ML20081M326

Monthly Operating Rept for Sept 1983

ML20081M326
Person / Time
Site:	LaSalle
Issue date:	09/30/1983
From:	Diederich G, Lin D COMMONWEALTH EDISON CO.
To:	NRC
References
NUDOCS 8311170211
Download: ML20081M326 (18)

Text

_

t LASALLE NUCLEAR POWER' STATION

' UNIT 1 MONTHLY PERFORMANCE REPORT SEPTEMBER'1983 COMMONWEALTP EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 e

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TABLE OF CONTENTS 1.

INTRODUCTION ll.

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 Requ3 ring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

LICENSEE EVENT REPORTS V.

DATA TABULATIONS A.

Operating Dats 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

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 Marsellies, Illinc(a. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent L&' 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 i

of initial-criticality was June 21, 1982.

The unit has-not commenced 4

commercial generation of power.

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

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extension 499 S

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SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE Septe:nber IJ22. The unit was shutdown due to the "B" Recirc Pump seals being replaced, heater drain modifications and local leak rate testing.

September 23-25 The reactor went critical at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on September 23 At 1140 hours0.0132 days <br />0.317 hours <br />0.00188 weeks <br />4.3377e-4 months <br /> on September 25 the reactor was manually scrammed due to receiving various scram lites on-full core display and noticed a downward trend on a couple of IRM's; could not verify rod position. The reactor was critical for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and 35 minutes.

sante ber 26-30. The reactor went critical at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on September 26.

m The reactor was critical for 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, t

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r lil. PLANT OR 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 specifications during the reporting period.

B.

Facility or Procedure Changes Requiring NRC Approval.

There were no facility or procedure changes requiring NRC approval during the reporting period.

C.

Tests and Experiments Requi ring 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 in-dicated in this summary include:

Work Request Numbers, LER Numbers, Componcnt Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.

WORK REQUEST LER C0llP0llEllT CAUSE CF 11ALFilllCT10ll RESULTS AllD EFFECTS C0ilRECilVI: ACil0li ON SAFE OPERAT10ll L26184 Flow Switch Defective Switch Swi~tch would not maintain Replaced switch OPDS-VC011 required 2" AP

'L26245 83-089/03L-0 LPCS Water Leg Purr.p Gages out-of-adjustment Pump does not meet required Recalibrated value gages L26742 83-102/03L-0 Unit 1 Division I Defectiv'e' Cell Voltage keep going down Replaced cell 125VDC Cell #40 af ter equalize charge L26954,,

83-100/03L-0 IVQ050 Dirty contacts Valve failed to close Cleaned contacts 1,

using'the control switch

• I 83-101/03L-0 RWCU Outboard Limit switch full of Valve trips when valve Replaced limit L27005 y

l Suction Stop Valve water and torque switch isn't moving switch and torque was burnt switch L27088 1E32-F002E and Valve stem dirty Valve would not open Cleaned and 1E32-F002N greased stem L27089 L27149 SBGT Wide Range Dirty connector High reading on recorder'i Recalibrated' Noble Gas Recorder Recorder L27155 Radwaste Discharge Detection chamber Excessive background Cleaned chamber Line Process contaminated detection Radiation Monitor L27194 83-104/03L-0 LPCI

'C' Minimum Setpoint more Valve will not auto open Calibrated Flow Valve conservative than when pump flow decreases 1E12-N010C required L27221

'C' Inboard MSlV

. Defective limit switch doesnt' show open position Replaced limit switch I

I L27286 Valve closed

'A' LPCI Test Check Grease hardened on switch Dual indication when full Cleaned switch e

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WORK REQUEST LER C0llP0llEllT CAUSE 0F mal.FullCTI0li RESULTS AllD EFFECTS C0ilRECilVE ACil0ll ON SAFE OPERATl0tl L27350 SBGT A Train Outlet Transmi tter out-of-Recorder shows 600 cfm with Recalibrated Flow Recorder adjustment no flow thru train transmitter

