39289

Rules and Regulations Federal Register Vol. 79, No. 132

Thursday, July 10, 2014

This section of the FEDERAL REGISTER for Docket ID NRC–2014–0007. Address are charged with implementing the contains regulatory documents having general questions about NRC dockets to Carol changes adopted to the list as soon as applicability and legal effect, most of which Gallagher; telephone: 301–287–3422; possible after approval. are keyed to and codified in the Code of email: [email protected]. For This final rule conforms the NRC’s Federal Regulations, which is published under technical questions, contact the 50 titles pursuant to 44 U.S.C. 1510. export and import regulations in 10 CFR individual listed in the FOR FURTHER part 110, ‘‘Export and Import of Nuclear INFORMATION CONTACT section of this The Code of Federal Regulations is sold by Equipment and Material,’’ and the Superintendent of Documents. Prices of final rule. new books are listed in the first FEDERAL • NRC’s Agencywide Documents appendices A, B, C, D, E, F, G, H, I, J, REGISTER issue of each week. Access and Management System K, N, and O, which contain illustrative (ADAMS): You may obtain publicly lists of items under the NRC’s export available documents online in the licensing authority, to current nuclear NUCLEAR REGULATORY ADAMS Public Documents collection at nonproliferation policies of the COMMISSION http://www.nrc.gov/reading-rm/ Executive Branch. These revisions are adams.html. To begin the search, select necessary to implement changes made 10 CFR Part 110 ‘‘ADAMS Public Documents’’ and then to the NSG Guidelines, ‘‘Guidelines for RIN 3150–AJ33 select ‘‘Begin Web-based ADAMS Nuclear Transfers (INFCIRC/254/ Search.’’ For problems with ADAMS, Revision 12/Part 1), June 2013,’’ as [NRC–2014–0007] please contact the NRC’s Public adopted by the governments Export Controls and Physical Security Document Room (PDR) reference staff at participating in the NSG at the June Standards 1–800–397–4209, 301–415–4737, or by 2012 and 2013 Plenary Meetings. In email to [email protected]. The addition, this rule amends § 110.30, AGENCY: Nuclear Regulatory ADAMS accession number for each ‘‘Members of the Nuclear Suppliers Commission. document referenced in this document Group,’’ to add Mexico and Serbia as ACTION: Final rule. (if that document is available in member countries of the NSG that are ADAMS) is provided the first time that eligible to receive radioactive materials SUMMARY: The U.S. Nuclear Regulatory a document is referenced. under certain general licenses for Commission (NRC) is amending its • NRC’s PDR: You may examine and export. The NSG Guidelines can be regulations pertaining to the export and purchase copies of public documents at import of nuclear materials and found at: the NRC’s PDR, Room O1–F21, One www.nuclearsuppliersgroup.org. equipment. This rulemaking is White Flint North, 11555 Rockville necessary to conform the export controls Pike, Rockville, Maryland 20852. In January 2011, the IAEA published the document titled, ‘‘Nuclear Security of the United States to the international FOR FURTHER INFORMATION CONTACT: export control guidelines of the Nuclear Brooke G. Smith, Office of International Recommendations on Physical Suppliers Group (NSG), of which the Programs, U.S. Nuclear Regulatory Protection of Nuclear Material and United States is a member, and to Commission, Washington, DC 20555– Nuclear Facilities (INFCIRC/225/ incorporate by reference the current 0001, telephone: 301–415–2347, email: Revision 5).’’ This rule also amends version of the International Atomic [email protected]. § 110.44 and appendix M to 10 CFR part Energy Agency’s (IAEA) document, SUPPLEMENTARY INFORMATION: 110 to incorporate by reference the ‘‘Nuclear Security Recommendations on update and recommendations contained Physical Protection of Nuclear Material Table of Contents in Revision 5 of this IAEA document. and Nuclear Facilities (INFCIRC/225/ I. Background The NRC staff has determined that Revision 5), January 2011.’’ Also, this II. Section-by-Section Analysis these changes are consistent with final rule makes certain editorial III. Regulatory Flexibility Certification revisions, and corrects typographical current U.S. policy, and will pose no IV. Regulatory Analysis unreasonable risk to the public health errors. V. Backfitting and Issue Finality VI. Plain Writing and safety or to the common defense DATES: The final rule is effective August and security of the United States. 11, 2014, except that the changes to VII. Environmental Impact Statement VIII. Paperwork Reduction Act § 110.44(a) and (b)(1) and appendix M to Because this rule involves a foreign IX. Congressional Review Act affairs function of the United States, the 10 CFR part 110 are effective December X. Voluntary Consensus Standards 31, 2014. The incorporation by reference notice and comment provisions of the of the material in this document is I. Background Administrative Procedure Act do not approved as of December 31, 2014. The NSG is a group of like-minded apply (5 U.S.C. 553(a)(1)). In addition, ADDRESSES: Please refer to Docket ID States that seeks to contribute to the solicitation of public comments would NRC–2014–0007 when contacting the nonproliferation of nuclear weapons delay the U.S. conformance with its NRC about the availability of through the implementation of international obligations, and would be information for this final rule. You can guidelines for nuclear exports and contrary to the public interest (5 U.S.C. access publicly-available information nuclear-related exports. As a 553(b)). The final rule is effective related to this final rule by any of the participating government in the NSG, August 11, 2014, except that the following methods: the United States has committed to changes to § 110.44(a) and (b)(1) and • Federal Rulemaking Web site: Go to controlling for export items on the NSG appendix M to 10 CFR part 110 are http://www.regulations.gov and search control lists. Participating governments effective December 31, 2014.

