLETED BY Diane L. Lin TELEPHONE (815)357-6:761 l OPERATING STATUS .

Ju'ly 1983 744 .

1. REPORTING PERICD: GROSS. HOURS IN REPORTING PERIOD:

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

DESIGN ELECTRICAL RATING (MWeNet): 1078 a

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

N/A

. A. REASONS FOR RESTRICTION (IF ANY1:

. THl3 MONTH YR TO DATE ",CUMULATIV E 580.6 2371.8 6009.2

5. 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 ......................

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

........ 421018

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

926363 1387138

11. NET ELECTRICAL ENERGY GENERATEC iMWH1 ............. 300122 NA NA NA

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

NA NA NA

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

NA NA NA

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

NA' NA NA

15. U NIT AVAILA51UTY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

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

NA NA NA f NA NA NA

17. UNIT CAPACITY FACTOR (Using Design MWe) . . . . . . . . . . . . . . . . .

NA NA NA

18. 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 INITIAL CRITICAUTY 6/21/83 .

9/4/82

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INITIAL ELECTRICITY .

COMM ERCI AL OPERATION -

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z ATTACHMENT A ,

AVERAGE DAILY UNIT POWER LEVEL '*-

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DOCKET NO. '050-373 -

E dNIT LaSalle Orie DATE Septt 7, 1983 .

COMPLETED BY Diane L.'Lin

_ . .. TELEPHONE (814T 447-6761

' . MONTH August 1983 ,:

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

=- (MWe-Net) (MWe-Ne t) m . .

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' ' ' *i Revision 2 .

I November 13,, 1979 6 , . . . ,

. . ATTACllHENT B ,

UNIT SHUTDOWNS AND POWER REDUCTIONS s DOCKET N0. . oso_173

' ' UNIT NAME Lasalle one DATE sept. 7, 1983 REPORT H0'lTH August 1983 .;

COMPLETED BY Diane L. Lin TELEPil0NE (815)357-6761 ,

i l HETl100 0F -

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- SiluTTING DOWN TYPE . THE REACTOR OR F: FORCED DURATION CORRECTIVE ACTIONS / COMMENTS REASON (1) REDUCING POWER.(2)

DATE S: SCllEDULED (1100RS) j H0. Reduced power *from 95% to 64%

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. Reduced, power for Reactor, 0' H , Recirc. testing 31 8/11/83 S

3 Reactor. scram due to APRM B

8/12/83 F 17.2 -

Hi Hi Alarm 32 -

5 'A' V6 Charcoal Bed got wet 0 A 33 8/l8/83 F ,

Reactor sqram due'to low A 3 8/20/83 F 278.5 - . Reactor water inlet flow 34 . l ,

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' [ Commonwealth Edison

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

'> , Marseilles, Illinois 61341

7N y T6tephone 815/357-6761 l

_ September-7, 1983 O

~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

.Very trul_y yours, x

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G. J. Diederich.

Station Superintendent i

l GJD/DLL/rmp Enclosure l-(; .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 u,

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ML20080E781

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SUMMARY

SUMMARY

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