ML19332F008

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LER 89-016-00:on 891109,RWCU Isolation Occurred While Instrument Surveillance on Ventilation Differential Temp Isolation Functional Test in Progress.Caused by Faulty Thermocouple.Thermocouple repaired.W/891208 Ltr
ML19332F008
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 12/08/1989
From: Diederich G, Lyon D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-016-04, LER-89-16-4, NUDOCS 8912130269
Download: ML19332F008 (4)
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. Commonwealth Edison i L. . LaSalle County Nuclear Station

  • Rural Route #1, Box 220 Marseilles. Illinois 61341
s. Telephone 815/357-6761  ;

December 8, 1989 f

Director of Nuclear Reactor Regulation  !

U.S. Nuclear Regulatory Commission Mail Station F1-137 Nashington, D.C. 20555  ;

j

Dear Sir:

Licensee Rvent Report #89-016-00, Docket #050-374 is being 1 submitted to your office in accordance with 10CFR50.73(a)(2)(iv).

U. J. Diederich*N Station Manager i LaSalle County Station GJD/DML/kg l Enclosure xc: Nuclear Licensing Administrator ,

NRC Resident Inspector l NRC Region III Administrator INPO - Records Center

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LICENSEE EVENT REPORT (LER)

Docket Number (2) Pace (3) l Facility Name (I)

% 11e County Station Unit 2 01 51 01 0' 01 31 11 4 1lof!0l3  !

Title (4) hoacter leater Cleanno isolation on H)oh Olfferential Tamerature Due 4ecort Dato (7) to Themanale Other Facilities involvedFailure (0)

R ". Date (5) LER Ihaber (6? hadet ihmber(s) j Day Year Facility Names Month Day Year Year /// Sequential Revision Month fff

/// thaber

///j/

j// thaber )

01510101of I I i

~~~

01116

~~~

01 0 112 01 e el 9 of51of0101 1 I l 11 1 01 9 el e el9 TH15 REPOR1 15 $UBMITIED PUR50 ANT TO THE REQUIREENTS OF 10CFR OPERAT M (Check one or esse of the followine) (11) 20.405(c) _X,_ 50.73(a)(2)(lv) ,,_,_ 73.71(b) 1 20.402(b) ,,,_

73.71(c) 20.405(a)(1)(1) 50.36(c)(1) ,_,,

50.73(a)(2)(v) ,,,,,,

Polder ,,,,,,

50.73(a)(2)(vil) Other (Specify 20.405(a)(1)(ll) 50.36(c)(2) _

tiVEL i i ,,,,,,,

50.73(a)(2)(vill)(A) in Abstract (10) 1I 01 0 20.40$(a)(1)(111) 50.73(a)(2)(l) ,,,,_,

50.73(a)(2)(vill)(B) below and in

///,/ / 20.405(a)(1)(lv) _,,,,, 50.73(a)(2)(ll) ,,,,,,

/// // // / // Text) 50.73(a)(2)(lil) ,,,,,,50.73(a)(2)(x)

/ / 20.405(a)(1)(v)

// / //'f/// / ,,,,,_

LICENSEE CONTACT FOR TH15 LER (12)

TELEPHONE NUPBER Name AREA CODE 8 l 1 15 31 51 11 -l 61 71 61 1 David M. Lyon. Technical Staff Enaineer. extension 2319 UsiETE ONE LINE FOR EACH CwruwENT FAILURE DESCRitED COMPONENT MANUF AC-IN REPORTA8LE THIS REPORT (13 REPORTA8LE CAUSE i SYSTEM CAUSE SYSTEM CopFOWENT MRNUFAC- 10 IfPRDS TURER TURER TO NPRDS l l l l i i l X Cl E l il DI 5 Pl41217 N I l l l l l l l I I I l i I Expected Month I Day l Year SUPPLEENTAL REPORT EXPECTED (14) Submission

( l l l

~

lyes (If wes. -:==lete EXPECTED SUBMISSION DATE) Yl 100 ABSTRACT (Limit to 1400 spaces, i.e, approximately fif teen single-space typewritten lines) (16)

On tiovember 9,1989, at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br />, with Unit 2 in the Run Mode at 100K power, a Olvlsion 1 Reactor ins Cleanup (IndCO) Isolation occurred while LaSalle Instrument Surveillance, Ll5-RT 403, ' Unit 2 IndCU l

i Ventilation Olfferential leaperature Isolation Functional test," was in progress. An Instrement Tech was reading the indication on the Olvision I ledCU Heat Exchanger Room Olfferential 1superature time of the isolation.

The cause of the isolation was due to a faulty thennocouple which developed a short circuit to grou tenperature switch was being read.

There was no safety lapact due to the event because the IndCU System isolated as designed a conductivity was maintained below the allowable Technical Specification limit during the event.

j the faulty thennocouple was repaired and the indCU System was returned to By 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, on November 10, 1989 service.

This event is reportable pursuant to the requirements of 10CFR50.73(a)(2)(lv) due to the actuatio Engineered Safety Feature System.

~ ' ' ' ~- - . , . , . _ . . , _ _ _ ,

.: .* _i 4 LMe""M EVfdif EPORT (LER) TEHT CAfflamittal Fem tev 2.0 .

