Source: https://www.federalregister.gov/documents/2014/07/10/2014-15828/export-controls-and-physical-security-standards
Timestamp: 2017-10-18 22:10:31
Document Index: 488686084

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Federal Register :: Export Controls and Physical Security Standards
The final rule is effective August 11, 2014, except that the changes to Sec. 110.44(a) and (b)(1) and appendix M to 10 CFR part 110 are effective December 31, 2014. The incorporation by reference of the material in this document is approved as of December 31, 2014.
39289-39300 (12 pages)
3150-AJ33
Export and Import of Nuclear Equipment and Material; Nuclear Suppliers Group Export Controls and Physical Security Standards
Section 110.2 Definitions
Section 110.26 General License for the Export of Nuclear Reactor Components
Section 110.30 Members of the Nuclear Suppliers Group
Section 110.42 Export Licensing Criteria
Section 110.44 Physical Security Standards
V. Backfit Analysis and Issue Finality
1.1 Rotating Components
1.2 Static Components
1.1 Gaseous Diffusion Barriers and Barrier Materials
1.2 Diffuser Housings
1.3 Compressors and Gas Blowers
1.4 Rotary Shaft Seals
1.5 Heat Exchangers for Cooling UF6
2.1 Feed Systems/Product and Tails Withdrawal Systems
2.2 Header Piping Systems
2.3 Vacuum Systems
2.4 Special Shut-Off and Control Valves
2.5 UF6 Mass Spectrometers/Ion Sources
https://www.federalregister.gov/d/2014-15828 https://www.federalregister.gov/d/2014-15828
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations pertaining to the export and import of nuclear materials and equipment. This rulemaking is necessary to conform the export controls of the United States to the international export control guidelines of the Nuclear Suppliers Group (NSG), of which the United States is a member, and to incorporate by reference the current version of the International Atomic Energy Agency's (IAEA) document, “Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5), January 2011.” Also, this final rule makes certain editorial revisions, and corrects typographical errors.
The final rule is effective August 11, 2014, except that the changes to § 110.44(a) and (b)(1) and appendix M to 10 CFR part 110 are effective December 31, 2014. The incorporation by reference of the material in this document is approved as of December 31, 2014.
Please refer to Docket ID NRC-2014-0007 when contacting the NRC about the availability of information for this final rule. You can access publicly-available information related to this final rule by any of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0007. Address questions about NRC dockets to Carol Gallagher; telephone: 301-287-3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this final rule.
Brooke G. Smith, Office of International Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone: 301-415-2347, email: Brooke.Smith@nrc.gov.
VII. Environmental Impact Statement
This final rule conforms the NRC's export and import regulations in 10 CFR part 110, “Export and Import of Nuclear Equipment and Material,” and appendices A, B, C, D, E, F, G, H, I, J, K, N, and O, which contain illustrative lists of items under the NRC's export licensing authority, to current nuclear nonproliferation policies of the Executive Branch. These revisions are necessary to implement changes made to the NSG Guidelines, “Guidelines for Nuclear Transfers (INFCIRC/254/Revision 12/Part 1), June 2013,” as adopted by the governments participating in the NSG at the June 2012 and 2013 Plenary Meetings. In addition, this rule amends § 110.30, “Members of the Nuclear Suppliers Group,” to add Mexico and Serbia as member countries of the NSG that are eligible to receive radioactive materials under certain general licenses for export. The NSG Guidelines can be found at: www.nuclearsuppliersgroup.org.
In January 2011, the IAEA published the document titled, “Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5).” This rule also amends § 110.44 and appendix M to 10 CFR part 110 to incorporate by reference the update and recommendations contained in Revision 5 of this IAEA document.
Because this rule involves a foreign affairs function of the United States, the notice and comment provisions of the Administrative Procedure Act do not apply (5 U.S.C. 553(a)(1)). In addition, solicitation of public comments would delay the U.S. conformance with its international obligations, and would be contrary to the public interest (5 U.S.C. 553(b)). The final rule is effective August 11, 2014, except that the changes to § 110.44(a) and (b)(1) and appendix M to 10 CFR part 110 are effective December 31, 2014.Start Printed Page 39290
Paragraph (2)(ii) of the definition of “Utilization facility” is amended to make conforming changes consistent with the changes to appendix A to 10 CFR part 110.
