ML20063P240

Monthly Operating Rept for Sept 1982

ML20063P240
Person / Time
Site:	LaSalle
Issue date:	10/07/1982
From:	Ullrich J COMMONWEALTH EDISON CO.
To:
Shared Package
ML20063P221	List: ML20063P220 ML20063P240
References
NUDOCS 8210130215
Download: ML20063P240 (14)

Text

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LASALLE NUCLEAR POWER STATION'

' UNIT I MONTHLY PERFORMANCE REPORT SEPTEMBER, 1982 l COMMONWEALTH EDIS0N COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-II l

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I 8210130215 82100y PDR ADOCK 05000373

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TABLE OF CONTENTS

1. INTRODUCTION 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 Equipnent IV. LICENSEE EVENT REPORTS V. DATA' TABULATIONS.

A. Operating Data Report. '

B. Average Daily Uni t Power Level C. Unit Shutdowns and Power Reductions VI. UNIQUE REPORTING REQUIREMENTS 4 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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1. INTRODUCTION.

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.The LaSalle Nuclear < Power Station Unit One is a Bolling Water Reactor with a designed electrical outpu't' of 1078 MWe net, located in Marseilles, ~ lilinois. The Station is; owned by l '

Commonwealth ~ Edison Company.. The Architect / Engineer ves Sargent &.Lundy, and the primary construction contractor was Commonwealth Edison Company.

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-The condenser cooling method is a closed cycle cooling pond.

The plant is subject to ' License Number NPF-11, issued on -

, Ap ri l' 17, 1982. The date of . initial criticality was' June 21, t

1982. The unit has not commenced commercial generation of power.

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

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11. ;

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE September 1-2 . The reactor went critical at 17:07 hours on September 1,1982 for 11 -hours and 10 minutes when it was shutdown due to an IRM Hl/H1 alarm while attempting to put the MDRFP on' .

September 2-10 The reactor:went critical at 21':00 hours ~on September 2, _1982 for 191 hours0.00221 days <br />0.0531 hours <br />3.158069e-4 weeks <br />7.26755e-5 months <br /> and 24 minutes when it was shutdown due to high SDV level while performing STP-28, " Shutdown from Outside the Control Room." During this time period the main turbine was synchronized to the grid and loaded as follows:

September 4 at 1404 to 60MWe at 2245 to 100HWe September 7 at 2347 to 90MWe September 8 at 2216 to 100MWe September 9 at 0505 to 180MWe^

at 1620 to 168MWe September 10 at 0108 to 140MWe September 13-30 The reactor went critical at 22:45 hours on Septembe r 13,1982 for 409 hours0.00473 days <br />0.114 hours <br />6.762566e-4 weeks <br />1.556245e-4 months <br /> and 15' minutes. 0.uring this time period the main turbine was synchronized to the grid and loaded as follows:

September 15 at 0356 to 110MWe September 22 at 00?O to 130MWe September 23 at 2143 to 133MWe September 26 at 0337 to 120MWe September 28 at 0237 to 123MWe

' lli. PLANT (NL 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-speci fications. during the reporting period.

8.- Facility or Procedure Changes Requiring NRC Approval.

There were no facility or procedure changes requiring NRC

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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.

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d D. Corrective Haintenance of Safety Related Equipnent.

The following tables present a summary of safety-related

maintenance completed on Unit One during the reported period.

i The headings indicated 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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WORK REQUEST LER C0llP0llEllT CAUSE OF HALFutiCTI0li RESULTS AllD EFFECTS CORRECTIVE ACT10ll Oil SAFE OPERATI0li L18354 82-100/03L,0 RCIC injection Line Spring tension out-of- Equalizing valve failed Adjusted preload L18355 Outboard Equalizing adj us tment to close on spring Valve L18546 ---

Standby Gas Treat- Bad pressure transducer Vacuum isn't tracked Replaced pressure ment Vent Monitoring --

transducer and Panel calibrated L18580, ---

1H IRM Drive Limit switches out-of- Causes fuses to blow Adjusted limi t

!q adj us tment switches l ,

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L18588 f ---

B IRM Drive cable disconnected Indicates UPSCALE HIGH Recoupled cable at output of drive motor on range 3 L18763 ---

MSV #1 Limit Switch Broken limit., switch Relay K10B deenergized Repaired limit switch L18774 ---

SRV Indication at Fuse holder broken No SRV position Indication Replaced fuse holder ifemote S/D Panel

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RCIC Indication at Fuse holder broken No indication when trans- Replaced fuse holder Remote S/D Panel fer switch is placed into emergency L18846 ---

LPRM 24-09A Loose connector Detector shows zero out- Tightened connection put when Rx is at ~ 279 I

L18857 ---

LPRM 56-25B Faulty high voltage Power supply is out of Replaced power

,e power supply acceptable range supply L18858 ---

LPRM 40-17A Bad solder connection Meter reads zero regard- Repaired solder

'less of calibration connection current q

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LER C0llP0llEllT CAUSE OF HALFUllCTI0il RESULTS AllD EFFECTS CORRECTIVE ACTI0ll WORK REQUEST O!! SAFE OPERATIO!!

