ML17305B777
| ML17305B777 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 02/29/1964 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Kouts H Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML17305B778 | List: |
| References | |
| FOIA-91-17 NUDOCS 9103200259 | |
| Download: ML17305B777 (6) | |
Text
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 202, WALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94596 March 11, 1981 Docket Nos. 50-528, 50-529, 50-530 Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 Attention:
Mr. E.
E.
Van Brunt, Jr.
Vice President, Nuclear Projects Gentlemen:
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M48 g 6 I98I e 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, R.
H. Engelken Director Encl osure:
IE Information Notice No. 81-06 cc w/enclosure:
F.
M. Hartley, APS
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SSINS No.:
6835 Accession No.:
8011040269 IN 81-06 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 11, 1981 IE Information Notice NO. 81-06:
FAILURE OF ITE MODEL K-600 CIRCUIT BREAKER
~Per ose:
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.
Descri tion of Circumstance:
By letter dated February 20, 1981, the Sacramento Municipal. Utility District informed us that, while performing preventive mai,ntenance on electrical circuit breakers at its Rancho Seco facility, an ITE Hodel. 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 size'd 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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RECENTLY ISSUED I E INFORMATION NOTICES Attachment IN 81-06 March ll, 1981 Information Notice No. 81-05 81-04 81-03 81-02 81-01 Sub ect Degraded DC System at Palisades Cracking in Main Steam Lines Checklist for Licensees Making Notifications of Significant Events in Accordance with 10 CFR 50.72 Transportation of Radiography Devices Possible Failures of General Electric Type HFA Relays Date of Issue
'/10/81 2/27/81 2/j.2/81 1/23/81.
1/16/81
' Issued'to' All power reactor facil.ities with an OL or CP All power reactor facilities with an OL
$11 power reactor facilities with an OL All Radiography licensees All power reactor facilities with an OL or CI'.
80-45 80-44 Potential Failure of BWR Backup Manual Scram Capability Actuation of ECCS in the Recirculation Mode While in Hot Shutdown 12/17/SQ Al] PWR,facilities wi.th,an OL or CP 12/16/80 A]l pWR facilities with an OL or CP 80-43 Failures of the Continuous 12/5/SQ
~ ~ater Level Honi tor for the Scram Discharge Volume at Dresden Unit No.
2 All nowor roac+or'aci,li ties. with an OL or Op 80 42 80-41 Effect of Radiation on Hydraulic Snubber Fluid Failure of Swing Check Valve in the Decay Heat Removal System at Davis-Besse Unit No.
1 11/24/80 11/10/80 All power reactor faciliti.es with an OL or CP All power reactor facilities with an OL or CP OL = Operating Licenses CP
= Construction Permi ts
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