'L27355

'B' RHR WS PRM PRM dirty Received Hi-Hi rad alarm Cleaned PRM

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Suppression Chamber Bad amplifier card Transmitter does not meet Replaced L27373 Wide Range Pressure required tolerance amplifier card Transmitter

L27429, Radwaste D.ischarge Valv.e failed to isolate Replace piston, Bad piston, rings and

'l Isolation Valve rings and "0" "0" rings r.ings L27745 [

Process Radiation

'lD' Main Steam Line Out-of-calibration Spurious Hi-Hi rad trips Recalibrated Monitor

'O' DIG Air Start Port on bottom of valve Valve, leaks Reballt valve L27764 Solenoid Valve leaks 1

ISA046 lsolation Bad packing Valve leaks through Installed new L27769 Volve packing ISA042 Isolation Bad packing Valve leaks through Installed new L27770 Valve packing L27998 IDG03J Panel Alarm module loose Annunciator would not Tightened alarm acknowledge or reset module 4

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IV. ~ LICENSEE EVENT REPORTS

- The following is' a tabular summary of all ' licensee event reports for LaSal' e Nuclear Power Station, Unit One, occurring during the l

reporting period, September 1 L through September 30, 1983. This information_is provided pursuant to the reportable occurrence.

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reporting requirements as set. forth in 'section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Da te Title of Occurrence

'83-095/03L-0

-8/6/83

~ Non-Conservative Process Computer Calculations 83-096/01T-0 8/24/83 Changing Rx Mode Without Surveillances 83-097/031-0 8/10/83 RT Area =T Module Failure 83-098/03L-0 8/10/83 U-2 Service Water Process Rad Monitor 83-099/03L-0 8/15/83 Diesel Genrator 2A Out-of-Syne Trip 83-100/03L-0 8/19/83 Primary Containment Nitrogen 83-101/03L-0 8/20/83 1G33-F004 RWCU 150 Valve 83-102/03L-0 8/17/83 Unit'1, Division i Battery 83-103/03L-0 8/23/83 Control Rod Scram Accumulator

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Pressure Switch Calibration 83-104/03L-0 8/27/83 RHR Minimum Flow Valve Auto Open Failure 83-105/03L-0 9/14/83 Draining of RPV Via "B" RHR I

83-106/03L-0 8/30/83 Blowdown Flow Transmitter 83-107/03L-0 9/1/83 Containment Leakage 0.6La Exceeded 1

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DATA TABULATIONS i

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The following data tabulations are presented in this report:

A.

Operating Data Report i;

B.

Average Daily Unit-Power Level C.

Unit Shutdowns and Power Reductions-4 4

3 a

4 I,

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.LTP-300-7 ATTACIDENT D Revi s io~rt 2

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NOvedber' 13,.1979

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OPERATING DATA REPORT DOCKET NO.

050-173 LaSalle One UNIT 10 M 83 DATE COMPLETED BY Diane L.

Lin (815)357-6761

_l TELEPHONE OPERATING STATUS 720 1993 GROSS. HOURS IN REPORTING PERIOD:

1. REPORTING PERIOD: Ca amba.-

4

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

MAX. DEPEND. CAPACITY (MWe Net): O DESIGN ELECTRICAL RATING (MWo. Net):

1076 i

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

A REASONS FOR RESTRICTION tlF ANY):

THl3 MONTH YR TO OATE ',CUMULATIV E E NUMBER OF HOURS REACTOR WAS CRITICAL...............

O 0

0 L REACTOR RESERVE SHUTDCWN HOURS...................

0 2557.98 4415.68

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

0 0

0 L UNIT RESERVE SHUTQOWN HOURS 24000 4591722 '

6732301

s. GROSS THER' MAL ENERGY GENER ATED (MWH1 0

1383413 1904712 l

10. GacSS ELECTRICAL ENERGY GENER ATED (MWHI...~..........

0 1268919 1729694

11. NET Et.ECTRICAL ENERGY GENERATED (MWH)

NA NA NA

12. R EACTOR SE RVICE' F ACTCM...........................

NA NA NA

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

NA NA NA L

1 A UNIT S ERVICE F ACT4)R..............................

NA NA NA 1L UNIT AVAILABILITY F ACTOR..........................

