ML19350B386
| ML19350B386 | |
| Person / Time | |
|---|---|
| Site: | Bailly |
| Issue date: | 03/11/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shorb E NORTHERN INDIANA PUBLIC SERVICE CO. |
| References | |
| NUDOCS 8103200386 | |
| Download: ML19350B386 (2) | |
Text
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o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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.E REGION 111 b[
7M ROOSEVELT ROAD e,
o GLEN ELLYN.1LLINOIS Go137 March 11, 1981 Gentlemen:
The enclosed IE Information Notice No. 81-06 contains information that may be applicable to your facility regarding the failure of an ITE Model K-600
. circuit breaker. No specific action or response is requested at this time; however, pending the results of NRC staff evaluations of this matter, further licensee actions may be requested.
Should you have any questions regarding this information notice, please contact this office.
Sincerely, f $ArY W D
[.rJamesG.Keppler V
Director
Enclosure:
IE Information Notice No. 81-06 9fo3e2x326 1
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SSINS No.-
6835 Accession No.:
8011040269 IN 81-06 UNITED STATES
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NUCLEAR REGULATORY COMMISSION oo 2
0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 11, 1981 IE Information Notice NO. 81-06:
FAILURE OF ITE MODEL K-600 CIRCUIT BREAKER
Purpose:
The purpose of this information notice is to provide early notification of a matter that could adversely affect the safety of nuclear power plants.
Toward this end, this information notice alerts holders of operating licenses and construction permits of a possibly generic deficiency involving Model K-600 circuit breakers manufactured by ITE.
Description of Circumstance:
By letter dated February 20, 1981, the Sacramento Municipal Utility District informed us that, while performing preventive maintenance on electrical circuit breakers at its Rancho Seco facility, an ITE Model K-600 breaker was observed not to trip.
An investigation revealed that a tripping coil wire had slipped out of its terminal.
Further examinations revealed that the coil wire size was AWG 20, whereas the mating lug was sized for AWG 16-14 wire.
A check of other ITE electrical breakers indicated that the problem may be generic.
Subsequent to the letter, the Sacramento Municipal Utility District informed us trally that ITE Model K-1600 breakers have the same deficiency and that
-Model K-3000 breakers may be similarly affected.
The information provided by the Sacramento Municipal Utility District is pre-liminary and will be followed by a complete report.
Consequently, we have not yet evaluated the safety significance of this event.
Nevertheless, the information herein is being provided as an early notification of a possibly significant event.
Although no specific action or response is requested at l
this time, recipients should review the information for possible applicability l
to their facilities.
If NRC evaluations so indicate, further licensee' actions l
may be requested.
If you have any question regarding the information contained herein, please contact the Director of the appropriate NRC Regional Office.
Attachment:
l Recently issued IE Information Notices l
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Attachment i
IN 81-06 March 11, 1981 RECENTLY ISSUED IE INFORMATION NOT:CES Information Date of Notice No.
Subject Issue Issued to f
81-05 Degraded DC System at 2/10/81 All power reactor Palisades facilities with an l
0L or CP t
81-04 Cracking in Main Steam 2/27/81 All power reactor r
Lines facilities with an OL 81-03 Checklist for Licensees 2/12/81 All power reactor Making Notifications of facilities with an Significant Events in OL Accordance with 10 CFR 50.72 81-02 Transportation of 1/23/81 All Radiography Radiography Devices licensees 81-01 Possible Failures of 1/16/81 All power reactor General Electric Type facilities with an i
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80-45 Potential Failure of 12/17/80 All PWR facilities BWR Backup Manual Scram' with an OL or CP Capability i
80-44 Actuation of ECCS.in the 12/16/80 All~PWR facilities Recirculation Mode While with an OL or CP in Hot Shutdown 80-43 Failures of the Continuous 12/5/80 All power reactor Water Level Monitor for facilities with an the Scram Discharge Volume OL or CP at Dresden Unit No. 2 80-42 Effect of Radiation on 11/24/80 All power reactor Hydraulic Snubber Fluid facilities with an OL or-CP 80-41 Failure of Swing ~ Check 11/10/80 All power reactor Valve in the Decay Heat facilities with an Removal System at Davis-OL or CP Besse Unit No. 1 OL = Operating Licenses CP = Construction Permits
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i Docket No. 50-367 Northern Indiana Public Service Company ATTN:
Mr. Eugene M. Shorb Senior Vice President 5265 Hohman Avenue Hammond, IN 46325 cc w/ encl:
Central Files AD/ Licensing AD/ Operating Reactors h ) k "
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Local PDR
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Mary Jo Murray, Office of
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Assistant Attorney General
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