ML19350B378
| ML19350B378 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/11/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 8103200371 | |
| Download: ML19350B378 (2) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION b b,*pg /
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REGION lit 799 ROOSEVELT ROAD o
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 mitter, further licensee actions may be requested.
Should you have any questions regarding this information notice, please contact this office.
Sincerely, h h-w WD
..rJames G. Keppler
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Director
Enclosure:
IE Information Notice No. 81-06 f/Q&200371
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SSINS No.:
6835 Accession No.:
8011040269 IN 81-06 1
UNITED STATES 1B ' "
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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 in'ormation notice is to provide early notification of a matter that could naversely affect the safety of nuclear power plants.
i Toward this end, thi, 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 ti.pping 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 inforced 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 b'y 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 nv specific action or response is requested at this time, recipients should review the information for possible applicability 4
to their facilities.
If NRC evaluations so indicate, further licensee actions may be requested.
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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 e
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Attachment IN 81-06 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 i
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 i
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. I t-SL = Operating Licenses CP = Construction Permits
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Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company A NN:
Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 cc w/ encl.
G. A. Reed, Plant ttanager Central Files Aw O)
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T. Colburn, ORB /NRR S
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i Resident Inspector, RIII
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C gN John J. Duffy, Chief Boiler Cu/j % /
Inspector Peter Anderson, Wisconsin's Environmental Decade Stanley York, Chairman Public Scrvice Commission
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