NA NA NA.

I 1& UNIT CAPACITY FACTOR IUsing MDC).....................

NA NA NA

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

NA NA NA 1E UNIT FO R CE D OUTAG E R ATE..........................

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19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. OATE. AND OURATION OF EACHl:

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20. IF SHUT DOWN AT END OF REPCRT PERIOO, ESTIMATED DATE OF STARTUP:

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21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPER ATION!:

FORECAST ACHIEVED S/71/A?

INITIAL CRITICALITY i

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INITIAL ELECTRICITY 11/1/A3 COMM ERCI AL OPER ATION i

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ATTACHMENT A M,

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AVERAGE DAILY" UNIT POWER LEVEL b.

DOCKET NO. :- 050-373: ' -

tjNIT LaS'alleONe' DATE 10/7/83 COMPLETED BY Diane I Lin TELEPHONE (815)357 6761

.. MONTH Seorember 198'l

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

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R;vizion 2 November i3, 1979 6

ATTACllHENT B UNIT SHUTDOWNS AND POWER REDUCTIONS

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D'0CKET NO.. 050-373 UNIT NAME tasniin onn se'ptember 1983 DATE 10/7/83 REPORT HONTH COMPl.ETED BY Diane L. Lin'-

j TELEP110NE Ri c_u 7_m METil0D OF SilUTTING DOWN TYPE Tile REACTOR OR F: FORCED DURATION NO.

DATE S: SCIIEDULED (110URS)

REASON (1)

REDUCING POWER.(2)

CORRECTIVE ACTIONS / COMMENTS 34 8/20/83 F

539.'7 A

4' Reactor scram'due.to low react,or water inlet flow.

35 9/23/83

^ F 180 3 -

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Received various scram

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lites on full core display & noticed a downward trend on a couple of IRM's.

Could not verify rod positions e

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Novemb:r 13, 1979 6

. ATTACilllENT B UNIT SHUTDOWNS AND POWER RsDUCTIONS D'0CKET NO.

050-373 LaSalle One UNIT NAME DATE 10/7/83 REPORT HONTH May 1983 (cneracred)

Diane L. Lin, COMPLETED BY TELEPil0NE 815-357-6761 HETl100 0F SilUTTING DOWN TYPE Tile REACTOR OR NO.

DATE ~ F: FORCED DURATION S: SCifEDULED (1100RS)

REASON (1)

REDUCING POWER.(2)

CORRECTIVE ACT10t!S/ COMMENTS 15 4-14-83 F

672.1-A 4

Rx scram on lok level e

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. ATTACll!!ENT H UNIT SHUTDOWNS AND POWER REDUCTIONS D'0CKET N0. _050-373 UNIT HAME La'Salle One DATE 10/7/83 REPORT HONTH June 1983 (corrected)

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Diane L. Lin.

COMPLETED By TELEPil0NE (815) 357-6761 HETI(OD OF SilUTTING DOWN TYPE lilE REACTOR OR F: FORCED DURATION NO.

DATE S: SCllEDULED (fl0URS)

. REASON (1)

' REDUCING POWER.(2)

CORRECTIVE ACTIONS /COHHENTS 3

Rx. scram due'to low level A

16 6-01-83' F

46.6 while conducting LOS-TG-SA1 A

3 8x. scram caused by a turbine. trip on high 17 6-06-83 F

30*0 vibration A

3 Rr.. scram due to, ranging 18 6-08-83 F

33 2 from 6 to 7 during LGP-3-2 i

l Due to turbine. trip from A.

