ML20084Q028

LER 017/03L-0:on 760427,while Performing Low Reactor Water Level Functional Test,Level Indicating Switch LIS-1-263-58A Tripped,Exceeding Tech Specs.Caused by Instrument Drift. Switch recalibr.W/760527 Forwarding Ltr

ML20084Q028
Person / Time
Site:	Quad Cities
Issue date:	05/27/1976
From:	Henson L, Kalivianakis N COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20084Q031	List: ML20084Q028 ML20084Q051
References
LER-76-017-03L-01, LER-76-17-3L-1, NJK-76-207, NUDOCS 8306130099
Download: ML20084Q028 (2)

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Comm 2:lth Edison b 'N Ouad-Cities Nuclear Power Station Post Office Box 216 g_ -, .y, 2,s_j _ gj fs

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Cordova, Illinois 61242 Telephone 309/654-2241 s

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NJK-76-207 g , N,hp ,.y '

j 3 ,* s. ' igy o 4 , y 47C, May 27, 1976 b%I . /

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J. Keppler, Regional Director Office of Inspection and Enforcement Region lil U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Reference:

Quad-Cities Nuclear Power Station

., Docket No. 254, DPR-29, Unit 1 Appendix A, Sections 3.1, 6.6.B.2.a Enclosed please f.ind Reportable Occurrence Report No. 50-254/76-17 for Quad-Cities Nuclear Power Station.

This report is submitted to you in accordance with the requirements of Technical Specification 6.6.B.2.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION ff N. J. Kallvianakis iltY' Station Superintendent l

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cc: G. A. Abrell  ;-

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8306130099 760527 PDR ADOCK 05000254 i:

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T CENSEE EVENT REPORT l CONTROL 8 LOCK:l l l l l l l (PLEASE PRINT ALL REQUIRED INFORMATION) 1 8 A E LCENSE NUMBER YPE O l l l Ll Ql Al 0 l 1 l l 0 l 0l-l0 l0 l 0 l 0 l 0 l-l0 l0 l l4 l1 lI l1l1l l0l 3l 7 89 14 15 25 28 30 31 32 CATEGCRY p OOCKET NUMBER EVENT CATE REPORT CATE O 1 CON'T l 7 8 57 l

58 l d59 lLl 60 l 01 Sl 0l-l0 l2 l 5 l 4 l 81 68 lo l4 l2 [7 l716 l l 015 l 217l 7l 6l 69 74 75 80 EVENT DESCR!PTION 95 l At 4:00 PM on April 27, 1976, while performing the low reactor water level l 7 89 80 EE l functional test, level indicating switch LIS-1-263-58A (Reactor Low Level) tripped l 7 89 80 EE l at +6.8" which exceeded the Technical Specification limit. Safety implications are l 7 89 80

$ l minimal since the reactor protection trip system can tolerate a single failure. l 7 89 HG l The switch was recalibrated and functionally tested satisfactorily. (R0 50-254/76-17)801 7 89 Pauf 80 E CODE COMPONENT CODE SUFPUER MANUFACTURER VOLATON

@ l l l A l (E__l 89 10 11 ll lN l S l Tl Rl Ul 12 17 d43 44 lY l0 lI l0 l 47 W48 CAUSE DESCRIPTION l

l fsj l (Proximate Cause - Component Failure) instrument drif t caused the 8" reactor vessel l 80 l

~l.]89l low level setpoint to change. This is the first occurrence for this type of l

} 89 60 DE l Instrument since July 19, 1974. l s  % POWEA OTHER STATUS O OVERY OSCOVERY DESCRIPTON 1 (g_l 9

l0l 9l 7l l NA l d45 l NA l 7 8 10 12 13 44 48 80 RL 0 CF LEASE AMOUNT OF ACTMTY LOCATON OF RELEASE EE 7 8 9 d Wl 10 11 NA l 44 l

45 NA l 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTON DE I lN l A l 7 89 11 Ul12 13 NA l l 80 PERSONNEL INJURIES NUMBER DESCRIPTON Pl lN l A l l NA l

7 89 11 12 80 OFFSITE CONSEQUENCES DE I NA l

7 89 -

80 LOSS OR OAMAGE TO FACIUTY I TYPE CESCRIPTON l

D] W 7 89 l

10 NA -

l 80 PUBLICITY gg l NA l

7 89 l 80 ADDITIONAL FACTORS fit 81 I l 7 89 80 DE l l Larry L. Henson (309) 654-2241 Ext. 24 [

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