This rule amends § 110.26 to make conforming changes to paragraph (a) consistent with the changes to appendix A to 10 CFR part 110.
This rule amends § 110.30 to update the list of NSG members by adding Mexico and Serbia.
This rule amends § 110.42 to make conforming changes to Footnote 1 consistent with the changes to appendix A to 10 CFR part 110.
Paragraphs (a) and (b)(1) of § 110.44 are amended to incorporate by reference the most recent revision to INFCIRC/225/Revision 5, “The Physical Protection of Nuclear Material and Nuclear Facilities.” The effective date for these changes is delayed until December 31, 2014, to provide adequate time for countries to meet the recommendations in Revision 5. “The Physical Protection of Nuclear Material and Nuclear Facilities,” INFCIRC/225/Revision 4 (corrected), July 1999, will continue to be used as the physical protection standard in recipient countries until the effective date for INFCIRC/225/Revision 5, as incorporated by reference in 10 CFR part 110.
These appendices are amended to reflect the updated guidelines of the NSG consistent with the IAEA document, “Guidelines for Nuclear Transfers, (INFCIRC/254/Revision 12/Part 1).” The appendices in 10 CFR part 110 are illustrative only and are not meant to be inclusive lists of facilities and equipment under the NRC's export licensing jurisdiction.
Appendix M is amended to update the Categorization of Nuclear Material table to be consistent with IAEA publication, INFCIRC/225/Revision 5. The changes to appendix M of 10 CFR part 110 are effective December 31, 2014.
Authority: Atomic Energy Act secs. 51, 53, 54, 57, 63, 64, 65, 81, 82, 103, 104, 109, 111, 126, 127, 128, 129, 161, 181, 182, 183, 187, 189, 223, 234 (42 U.S.C. 2071, 2073, 2074, 2077, 2092-2095, 2111, 2112, 2133, 2134, 2139, 2139a, 2141, 2154-2158, 2201, 2231-2233, 2237, 2239, 2273, 2282); Energy Reorganization Act sec. 201 (42 U.S.C. 5841; Solar, Wind, Waste, and Geothermal Power Act of 1990 sec. 5 (42 U.S.C.2243); Government Paperwork Elimination Act sec. Start Printed Page 392911704, 112 Stat. 2750 (44 U.S.C. 3504 note); Energy Policy Act of 2005, 119 Stat. 594.
2. In § 110.2, revise paragraph (2)(ii) of the definition of “Utilization facility” to read as follows:
3. In § 110.26, revise the introductory text of paragraph (a) to read as follows:
4. Amend § 110.30 by adding the words “Mexico” and “Serbia” in alphabetical order.
5. In § 110.42, revise footnote 1 to read as follows:
1 Export of nuclear reactors, reactor pressure vessels, reactor primary coolant pumps and circulators, “on-line” reactor fuel charging and discharging machines, and complete reactor control rod systems, as specified in paragraphs (1) through (4) of appendix A to this part, are subject to the export licensing criteria in § 110.42(a). Exports of nuclear reactor components, as specified in paragraphs (5) through (11) of appendix A to this part, when exported separately from the items described in paragraphs (1) through (4) of appendix A to this part, are subject to the export licensing criteria in § 110.42(b).
6. In § 110.44, revise paragraphs (a) and (b)(1) to read as follows:
(a) Physical security measures in recipient countries must provide protection at least comparable to the recommendations in the current version of IAEA publication, “Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities” (INFCIRC/225/Revision 5), January 2011, which is incorporated by reference in this part. This incorporation by reference was approved by the Director of the Office of the Federal Register in accordance with 5 U.S.C. 552(a) and 1 CFR part 51. Notice of any changes made to the material incorporated by reference will be published in the Federal Register. Copies of INFCIRC/225/Revision 5 may be obtained from the Marketing and Sales Unit, Publishing Section, IAEA, Vienna International Centre, P.O. Box 100, 1400 Vienna Austria; Fax: 43 1 2600 29302; telephone: 43 1 2600 22417; email: sales.publications@iaea.org; Web site: http://www.iaea.org/​books. You may inspect a copy at the NRC Library, 11545 Rockville Pike, Rockville, Maryland 20852-2738, telephone: 301-415-4737 or 1-800-397-4209, between 8:30 a.m. and 4:15 p.m.; or at the National Archives and Records Administration (NARA). For information on the availability of this material at NARA, call 202-741-6030, or go to: http://www.archives.gov/​federal-register/​cfr/​ibr-locations.html.
