ML19263C683
| ML19263C683 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/08/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Barton A ALABAMA POWER CO. |
| References | |
| NUDOCS 7902280518 | |
| Download: ML19263C683 (2) | |
Text
e 7 E#o pa stou UNITED STATES NUCLEAR REGULATORY COMMISSIOt.
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EB a 'G79 In Reply Refer To:
RII:JPO 50-364 Alabama Power Company Attn:
Mr. A. R. Barton Executive Vice President Post Office Box 2641 Birmingham, Alabama 35291 Gentlemen:
Enclosed is IE Bulletin 79-01.
It requires action by you with regard to power reactor facilities with an operating license except for the 11 SEP plants which are listed in Enclosure 3.
This Bulletin is also being sent for information to the 11 SEP plants and all power reactor facilities with a construction permit. No action or written response is required for construction permit facilities or the 11 SEP plants.
Should you h e questions regarding this Bulletin or the actions required of you, ple se contact this office.
Sincerely,
<QNVn'hw _-
James P. O'Reilly N9 irector
Enclosures:
1.
List of IE Bulletins Issued in the past 12 months 3.
List of SEP Plants (11) 790 228 06($
Alabama Power Company cc w/ encl:
Mr. R. E. Hollands, Jr.
Quality Assurance Supervisor Farley Nuclear Plant Post Office Box U Ashford, Alabama 36312
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-01 Date:
February 8,1979 Page 1 of 3 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Description of Circumstances:
The intent of IE Circular 78-08 was to highlight to all licensees important lessons learned from environmental qualification deficiencies reported by individual licensees.
In this regard, licensees were requested to examine installed safety-related electrical equipment and determine that proper documentation existed which provided assurance that this equipment would function under postulated accident conditions. The scope of IE Circular 78-08 was much broader than other previously issued Bulletins and Circulars (such as IEB 78-04 and IEB 78-02) which addressed specific component failures.
The intent of this Bulletin is to raise the threshold of IE Circular 78-08 to the level of a Bulletin; i.e., action requiring a licensee response.
Inspections conducted to date by the NRC of licensees' activities in response to IE Circular 78-08 have identified one component which licensees have found to be unqualified for service within the LOCA environment.
Specificially, unqualified stem mounted limit switches (SMLS), other than those identified in previously issued IE Bulletin 78-04, were found to be installed on safety-related valves inside containment at both Duane Arnold and Quad Cities 1 and 2 Nuclear Generating Stations.
The unqualified switches are identified as NAMC0 Models SL2-C-11, S3CML, SAI-3I, SAI-32, D1200j, EA-700 and EA-770 switches.
According to the manufacturer, these switches are designed only for general purpose applications and are not co'nsidered suitable devices for service in the LOCA environment.
Consequently, switches are being replaced at the above power plants with qualified components.
Also, NRC inspection of component qualification has identified equipment which does not have documenution indicatina it is qualified for the LOCA environment.
The in s'
re-review and resolution attention from all licens of the protracted schedul DUPLICATE DOCUMENT requesting the power reac xpedite completion of tht.
Entire document previously IE Circular 78-08 dated Mr.
entered into system under:
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