ML19350B318
| ML19350B318 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/11/1981 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8103200258 | |
| Download: ML19350B318 (1) | |
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UNITED STATES o
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.-c REGION 11
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j' ATLANTA, G EoRGIA 30303 MAR 111981 In Reply Refer To:
50-416 5_0-417j Mississippi Power and Light Company ATTN:
N. L. Stampley Vice President of Production P. O. Box 1640 Jackson, MS 39205 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 cir-cuit 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, h
61 Av James P. O'Reilly
-Director
Enclosures:
~1.
IE Information Notice No. 81-06 2.
List of Recently Issued IE Information Notices cc'w/ encl:
-C. K. McCoy,-Plant Manager
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SSINS No.:
6835 Accession No.:
8011040269 IN 81-06 0
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UNITED STATES NUCLEAR REGULATORY COMMISSION us ev J
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.4h 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 11, 1981 IE In. formation Notice No. 81-06:
FAILURE OF ITE MODEL K-600 C,IRCUIT BREAKER
Purpose:
EThe purpose of this fnformation. notice ~is to' provide early notification of-
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a matter that could adversely affect the safety of nuclear power plants.
Toward this end, this.nformation' 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 fcr 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 bb 'followed 'by a complste. report'. ' Consequently, we have not yet evaluated the safety significance of this event.
Nevertheless, the
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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 questions regarding the information contained herein, please contact the Director of the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices 1
4
a 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 i
Accordance with 10 CFR 50.72 81-02 Trar.sportation of 1/23/81 All Radiography Radic3raphy Devices licensees 81-01 Possible Failures of 1/16/81 All power reactor General Electric Type facilities with an HFA Relays OL or CP.
4 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
~'Recircula'io'n Mode'While with an 0L or CP t
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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 Removal System at Davis-OL or CP Besse Unit No. 1 OL = Operating Licenses CP = Construction Permits
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