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Timestamp: 2019-11-14 02:52:08
Document Index: 111791526

Matched Legal Cases: ['art 50', 'art 50', '§ 50', '§ 50', '§ 50', '§ 50', 'art 2', 'art050', 'art050', 'art_50']

10 CFR 50 Appendix N, Appendix N to Part 50-Standardization of Nuclear Power Plant Designs: Permits to Construct and Licenses to Operate Nuclear Power Reactors of Identical Design At Multiple Sites - kanterella
Appendix N to Part 50-Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites Section 101 of the Atomic Energy Act of 1954, as amended, and § 50.10 of this part require a Commission license to transfer or receive in interstate commerce, manufacture, produce, transfer, acquire, possess, use, import or export any production or utilization facility. The regulations in this part require the issuance of a construction permit by the Commission before commencement of construction of a production or utilization facility, except as provided in § 50.10(e), and the issuance of an operating license before operation of the facility.
This appendix sets out the particular requirements and provisions applicable to situations in which applications are filed by one or more applicants for licenses to construct and operate nuclear power reactors of essentially the same design to be located at different sites.<a href="#N_1_appn" id="ftn1" title="Footnote 1 hyperlink">1</a>
For the technical information required by §§ 50.34(a) (1) through (5) and (8) and 50.34a (a) and (b), reference may be made to a single preliminary safety analysis of the design<a href="#N_2_appn" id="ftn2" title="Footnote 2 hyperlink">2</a> which, for the purposes of § 50.34(a)(1) includes one set of site parameters postulated for the design of the reactors, and an analysis and evaluation of the reactors in terms of such postulated site parameters. Such single preliminary safety analysis shall also include information pertaining to design features of the proposed reactors that affect plans for coping with emergencies in the operation of the reactors, and shall describe the quality assurance program with respect to aspects of design, fabrication, procurement and construction that are common to all of the reactors.
[[[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=1975_register&page=2977&position=1%7C40 FR 2977, Jan. 17, 1975]], as amended at [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=1984_register&page=9405&position=1%7C49 FR 9405, Mar. 12, 1984]]; [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=1986_register&page=40311&position=1%7C51 FR 40311, Nov. 6, 1986]]; [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=2005_register&page=61888&position=1%7C70 FR 61888, Oct. 27, 2005]]; [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=2007_register&page=49508&position=1%7C72 FR 49508, Aug. 28, 2007]]]
<a href="#ftn1" name="N_1_appn" title="Footnote 1">1</a> If the design for the power reactor(s) proposed in a particular application is not identical to the others, that application may not be processed under this appendix and Subpart D of Part 2 of this chapter.
<a href="#ftn2" name="N_2_appn" title="Footnote 2">2</a> As used in this appendix, the design of a nuclear power reactor included in a single referenced safety analysis report means the design of those structures, systems and components important to radiological health and safety and the common defense and security.
[[URL::http://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-appn.html%7CNRC website 10 CFR 50 Appendix N]]
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