ML19224C383
| ML19224C383 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 06/11/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 7907020254 | |
| Download: ML19224C383 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION y4 r/[ $
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-f JUN 11 1979 Docket No. 50-461 Docket No. 50-462 Illinois Power Company ATTN:
Mr. W. C. Gerstner Executive Vice President 500 South 27th Street Decatur, IL 62525 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, w
JamesG.Kepffer Director
Enclosure:
IE Information Notice No. 79-14 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General g,
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lJJ 7 007020$$Y
e U.S. NUCLEAR RECl'LATORY COMMISSION OFFICE OF INSPECTION AND ENF0FCEMENT
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REGION III June 11, 1979 IE Information Notice No. 7 0 - 1/.
SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS 2
S m ry:
The NRC inspection staf f has found that in several cases, facilities under construction have not applied the pertinent quality assurance require =ents of 10 CFR 50, Appendix B to the design, procurement, and installation of cable trays and their support systezas for Class IE electrical cables. This notice is being issued to all applicants for, and holders of construction permits, to re=ind the of the Commission's regulations on this subject.
Description of Circu= stances:
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 of.... earthquakes....without loss of capability to perfore their safety functions...."
2.
The C W ssion's Regulations on Reactor Site Criteria, Fart 100, Appendix A, define a " safe shutdown earthquake," (SSE) and generally identify the structures, syste=s and components which are required to re=ain functfenal during such an earthquake.
3.
Regulatory Guide 1.29 " Seismic Design Classification" states in pertinent part:
"C.I.
The following structures, systems and components of a nuclear power plant, includir.g their foundations and supports (e=phasis 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 these structures, systems and components."
"C1.q.
The Class II electric systems, including the auxiliary systems for the on-site electric power supplies, that provide the emergency electric power... "
No written response to this information a
questions regarding the matter, please c ifrC Regional Office.
DUPLICATE DOCUMENT 9/O f
Entire document previou, sly d"Atered
Attachment:
List of IE Information Notices Issued in 1979 into system under:
ANO No. of pages:
7
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