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II. Section by Section Analysis publication, INFCIRC/225/Revision 5. approved by the Office of Management The changes to appendix M of 10 CFR and Budget (OMB) under approval Section 110.2 Definitions part 110 are effective December 31, number 3150–0036. Paragraph (2)(ii) of the definition of 2014. ‘‘Utilization facility’’ is amended to Public Protection Notification make conforming changes consistent III. Regulatory Flexibility Certification The NRC may not conduct or sponsor, with the changes to appendix A to 10 As required by the Regulatory and a person is not required to respond CFR part 110. Flexibility Act of 1980 (5 U.S.C. 605(b)), to, a request for information or an the Commission certifies that this final information collection requirement Section 110.26 General License for the rule will not have a significant unless the requesting document Export of Nuclear Reactor Components economic impact on a substantial displays a currently valid OMB control This rule amends § 110.26 to make number of small entities. This rule number. conforming changes to paragraph (a) affects only companies exporting IX. Congressional Review Act consistent with the changes to appendix nuclear equipment and material to and A to 10 CFR part 110. from the United States and they do not Under the Congressional Review Act fall within the scope of the definition of of 1996, the NRC has determined that Section 110.30 Members of the this action is not a major rule and has Nuclear Suppliers Group ‘‘small entities’’ set forth in the Regulatory Flexibility Act (5 U.S.C. verified this determination with the This rule amends § 110.30 to update 601(3)), or the Size Standards Office of Information and Regulatory the list of NSG members by adding established by the NRC (10 CFR 2.810). Affairs of OMB. Mexico and Serbia. IV. Regulatory Analysis X. Voluntary Consensus Standards Section 110.42 Export Licensing The National Technology Transfer Criteria This rulemaking is necessary to reflect the nuclear nonproliferation policy of and Advancement Act of 1995 (Pub. L. This rule amends § 110.42 to make the Executive Branch including U.S. 104–113) requires that Federal Agencies conforming changes to Footnote 1 Government commitments to use technical standards that are consistent with the changes to appendix controlling export items on the NSG developed or adopted by voluntary A to 10 CFR part 110. control lists and the IAEA publication, consensus standards bodies unless INFCIRC/225/Revision 5. This final rule using such a standard is inconsistent Section 110.44 Physical Security with applicable law or otherwise Standards is expected to have no changes in the information collection burden or cost to impractical. This final rule does not Paragraphs (a) and (b)(1) of § 110.44 the public. constitute the establishment of a are amended to incorporate by reference standard for which the use of a the most recent revision to INFCIRC/ V. Backfit Analysis and Issue Finality voluntary consensus standard would be 225/Revision 5, ‘‘The Physical The NRC has determined that a applicable. Protection of Nuclear Material and backfit analysis is not required for this List of Subjects in 10 CFR Part 110 Nuclear Facilities.’’ The effective date rule because these amendments do not for these changes is delayed until include any provisions that would Administrative practice and December 31, 2014, to provide adequate impose backfits as defined in 10 CFR procedure, Classified information, time for countries to meet the Chapter I. Criminal penalties, Export, Import, recommendations in Revision 5. ‘‘The Incorporation by reference, Physical Protection of Nuclear Material VI. Plain Writing Intergovernmental relations, Nuclear and Nuclear Facilities,’’ INFCIRC/225/ The Plain Writing Act of 2010 (Pub. materials, Nuclear power plants and Revision 4 (corrected), July 1999, will L. 111–274) requires Federal agencies to reactors, Reporting and recordkeeping continue to be used as the physical write documents in a clear, concise, and requirements, Scientific equipment. protection standard in recipient well-organized manner. The NRC has For the reasons set out in the countries until the effective date for written this document to be consistent preamble and under the authority of the INFCIRC/225/Revision 5, as with the Plain Writing Act as well as the Atomic Energy Act of 1954, as amended, incorporated by reference in 10 CFR Presidential Memorandum, ‘‘Plain the Energy Reorganization Act of 1974, part 110. Language in Government Writing,’’ as amended, and 5 U.S.C. 552 and 553, published June 10, 1998 (63 FR 31883). the NRC is adopting the following Appendices A, B, C, D, E, F, G, H, I, J, amendments to 10 CFR part 110. K, N and O to Part 110 VII. Environmental Impact: Categorical These appendices are amended to Exclusion PART 110—EXPORT AND IMPORT OF reflect the updated guidelines of the The NRC has determined that this NUCLEAR EQUIPMENT AND NSG consistent with the IAEA final rule is the type of action described MATERIAL document, ‘‘Guidelines for Nuclear in categorical exclusion 10 CFR ■ Transfers, (INFCIRC/254/Revision 12/ 51.22(c)(1). Therefore, neither an 1. The authority citation for part 110 Part 1).’’ The appendices in 10 CFR part environmental impact statement nor an continues to read as follows: 110 are illustrative only and are not environmental assessment has been Authority: Atomic Energy Act secs. 51, 53, meant to be inclusive lists of facilities prepared for the rule. 54, 57, 63, 64, 65, 81, 82, 103, 104, 109, 111, and equipment under the NRC’s export 126, 127, 128, 129, 161, 181, 182, 183, 187, VIII. Paperwork Reduction Act licensing jurisdiction. 189, 223, 234 (42 U.S.C. 2071, 2073, 2074, Statement 2077, 2092–2095, 2111, 2112, 2133, 2134, 2139, 2139a, 2141, 2154–2158, 2201, 2231– Appendix M to Part 110— This final rule does not contain new Categorization of Nuclear Material 2233, 2237, 2239, 2273, 2282); Energy or amended information collection Reorganization Act sec. 201 (42 U.S.C. 5841; Appendix M is amended to update requirements subject to the Paperwork Solar, Wind, Waste, and Geothermal Power the Categorization of Nuclear Material Reduction Act of 1995 (44 U.S.C. 3501 Act of 1990 sec. 5 (42 U.S.C.2243); table to be consistent with IAEA et seq.). Existing requirements were Government Paperwork Elimination Act sec.

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1704, 112 Stat. 2750 (44 U.S.C. 3504 note); ■ 6. In § 110.44, revise paragraphs (a) (2) On-line (e.g., CANDU) reactor fuel Energy Policy Act of 2005, 119 Stat. 594. and (b)(1) to read as follows: charging and discharging machines, i.e., Sections 110.1(b)(2) and 110.1(b)(3) also manipulative equipment especially designed issued under 22 U.S.C. 2403. Section 110.11 § 110.44 Physical security standards. for inserting or removing fuel in an operating also issued under Atomic Energy Act secs. (a) Physical security measures in nuclear reactor. 54(c), 57(d), 122 (42 U.S.C. 2074, 2152). recipient countries must provide (3) Complete reactor control rod system, Section 110.50(b)(3) also issued under protection at least comparable to the i.e., rods especially designed or prepared for the control of the reaction rate in a nuclear Atomic Energy Act sec. 123 (42 U.S.C. 2153). recommendations in the current version Section 110.51 also issued under Atomic reactor, including the neutron absorbing part of IAEA publication, ‘‘Nuclear Security and the support or suspension structures Energy Act sec. 184 (42 U.S.C. 2234). Section Recommendations on Physical 110.52 also issued under Atomic Energy Act therefor. sec. 186, (42 U.S.C. 2236). Sections 110.80– Protection of Nuclear Material and (4) Reactor primary coolant pumps or 110.113 also issued under 5 U.S.C. 552, 554. Nuclear Facilities’’ (INFCIRC/225/ circulators, i.e., pumps or circulators Sections 110.130–110.135 also issued under Revision 5), January 2011, which is especially designed or prepared for 5 U.S.C. 553. Sections 110.2 and 110.42(a)(9) incorporated by reference in this part. circulating the primary coolant in a nuclear also issued under Intelligence Authorization This incorporation by reference was reactor. Act sec. 903 (42 U.S.C. 2151 et seq.). approved by the Director of the Office (5) Reactor pressure tubes, i.e., tubes of the Federal Register in accordance especially designed or prepared to contain ■ 2. In § 110.2, revise paragraph (2)(ii) of both fuel elements and the primary coolant with 5 U.S.C. 552(a) and 1 CFR part 51. the definition of ‘‘Utilization facility’’ to in a nuclear reactor. Notice of any changes made to the read as follows: (6) Zirconium tubes, i.e., zirconium metal material incorporated by reference will and alloys in the form of tubes or assemblies § 110.2 Definitions. be published in the Federal Register. of tubes