10 CFR Appendix O to Part 110, Illustrative List of Fuel Element Fabrication Plant Equipment and Components Under NRC's Export Licensing Authority

Appendix O to Part 110 - Illustrative List of Fuel Element Fabrication Plant Equipment and Components Under NRC's Export Licensing Authority

Nuclear fuel elements are manufactured from source or special nuclear material. For oxide fuels, the most common type of fuel equipment for pressing pellets, sintering, grinding and grading will be present. Mixed oxide fuels are handled in glove boxes (or equivalent containment) until they are sealed in the cladding. In all cases, the fuel is hermetically sealed inside a suitable cladding which is designed to be the primary envelope encasing the fuel so as to provide suitable performance and safety during reactor operation. Also, in all cases, precise control of processes, procedures and equipment to extremely high standards is necessary in order to ensure predictable and safe fuel performance.

(a) Items that are considered especially designed or prepared for the fabrication of fuel elements include equipment that:

(1) Normally comes in direct contact with, or directly processes or controls, the production flow of nuclear material;

(2) Seals the nuclear material within the cladding;

(3) Checks the integrity of the cladding or the seal;

(4) Checks the finished treatment of the sealed fuel; or

(5) Is used for assembling reactor fuel elements.

(b) This equipment or systems of equipment may include, for example:

(1) Fully automatic pellet inspection stations especially designed or prepared for checking final dimensions and surface defects of fuel pellets;

(2) Automatic welding machines especially designed or prepared for welding end caps onto the fuel pins (or rods);

(3) Automatic test and inspection stations especially designed or prepared for checking the integrity of completed fuel pins (or rods). This item typically includes equipment for:

(i) X-ray examination of pin (or rod) end cap welds;

(ii) Helium leak detection from pressurized pins (or rods); and

(iii) Gamma-ray scanning of the pins (or rods) to check for correct loading of the fuel pellets inside.

(4) Systems especially designed or prepared to manufacture nuclear fuel cladding.

(c) Any other components especially designed or prepared for use in a fuel element fabrication plant or in any of the components described in this appendix.

[ 79 FR 39299, July 10, 2014]

This is a list of United States Code sections, Statutes at Large, Public Laws, and Presidential Documents, which provide rulemaking authority for this CFR Part.

This list is taken from the Parallel Table of Authorities and Rules provided by GPO [Government Printing Office].

It is not guaranteed to be accurate or up-to-date, though we do refresh the database weekly. More limitations on accuracy are described at the GPO site.

United States Code

§ 2071 - Determination of other material as special nuclear material; Presidential assent; effective date

§ 2073 - Domestic distribution of special nuclear material

§ 2074 - Foreign distribution of special nuclear material

§ 2077 - Unauthorized dealings in special nuclear material

§ 2092 - License requirements for transfers

§ 2093 - Domestic distribution of source material

§ 2094 - Foreign distribution of source material

§ 2095 - Reports

§ 2111 - Domestic distribution

§ 2112 - Foreign distribution of byproduct material

§ 2133 - Commercial licenses

§ 2134 - Medical, industrial, and commercial licenses

§ 2139 - Component and other parts of facilities

§ 2139a - Regulations implementing requirements relating to licensing for components and other parts of facilities

§ 2141 - Licensing by Nuclear Regulatory Commission of distribution of special nuclear material, source material, and byproduct material by Department of Energy

§ 2151 - Effect of international arrangements

§ 2152 - Policies contained in international arrangements

§ 2153 - Cooperation with other nations

§ 2153a - Approval for enrichment after export of source or special nuclear material; export of major critical components of enrichment facilities

§ 2153b - Export policies relating to peaceful nuclear activities and international nuclear trade

§ 2153c - Renegotiation of agreements for cooperation

§ 2153d - Authority to continue agreements for cooperation entered into prior to March 10, 1978

§ 2153e - Protection of environment

§ 2153e-1

§ 2153f - Savings clause; Nuclear Non-Proliferation Act of 1978

§ 2154 - International atomic pool

§ 2155 - Export licensing procedures

§ 2155a - Regulations establishing Commission procedures covering grant, suspension, revocation, or amendment of nuclear export licenses or exemptions

§ 2156 - Criteria governing United States nuclear exports

§ 2156a - Regulations establishing levels of physical security to protect facilities and material

§ 2157 - Additional export criterion and procedures

§ 2158 - Conduct resulting in termination of nuclear exports

§ 2159 - Congressional review procedures

§ 2160 - Subsequent arrangements

§ 2160a - Review of Nuclear Proliferation Assessment Statements

§ 2160b - Authority to suspend nuclear cooperation with nations which have not ratified the Convention on the Physical Security of Nuclear Material

§ 2160c - Consultation with Department of Defense concerning certain exports and subsequent arrangements

§ 2160d - Further restrictions on exports

§ 2201 - General duties of Commission

§ 2231 - Applicability of administrative procedure provisions; definitions

§ 2232 - License applications

§ 2233 - Terms of licenses

§ 2234 - Inalienability of licenses

§ 2236 - Revocation of licenses

§ 2237 - Modification of license

§ 2239 - Hearings and judicial review

§ 2243 - Licensing of uranium enrichment facilities

§ 2273 - Violation of sections

§ 2282 - Civil penalties

§ 5841 - Establishment and transfers

Statutes at Large