ML19224C276
| ML19224C276 | |
| Person / Time | |
|---|---|
| Site: | 05000471 |
| Issue date: | 06/11/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Rhonda Butler BOSTON EDISON CO. |
| References | |
| NUDOCS 7907020042 | |
| Download: ML19224C276 (1) | |
Text
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((y,,, c 'h UNITED STATES j
NUCLEAR REGULATORY COMMISSION y;;l 7, D '
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KING OF PRUSSIA, PENNSYLVANI A 19406 June 11,1979 Docket No. 50-471 Boston Edison Company ATTN: Mr. R. M. Butler Nuclear Projects Manager 800 Boylston Street Boston, MA 02199 Gentlemen:
This Information Notice 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.
No written response is raquired.
If you have questions regarding this matter, please contact this office.
Sincerely, h
W Boyce H. Grier
~ Director
Enclosures:
1.
IE Information Notice No. 79-14 2.
List of Information Notices Issued in 1979 cc w/encls:
J. E. Howard, Vice President - Nuclear W. M. Sides, Quality Assurance Manager n,.
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7 007020 0 9 'A (P
A ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-14 bate:
June 11, 1979 Page 1 of 1 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 o'T 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, tc remirid them of the Commissior.'s regulations on this subject.
Descri tien 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 Regula. ions on Reactor Site Criteria, Part 100, Appendix A, define a " safe shutdown earthquake," (SSE) and generally identify the str'ictures, 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.l.
The following structures, systems and components of a nuclear power plant, including their foundations and supports (emphasis added) are designated as Seismic Category 1 ana 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."
"Cl.q.
The Class IE electric systems, including the auxiliary systems for the onsite electric power supplies, that provide the emergency electric power..."
No written response to this informatio
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questions regarM og the matter, pleas DUPLICATE DOCUMENT NRC Regional Orrice.
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