especially designed or prepared for * * * * * Copies of INFCIRC/225/Revision 5 may use as fuel cladding in a nuclear reactor. Utilization facility means: be obtained from the Marketing and (7) Reactor internals, e.g., core support Sales Unit, Publishing Section, IAEA, structures, control and rod guide tubes, fuel * * * * * Vienna International Centre, P.O. Box channels, calandria tubes, thermal shields, (2) * * * 100, 1400 Vienna Austria; Fax: 43 1 baffles, core grid plates, and diffuser plates (ii) Reactor primary coolant pump or 2600 29302; telephone: 43 1 2600 especially designed or prepared for use in a nuclear reactor. circulator; 22417; email: sales.publications * * * * * (8) Reactor control rod drive mechanisms, @iaea.org; Web site: http:// including detection and measuring ■ 3. In § 110.26, revise the introductory www.iaea.org/books. You may inspect a equipment to determine neutron flux levels text of paragraph (a) to read as follows: copy at the NRC Library, 11545 within the core of a nuclear reactor. Rockville Pike, Rockville, Maryland (9) Heat exchangers, e.g., steam generators § 110.26 General license for the export of 20852–2738, telephone: 301–415–4737 especially designed or prepared for the nuclear reactor components. or 1–800–397–4209, between 8:30 a.m. primary, or intermediate, coolant circuit of a (a) A general license is issued to any and 4:15 p.m.; or at the National nuclear reactor or heat exchangers especially person to export to a destination listed Archives and Records Administration designed or prepared for use in the primary in paragraph (b) of this section any (NARA). For information on the coolant circuit of a nuclear reactor. (10) External thermal shields especially nuclear reactor component of U.S. availability of this material at NARA, origin described in paragraphs (5) designed or prepared for use in a nuclear call 202–741–6030, or go to: http:// reactor for reduction of heat loss and also for through (11) of appendix A to this part www.archives.gov/federal-register/cfr/ containment vessel protection. if— ibr-locations.html. (11) Any other components especially * * * * * (b) * * * designed or prepared for use in a nuclear (1) Receipt by the appropriate U.S. reactor or in any of the components § 110.30 [Amended] Executive Branch Agency of written described in this appendix. ■ 4. Amend § 110.30 by adding the assurances from the relevant recipient ■ 8. Revise appendix B to part 110 to words ‘‘Mexico’’ and ‘‘Serbia’’ in country government that physical read as follows: alphabetical order. security measures providing protection ■ 5. In § 110.42, revise footnote 1 to read at least comparable to the Appendix B to Part 110—Illustrative as follows: recommendations set forth in INFCIRC/ List of Gas Centrifuge Enrichment Plant 225/Revision 5. Components Under NRC’s Export § 110.42 Export licensing criteria. * * * * * Licensing Authority * * * * * ■ 7. Revise appendix A to part 110 to 1 Export of nuclear reactors, reactor read as follows: 1. Assemblies and components especially pressure vessels, reactor primary designed or prepared for use in gas coolant pumps and circulators, ‘‘on- Appendix A to Part 110—Illustrative centrifuges. Note: The gas centrifuge normally consists line’’ reactor fuel charging and List of Nuclear Reactor Equipment Under NRC Export Licensing Authority of a thin-walled cylinder(s) of between 75 discharging machines, and complete mm and 650 mm diameter contained in a reactor control rod systems, as specified Note: A nuclear reactor basically includes vacuum environment and spun at high in paragraphs (1) through (4) of the items within or attached directly to the peripheral speed (of the order of 300 m/per appendix A to this part, are subject to reactor vessel, the equipment which controls second and more) with the central axis the export licensing criteria in the level of power in the core, and the vertical. In order to achieve high speed, the § 110.42(a). Exports of nuclear reactor components which normally contain or come materials of construction for the rotating components, as specified in paragraphs in direct contact with or control the primary rotor assembly, and hence its individual (5) through (11) of appendix A to this coolant of the reactor core. components, have to be manufactured to very close tolerances in order to minimize the part, when exported separately from the (1) Reactor pressure vessels, i.e., metal vessels, as complete units or major shop- unbalance. In contrast to other centrifuges, items described in paragraphs (1) fabricated parts, especially designed or the gas centrifuge for uranium enrichment is through (4) of appendix A to this part, prepared to contain the core of a nuclear characterized by having within the rotor are subject to the export licensing reactor and capable of withstanding the chamber a rotating disc-shaped baffle(s) and criteria in § 110.42(b). operating pressure of the primary coolant. a stationary tube arrangement for feeding and

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extracting uranium hexafluoride (UF6) gas (c) Filamentary materials suitable for use in frequency of 600 Hz or greater and a power and featuring at least three separate channels composite structures and having a specific of 40 volts amps or greater. The stators may of which two are connected to scoops modulus of 3.18 × 106 m or greater and a consist of multi-phase windings on a extending from the rotor axis towards the specific ultimate tensile strength of 7.62 × laminated low loss iron core comprised of periphery of the rotor chamber. Also 104 m or greater. thin layers typically 2.0 mm thick or less. contained within the vacuum environment (‘‘Specific Modulus’’ is the Young’s modulus (e) Centrifuge housing/recipients: are a number of critical items which do not in N/m2 divided by the specific weight in Components especially designed or prepared rotate and which, although they are N/m3 when measured at a temperature of 23 to contain the rotor tube assembly of a gas especially designed, are not difficult to ± 20 °C and a relative humidity of 50 ± 5 centrifuge. The housing consists of a rigid fabricate nor are they fabricated out of unique percent. ‘‘Specific tensile strength’’ is the cylinder of wall thickness up to 30 mm with materials. A centrifuge facility, however, ultimate tensile strength in N/m2 divided by precision machined ends to locate the requires a large number of these components the specific weight in N/m3 when measured bearings and with one or more flanges for so that quantities can provide an important at a temperature of 23 ± 20 °C and a relative mounting. The machined ends are parallel to indication of end use. humidity of 50 ± 5 percent.) each other and perpendicular to the 1.1 Rotating Components cylinder’s longitudinal axis to within 0.05 1.2 Static Components degrees or less. The housing may also be a (a) Complete Rotor Assemblies: Thin- (a) Magnetic Suspension Bearings: 1. honeycomb type structure to accommodate walled cylinders, or a number of Especially designed or prepared bearing several rotor tubes. interconnected thin-walled cylinders, assemblies consisting of an annular magnet (f) Scoops: Especially designed or prepared manufactured from one of the high strength- suspended within a housing containing a tubes for the extraction of UF gas from to-density ratio materials described in the 6 damping medium. The housing will be within the rotor tube by a Pitot tube action footnote to this section. If interconnected, the cylinders are joined manufactured from a UF6 resistant material (that is, with an aperture facing into the together by flexible bellows or rings as (see footnote to § 2 of this appendix). The circumferential gas flow within the rotor described in § 1.1(c) of this appendix. The magnet couples with a pole piece or a second tube, for example by bending the end of a rotor is fitted with an internal baffle(s) and magnet fitted to the top cap described in radially disposed tube) and capable of being end caps, as described in § 1.1(d) and (e) of § 1.1(e) of this appendix. The magnet may be fixed to the central gas extraction system. this appendix, if in final form. However, the ring-shaped with a relation between outer 2. Especially designed or prepared complete assembly may be delivered only and inner diameter smaller or equal to 1.6:1. auxiliary systems, equipment, and partly assembled. The magnet may be in a form having an components for gas centrifuge enrichment (b) Rotor Tubes: Especially designed or initial permeability of 0.15 Henry/meter or plants. prepared thin-walled cylinders with more, or a remanence of 98.5 percent or Note: The auxiliary systems, equipment, thickness of 12 mm or less, a diameter of more, or an energy product of greater than and components for a gas centrifuge between 75 mm and 650 mm, and 80,000 joules/m3. In