ML19350B330
| ML19350B330 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/11/1981 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Hancock J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8103200278 | |
| Download: ML19350B330 (1) | |
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'o UNITED STATES 8 ",
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NUCLEAR REGULATORY COMMISSION o
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101 MARIETTA ST., N.W.. SUITE 3100
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Florida Power Corporation ATTN:
J. A. Hancock, Assistant Vice President Nuclear Operations P. O. Box 14042, Mail Stop C-4 St. Petersburg, FL 33733 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 j
licensee actions may be requested.
Should you have any questions regarding this information notice, please contact this office.
Sincerely, As d James P. O'Reilly Director 4
'Unclosure's:
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IE Information Notice No. 81-06 2.
List of Recently Issued l
IE Information Notices l-cc.w/ encl:
D. C. Poole, Nuclear Plant Manager 1
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UNITED STATES
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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 Purcose:
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 Mcdel K-600 circuit breakers manufactured by ITE.
Descriotion of Circumstance:
I By letter dated February 20, 1981, the 5acramento 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 cbserved not to trip. An investigation revealed that a tripping coil wire had slipped out of.its termir>1.
Further examinations revealed that the coil wire size was AWG 20, where the mating lug was sized for AWG 16-14 wire. A check of other ITE electr:
l breakers indicated that the problem may be generic.
Subsequent to the 4etter, 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 ' wilt be followed'by' a complete report. ' Consequ'ently, wc nave not yet evaluated the safety significance of this event. -Nevertheless, the
~ information herein is.being provided as an early notification of a possibly significant svent. Although no specific action or response is requested at this time, recipients should review the information for possible applicability to tneir facilities.
If NRC evaluations so indicate, further licensee actions may be requested.
LIf you have any questions regarding the information contained herein, please contact the Director of the appropriate NRC Regional Office.
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Attachment:
Recently issued IE Information Notices h
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1 Attachment IN 81-06 March 11, 1981 i
RECENTLY ISSUED 1
IE INFORMATION NOTICES Information Date of i
Notice No.
Subject Issue Issued to 81-05 Degraded DC System at 2/10/81 All power reactor i
Palisades facil-ities with an
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81-04 Cracking in Main 'iteam 2/27/81 All power reactor Li,n.e s facilities with an OL l
81-03 Checklist for. Licensees 2/12/81 All power reactor Makinc Noti #ications of facilities with an Significant Events in OL l
Accordance with 10 i
CFR 50.72 i
81-02 Transportation of.
1/23/81 All Radiography j
Radiography Devices licensees 81-01 Possible Failures of.
1/16/81 All power reactor 1
i General Electric Type facilities with an l
t j
80-45 Potential Failure of 12/17/80 All PWR facilities BWR Backup Manual Scram with an OL or CP i
Capability 1
80-44e.
.. Actuation. oft ECCS in the, 12/16/80
- All.PWR facilities
~
Recirculation Mode While
-with an OL or CP in Hot Shutdown l
80-43 Failure., :f ~he Continuous 12/5/80 ~
All power reactor Water Level Monitor for facilities with an l
the Scram Discharge Volume OL or CP at Oresden Unit No. 2 l-l 80-42 Effect of Radiation on 11/24/80 All power' reactor j-Hydraulic Snubber Fluid racilities with an OL or CP i
80 Failure'of Swing Check 11/10/80 All power reactor
(
Valve in the Decay Heat
' facilities with an i
Removal System at Davis-0L'or CP
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'Besse Unit No. 1 l
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'OL = Operating Licenses l
CP = Construction Permits I
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