ML19350B380
| ML19350B380 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 03/11/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shields S PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA |
| References | |
| NUDOCS 8103200375 | |
| Download: ML19350B380 (2) | |
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UNITED STATES
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REGION 111 f3
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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 $xt
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,w James G. Keppler
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Director
Enclosure:
IE Information Notice No. 81-06
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SSlNS No.-
6835 Accession No..
8011040269 IN 81-06 3
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&d ig 0FFICE OF INSPE;.lu? AND ENFORCEMENT WASHIN' TON, 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 plaats.
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 ts il wire size was AWG 20, wrareas 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 l
Model K-3000 breakers may be similarly affected.
The information provided by the Sacramento Municipal Utility District is ore-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 soecific action or response is requested at this time, recipients should rr /iew the information for possible applicability to their facilities.
If NRC e:aluations so indicate, further licensee actions may be requested.
If you have any question regarding the information contained herein, pli.
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 o
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 LCCS in the 12/16/80 All PWR facilities Recirculation Mode Whi'ie with an OL or CP in Hot Shutdown f
80-43 Failures of the Continuous 12/5/80 All power reactor Water Level Monitor for facilities with an the Scram Disctarge 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 Syctcin at Davis-0; ar CP Besse Unit No. 1 OL = Operating Licenses CP = Construction Permits
4 Docket No. 50-546 Docket No. 50-547 Public Service of Indiana ATTN:
Mr. S. W. Shields l
Senior Vice President Nuclear Division Post Office Box 190 l
New Washington, IN 47162 cc w/ enc 1:
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Steve J. Brewer, P:-lear Safety I
and Licensing Supervisor f/
Central Files S
AD/ Licensing 7
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AD/ Operating Reactors PDR h u,SQQy'C 19 9 Local PDR
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'l LeBoeuf, Lamb, Leiby & MacRa,-
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i Dave Martin, Office of the.
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l Attorney General l
John R. Galloway, Staff Director, Environment, Erergy l
and Natural Resources Subcommittee i
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