addition to the usual enrichment plant are the systems of the plant manufactured from one of the high strength- material properties, it is a prerequisite that needed to feed UF6 to the centrifuges to link to-density ratio materials described in the the deviation of the magnetic axes from the the individual centrifuges to each other to footnote to this section. geometrical axes is limited to very small form cascades (or stages) to allow for (c) Rings or Bellows: Components tolerances (lower than 0.1 mm) or that progressively higher enrichments and to especially designed or prepared to give homogeneity of the material of the magnet is extract the product and tails of UF6 from the localized support to the rotor tube or to join specially called for. centrifuges, together with the equipment together a number of rotor tubes. The bellows 2. Active magnetic bearings especially required to drive the centrifuges or to control in a short cylinder of wall thickness 3 mm designed or prepared for use with gas the plant. or less, a diameter of between 75 mm and 650 centrifuges. These bearings usually have the Normally UF6 is evaporated from the solid mm, having a convolute, and manufactured following characteristics: using heated autoclaves and is distributed in from one of the high strength-to-density ratio (i) Designed to keep centred a rotor gaseous form to the centrifuges by way of materials described in the footnote to this spinning at 600 Hz or more; and cascade header pipework. The ‘‘product’’ and section. (ii) Associated to a reliable electrical power ‘‘tails’’ of UF6 gaseous streams flowing from (d) Baffles: Disc shaped components of supply and/or to an uninterruptible power the centrifuges are also passed by way of between 75 mm and 650 mm diameter supply (UPS) unit in order to function for cascade header pipework to cold traps especially designed or prepared to be more than 1 hour. (operating at about 203 K (¥70 °C)) where mounted inside the centrifuge rotor tube, in (b) Bearings/Dampers: Especially designed they are condensed prior to onward transfer order to isolate the take-off chamber from the or prepared bearings comprising a pivot/cup into suitable containers for transportation or main separation chamber and, in some cases, assembly mounted on a damper. The pivot is storage. Because an enrichment plant to assist the UF6 gas circulation within the normally a hardened steel shaft polished into consists of many thousands of centrifuges main separation chamber of the rotor tube, a hemisphere at one end with a means of arranged in cascades, there are many and manufactured from one of the high attachment to the bottom cap described in kilometers of cascade header pipework strength-to-density ratio materials described § 1.1(e) of this appendix at the other. The incorporating thousands of welds with a in the footnote to this section. shaft may, however, have a hydrodynamic substantial amount of repetition of layout. (e) Top Caps/Bottom Caps: Disc shaped bearing attached. The cup is pellet-shaped The equipment, component and piping components of between 75 mm and 650 mm with hemispherical indentation in one systems are fabricated to very high vacuum diameter especially designed or prepared to surface. These components are often and cleanliness standards. fit to the ends of the rotor tube, and so supplied separately to the damper. Some of the items listed below either come contain the UF within the rotor tube, and in 6 (c) Molecular Pumps: Especially designed into direct contact with the UF process gas some cases to support, retain or contain as an 6 or prepared cylinders having internally or directly control the centrifuges and the integrated part, an element of the upper machined or extruded helical grooves and passage of the gas from centrifuge to bearing (top cap) or to carry the rotating elements of the motor and lower bearing internally machined bores. Typical centrifuge and cascade to cascade. Materials (bottom cap), and manufactured from one of dimensions are as follows: 75 mm to 650 mm resistant to corrosion by UF6 include copper, the high strength-to-density ratio materials internal diameter, 10 mm or more wall copper alloys, stainless steel, aluminum, described in the footnote to this section. thickness, with a length equal to or greater aluminum oxide, aluminum alloys, nickel or than the diameter. The grooves are typically alloys containing 60 percent or more nickel, Footnote rectangular in cross-section and 2 mm or and fluorinated hydrocarbon polymers. The materials used for centrifuge rotating more in depth. (a) Feed Systems/Product and Tails components include the following: (d) Motor Stators: Especially designed or Withdrawal Systems: Especially designed or (a) Maraging steel capable of an ultimate prepared ring shaped stators for high speed prepared process systems or equipment for tensile strength of 1.95 GPa or more. multi-phase alternating current (AC) enrichment plants made of or protected by (b) Aluminum alloys capable of an ultimate hysteresis (or reluctance) motors for materials resistant to corrosion by UF6 tensile strength of 0.46 GPa or more. synchronous operation within a vacuum at a including:

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1. Feed autoclaves, ovens, or systems used Appendix C to Part 110—Illustrative 1.1 Gaseous Diffusion Barriers and Barrier for passing UF6 to the enrichment process. List of Gaseous Diffusion Enrichment Materials 2. Desublimers, cold traps, or pumps used Plant Assemblies and Components (a) Especially designed or prepared thin, to remove UF6 from the enrichment process Under NRC Export Licensing Authority porous filters, with a pore size of 10–100 nm, for subsequent transfer upon heating. a thickness of 5 mm or less, and for tubular 3. Solidification or liquefaction stations Note: In the gaseous diffusion method of forms, a diameter of 25 mm or less, made of uranium isotope separation, the main used to remove UF6 from the enrichment metallic, polymer or ceramic materials technological assembly is a special porous process by compressing and converting UF6 resistant to corrosion by UF (See Note in § 2 gaseous diffusion barrier, heat exchanger for 6 to a liquid or solid form. of this appendix). cooling the gas (which is heated by the 4. ‘‘Product’’ and ‘‘tails’’ stations used for (b) Especially prepared compounds or process of compression), seal valves and transferring UF6 into containers. control valves, and pipelines. Inasmuch as powders for the manufacture of such filters. (b) Machine Header Piping Systems: Such compounds and powders include Especially designed or prepared piping gaseous diffusion technology uses uranium hexafluoride (UF ), all equipment, pipeline nickel or alloys containing 60 percent or systems and header systems for handling UF 6 6 and instrumentation surfaces (that come in more nickel, aluminum oxide, or UF6- within the centrifuge cascades. contact with the gas) must be made of resistant fully fluorinated hydrocarbon This piping network is normally of the materials that remain stable in contact with polymers having a purity of 99.9 percent by ‘‘triple’’ header system with each centrifuge UF6. A gaseous diffusion facility requires a weight or more, a particle size less than 10 connected to each of the headers. There is number of these assemblies, so that mm, and a high degree of particle size therefore a substantial amount of repetition quantities can provide an important uniformity, which are especially prepared for in its form. It is wholly made of or protected indication of end use. the manufacture of gaseous diffusion barriers. by UF6 resistant materials (see Note to this The auxiliary systems, equipment, and 1.2 Diffuser Housings section) and is fabricated to very high components for gaseous diffusion enrichment Especially designed or prepared vacuum and cleanliness standards. plants are the systems of plant needed to feed hermetically sealed vessels for containing the (c) Special shut-off and control valves: UF6 to the gaseous diffusion assembly to link 1. Shut-off valves especially designed or the individual assemblies to each other to gaseous diffusion barrier, made of or prepared to act on the feed, ‘‘product’’ or form cascades (or stages) to allow for protected by UF6-resistant materials (See Note in § 2 of this appendix). ‘‘tails’’ UF6 gaseous streams of an individual progressively higher enrichments and to gas centrifuge. extract the ‘‘product’’ and ‘‘tails’’ UF6 from 1.3 Compressors and Gas Blowers 2. Bellows-sealed valves, manual or the diffusion cascades. Because of the high Especially designed or prepared automated, shut-off or control, made of or inertial properties of diffusion cascades, any compressors or gas blowers with a suction protected by materials resistant to corrosion interruption in their operation, and volume capacity of 1 m3 per minute or more especially their shut-down, leads to serious by UF6, with an inside diameter of 10 to 160 of UF6, and with a discharge pressure of up mm, especially designed or prepared for use consequences. Therefore, a strict and to 500 kPa, designed for long-term operation constant maintenance of vacuum in all in main or auxiliary systems of gas centrifuge in the UF environment, as well as separate technological systems, automatic protection 6 enrichment plants. assemblies of such compressors and gas for accidents, and precise automated Typical especially designed or prepared blowers. These compressors and gas blowers regulation of the gas flow is of importance in valves include bellow-sealed valves, fast have a pressure ratio of 10:1 or less and are a gaseous diffusion plant. All this leads to a acting closure-types, fast acting valves, and need to equip the plant with a large number made of, or protected by, materials resistant others. of special measuring, regulating, and to UF6 (See Note in § 2 of this appendix). (d) UF6 Mass Spectrometers/Ion Sources: controlling systems. 