ML20067D279

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Monthly Operating Rept for Nov 1982
ML20067D279
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 12/06/1982
From: Ullrich J
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20067D277 List:
References
NUDOCS 8212130177
Download: ML20067D279 (16)
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT NOVEMBER, 1982 COMMONWEALTH EDISON COMPANY l

NRC DOCKET NO. 059-373 1

LICENSE NQ. h?f-11 4

i 8212130177 821206 PDR ADOCK 05000373

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  • TABLE OF CONTENTS
1. .lNTRODUCTION
11.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE Ill. 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 a

IV. LICENSEE EVENT REPORTS V. DATA TA3ULATIONS A. Operating Data Report <

B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations B. 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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l. 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.

The condenser cooling method is a closed cycle cooling pond.

The plant is subject to License Number NPF-11, issued on April 17, 1962. The date of initial criticality was June 21, 1982. The unit has not commenced commercial generation of power.

T This repor t was compiled by John Ullrich, telephone number (815)357-6761, extension 481.

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11.

SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE November 1-9 The unit started the reporting period at approximately 44% Reactor Power. At 1048 on November 1 the unit was at 25% Reactor Power. At 0900 on November 7,1982 the unit was back up to 47% Reactor Power. On November 9 at 1641 the Reactor scrammed due to low reactor water level resulting from a low suction pressure trip of all feed-water pumps. The reactor was critical for 208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br /> and 41 minutes from November 1 to November 9 Novenber 10-15 The reactor went criticel ac 21:50 hours on November 10, 1932. At 1535 on November 11 the main generator was synchronized to the grid and Icad increased to 53 MWe. At 0500 on Nover:ber 12, load was increased to 440 MWe. At 13h0 on November 15 the reactor scrammed due to low condenser vacuum resulting from a circulating water pump trip.

The reactor was critical for 111 hours0.00128 days <br />0.0308 hours <br />1.835317e-4 weeks <br />4.22355e-5 months <br /> and 50 minutes.

Novembr 16 The reactor went critical at 0605 on November 16. At 1419 j the reactor scrammed due to overfeeding the reactor with "B" TDRFP and a Condensate / Condensate Booster Pump. The reactor was critical for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 14 minutes.

November 17-zl The reactor went critical at 0330 on November 17 At i

1728 on November 17 the main generator was synchronized to the grid and loaded to 122 MWe, At 2230 the turbine was tripped for STP-27, " Turbine l

Trip and Generator Load Rejection." At 2255 the main generator was syn-l I

chronized to the grid and loaded to 160 MWe, At 0831 on November 21 the 1

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reactor scrammed due to RPS relay, IC71A-K3H, being deenergized for no apparent reason during MSIV testing. The reactor was critical for _101 hours and I minutes.

November 21-30 The reactor went critical at 2115 on November 21. At 0522 on November 22 the main generator was synchronized to the grid and load was slowly increased to approximately 400 MWe at 2000. At 0345 on November 24, 1982 power was reduced to 25% for GE work on the IA TDRFP.

At 0730 on November 26 power was at 46%.

. ., a 111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications.

AMENDMENT 9 This Amendment consists of changes to the Technical Specifications for removing test specimens from only one reactor vessel material surveillance capsule holder instead of three holders for the LaSalle County Station Unit I reactor vessel material surveillance progrant.

B. Facility or Procedure Changes Requiring NRC Approval.

There were no facility or procedu.e changes requiring HRC 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 indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.

