ML19224C390
| ML19224C390 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/11/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 7907020262 | |
| Download: ML19224C390 (1) | |
Text
o UNITED STATES 9',
NUCLEAR REGULATORY COMMISSION
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WALNUT CREEK, CALIFORNIA 94S96 Junc.11,1979 Docket flos. 50-528 50-529 50-530 Arizona Public Service Company P. O. Box 21666 Phoenix, Arizona 85036 Attention: f4r. E. E. Van Brunt, Jr.
Vice President, Construction Projects Gentleraen:
This Information flotice is being issued to call to your attention an aspect of the Commission's regulations which IE inspectors have found is not always being fully implemented.
fio written response is required.
If ycu have questions regarding this matter, please contact me.
Sincerely,
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R. H. Engelken - F 7
- Director V
Enclosure:
IE Information flotice fio. 79-14 cc: w/ enclosure:
F. W. Hartley, APS 271 060 790702 0p(02
UNITED STATES NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 11, 1979 IE Information Not. ice No. 79-14 SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS Sumary:
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, Appendix 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 renind them of the Commission's regulations 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 of.... earthquakes....without loss of capability to perform their safety functions...."
2.
The Commission's Regulations on Reactor Site Criteria, Part 100, Appendix A, define a " safe shutdown earthquake," (SSE) and generally identify the structures, systens and components which are required to remain functional during such an earthquake.
3.
Regulatory Guide 1.29 " Seismic Design Classification" states in pertinent part:
"C.1.
The following structures, systems and conoonents of a nuclear power plant, includin:) their foundations and supports (emphasis added) are designated as Se'smic 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 IE electric systems, including the auxiliary systems for the on-site electric power supplies, that provide the emergcncy electric power... "
No written response to this information notice is required.
If you have questions regarding the matter, please T
=r r'
NRC Regional Office.
DUPLICATE DOCUMENT 2 71 061 Entire document previously entered into system under:
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