1.4 Rotary Shaft Seals Especially designed or prepared mass Normally UF6 is evaporated from cylinders Especially designed or prepared vacuum spectrometers capable of taking on-line placed within autoclaves and is distributed seals, with seal feed and seal exhaust samples from UF gas streams and having all 6 in gaseous form to the entry point by way of connections, for sealing the shaft connecting of the following: cascade header pipework. The ‘‘product’’ and the compressor or the gas blower rotor with 1. Capable of measuring ions of 320 atomic ‘‘tails’’ UF6 gaseous streams flowing from exit the driver motor so as to ensure a reliable mass units or greater and having a resolution points are passed by way of cascade header seal against in-leaking of air into the inner of better than 1 part in 320. pipework to either cold traps or to chamber of the compressor or gas blower 2. Ion sources constructed of or protected compression stations where the UF6 gas is which is filled with UF6. Such seals are by nickel, nickel-copper alloys with a nickel liquified prior to onward transfer into normally designed for a buffer gas in-leakage content of 60 percent or more by weight, or suitable containers for transportation or rate of less than 1000 cm3 per minute. nickel-chrome alloys. storage. Because a gaseous diffusion 3. Electron bombardment ionization enrichment plant consists of a large number 1.5 Heat Exchangers for Cooling UF6 sources. of gaseous diffusion assemblies arranged in Especially designed or prepared heat 4. Having a collector system suitable for cascades, there are many kilometers of exchangers made of or protected by UF6 isotope analysis. cascade header pipework, incorporating resistant materials (see Note to § 2 of this (e) Frequency Changers: Frequency thousands of welds with substantial amounts appendix) and intended for a leakage changers (also known as converters or of repetition of layout. The equipment, pressure change rate of less than 10 Pa per inverters) especially designed or prepared to components, and piping systems are hour under a pressure difference of 100 kPa. supply motor stators as defined under fabricated to very high vacuum and 2. Auxiliary systems, equipment, and § 1.2(d) of this appendix, or parts, cleanliness standards. components especially designed or prepared components, and subassemblies of such The items listed below either come into for use in gaseous diffusion enrichment. frequency changers having all of the direct contact with the UF6 process gas or Note: The items listed below either come directly control the flow within the cascade. following characteristics: into direct contact with the UF6 process gas All surfaces which come into contact with 1. A multiphase output of 600 Hz or or directly control the flow within the the process gas are wholly made of, or lined greater; and cascade. Materials resistant to corrosion by with, UF6-resistant materials. For the UF6 include copper, copper alloys, stainless 2. High stability (with frequency control purposes of this appendix, the materials better than 0.2 percent). steel, aluminum, aluminum oxide, aluminum resistant to corrosion by UF6 include copper, alloys, nickel or alloys containing 60 percent (f) Any other components especially copper alloys, stainless steel, aluminum, designed or prepared for use in a gas or more nickel, and fluorinated hydrocarbon aluminum oxide, aluminum alloys, nickel or polymers. centrifuge enrichment plant or in any of the alloys containing 60 percent or more nickel components described in this appendix. and fluorinated hydrocarbon polymers. 2.1 Feed Systems/Product and Tails 1. Assemblies and components especially Withdrawal Systems ■ 9. Revise appendix C to part 110 to designed or prepared for use in gaseous Especially designed or prepared process read as follows: diffusion enrichment. systems or equipment for enrichment plants

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made of, or protected by, materials resistant over a curved-wall geometry. Two processes (7) Feed systems/product and tails to corrosion by UF6, including: of this type have been successfully withdrawal systems. (1) Feed autoclaves, ovens, or systems used developed: The separation nozzle process Especially designed or prepared process for passing UF6 to the enrichment process; and the vortex tube process. For both systems or equipment for enrichment plants (2) Desublimers, cold traps, or pumps used processes, the main components of a made of, or protected by, materials resistant to remove UF6 from the enrichment process separation stage included cylindrical vessels to corrosion by UF6, including: for subsequent transfer upon heating; housing the special separation elements (i) Feed autoclaves, ovens, or systems used (3) Solidification or liquefaction stations (nozzles or vortex tubes), gas compressors, for passing UF6 to the enrichment process; used to remove UF6 from the enrichment and heat exchangers to remove the heat of (ii) Desublimers (or cold traps) used to process by compressing and converting UF6 compression. An aerodynamic plant requires remove UF6 from the enrichment process for to a liquid or solid form; a number of these stages, so that quantities subsequent transfer upon heating; (4) ‘‘Product’’ or ‘‘tails’’ stations used for can provide an important indication of end (iii) Solidification or liquefaction stations transferring UF6 into containers. use. Because aerodynamic processes use UF6, used to remove UF6 from the enrichment all equipment, pipeline and instrumentation 2.2 Header Piping Systems process by compressing and converting UF6 surfaces (that come in contact with the gas) to a liquid or solid form; and Especially designed or prepared piping must be made of, or protected by, materials (iv) ‘‘Product’’ or ‘‘tails’’ stations used for systems and header systems for handling UF6 that remain stable in contact with UF6. All transferring UF6 into containers. within the gaseous diffusion cascades. This surfaces which come into contact with the (8) Header piping systems. piping network is normally of the ‘‘double’’ process gas are made of, or protected by, UF6- Especially designed or prepared header header system with each cell connected to resistant materials; including copper, copper piping systems, made of or protected by each of the headers. alloys, stainless steel, aluminum, aluminum materials resistant to corrosion by UF6, for 2.3 Vacuum Systems oxide, aluminum alloys, nickel or alloys handling UF6 within the aerodynamic containing 60 percent or more nickel by cascades. The piping network is normally of (a) Especially designed or prepared weight, and fluorinated hydrocarbon vacuum manifolds, vacuum headers and the ‘‘double’’ header design with each stage polymers. or group of stages connected to each of the vacuum pumps having a suction capacity of The following items either come into direct 5 m3 per minute or more. headers. contact with the UF6 process gas or directly (b) Vacuum pumps especially designed for (9) Vacuum systems and pumps. control the flow within the cascade: (i) Especially designed or prepared vacuum service in UF6-bearing atmospheres made of, (1) Separation nozzles and assemblies. or protected by, materials resistant to systems consisting of vacuum manifolds, Especially designed or prepared separation vacuum headers and vacuum pumps, and corrosion by UF6 (See Note to this section). nozzles and assemblies thereof. The designed for service in UF -bearing These pumps may be either rotary or positive separation nozzles consist of slit-shaped, 6 atmospheres. displacement, may have fluorocarbon seals, curved channels having a radius of curvature (ii) Especially designed or prepared and may have special working fluids present. less than 