L18946 ---

Primary Containment Leaky transistor Noble gas detector Replaced transistor Noble Gas Monitor channel does not respond to check source L19006 ---

Solenoid Operated Limit sw(tch out-of- Does not open properly Adjusted limit switch Suction Valve for adj us tment when pump starts Diesel Fuel Oil Transfer Pump b*

L19027 ' ---

'A' MSL Rad Monitor Loose zener diode Indication erratic Resoldered diode in y place 1

L19038 ,

LPRM Channel B CR-1 and CR-2 were "LPRM Hi" and "LPRM Replaced CR-1 and shorted DWNSCL" alarms were not CR-2 received with the switch In calibrate ..

L19099 ---

RclC Flow Controller Balance control out-of- Flow controller regulated Adjusted output -

adj us tment system flow 30 gpm / balance control higher than required L19124 ---

IPM13J B103 , IPL77J out-of-adj ustment Drywell hydrogen is very Recalibrated IPL77J low by indication L19263 ---

RHR Pressure Trans- Failed transmitter No effect Installed new mitter transmitter L19350 -- , 'B' RHR Service Has blown gasket on Pump Isolated Replaced gasket

' Water PRM pump L13188 ---

Various Motor Replace motor pinion No effect Replaced keys Operated Valves keys

LER C0ilPO!1EllT CAUSE OF MALFullCTI0il RESULTS MID EFFECTS CORRECTIVE ACTI0li k'ORK REQUEST -

Oil SAFE OPERATION L15865 ---

'B' RHR Loop Normal . Disc screw assembly Switch in open position Cleaned assembly Sample Valve stuck and valve indicates and set Ilmits

. closed L16811 ---

RHR Heat Exchanger Valve porition indica- No effect Adjusted valve Vent Valve tion out-of-adjustment position L18172' ---

"D" Fuel Pool Vent . Bad sensor converter Mon'itor drifting high Replaced sensor jli

. Exhaust PRM converter J

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IV. . LI CENSEE . EVENT REPORTS -

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The -following Is a tabularL summary of~ all licensee event reports -

l  : for LaSalle Nuclear. Power Station, Unit One, _ occurring during the i

i' report ing period,- September ?1 to September -30, -1982. .This l

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information is provided_ pursuant- to.the reportable occurrence -

p reporting requi rements as set. forth -in section 6.6.B.1 and 6.6.B.2 of .the Technical Speci fications.

. Licensee Event -Report Numbe r' Date Title of Occurrence .

82-99/03L-0 8/30/82 Service Water Effluent Water 82-100/03L-0 9/3/82- - RCIC Equalizing Valves 82-101/03L-0 ' 9/14/82 -Primary Containnent Continuous Air Monitor Panel

• 82-102/03L-0 9/16/82 Reactor. Vessel Lo Water Level Scram

! 82-103/03L-0 9/19/82 "d" RHR Se rv Wt r . Rad Mon i tor

! 82-104/03L-0 '9/16/82 Both Off Gas'H2 Analyzers l 82-105/03L-0 9/20/82. IB33-F020 greater ;than 5 sec

Cycle Time to Close 82-106/03L-0 9/20/82 1B33-F019 Failure to Cycle i

j 82-107/03L-0 8/13/82- ' A and B "CRD" Pumps Tripped Requiring Shutdown. per TS 3 1 3.5.A.2.a

! 82-110/03L-0 9/20/82 SBLC Tank Level Low I

82-108/03L-0 9/20/82 Failure to Perform LIS-NB 82-109/03L-0 9/25/82 Rx Low Pressure RCIC isolation s

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V. DATA TABULATIONS i

! The followin data tabulations are presented in this report:  ;

, A .' Operating Data Report

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1 j B. Average Daily Unit Power Level 1-i C. Unit Shutdowns and Power Reductions 5

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. .-lLTP-350-7 ATTACicfERI D Rsvision 2

. 't November 13,.1979

.- : 9 ,,

' OPERATING DATA REPORT

.' 050-373 DOCKET NO.

UNIT LaSal1e_1, DATE October 7. 1982

- COMPLETED BY John UfIrIch

• TELEPHONE 815/357-6761 Ext 81 _

s OPERATING STATUS . .