LER C0flPONEllT CAUSE OF mal.F0llCTI0ll RESULTS AllD EFFECTS CORRECTIVE ACT.lon WORK REQUEST Oil SAFE OPERATI0tl System Effluent Transmitter out-of- Did not operate Recalibrated Ll7458 transmitter Flow Transmitter adjustment Replaced starter Ll7684 ---

Petter Diesel Air Bad starter Faifed to start

-. Compressor Control Room Bad ampl4-fier board Recorder failed Replaced Amplifier L18379 Board Radiation Recorder Squib Valve Alarm Bad relay Alarm frequently came up Replaced relay L18611 ---

without losing continuity

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0/G IB Main Oil Indicator out-of-adjust- Gauge reads high R'ecalibrated L18815 indicator I Temperature Gauge ment ,

LPRM Card 24-09D Bad integrated circuit No LPRM downscale alarm Replaced integrated L19730 circuit "B" VE A/C Com- Compressor malfunctioned Did not trip on low suc- Repaired compressor L19836 tion pressure 'l pressor Broken cabit No effect Replaced cable L19839 Cable to Chlorine ,

detector ,,

SBGT Flow Recorder Bad Motor Recorder's paper drive did Replaced motor L19926 not work L19953 ---

Outboard MSIV Valve limits out-of- Received dual indication Adjusted limits adj us tinen t when valve is full closed Ba' trarismi t ter Temperatureindicaging Replaced L20037

--- H?CS Pump Room Temperature Indi- controller reads 8 F Transmitter cation and Alarm 'e

-+ "0" D/G Cooling Instrament cat-of- Indicates low pressure Recalibrated L20076 pressure indicator Water Pump Differ- adjustment ential Pressure i

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WORK REQUEST LER C0llPO!1EllT CAUSE OF mal.ful:CTIO!! RESULTS AllD EFFECTS CORRECTIVE ACT.'0li l

Oil SAFE OPERATIO!!

L20093 ---

Division 1 Main Steam Bad in~put logic board No. Hathaway printout Replaced input logic Line Radiation Moni- board tor Downscale Annun-ciator L20139 ---

Containment Tempera- Dirty slidewire and low Continually prints 75 F Cleaned slldewire ture Controller amplifier gain and increased amplifier gain L20141 82-140/03L-0 Pretreatment Sample Valve was installed wrong Sample room goes airborne Reinstalled valve a'

q Purge Valve when purging correctly L20146 ---

"B" VC. Chlorine Bad aiarm light Failed trip surveillance Replaced light 1

Detector f

L20147 82-139/03L-0 Post LOCA 20 Divi- Moisture in flow indi- Monitor reading erratic Purged panel, sion ll cating controller removed moisture from flow indi-cating controller Gauge reading wrong

.] Replaced movement L20156 ---

D/G 1A Cooling Water Worn out movement -

Ppmp Suction L20224 ---

HPCS Sparger Pressure indicator out- Instrument reading / Recalibrated Integrity o f-adj us tmen t incorrectly indicator L20226 82-143/03L-0 Off-Gas Pretreatment Sample lines full of Monitor read downscale Drained and dried Radiation Monitor water sample lines L20227 82-142/03L-0 Radwaste Discharge Debris found in valve No valve position indi- Cleaned valve Flow Control Valve internals cation internals L20234 ---

2A D/G CO Unit Burned out bulbs Meither CO2 system normal Replaced bulbs 2

Status Panel ndr CO system actuated 2

lights are lit e

L20238 ---

IB D/G CO Unit Burned out bulbs Neither CO2system normal Replaced bulbs 2

Status Panel nor CO system actuated 2

' lights are lit

WORK REQUEST LER C0llP0flEllT CAUSE OF HAi.FullCT!0il RESULTS Afl0 EFFECTS C0llRECTIVEACTidh O!1 SAFE OPERATI0li -

L20273 ---

VE refrig. comp. Bad contrcelier "B" VE out-of-service Replaced controller "B" High Oil Temperature Con-troller L20309 ---

Unit i Division i Bad brea,ker Breaker trips spuriously Replaced breaker DC Output L20338 ---

