ML19224C345
| ML19224C345 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/11/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Clayton F ALABAMA POWER CO. |
| References | |
| NUDOCS 7907020190 | |
| Download: ML19224C345 (1) | |
Text
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'o UNITED STATES l'
I, NUCLEAR REGULATORY COMMISSION
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E REGION 11 k
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101 M ARIE TT A ST., N.W., EUITE 3100 E
ATLANT A GEORGIA 30303
<g In Reply Refer To:
RII:FJL 50-364 Alabama Power Company ATTN:
F. L. Clayton, Jr.
Senior Vice President P. O. Box 2641 Birmingham, AL 35291 Centlemen:
This Informatien Notice is being issved to call to your attention an aspect of the Corzsission's regulations which IE inspectors have found is not always being fully implemented. No written response is required.
If you have questions regarding this matter, please contact me.
a Sincerely, 5 [_
g~ James P. O'Reilly Director Enclosure IE Infomation Notice No. 79-14 "90f alggtg-268 i00 7 907020 /90 fp
. Alabama Power Company s
cc w/ encl:
A. R. Barton Executive Vice President Post Office Box 2641 Birmingham, Alabama 35291 C. Biddinger, Jr.
Manager-Corporate Quality Assurance Post Office Box 2641 Birmingham, Alabama 35291 R. E. Hollands, Jr.
QA Supervisor Post Office Box U Ashford, Alabama 36312 4
se 268
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UNITED STATES NUCLEAR REGULAIVRY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINCION, D.C.
20555 June 11, 1979 IE Inf ormation Notice No. 79-14 SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTDiS Suacary:
The NRC inspection staff has found that in several cases, facilities under construction have not applied the pertinent quality assurance requirenents of 10 CFR 50, Appendix B to the design, procurment, and installation of cable This notice trays and their support systees for Class IE electrical cables.
is being issued to all applicants for, and holders of construction pemits, to rescind them of the Cocmission's regulations on this subject.
Description of Ciretanstances:
In the Cocmission's Regulations for Licensing of Production and 1.
Utilir.ation Facilities - 10 CFR Part 50 Criterion 2 of Appendix A, states in part that " Structures, systems and emponents important to safety shall be des igned to withs tand the ef f ects of.... earthquakes....without loss of capability to perform their saf ety functions...."
The Commission's Regulations on Reactor Site Criteria, Part 100, 2.
Appendix A, define a "saf e shutdown earthquake," (SSE) and generally identify the structures, systems and components which are required to remain functional during such an earthquake.
Regulatory Guide 1.29 " Seismic Design Classification" states in pertinent 3.
part:
systens and components of a nuclear The f ollowing structures, "C.).
including their foundations and supports (ecphasis added) power plant, are designated as Seis=ic Category 1 and should be designed to withstand the ef fects of the SSE and recain functional. The pertinent quality assurance requirements of Appendix B to 10 CFR 50 should be applied to all activities af fecting the saf ety related functions of these structures, systems and emponents."
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The Class IE electrie_--% _ gg*the auxiliary
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systems for the on-site elec DUPLICATE DOCUMENT- ( 0
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k No written response to this infor Entire document previously ntered into system under:
questions regarding the matter, p h &[ }l NRC Regional Of fice. ANO No. of pages: Q}}