ML19350B335

Forwards IE Info Notice 81-06, Failure of Ite Model K-600 Circuit Breaker. No Response Required

ML19350B335
Person / Time
Site:	Perkins, Cherokee
Issue date:	03/11/1981
From:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Dail L DUKE POWER CO.
References
NUDOCS 8103200289
Download: ML19350B335 (1)

Text

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4 f **%c UNITED STATES c

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NUCLEAR REGULATORY COMMISSION 3-r REGION 11

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101 MARIETTA ST N.W., SUITE 3100

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g' ATLANTA. GEORGIA 30303 MAR 1 ! 1931 In Reply Refer To:

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50-491,.50-492

-i Duke Power Company

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ATTN:

L. C. Dail, Vice President Design Engireering P. - 0. Box 33189 r

Charlotte, NC 28242 Gentlemen:

f 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 cir-cuit breaker.

No specific action or response is requested at this time; however, pending the results of NRC staff evaluations of th's matter, further licensee actions may be requested.

Should'you have any questions'regarding this information nctice, please contact this office.

Sincerely, f'_

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hfYce-.

. James P. O'Reilly~

Director

Enclosures:

1.

IE Information Notice No. 81-06 2.

List.of Recently issued IE Information Notices I

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8011040269 IN 81-06 fD OffD D d JJyj7 [f lg UNITED STATES 4

NUCLEAR REGULATORY COMMISSION

L OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 March 11, 1981 IE Information Notice No. 81-06:

FAILURE OF ITE MCOEL K-600 CIRCUIT BREAKER 4

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 1

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.

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.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

'informatior, 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.

l If you have any questions regarding the information contained.herein, please contact the Director of the appropriate NRC Regional Office.

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Attachment:

l Recently issued IE Information Notices l

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I 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 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 30-43 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 11/2?/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 u

OL'= Operating Licenses CP.= Construction Permitsi

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