ML19350B319
| ML19350B319 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/11/1981 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8103200259 | |
| Download: ML19350B319 (1) | |
Text
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~i NUCLEAR REGULATORY COMMISSION E
REGION V 0,
1990 N. CALIFORNIA BOULEVARD SulTE 202, WALNUT CREEK PLAZA WALNUT CREE K, CALIFORNIA 94596 March 11, 1981 Docket Nos. 50-528, 50-529, 50-530
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Arizona Public Service Company Ok C P. O. Box 21666
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Phoenix, Arizona 85036 g
p Attention: Mr. E. E. Van Brunt, Jr.
4 Vice President, Nuclear Projects
/ ro Gentlemen:
The enclosed IE Informtie7 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 i
Director
Enclosure:
IE Information Notice No. 81-06 l
l cc W/ enclosure:
F. W. Hartley, APS i
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r SSINS No.:
6835 Accession No.:
8011040269 IN 81-06 h
UNITED STATES
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NUCLEAR REGULATORY COMMISSION 4 #J s
- Jlnlu, 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 11, 1981 IE Information Notice N0. 81-06:
FAILURE OF ITE MODEL K-600 CIRCUIT BREAKER
Purpose:
The purpose of this infonnation 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 out of its terminal.
Further examinations revealed that the coil wire size was AWG 20, whercas 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.
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 '!otices
b 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 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
- Capabili ty 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 nowar raac+or u ter Level Monitor.for facilities.with an a
the ' Scram Discharge Volume OL or OP at Dresden Unit No. 2 80 42.
Effect of Radiation on '
11/24/80
-All-power reactor
- Hydraulic Snubber Fluid facilities with an 10L or CP 80. Failure of. Swing Check
.11/10/80 All power. reactor-i~
Valve in the Decay Heat
' facilities with an l
- Removal System'at Davis-OL or CP Besse Unit No. 1 4
e t
l 1 0L '= Operating ~ Licenses L
2 CP =fConstruction Permits J
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