ML19350B552
| ML19350B552 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/11/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 8103200873 | |
| Download: ML19350B552 (2) | |
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Docket No. 50-461 9
Docke. No. 50-462 86=J-I MAR 171981 4
Illinois Power Company 6
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Mr. W. C. Gerstner
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Executive Vice President q
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tral Files AD/ Licensing AD/ Operating Reactors PDR Local PDR NSIC TIC Mary Jo Murray, Office of Assistant Attorney General Gary N. Wright, Deputy Director Randall L. Plant, Prairie Alliance 4
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'o UNITED STATES
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g NUCLEAR REGULATORY COMMISSION t
.. s REGION 111 q
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OLEN ELLYN,ILUNOIS so137 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, O
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[wJamesG.Keppler U Director
Enclosure:
IE Information Notice No. 81-06
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SSINS No.:
6335 Accession No.:
8011040269 IN 81-06 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 11, 1981 IE Information Notice NO. 81-06:
FAILURE OF ITE H0 DEL 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 orally 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 i
information herein is being provided as an early notification of a possibly I
significant event. Although no specific action or response is requested at this time, recipients should review the information for possible applicability I
to their facilities.
If NRC evaluations so indicate, further licensee actions j
may be requested.
If you have any question regarding the information contained herein, please contact the Director of the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices l
Attachment IN 81-06 March 11, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Inf ormation Date of Notice No.
Subiect Issue Issued to 81-05 Degraded DC System at 2/10/81 All power reactor Palisades facilities with an OL or CP 81-04 Cracking in Main Steam 2/27/81 All power reactor 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 HFA Relays OL or CP.
80-45 Potential Failure of 12/17/80 All PWR facilities BWR Backup Manual Scram with an OL or CP Capability 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 Oresden Unit No. 2 80-42 Effect of Radiation on 11/24/80 All power reactor Hydraulic Snubber Flutu 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