SeDtember 1982 GROSS. HOUR $ lN REPORTING PERICO:

720

1. REPORTING PERIOD: e A

M AX. 0EPEND. CAPACITY (MWe Neti: 0

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt!: 50? ,

DESIGN ELECTReCAL M ATING (MWo. Net): 107R l 50%

- 3. POWER LEVEL TO vvMICH RESTRICTED (IF ANY) (MWeNet):

4. REASONS POR RESTRICTION llF ANY : License Condition on HVAC Review THl3 MONTH YR TO DATE ',CUMULATIV E S. NUA8SER OF HOUMS MEACTOR WAS CRmCAL . . . . . . . . . . . . . . .

bII OI II23 kk II23 kk 0 ___0 0 S. mEACToR RESERVE 5HUTDOWN HOURS . . . . . . . . . . . . . . . . . . . _

{ 7. Nou S m .ERATo. ON u~E ..........................

,80 _ 280 so O O O

- 8. UNIT RESERVE SHUTOOWN HOURS .....................

7EEEE7 3717LE 3717LC

9. Gnoss THERMAL ENERGY GENER ATED (MWH) ..............

' 47177 E7177 C7377

10. GROSS ELECTR: CAL ENERGY GENERATED (MWHI . . . . ........

1AEnn 3A nn 18400

11. NET ELECTn CAL ENERGY GENERATED (MWHI NA NA "A

12. n sACToM serv Cr rACTOR . . . . . . . . . .. . . . . . . . . . . . . . . . . .

NA NA MA

13. REACTOR AVAILA88LITY FACTOR . . . . . , . . . . ............

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• NA NA Ma

14. UNIT SE RVIC E F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

NX NA ua r 15. UNIT AV AILA BluTY F ACTO R . . . . . . . . . . . . . . . . . . . . . . . . . .

HA NA '^'

L 18. UNIT CAPACITY FACTOR (Using MOC) .....................

NA

17. UNIT CAPACITY FACTOR (Us.no Design MWel . ...............

NA NA NA

18. UNIT F O R CE D OUTAG E A AT E . . . . . . . . . . . . . . . . . . . . . . . . . . e i 19. SHUTDOWNS SCHEDULED OvER NEXT 6 MONTHS ITYPE. 0 ATE. ANO QURATION OF EACHl:

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

NA , _

21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL CPER ATICN): FORECAST ACHIEVED sNm AL CRITICAUTY 6/21/82 .

iNmAL ELECTn C TY ,

3/b/02

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COMMERCI AL OPERATION II/l/A7 j L

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-LTP-300-7

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Revision 2-

, November 13, 1979 E*

5 ATTACHMENT A

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-373 UNIT LaSalle 1 1 DATE Octo'bE r 7. 1982 COMPLETED BY John Ullrich i TELEPHONE 815/357-6761 , _ _ . .

Ext. 481 MONTH September, 1982 DAY AVERAGE DAILY POWER LEVEL . DAY AVERAGE DAILY POWER LEVEL (MWe-He t) (MWe-Net)

I . 1. -18 .~ 17 87

2. -19 18. 109 3 -20 19 110 -

4. -8 20. 116 f

5. t i t. 21. 78

6. i37 22. gi 7 ny 23 ing I .

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24. -13

,9 82 25 -23

10. 58 26. 91

11. -15 27 _

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12. -17 28. qR 13 -16 '29 140 14.. -1o 30. 125

15. 87 31.

16.

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LTP-300-7 R; vision 2

• November 13, 1979 6 .

. v ATTACilMENT B ,.

UNIT SHUTbDVNS AND POWER REDUCTIONS

• DOCKET NO. 050-373 UNIT NAME LaSalle 1 DATE October 7, 1902' REPORT MONTH _, September, 1982 COMPLETED BY John Ullrich l

TELEP110HE 815/357-6761 Ext. 481 HETHOD OF l SHUTTING DOWN TYPE THE REACTOR OR F: FORCED DURATION CORRECTIVE ACTIONS /COHHENTS REASON (I) REDUCING POWER (2).

NO. DATE S: SCHEDULED (HOURS) 3 Due to leaky' feed regulatio e 16.7 hrs A 1 9/2/82 F valve, Reactor level increas'cd' es7" while putting the Hotod' Driven Feed Pump or the lind during a Reactor Startup.

Feed Reg. Valve has since

~ been repaired. ,

! 3 Scram was due to a simulatec-2 9/10/82 S 74.35 hrs B hi SDV level while perform- ,

l ing STP-28 " Shutdown from

- . outside the Control Rood'.

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VI. UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations for Unit 1 There were no main steam relief valve operations for the reporting period.

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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 -

1-1522-82 LPCS Pump To inspect hot bearing 1-1554-82 LPCS Pump LTS-100-44, Leak Rate Test 1-1609-82 HPCS Water inspect for oil leaks on Leg Pump HPCS Water Leg Pump and to adjust oil leveller C. Off-Site Dose Calculation Manual There were no changes to the Off-Site Dose Calculations Manual l during this reporting period.

f D. Radioactive Waste Treatnent System There were no changes to the Radicactive Waste Treatment 4

System during this reporting period.

E. Process Control Program i

There were no changes to the Process Control Program during this reporting period. '

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