1 mm, resistant to corrosion by UF 6 vacuum pumps for service in UF -bearing and having a knife-edge within the nozzle 6 2.4 Special Shut-Off and Control Valves atmospheres and made of, or protected by, that separates the gas flowing through the Especially designed or prepared bellows- nozzle into two fractions. materials resistant to corrosion by UF6. These sealed valves, manual or automated, shut-off (2) Vortex tubes and assemblies. pumps may use fluorocarbon seals and or control valves, made of, or protected by, Especially designed or prepared vortex special working fluids. materials resistant to corrosion by UF6, for tubes and assemblies thereof. The vortex (10) Special shut-off and control valves. installation in main and auxiliary systems of tubes are cylindrical or tapered, made of, or Especially designed or prepared bellows- gaseous diffusion enrichment plants. protected by, materials resistant to corrosion sealed valves, manual or automated, shut-off or control valves made of, or protected by, 2.5 UF6 Mass Spectrometers/Ion Sources by UF6, and with one or more tangential inlets. The tubes may be equipped with materials resistant to corrosion by UF6 with Especially designed or prepared mass a diameter of 40 mm or greater for spectrometers capable of taking on-line nozzle-type appendages at either or both ends. installation in main and auxiliary systems of samples from UF6 gas streams and having all aerodynamic enrichment plants. of the following: The feed gas enters the vortex tube (11) UF6 mass spectrometers/ion sources. (a) Capable of measuring ions of 320 tangentially at one end or through swirl vanes or at numerous tangential positions Especially designed or prepared mass atomic mass units or greater and having a spectrometers capable of taking on-line resolution of better than 1 part in 320; along the periphery of the tube. (3) Compressors and gas blowers. samples from UF6 gas streams and having all (b) ion sources constructed of or protected of the following: by nickel, nickel-copper alloys with a nickel Especially designed or prepared compressors or gas blowers made of, or (i) Capable of measuring ions of 320 atomic content of 60 percent or more by weight, or mass units or greater and having a resolution nickel-chrome alloys; protected by, materials resistant to corrosion by the UF6/carrier gas (hydrogen or helium) of better than 1 part in 320; (c) electron bombardment ionization (ii) Ion sources constructed of or protected sources; and mixture. (4) Rotary shaft seals. by nickel, nickel-copper alloys with a nickel (d) having a collector system suitable for content of 60 percent or more by weight, or isotopic analysis. Especially designed or prepared rotary shaft seals, with seal feed and seal exhaust nickel-chrome alloys; 3. Any other components especially connections, for sealing the shaft connecting (iii) Electron bombardment ionization designed or prepared for use in a gaseous the compressor rotor or the gas blower rotor sources; and diffusion enrichment plant or in any of the with the driver motor to ensure a reliable seal (iv) Collector system suitable for isotopic components described in this appendix. against out-leakage of process gas or in- analysis. ■ 10. Revise appendix D to part 110 to leakage of air or seal gas into the inner (12) UF6/carrier gas separation systems. read as follows: chamber of the compressor or gas blower Especially designed or prepared process which is filled with a UF6/carrier gas systems for separating UF6 from carrier gas Appendix D to Part 110—Illustrative mixture. (hydrogen or helium). List of Aerodynamic Enrichment Plant (5) Heat exchangers for gas cooling. These systems are designed to reduce the Equipment and Components Under Especially designed or prepared heat UF6 content in the carrier gas to 1 ppm or NRC Export Licensing Authority exchangers, made of, or protected by, less and may incorporate equipment such as: materials resistant to corrosion by UF6. (i) Cryogenic heat exchangers and Note: In aerodynamic enrichment (6) Separation element housings. cryoseparators capable of temperatures of 153 processes, a mixture of gaseous UF6 and light Especially designed or prepared separation K (–120 °C) or less; gas (hydrogen or helium) is compressed and element housings, made of, or protected by, (ii) Cryogenic refrigeration units capable of then passed through separating elements materials resistant to corrosion by UF6, for temperatures of 153 K (–120 °C) or less; wherein isotopic separation is accomplished containing vortex tubes or separation (iii) Separation nozzle or vortex tube units by the generation of high centrifugal forces nozzles. for the separation of UF6 from carrier gas; or

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(iv) UF6 cold traps capable of freezing out uranium from one valence state to another for These systems may incorporate equipment UF6. uranium enrichment using the chemical such as: (13) Any other components especially exchange process. The cell materials in (i) Equipment for contacting chlorine and designed or prepared for use in an contact with process solutions must be oxygen with the aqueous effluent from the aerodynamic enrichment plant or in any of corrosion resistant to concentrated isotope separation equipment and extracting the components described in this appendix. hydrochloric acid solutions. the resultant U∂4 into the stripped organic The cell cathodic compartment must be stream returning from the product end of the ■ 11. Revise appendix E to part 110 to designed to prevent re-oxidation of uranium cascade; and read as follows: to its higher valence state. To keep the (ii) Equipment that separates water from uranium in the cathodic compartment, the hydrochloric acid so that the water and the Appendix E to Part 110—Illustrative cell may have an impervious diaphragm concentrated hydrochloric acid may be List of Chemical Exchange or Ion membrane constructed of special cation reintroduced to the process at the proper Exchange Enrichment Plant Equipment exchange material. The cathode consists of a locations. and Components Under NRC Export suitable solid conductor such as graphite. B. In the solid-liquid ion-exchange process, Licensing Authority These systems consist of solvent extraction enrichment is accomplished by uranium equipment for stripping the U∂4 from the adsorption/desorption on a special, fast- Note: The slight difference in mass organic stream into an aqueous solution, acting, ion-exchange resin or adsorbent. A between the isotopes of uranium causes evaporation and/or other equipment to solution of uranium in hydrochloric acid and small changes in chemical reaction equilibria accomplish solution pH adjustment and other chemical agents is passed through that can be used as a basis for separation of control, and pumps or other transfer devices cylindrical enrichment columns containing the isotopes. Two processes have been for feeding to the electrochemical reduction packed beds of the adsorbent. For a successfully developed: Liquid-liquid cells. A major design concern is to avoid continuous process, a reflux system is chemical exchange and solid-liquid ion contamination of the aqueous stream with necessary to release the uranium from the exchange. certain metal ions. For those parts in contact adsorbent back in the liquid flow so that A. In the liquid-liquid chemical exchange with the process stream, the system is ‘‘product’’ and ‘‘tails’’ can be collected. This process, immiscible liquid phases (aqueous constructed of equipment made of, or is accomplished with the use of suitable and organic) are countercurrently contacted protected by, materials such as glass, reduction/oxidation chemical agents that are to give the cascading effect of thousands of fluorocarbon polymers, polyphenyl sulfate, fully regenerated in separate external circuits separation stages. The aqueous phase polyether sulfone, and resin-impregnated and that may be partially regenerated within consists of uranium chloride in hydrochloric graphite. the isotopic separation columns themselves. acid solution; the organic phase consists of (ii) Especially designed or prepared The presence of hot concentrated an extractant containing uranium chloride in systems at the product end of the cascade for hydrochloric acid solutions in the process an organic solvent. The contactors employed taking the U∂4 out of the organic stream, requires that the equipment be made of, or in the separation cascade can be liquid-liquid adjusting the acid concentration, and feeding protected by, special corrosion-resistant exchange columns (such as pulsed columns to the electrochemical reduction cells. materials. with sieve plates) or liquid centrifugal These systems consist of solvent extraction (1) Fast reacting ion exchange resins/ contactors. Chemical conversions (oxidation equipment for