Unit 1 Division I Bad breaker Breaker did not stay Replaced breaker

,, ,, Battery Charger closed B reake r

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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, November 1 to November 30, 1982. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 82-141/03L-0 11/2/82 Failure of Primary' Containment isolation Valve IE51-F066 Indicators 82-142/03L-0 11/2/82 Radwaste Discharge High Radiation isolation Valve 82-143/03L-0 11/2/82 Off-Gas Pretreatment Process Radiation Monitor 82-144/03L-0 11/7/82. Unit I Division i Battery Charger 82-145/03L-0 11/7/82 Ammonia / Chloride Detector 82-146/03L-0 11/11/82 Reactor Building Ventilation Radiation Monitor 82-147/03L-0 11/11/82 Off-Gas Hydrogen Analyzer 82-148/03L-0 11/12/82 IPL 7J INOP 82-149/03L-0 11/12/82 Lake Blowdown Flow Recorder 0FR-WF005B l

i 82-150/03L-0 11/11/82 RCIC Flow I

82-151/03L-0 11/17/82 B VC Makeup Train 82-152/03L-0 11/15/82 Steam Line High Flow RCIC lsolation Calibration 82-153/03L-0 11/18/82 "B" Cleanup Room Leak l

82-154/03L-0 11/18/82 IE51-F066 Open Indication i 82-155/03L-0 11/18/82 Loss of Secondary Containment

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IV. LICENSEE EVENT REPORTS (cont'd)

Licensee Event Report Number Date Title of Occurrence 82-156/03L-0 11/19/82 Rx Coolant Conductivity >l.0 82-157/03L-0 11/21/82 Ammonia Detector inop 82-158/03L-0 11/22/82 Valve IB21-F016 Will Not Seal in Close 82-159/03L-0 11/22/82 APRM Flow Biased Setpo?nt 82-160/03L-0 11/24/82 Leak in a System Designed to Contain Radioactive Water 82-161/03L-0 11/25/82 Low Temperature - 2A D/G Room 82-162/03L-0 11/27/82 Single Loop Recirc Pump Operation i 82-163/03L-0 11/29/82 RCIC Pipe Routing Area High Temp and Diff Temp Isolation 82-164/03L-0 11/29/82 Single Loop Recirc Pump Operation.

82-165/03L-0 11/30/82 SBGT Wide Range PRM Low Range Sample Pump s

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i V. DATA TABULATIONS o

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I The following data tabulations are presented in this report:

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A. Operating Data Report i

B. Average Daily Unit Power Level t

i C. Unit Shutdowns and Power Reductions F

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  • OPERATING DATA REPORT q ..

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CPER ATING STATUS . ,

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PERICO: 720 ,.

1. REPORTING PERICO: November 1982 _ GRCss HCuRs iN REPORTI
  • l 2. CURRENTLY AUTHCRl2E0 PCWER LEVEL (MWO:

YM 'VAX.'CEPENO. ~ '

CA7AC10 #*

(MWewd: 0 3

DESIGN ELECTalCAt. RATING IMWo.Ned: IO78 i 5d""" ' ' '

a 3. POWER LEVTLTO WHICH RESTRICTEO hF ANY) lMW Ntt): ' - 1 5

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4. REAsCNS FCR RESTRICTION HF ANYl
  • License Cor'ditick on MVAC Review 5

- TNT MONTH YR 70 CATE '.CUMULATIV E 2434.5 L NUMSER OF HOURS REACTCM WAS CalT.* CAL ...........Jt'. '. 648.3 -2434.5 S. REACTCM R ESERVE SHUTCCWN HCbMS .'. . . . . . . / , . . . J . . . . .

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600.0 1591.4 1591.4 '

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7. HCU RS C E NERATO R CN LIN E . . . . . . . . . . . . . . . . . . . . . . . . h
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s. UNIT RESERVE SHUTOCWN HOURS ...................... ,
s. Cross THERMA 1. ENERGY GENER ATED (MWul

..........,. 765566 1774082 ' 1774082 __.

