ML19350B343
| ML19350B343 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/11/1981 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 8103200298 | |
| Download: ML19350B343 (1) | |
Text
-:.,,
~
Q.
ggg7
.?
%g UNITED STATES 8%
NUCLEAR REGULATORY COMMISSION e
o REGION 1
\\
[y'M)8(h,,),J D
,A o
631 PARK AVENUE V
KING OF PRUSSIA, PENNSYLVANIA 19406 N
g*****o h,-
y2 s
Docket No. 50-219
~
Jersey Central Power and Light Company A " '* %'E'7#" 3
'A ATTN: Mr. Ivan R. Finfrock, Jr.
Vice President b
9 Oyster Creek Nuclear Generating Station g
P. O. Box 388
~
Forked River, New Jersey 08731 Gentlemen:
The enclosed IE Information Notice No. 81-06, dFailure of ITE Model K-600 Circuit Breaker," is forwarded to you for inf:rmation.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
/
Boy e H. Grier Director
Enclosure:
1.
IE Information Notice No. 81-06 with 1 attachment CCNTACT:
3
- 0. Ebneter (215-337-5283) cc w/ encl:
M. Laggart, Licensing Supervisor J. Knubel, BWR Licensing Manager 8103200Q4'f
~6 SSINS No.:
6835 Accession No.:
8011040269 IN 81-06 19 9 N D""
/h 5"9"
~~E UNITED STATES NUCLEAR REGULATORY COMMISSION O
mu IAJ
. wL 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
Purpose:
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.
Description of Circumstance:
By letter dated February 20, 1981, the Sacramento Municipal Uti'lity 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 sfzed 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 Notic7-
IN 31-05 March 11, 1931 RECENTLY ISSUED IE INFORMATION NOTICES Infcrmation Subject Date Issued to Notice No.
Issued 81-05 Degraded DC Systes 3/10/31 All holders of at Palisades a power reactor OL or CP 81-04 Cracking in Main 2/27/S1 All holcers of a Steam Lines cower reactor OL or CP 81-03 Checklist for 2/2/31 All holders of a Licensees Making power reactor Notifications of OL or NIOL Significant Events in Accordance with 10 CFR 50.72 81-02 Transportation of 1/23/31 All holders of a Radiography Devices radicgraphy license 81-01 Possible Failures of 1/15/51 All holders of a General Electric power reactor OL Type FFA Relays or CF 50-45 Potential Failure of 12/17/30 All holders of a E'4R Backup Manual power reacter Scram Capability OL or CP S0-44 Actuation of ECCS in 12/14/50 All holders of a the Recirculation Mode PWR power reactor OL While in Hot Shutdown or CP S0-43 Failures of the 12/5/80 All holders of a-Continuous Water Level SWR power reactor Monitor for the Scram OL or CP Discharge Volume at Dresden Unit'No. 2 80-29 Broken Studs on Terry 11/25/50 All holders'of a Supplement Turbine Steam Inlet power reactor No. I-Flange OL or CP
.