stripping the U∂4 from the adsorbents. and reduction) are required at both ends of organic stream into an aqueous solution, Especially designed or prepared for the separation cascade in order to provide for evaporation and/or other equipment to uranium enrichment using the ion exchange the reflux requirements at each end. A major accomplish solution pH adjustment and process, including porous macroreticular design concern is to avoid contamination of control, and pumps or other transfer devices resins, and/or pellicular structures in which the process streams with certain metal ions. for feeding to the electrochemical reduction the active chemical exchange groups are Plastic, plastic-lined (including use of cells. A major design concern is to avoid limited to a coating on the surface of an fluorocarbon polymers) and/or glass-lined contamination of the aqueous stream with inactive porous support structure, and other columns and piping are therefore used. certain metal ions. For those parts in contact composite structures in any suitable form (1) Liquid-liquid exchange columns. with the process stream, the system is including particles or fibers. These ion Countercurrent liquid-liquid exchange constructed of equipment made of, or exchange resins/adsorbents have diameters of columns having mechanical power input protected by, materials such as glass, 0.2 mm or less and must be chemically especially designed or prepared for uranium fluorocarbon polymers, polyphenyl sulfate, resistant to concentrated hydrochloric acid enrichment using the chemical exchange polyether sulfone, and resin-impregnated solutions as well as physically strong enough process. For corrosion resistance to graphite. so as not to degrade in the exchange concentrated hydrochloric acid solutions, (4) Feed preparation systems. columns. The resins/adsorbents are these columns and their internals are Especially designed or prepared systems especially designed to achieve very fast normally made of, or protected by, suitable for producing high-purity uranium chloride uranium isotope exchange kinetics (exchange plastic materials (such as fluorinated feed solutions for chemical exchange rate half-time of less than 10 seconds) and are hydrocarbon polymers) or glass. The stage uranium isotope separation plants. capable of operating at a temperature in the residence time of the columns is normally These systems consist of dissolution, range of 373 K (100 °C) to 473 K (200 °C). designed to be 30 seconds or less. solvent extraction and/or ion exchange (2) Ion exchange columns. (2) Liquid-liquid centrifugal contactors. equipment for purification and electrolytic Cylindrical columns greater than 1000 mm Especially designed or prepared for cells for reducing the uranium U∂6 or U∂4 in diameter for containing and supporting uranium enrichment using the chemical to U∂3. These systems produce uranium packed beds of ion exchange resin/adsorbent, exchange process. These contactors use chloride solutions having only a few parts especially designed or prepared for uranium rotation to achieve dispersion of the organic per million of metallic impurities such as enrichment using the ion exchange process. and aqueous streams and then centrifugal chromium, iron, vanadium, molybdenum, These columns are made of, or protected by, force to separate the phases. For corrosion and other bivalent or higher multi-valent materials (such as titanium or fluorocarbon resistance to concentrated hydrochloric acid cations. Materials of construction for portions plastics) resistant to corrosion by solutions, the contactors are normally made of the system processing high-purity U∂3 concentrated hydrochloric acid solutions and of, or protected by, suitable plastic materials include glass, fluorinated hydrocarbon are capable of operating at a temperature in (such as fluorinated hydrocarbon polymers) polymers, polyphenyl sulfate or polyether the range of 373 K (100 °C) to 473 K (200 °C) or glass. The stage residence time of the sulfone plastic-lined and resin-impregnated and pressures above 0.7 MPa. centrifugal contactors is designed to be short graphite. (3) Ion exchange reflux systems. (30 seconds or less). (5) Uranium oxidation systems. (i) Especially designed or prepared (3) Uranium reduction systems and Especially designed or prepared systems chemical or electrochemical reduction equipment. for oxidation of U∂3 to U∂4 for return to the systems for regeneration of the chemical (i) Especially designed or prepared uranium isotope separation cascade in the reducing agent(s) used in ion exchange electrochemical reduction cells to reduce chemical exchange enrichment process. uranium enrichment cascades.

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The ion exchange enrichment process may Especially designed or prepared uranium Especially designed or prepared ∂3 use, for example, trivalent titanium (Ti ) as metal vaporization systems for use in laser compressors for UF6/carrier gas mixtures, a reducing cation in which case the reduction enrichment. designed for long term operation in a UF6 system would regenerate Ti∂3 by reducing These systems may contain electron beam environment. Components of these Ti∂4. guns and are designed to achieve a delivered compressors that come into contact with (ii) Especially designed or prepared power (1 kW or greater) on the target process gas are made of, or protected by, chemical or electrochemical oxidation sufficient to generate uranium metal vapour materials resistant to UF6 corrosion. systems for regeneration of the chemical at a rate required for the laser enrichment (8) Rotary shaft seals (molecular based oxidizing agent(s) used in ion exchange function. methods). uranium enrichment cascades. (2) Liquid or vapor uranium metal Especially designed or prepared rotary The ion exchange enrichment process may handling systems and components (atomic shaft seals, with seal feed and seal exhaust ∂ use, for example, trivalent iron (Fe 3) as an vapor based methods). connections, for sealing the shaft connecting oxidant in which case the oxidation system Especially designed or prepared systems the compressor rotor with the driver motor to ∂ ∂ would regenerate Fe 3 by oxidizing Fe 2. for handling molten uranium, molten ensure a reliable seal against out-leakage of C. Any other components especially uranium alloys, or uranium metal vapor. process gas or in-leakage of air or seal gas designed or prepared for use in a chemical The liquid uranium metal handling into the inner chamber of the compressor exchange or ion exchange enrichment plant systems may consist of crucibles and cooling which is filled with a UF6/carrier gas or in any of the components described in this equipment for the crucibles. The crucibles mixture. appendix. and other system parts that come into contact (9) Fluorination systems (molecular based ■ 12. Revise appendix F to part 110 to with molten uranium, molten uranium methods). read as follows: alloys, or uranium metal vapor are made of, Especially designed or prepared systems or protected by, materials of suitable for fluorinating UF5 (solid) to UF6 (gas). Appendix F to Part 110—Illustrative corrosion and heat resistance, such as These systems are designed to fluorinate List of Laser-Based Enrichment Plant tantalum, yttria-coated graphite, graphite the collected UF5 powder to UF6 for Equipment and Components Under coated with other rare earth oxides, or subsequent collection in product containers NRC Export Licensing Authority mixtures thereof. or for transfer as feed for additional (3) Uranium metal ‘‘product’’ and ‘‘tails’’ enrichment. In one approach, the Note: Present systems for enrichment collector assemblies (atomic vapor based fluorination reaction may be accomplished processes using lasers fall into two methods). within the isotope separation system to react categories: The process medium is atomic Especially designed or prepared ‘‘product’’ and recover directly off the ‘‘product’’ uranium vapor and the process medium is and ‘‘tails’’ collector assemblies for uranium collectors. In another approach, the UF5 the vapor of a uranium compound, metal in liquid or solid form. powder may be removed/transferred from the sometimes mixed with another gas or gases. Components for these assemblies are made ‘‘product’’ collectors into a suitable reaction Common nomenclature for these processes of or protected by materials resistant to the vessel (e.g., fluidized-bed reactor, screw include: First category-atomic vapor laser heat and corrosion of uranium metal vapor or reactor or flame tower) for fluorination. In isotope separation; and second category- liquid, such as yttria-coated graphite or both approaches, equipment is used for molecular laser isotope separation including tantalum, and may include pipes, valves, storage and transfer of fluorine (or other chemical reaction