7. Revise appendix A to part 110 to read as follows:
8. Revise appendix B to part 110 to read as follows:
Note: The gas centrifuge normally consists of a thin-walled cylinder(s) of between 75 mm and 650 mm diameter contained in a vacuum environment and spun at high peripheral speed (of the order of 300 m/per second and more) with the central axis vertical. In order to achieve high speed, the materials of construction for the rotating rotor assembly, and hence its individual components, have to be manufactured to very close tolerances in order to minimize the unbalance. In contrast to other centrifuges, the gas centrifuge for uranium enrichment is characterized by having within the rotor chamber a rotating disc-shaped baffle(s) and a stationary tube arrangement for feeding and Start Printed Page 39292extracting uranium hexafluoride (UF6) gas and featuring at least three separate channels of which two are connected to scoops extending from the rotor axis towards the periphery of the rotor chamber. Also contained within the vacuum environment are a number of critical items which do not rotate and which, although they are especially designed, are not difficult to fabricate nor are they fabricated out of unique materials. A centrifuge facility, however, requires a large number of these components so that quantities can provide an important indication of end use.
If interconnected, the cylinders are joined together by flexible bellows or rings as described in § 1.1(c) of this appendix. The rotor is fitted with an internal baffle(s) and end caps, as described in § 1.1(d) and (e) of this appendix, if in final form. However, the complete assembly may be delivered only partly assembled.
(a) Magnetic Suspension Bearings: 1. Especially designed or prepared bearing assemblies consisting of an annular magnet suspended within a housing containing a damping medium. The housing will be manufactured from a UF6 resistant material (see footnote to § 2 of this appendix). The magnet couples with a pole piece or a second magnet fitted to the top cap described in § 1.1(e) of this appendix. The magnet may be ring-shaped with a relation between outer and inner diameter smaller or equal to 1.6:1. The magnet may be in a form having an initial permeability of 0.15 Henry/meter or more, or a remanence of 98.5 percent or more, or an energy product of greater than 80,000 joules/m3. In addition to the usual material properties, it is a prerequisite that the deviation of the magnetic axes from the geometrical axes is limited to very small tolerances (lower than 0.1 mm) or that homogeneity of the material of the magnet is specially called for.
(b) Bearings/Dampers: Especially designed or prepared bearings comprising a pivot/cup assembly mounted on a damper. The pivot is normally a hardened steel shaft polished into a hemisphere at one end with a means of attachment to the bottom cap described in § 1.1(e) of this appendix at the other. The shaft may, however, have a hydrodynamic bearing attached. The cup is pellet-shaped with hemispherical indentation in one surface. These components are often supplied separately to the damper.
(a) Feed Systems/Product and Tails Withdrawal Systems: Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6 including:Start Printed Page 39293
(e) Frequency Changers: Frequency changers (also known as converters or inverters) especially designed or prepared to supply motor stators as defined under § 1.2(d) of this appendix, or parts, components, and subassemblies of such frequency changers having all of the following characteristics:
9. Revise appendix C to part 110 to read as follows:
(a) Especially designed or prepared thin, porous filters, with a pore size of 10-100 nm, a thickness of 5 mm or less, and for tubular forms, a diameter of 25 mm or less, made of metallic, polymer or ceramic materials resistant to corrosion by UF6 (See Note in § 2 of this appendix).
Especially designed or prepared hermetically sealed vessels for containing the gaseous diffusion barrier, made of or protected by UF6-resistant materials (See Note in § 2 of this appendix).
Especially designed or prepared compressors or gas blowers with a suction volume capacity of 1 m3 per minute or more of UF6, and with a discharge pressure of up to 500 kPa, designed for long-term operation in the UF6 environment, as well as separate assemblies of such compressors and gas blowers. These compressors and gas blowers have a pressure ratio of 10:1 or less and are made of, or protected by, materials resistant to UF6 (See Note in § 2 of this appendix).
