ML19224C393
| ML19224C393 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/11/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane P PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7907020265 | |
| Download: ML19224C393 (1) | |
Text
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UNITED STATES 8 y
g NUCLEAR REGULATORY COMMISSION GO s
REGION V S hA,
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1990 N. CALIFORNIA BOULEVARD
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WALNUT CR E E K, CALIFORNIA 94595 June 11,1979 Docket Nos. 50-275 50-323 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention:
Mr. Philip A. Crane, Jr.
Assistant General Counsel Gentlemen:
This Information tiotice 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 you have questions regarding this matter, please contact me.
Sincerely,
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[R ' H Engelken / f Director b
Enclosure:
IE Information tiotice flo. 79-14 cc w/ enclosures:
W. A. Raymond, PG&E J. D. Worthington, PG&E R. Ramsay, Diablo Canyon 271 062 2 eon 2 0:z65^
UNITED STATES NUCLEAR REGULATORY COMilISSION 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 11, 1979 IE Infoi mation Notice No. 79-14 SAFETY CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTEMS Sunmary:
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 remind them of the Commission's regulationc 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, de"ine a " safe shutdown earthquake," (SSE) and generally identify the structures, systems 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 components of a nuclear power plant, including 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 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 emergency electric power..."
No written response to this information notice is required.
If you have questions regarding the natter, please g
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NP.C Regional Office.
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