ML19224C371
| ML19224C371 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/11/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7907020233 | |
| Download: ML19224C371 (1) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION y ' s,, (y,g REGION 11
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101 MARIETT A ST., N W., SUITE 3100 o,,
8 AT LANT A, G EORGI A 30303
%,.....,o JUN 111979 In Reply Refer To:
RII:FJL 50-404 50-405 Virginia Electric and Power Company ATTN:
W. L. Proffitt Senior Vice President, Power P. O. Box 26666 Riche:ond, VA 23261 Gentlemen:
This Information Notice is being issued to call to your attention an aspect of the Cmission'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, N James P.'O'Reilly Director
Enclosure:
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IE Information Notice h
No. 79-14 1
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79070204'3 3 w. aw k
Virginia Electric and
' Power Company cc w/ encl:
W. R. Cartwright, Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. Perry Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 W. L. Stewart, Manager Post Office Box 315 Surry, Virginia 23883 e
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T UNITED STATES hTCLEAR REGULATDRY COMMISSION OFFICE OF INSPECTION AND EhTORCEMENT WASHINGTON, D.C.
20555 June 11, 1979 IE Information Notice No. 79-14 SAFETT CLASSIFICATION OF ELECTRICAL CABLE SUPPORT SYSTDiS Summary:
Ihe NRC inspection staff has found that in several cases, facilities under f
construction have not applied the pertinent quality assurance requirements o and installation of cable 10 CFR 50, Appendix B to the design, procurecent, This notice trays and their support systens for Class IE electrical cables.
remind them of the Coc: mission's regulations on this subject.
Descrf ption of Circumstances In the Cocsission's Regulations for Licensing of Production and Utilitation Facilities - 10 CFR Part 50, criterion 2 of Appendix A, states 1.
in part that " Structures, systems and ceaponente important to saf ety shall be designed to withs tand the ef f ecte of.... earthquakes....vithout loss of capability to perform their safety functions...."
The Cocnission's Regulations on Reactor Site Criteria, Part 100, Appendix A, define a "saf e shutdown earthquake," (SSE) and generally 2.
identify the structures, systems and conponents which are required to remain functional during such an earthquake.
Regulatory Guide 1.29 " Seismic Design " Classification" states in pertinent 3.
part:
The f ollowing structures, systems and components of a nuclear power plant, including their foundations and supports "C.I.
The pertinent quality the ef fects of the SSE and recain functional.
assurance requirements of Appendix B to 10 CFR 50 should be applied to all activities af fecting the safety related functions of these structures, systems and components."
including the auxiliery "C1.q.
The Class IE electric systecs, systems for the on-site electri m m g g g "that provide
- Lw cm the energency electric power...
DUPLICATE DOCUMENT
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's' Fo written response to this informa Entire document previous;y entered questions regarding the matter, ple into system under:
NRC Regional Office.
(( y/Q No Of pages: 2
1 Enclosure IE Inf ormation Notice No. 79-14 Page 1 of 1 June 11, 1979 LISTING OF IE INFORMATION }OTICES ISSUED IN 1979 Date Issued To Information Subject Issued Notice No. 79-01 Bergen-Paterson Bydraulic 2/2/79 All power reactor facilities with ac Shock and Sway Arrestor OL or a CP 79-02 Attempted Extortion - 2/2/79 All Fuel Facilities Low Enriched Uranium 79-03 Limitorque Valve Geared 2/9/79 All power reactor facilities with an Limit Switch Imbricant OL cr a CP 79-04 Degradation of 2/16/79 All power reactor f acilities with an Engineered OL or a CP Safety Features 79-05 Use of Improper Materials 3/21 /7 9 All power reactor facilities with an in Saf ety-Related Components OL or CP 79-06 Stress Analysis of 3/23/79 All Holders of Reactor OL or CP Safety-Related Piping 79-07 Rupture of Padvaste Tanka - 3/26/79 All power reactor facilities with an OL or CP 7 9-08 Interconnection of 3/28/79 All power reactor Contaminated Systecs with facilities with an Service Air Systens Used OL and Pu Processing As the Source of Breathing fuel f acilities Air 79-09 Spill of Radioactively 3/33/79 All power reactor f acilities with an Conta=inated Resin OL 79-10 Nonconforcing Pipe 4/16/79 All power reactor facilities with a Support Struts CP f}}