Especially designed or prepared heat exchangers made of or protected by UF6 resistant materials (see Note to § 2 of this appendix) and intended for a leakage pressure change rate of less than 10 Pa per hour under a pressure difference of 100 kPa.
Especially designed or prepared process systems or equipment for enrichment plants Start Printed Page 39294made of, or protected by, materials resistant to corrosion by UF6, including:
10. Revise appendix D to part 110 to read as follows:
(iii) Separation nozzle or vortex tube units for the separation of UF6 from carrier gas; orStart Printed Page 39295
11. Revise appendix E to part 110 to read as follows:
(i) Especially designed or prepared chemical or electrochemical reduction systems for regeneration of the chemical reducing agent(s) used in ion exchange uranium enrichment cascades.Start Printed Page 39296
12. Revise appendix F to part 110 to read as follows:
(12) UF6/carrier gas separation systems (molecular based methods).Start Printed Page 39297
13. Revise appendix G to part 110 to read as follows:
Note: In the plasma separation process, a plasma of uranium ions passes through an electric field tuned to the 235 U ion resonance frequency so that they preferentially absorb energy and increase the diameter of their corkscrew-like orbits. Ions with a large-diameter path are trapped to produce a product enriched in235 U. The plasma, made by ionizing uranium vapor, is contained in a vacuum chamber with a high-strength magnetic field produced by a superconducting magnet. The main technological systems of the process include the uranium plasma generation system, the separator module with superconducting magnet, and metal removal systems for the collection of “product” and “tails.”
14. In appendix H to part 110, add a new paragraph (4) to read as follows:
15. Revise appendix I to part 110 to read as follows:
(ii) A maximum diameter of 175 mm (7 in) for cylindrical vessels, orStart Printed Page 39298
16. In appendix J to part 110, add a new paragraph (c) to read as follows:
17. Revise appendix K to part 110 to read as follows:
Complete heavy water upgrade systems or columns especially designed or prepared for Start Printed Page 39299the upgrade of heavy water to reactor-grade deuterium concentration. These systems, which usually employ water distillation to separate heavy water from light water, are especially designed or prepared to produce reactor-grade heavy water (i.e., typically 99.75 percent deuterium oxide) from heavy water feedstock of lesser concentration.
18. Revise appendix M to part 110 to read as follows:
[From IAEA INFCIRC/225/Revision 5]
Category III 3
1. Plutonium1 Unirradiated 2 2 kg or more Less than 2 kg but more than 500 g 500 g or less but more than 15 g.
2. Uranium-235 (235 U) Unirradiated 2:
—Uranium enriched to 20 percent235 U or more 5 kg or more Less than 5 kg but more than 1 kg 1 kg or less but more than 15 g.
—Uranium enriched to 10 percent235 U but less than 20 percent235 U 10 kg or more Less than 10 kg but more than 1 kg.
—Uranium enriched above natural, but less than 10 percent235 U 10 kg or more.
3. Uranium-233 (233 U) Unirradiated 2 2 kg or more Less than 2 kg but more than 500 g 500 g or less but more than 15 g.
4. Irradiated Fuel (The categorization of irradiated fuel in the table is based on international transport considerations. The State may assign a different category for domestic use, storage and transport taking all relevant factors into account) Depleted or natural uranium, thorium or low enriched fuel (less than 10 percent fissile content) 4 5
1 All plutonium except that with isotopic concentration exceeding 80 percent in plutonium-238.
2 Material not irradiated in a reactor or material irradiated in a reactor but with a radiation level equal to or less than 1 Gy/h (100 rad/h) at 1 m unshielded.
3 Quantities not falling in Category III and natural uranium, depleted uranium and thorium should be protected at least in accordance with prudent management practice.
4 Although this level of protection is recommended, it would be open to States, upon evaluation of the specific circumstances, to assign a different category of physical protection.
5 Other fuel which by virtue of its original fissile material content is classified as Category I or II before irradiation may be reduced one category level while the radiation level from the fuel exceeds 1 Gy/h (100 rad/h) at one meter unshielded.
19. In appendix N to part 110, add a new paragraph c. to read as follows:
20. Revise appendix O to part 110 to read as follows:
(b) This equipment or systems of equipment may include, for example:Start Printed Page 39300
[FR Doc. 2014-15828 Filed 7-9-14; 8:45 am]