3 13 6-14-83 F

19.7 high vibration on breaking

1. 8 20 6-16-83 F

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5 Per,16ad dispatcher 0

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• For sequence change 21 6-24-83 F.

Turbine t'rlp and Rx.

22 6-30-83 F'

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ATTACillfENT H Ullli SilVTDOWilS AND POWER RsDUCTIONS DOCKET H0. 050-373 UNIT NAME tasalle One DATE 10/7/83 REPORT H0HTil July 1983 (cm,~c

.d )

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COMPLETED BY Diane L. Lin TELEPil0NE (815)357-6761 METil0D OF

- SiluTTillG DOWN TYPE Tile REACTOR OR F: FORCED DURATI0li NO.

DATE 5: SCilEDULED (ll0URS)

REA50tl(1)

REDUClllG POWER.(2)

CORRECTIVE ACTI0llS/ COMMENTS 8

4 Rx. scram from S U -27 23 7-1-83 3

84.9 0'

11 5

For STP-30 24 7-7-83 3

5 For STP'-29 0

11 25 7-8-83 3

Rx. scram on Tu M ne Control A

3 26 7-16-83 F

42.5 Valve fast closure 3

Rx. scram f rora level 3 due 8

27 7-18-83 F

52.5 to loss of power supply while the instrument Department was troubishootin i

the system.

A 3

Rx. scram due to'MSlV 28

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7-27-83 F

42.5 closure A

3

'Rx. scram due to MSlV 29 7-29-83

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20.2 closure on low steam

. line pressure.

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s ATTACllHENT B UNIT SHUT 60WNS AND POWER R$ DUCTIONS DOCKET No. Oso-373 UNIT NAME LaSalle one DATE

__in/7/At REPORT HONTH August 1983 (corrected)

COMPT.ETED BY Diane L. Lin TELEPil0NE (815)357-6761 _

HETit0D OF SilUTTlHG DOWN TYPE Tile REACTOR OR F: FORCED DURATION HO.

DATE S: SCllEDULED (HOURS)

REASON (1)

REDUClHG POWER.(2)

CORRECTIVE ACTI0llS/COHHEHTS Reduced power *from 951 to 64%

30 8/09/83 F

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5 5

Reduced, power for Reactor 31 8/11/83 S

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Recirc. testing Reactor.scra.n due to APRM 32 8/12/83 F

25.4

-3 8

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Hi Hi Alarm

'A' VE Charcoal Bed got wet 33 8/18/83 F

0 A

5 Reactor sqram due'to low 34 8/20/83 F

278.5 6

3 Reactor water inlet flow l

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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.

B.

ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period:

Outage-No.

Equipment Purpose of Outage 1-968-83 1B HPCS D/G Six month inspection 1-1042-83 HPCS 0/G Cooling Clean strainer Water Strainer C.

Off-Site Dose Calculation Manual

.There were no changes to the Off-Site Dose Calculations Manual during this reporting period.

l_

D.

Radioactive Waste Treatment System t

There'were no changes to the Radioactive Waste Treatment System during this reporting period.

E.

Process Control Program

- There were-no changes to the Frocess. Control Program dur eng this

- reporting period.

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Commonwe:lth Edison

o LaSalle County Nuclear Station Rural Routs #1, Box 220 V j/

Marseilles, Illinois 61341 Telephone 815/357-6761 October 7,1983 Di rector, Of fice of Management Information

~ and Program Control l.

United States Nuclear Regulatory Conmission l

Washington, DC 20555 ATTN:

Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report coverina LaSalle County Nuclear Power Station, Unit One, for the period covering September I through September 30, 1983.

Ve ry t rul y you rs,

/

" ^-

G. J. Diederich

)

Superintendent LaSalle County Station 3

GJD/DLL/rg Enclosu re xc:

J. G. Keppler, NRC Region li t j

NRC Resident inspector, LaSalle l

Gary Wright, 111. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center Ron Johnson, CECO i

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