ML19343C385
| ML19343C385 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/11/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dolan J AMERICAN ELECTRIC POWER CO., INC., INDIANA MICHIGAN POWER CO. |
| References | |
| NUDOCS 8103240006 | |
| Download: ML19343C385 (2) | |
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Docket No'. 50-315 Docket No. 50-316 American Electric Power Service Corporation Indiana and Michigan Power Company ATTN:
Mr. John E. Dolan Vice Chairman
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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GLEN ELLYN, ILLINOIS 60137 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&h
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< James G.-Keppler Director
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Enclosure:
IE Information Notice No. 81-06
O SSINS No.:
6835 s'
Accession No.:
t 8011040269 IN 81-06 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 11, 1981 IE Information Notice N0. 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 constructiul 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 A -
not to trip.
.n 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.
information herein is being provided as an early notification of a possibly significant event.
Although no specific action or response is requested at this time, recipients should review the -information.for possible applicability to their facilities.
If NRC evaluations so indicate, further licensee actions
-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
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t Attachment IN 81-06
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March 11, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject 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-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 1
Removal System at Davis-OL or CP Besse Unit No. 1 OL_= Operating Licenses CP = Construction Permits :
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