LIR IRNGER (6) Pane Cl)

FRCILITY lilWE (1) DOCKET IRNGER (2)

Year seguential Revision

. . ~

m, 015101010131714 eit 01116 - 0Io el 2 0F of 3 m ile e ev 5tatlan unit 2 -

TEXT. Energy Industry identification System (Ell 5) codes are identified in the tent as (KK) ptAlff Als $Y$1EM IDEN11FICAT10N General Electric - Dolling Water Reactor Energy ladustry identification System (Elis) codes are identified in the tent as [KX).

A. CONDlil0N PRIOR 70 EVENT Event Date: 11/09/09 Event Ilme: 0245 Hours Unit (s): 1 heactor Mode (s): 1 Mode (s)Isame: A PowerLevel(s): __1005

8. DESCRIPfl0N OF EVENT On llovember 9,1999, at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br />, with Unit 2 in the hun Mode at 1005 power, the Instrument Maintenance Department (IM) was performing taSalle Instrisment Survelliance Lis-AT-dO3, " Unit 2 Reactor Per the Mater Cleanup (IndCU) [CE) Area Ventilation Olfferential legerature isolation functional Test."

surveillance, an IM 1echnician was cogaring the indication of the Olvision 2 ltdCU Heat Enchanger Room Differential lemperature Indicating Switch,15-2E31-40600H, to the redundant Olvision 1 Differential To obtain the lhlCU Heat Enchanger Room differential legc'rature Indicating Switch,15-2E31-41600G. )

temperatures for comparing Division 2 to Division I readings, L15-RT-dO3 directs the Techniclan to 1 depress the " read" switches on TS-2E31-41600H and TS-2E3141600G while observing both switches meter Indications. leien the IM Technician depressed the " read" switch on 15-2E31-N600G, the temperature  !

switch indicating meter went upscale and 15-2E31-N600G tripped, causing a IndCU Suction Line Division 1  :

Nigh Differential Temperature isolation. The Olvision-1 isolation caused an automatic closure$ lace of the ,

ladCU Section Line Outboard Isolation Valve, 2G33-F004, and an automatic trip of the IndCU pisips. l the isolation could not be reset, the IndCU System was secured by 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on leovember 9,1989.

1 idork Roguest L94316 was initiated to investigate and correct the problem which caused the isolation. Sy '

2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br /> on leoveeer 9,1989, the problem was corrected and the Division 1 ludCU Neat Exchanger Area l

Differential temperature Switch was declared operable. By 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on November 10, 1989, the ledCU System was restarted with two filter /demineralizers in services. The delay in placing the IndCU System back in service was due to another IndCU System problem unrelated to the isolation. ,

1his event is reportable in accortlance with 10CFR$0.73(a)(2)(lv) due to an Engineered Safety Feature (ESF) actuation.

l C. APPARENT CAUSE OF EVENT

.The cause of the trip of Temperature Shiltch TS-2E31-W600G was a short circuit to plant ground at the IndCU Heat Enchanger Ventilation inlet thernocouple, TE-2E31-N001G. The faulty A transient or therinoccuple induced voltagedevelope l

the ground when the temperature switch was taken to the " read" position.

across TE-2E31-41001G most ilkely caused the faulty thernocouple to develop a short to ground when th lechnician was reading the Division 1 Tenperature Switch. The therinocouple was most Ilkely faulty pr l

to the isolation functional test.

I . .

]

  • Fom Arv 2.0 L M 8f EVENT KPORT (LER) TEKT COWileMAT10W FACILITY linfE (1) 00CKE1 NUSER (2) LER NUSER (6) _ Pane (3)

Year /// Sequential ff//j/ Revision f,,

/T/ thaber /// thster

% 11e C ety station unit 2 0 1 5 1 0 1 0 1 0 1 31 11 4 e19 - 01116 - 0Io 01 3 0F 01 3 TEK1 Energy Industry identification System (Ells) codes are identified in the text as [KK)

D. 5AFETY ANALYSIS OF EVENT The IndCU suction line outboard isolation and subsequent shutdown of the IndCU System had no lapact on the safe operation of Unit 2. 15-2E31-48600G tripped and caused a IndCU 5ection Line outboard Isolation as designed. The IndCU System was shutdown, due to the isolation, from November 9,1999 at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> to leovember 10, 1999 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />. During that time, Reactor Coolant conductivity was well below the 1.0 During that microsho per centimeter allowable ilmit as specified in lechnical Specification 3.4.4.

time, Reactor Coolant conductivity reached a maalansn of 0.317 micrenhos por centimeter.

E. CORRECilVE ACTIONS f'

The IndCU High Differential lamperature Isolation occurred at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> on November 9,1989. By 2020 The IndCU l hours on llovember 9, the thersocouple was replaced and 15-2E31-4s600G was declared operable.

System was placed back in service by 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on November 10, 1999. 1 i

Periodic survelllances to check for grounded or partially grounded thennocouples for leakage detection  ;

Action Item Record (AIR) high temperature and high differential touperature will be investigated. '

374-200-09-06301 will track the completion of this investigation.  !

f. PREVIOUS EVEN15 LER 10 amber Title 374/84-016-00 indCU High Ambient Temperature Isolation l

374/64-031-00 IndCU High Differential Temperature isolation G. CopFOWENT FAILURE DATA Model Number MFG Part Number Manufacturer teamenclature temperature Element 145C3224P002 102-9039-08-4 Pyco l

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