ML19224C374
| ML19224C374 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, LaSalle  |
| Issue date: | 06/11/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Brian Lee COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 7907020237 | |
| Download: ML19224C374 (1) | |
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UNITED STATES s
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NUCLEAR REGULATORY COMMISSION
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JUN 11 1979 Docket Nos. 50-373, 50-374, 50-454, 50-455, 50-456 and 50-457 Commonwealth Edison Company ATTN:
Mr. Byron Lee, Jr.
V;ce President Post Office Box 767 Chicago, IL 60690 Gentlemen:
This Information Notice is being issued to call to your attention an aspect of the Commissions'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.
Sincerely, bb VJames G. Kepp er Director
Enclosure:
IE Informaticn Notice No. 79-14 cc w/ encl:
Mr. L. J. Burke, Site PDR Project Superintendent Local PDR Mr. T. E. Quaka, Quality NSIC Assurance Supervisor TIC Mr. R. H. Holyoak, Station Mr. Dean Hansell, Office of Superintendent Assistant Attoreny General Mr. Gunner Sorensen, Site Project Superintendent Mr. R. Cosaro, Project Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 1
~ REGION III June 11, 1979 IE Information Notice No. 79-14 SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS S m ry:
The NRC inspection staff has found that in several cases, facilities under construction have not applied the pertinent quality assurance requirements of 10 CFR 50, Appe dix B to the design, procurement, and installation of cable trays and their support systems for Class IE electrical cables. This notice is being issued to all applicants for, and holders of construction permits, to remind them of the Commission's regulstions on this subject.
Description of Circumstances:
1.
In the Commission's Regulations for Licensing of Production and Utilization Facilities - 10 CFR Part 50, Criterion 2 of Appendix A, states in part that " Structures, systems and components important to safety shall be designed to withstand the effects or.... earthquakes....without loss of capability to perform their safety functions...."
2.
The C d ssion's Regulations on Reactor Site Criteria, Part 100, Appendix A, define a " safe shutdown earthquake," (SSE) and generally identify the structures, systems and components which are required to re=ain functional during such an earthquake.
3.
Regulatory Guide 1.29 " Seismic Design Classification" states in pertinent part:
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The following structures, systems and co=ponents of a nuclear powcr plant, inclu!ing their foundations and supports (emphasis added) are designated as Seismic Category 1 and should be designed to withstand the effects of the SSE and remain functional. The pertinent quality assurance requirements of Appendix B to 10 CFR 50 should be applied to all activities affecting the safety related functions of the.se structures, systems and components."
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The Class II electric systems, including the auxiliary systens for the on-site electric power supplies, that provide the emergency electric power... "
No written response to this informati St4he d s fnt;f-T' qq nuestions regarding the matter, pleas NhC Regional Office.
DUPLICATE DOCUMENT
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Attachment:
List of IE Information Entire document previously entered Notices Issued in 1979 Into system under:
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