Source: https://www.ecfr.gov/cgi-bin/text-idx?mc=true&node=sg10.2.73.sg0&rgn=div7
Timestamp: 2020-07-12 10:34:38
Document Index: 691989245

Matched Legal Cases: ['§73', '§73', 'art 73', '§73', '§73', '§73', '§73', '§73', 'art 50', 'art 70', '§73', '§73', '§73', '§73', '§73', '§73']

§73.3 Interpretations.
§73.4 Communications.
(a) By mail addressed to: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation, Director, Office of Nuclear Material Safety and Safeguards, or Director, Office of Nuclear Security and Incident Response, as appropriate, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
(b) By hand delivery to the NRC's offices at 11555 Rockville Pike, Rockville, Maryland;
(d) Classified communications shall be transmitted to the NRC Headquarters' classified mailing address as specified in appendix A to part 73 of this chapter or delivered by hand in accordance with this paragraph.
[68 FR 58819, Oct. 10, 2003, as amended at 73 FR 5725, Jan. 31, 2008; 74 FR 62684, Dec. 1, 2009; 80 FR 74981, Dec. 1, 2015; 83 FR 58723, Nov. 21, 2018; 84 FR 65646, Nov. 29, 2019]
§73.5 Specific exemptions.
§73.8 Information collection requirements: OMB approval.
(a) The Nuclear Regulatory Commission has submitted the information collection requirements contained in this part to the Office of Management and Budget (OMB) for approval as required by the Paperwork Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information is it does not display a currently valid OMB control number. OMB has approved the information collection requirements contained in this part under control number 3150-0002.
(b) The approved information collection requirements contained in this part appear in §§73.5, 73.20, 73.21, 73.23, 73.24, 73.25, 73.26, 73.27, 73.37, 73.38, 73.40, 73.45, 73.46, 73.50, 73.51, 73.54, 73.55, 73.56, 73.57, 73.58, 73.60, 73.67, 73.70, 73.71, 73.72, 73.73, 73.74, and appendices B, C, and G to this part.
(1) In §§73.71 and 73.77, NRC Form 366 is approved under control number 3150-0104.
[62 FR 52189, Oct. 6, 1997, as amended at 67 FR 67101, Nov. 4, 2002; 73 FR 63574, Oct. 24, 2008; 74 FR 13970, Mar. 27, 2009; 77 FR 39909, July 6, 2012; 78 FR 29550, May 20, 2013; 80 FR 67275, Nov. 2, 2015; 80 FR 74981, Dec. 1, 2015]
§73.20 General performance objective and requirements.
(a) In addition to any other requirements of this part, each licensee who is authorized to operate a fuel reprocessing plant pursuant to part 50 of this chapter; possesses or uses formula quantities of strategic special nuclear material at any site or contiguous sites subject to control by the licensee; is authorized to transport or deliver to a carrier for transportation pursuant to part 70 of this chapter formula quantities of strategic special nuclear material; takes delivery of formula quantities of strategic special nuclear material free on board (f.o.b.) the point at which it is delivered to a carrier for transportation; or imports or exports formula quantities of strategic special nuclear material, shall establish and maintain or make arrangements for a physical protection system which will have as its objective to provide high assurance that activities involving special nuclear material are not inimical to the common defense and security, and do not constitute an unreasonable risk to the public health and safety. The physical protection system shall be designed to protect against the design basis threats of theft or diversion of strategic special nuclear material and radiological sabotage as stated in §73.1(a).
(b) To achieve the general performance objective of paragraph (a) of this section a licensee shall establish and maintain, or arrange for, a physical protection system that:
(1) Provides the performance capabilities described in §73.25 for in-transit protection or in §73.45 for fixed site protection unless otherwise authorized by the Commission;
(2) Is designed with sufficient redundancy and diversity to ensure maintenance of the capabilities described in §§73.25 and 73.45;
(3) Includes a safeguards contingency capability that can meet the criteria in appendix C to this part “Licensee Safeguards Contingency Plans;” and
(4) Includes a testing and maintenance program to assure control over all activities and devices affecting the effectiveness, reliability, and availability of the physical protection system, including a demonstration that any defects of such activities and devices will be promptly detected and corrected for the total period of time they are required as a part of the physical protection system.
(c) Each licensee subject to the requirements of paragraphs (a) and (b) of this section shall establish, maintain, and follow NRC-approved safeguards physical protection and safeguards contingency plans that describe how the licensee will comply with the requirements of paragraphs (a) and (b) of this section.
[44 FR 68188, Nov. 28, 1979, as amended at 57 FR 33430, July 29, 1992]
§73.24 Prohibitions.
(a) Except as specifically approved by the Nuclear Regulatory Commission, no shipment of special nuclear material shall be made in passenger aircraft in excess of (1) 20 grams or 20 curies, whichever is less, of plutonium or uranium-233, or (2) 350 grams of uranium-235 (contained in uranium enriched to 20 percent or more in the U-235 isotope).
(b) Unless otherwise approved by the Nuclear Regulatory Commission, no licensee may make shipments of special nuclear material in which individual shipments are less than a formula quantity, but the total quantity in shipments in transit at the same time could equal or exceed a formula quantity, unless either of the following conditions are met:
(1) The licensee shall confirm and log the arrival at the final destination of each individual shipment and retain the log for three years from the date of the last entry in the log. The licensee shall also schedule shipments to ensure that the total quantity for two or more shipments in transit at the same time does not equal or exceed the formula quantity, or
(2) Physical protection in accordance with the requirements of §§73.20, 73.25, and 73.26 is provided by the licensee for such shipments as appropriate so that the total quantity of special nuclear material in the remaining shipments not so protected, and in transit at the same time, does not equal or exceed a formula quantity.
[44 FR 68188, Nov. 28, 1979, as amended at 53 FR 19257, May 27, 1988]