210792 436211 4i6'?11 ,

10. CROSS ELECTRICAL ENERGY GENER ATED l>JWHI . . i . . . . . . . . . .

58 26% WM

11. NET ELECTRICAL ENERGY GENERATED IMWHI . . . . . . . . . .$ . . . .I . t
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12. R EACTO R SERvlCE FACTO R . . . . . . . . . .- . . . . . . . . . . . . . . . . . - t

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13. REACTOR AVAILAstLITY F ACTOR . . . . . . . . . . . . . . . . . . ,. . . . .

z NA NA NA IdL UNIT SERVICE F ACTCR ............................

44.

\ Na m%

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IL UNIT AV AILASILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . 'I % 4 NA NA g l 1& UNIT CAP ACITY F ACTOR (UsW MCQ . . . . . . . . . . . . . . . . . . .'. . .

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17. UNIT CAPACITY FACTCR tus.ng C gn MWel . ..............._

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IL UNIT FORCEO CUTAG E R AT E . . . . . . . . . . . . . . . . . . . . . . . . . . g 8

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19. ,5HUTCCWNS JCHE00 LEO CVER NEXT S MCNTHS (TYPE. CATE. ANC O'ARATICN CR EACHl:

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20. IF 3 HUT OCWN AT END OF RE7CRT PERICO. ESTIMATED DATE CF STARTUP -

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21. UNITS IN TEST STATV5 (PRICR TO CCMMERC!AL CPERAT'dNI:

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INITI AL CRITICALITY yg.$.$2 g' INITIAL ELECTRICtTY us , 4 l

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ATTACHMENT A

.i AVERAGE OAILY' UNIT PCVER LEVEL 050-373

) 00CKET NO.

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LaSalle 1

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I i DATE Decembe'r 7, 1982 i*

s COMPLETED SY John Ullrich (810 tc7-6761

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TELEPHONE X481-q

(*. MONTH November 1982 DAY AVERAGE DAILY PCWER LEVEL . CAY AVERAGE DAILY PCWER LEVEL (MWe-Ne t) (FWe-Ne t) i s ,

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1. 260 . 17, 22 4 . .

. 2. 174 18, 291 1

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3.. 175 19 428 .

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!A'. I74 20. 330-F. 16e 21. 113

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6. 17c 2nn

- 7 392 23 410 l' 8. 426 I 24. 302 1

, 9 292 25 184 L 10. _

-16 26. 360

11. 69 27 401
12. 417 28. Los 13 69c 29 Lic
14. 45'2 30. 443 3 233 31.
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R: vision 2 l Novenhcr 13, 1979 .

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ATTACllHFNr B *'

UNIT SilVT00Wils AND POWER REDUCTIONS .

DOCKET NO. 050-373

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UNIT NAME LaSalle i DATE December 7, 1982 REPORT HONT}l November 1982 ,

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C0ttPLETED BY John Ullrich.

I TELEPil0llE (815) 357-6761 X481 i

HETH00 0F 1 SHUTTING DOWN '

TYPE Tile REACTOR OR F: FORCED DURATION CORRECTIVE ACTIONS /C0tutENTS REASON (1) REDUCING POWER (2)

NO. DATE 5: SCllEDULED (ll0URS) i A 3 Auto scram due to low n 4 11/9/82 F 29 15 Reactor water level due to I low suction pressure trip  !

of all feedwater pumps l f

A 3, Auto scram due to low con-5 II/15/s2 F 16.4, .

denser vacuum due to circu-lating water pump trip A 3 Auto scram due to overfeeding 6 11/16/82 F 13 2 the Reactor with the "B" TDRFP and a Cond/Cond. Booste r Pump l l

3 Auto scram due to relay I'/21/82 F 12.7 A 7 IC71A-K311 was deenergized for no apparent reason during i HSIV testing j

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    • 's s VI. Unique REPORTING REQUIREMENTS A. Mai.' Steam Relief Valve Operations for Unit 1 There were no main steam relief valve operations for the repori!nc period.

B. ECCS Systems Outages There were no ECCS outages during this reporting period.

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 I

during this reporting period.

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