by isotope selective laser activation. The systems, equipment, and fittings, ‘‘gutters,’’ feed-throughs, heat suitable fluorinating agents) and for components for laser enrichment plants exchangers and collector plates for magnetic, collection and transfer of UF6. include: (a) Devices to feed uranium-metal electrostatic, or other separation methods. (10) UF6 mass spectrometers/ion sources vapor for selective photo-ionization or (4) Separator module housings (atomic (molecular based methods). devices to feed the vapor of a uranium vapor based methods). Especially designed or prepared mass compound (for selective photo-dissociation Especially designed or prepared cylindrical spectrometers capable of taking on-line or selective excitation/activation); (b) devices or rectangular vessels for containing the samples from UF6 gas streams and having all to collect enriched and depleted uranium uranium metal vapor source, the electron of the following characteristics: metal as ‘‘product’’ and ‘‘tails’’ in the first beam gun, and the ‘‘product’’ and ‘‘tails’’ (i) Capable of measuring ions of 320 atomic category, and devices to collect enriched and collectors. These housings have multiplicity mass units or greater and having a resolution depleted uranium compounds as ‘‘product’’ of ports for electrical and water feed- of better than 1 part in 320; and ‘‘tails’’ in the second category; (c) throughs, laser beam windows, vacuum (ii) Ion sources constructed of or protected process laser systems to selectively excite the pump connections, and instrumentation by nickel, nickel-copper alloys with a nickel uranium-235 species; and (d) feed diagnostics and monitoring with opening and content of 60 percent or more by weight, or preparation and product conversion closure provisions to allow refurbishment of nickel-chrome alloys; equipment. The complexity of the internal components. (iii) Electron bombardment ionization spectroscopy of uranium atoms and (5) Supersonic expansion nozzles sources; and compounds may require incorporation of a (molecular based methods). (iv) Collector system suitable for isotopic number of available laser and laser optics Especially designed or prepared supersonic analysis. technologies. expansion nozzles for cooling mixtures of (11) Feed systems/product and tails ¥ ° All surfaces that come into direct contact UF6 and carrier gas to 150 K ( 123 C) or withdrawal systems (molecular based with the uranium or UF6 are wholly made of, less which are corrosion resistant to UF6. methods). or protected by, corrosion-resistant materials. (6) ‘‘Product’’ or ‘‘tails’’ collectors Especially designed or prepared process For laser-based enrichment items, the (molecular based methods). systems or equipment for enrichment plants materials resistant to corrosion by the vapor Especially designed or prepared made of or protected by materials resistant to or liquid of uranium metal or uranium alloys components or devices for collecting corrosion by UF6, including: include yttria-coated graphite and tantalum; uranium product material or uranium tails (i) Feed autoclaves, ovens, or systems used and the materials resistant to corrosion by material following illumination with laser for passing UF6 to the enrichment process; UF6 include copper, copper alloys, stainless light. (ii) Desublimers (or cold traps) used to steel, aluminum, aluminum oxide, aluminum In one example of molecular laser isotope remove UF6 from the enrichment process for alloys, nickel or alloys containing 60 percent separation, the product collectors serve to subsequent transfer upon heating; or more nickel by weight, and fluorinated collect enriched uranium pentafluoride (UF5) (iii) Solidification or liquefaction stations hydrocarbon polymers. Many of the solid material. The product collectors may used to remove UF6 from the enrichment following items come into direct contact with consist of filter, impact, or cyclone-type process by compressing and converting UF6 uranium metal vapor or liquid or with collectors, or combinations thereof, and must to a liquid or solid; and process gas consisting of UF6 or a mixture of be corrosion resistant to the UF5/UF6 (iv) ‘‘Product’’ or ‘‘tails’’ stations used to UF6 and other gases: environment. transfer UF6 into containers. (1) Uranium vaporization systems (atomic (7) UF6/carrier gas compressors (molecular (12) UF6/carrier gas separation systems vapor based methods). based methods). (molecular based methods).

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Especially designed or prepared process Especially designed or prepared ‘‘product’’ disposition of the recovered materials, and systems for separating UF6 from carrier gas. and ‘‘tails’’ collector assemblies for uranium the safety and maintenance philosophy These systems may incorporate equipment metal in solid form. These collector incorporated into the design of the facility. A such as: assemblies are made of, or protected by, plant for the reprocessing of irradiated fuel (i) Cryogenic heat exchangers or materials resistant to the heat and corrosion elements includes the equipment and cryoseparators capable of temperatures of 153 of uranium metal vapor, such as yttria-coated components which normally come in direct K (¥120 °C) or less; graphite or tantalum. contact with and directly control the (ii) Cryogenic refrigeration units capable of (5) Separator module housings. irradiated fuel and the major nuclear material temperatures of 153 K (¥120 °C) or less; or Especially designed or prepared cylindrical and fission product processing streams. (iii) UF6 cold traps capable of freezing out vessels for use in plasma separation (1) Irradiated fuel element chopping UF6. enrichment plants for containing the machines. (13) Lasers or Laser systems. uranium plasma source, radio-frequency Remotely operated equipment especially Especially designed or prepared for the drive coil, and the ‘‘product’’ and ‘‘tails’’ designed or prepared for use in a separation of uranium isotopes. collectors. reprocessing plant and intended to cut, chop, The laser system typically contains both These housings have a multiplicity of ports or shear irradiated nuclear fuel assemblies, optical and electronic components for the for electrical feed-throughs, diffusion pump bundles, or rods. This equipment breaches management of the laser beam (or beams) and connections, and instrumentation diagnostics the cladding of the fuel to expose the the transmission to the isotope separation and monitoring. They have provisions for irradiated nuclear material to dissolution. chamber. The laser system for atomic vapor opening and closure to allow for Especially designed metal cutting shears are based methods usually consists of tunable refurbishment of internal components and the most commonly employed, although advanced equipment, such as lasers, may be dye lasers pumped by another type of laser are constructed of a suitable non-magnetic used. (e.g., copper vapor lasers or certain solid- material such as stainless steel. (2) Dissolvers. state lasers). The laser system for molecular (6) Any other components especially Critically safe tanks (e.g. small diameter, based methods may consist of CO2 lasers or designed or prepared for use in a plasma excimer lasers and a multi-pass optical cell. annular, or slab tanks) especially designed or separation enrichment plant or in any of the prepared for use in a reprocessing plant, Lasers or laser systems for both methods components described in this appendix. require spectrum frequency stabilization for intended for dissolution of irradiated nuclear operation over extended periods of time. ■ 14. In appendix H to part 110, add a fuel and which are capable of withstanding (14) Any other components especially new paragraph (4) to read as follows: hot, highly corrosive liquid, and which can designed or prepared for use in a laser-based be remotely loaded and maintained. enrichment plant or in any of the Appendix H to Part 110—Illustrative Dissolvers normally receive the chopped- components described in this appendix. List of Electromagnetic Enrichment up spent fuel. In these critically safe vessels, Plant Equipment and Components the irradiated nuclear material is dissolved in ■ 13. Revise appendix G to part 110 to nitric acid and the remaining hulls removed Under NRC Export Licensing Authority read as follows: from the process stream. * * * * * (3) Solvent extractors and solvent Appendix G to Part 110—Illustrative (4) Any other components especially extraction equipment. List of Plasma Separation Enrichment designed or prepared for use in an Especially designed or prepared solvent Plant Equipment and Components electromagnetic enrichment plant or in any extractors such as packed or pulse columns, Under NRC Export Licensing Authority of the components described in this mixer settlers, or centrifugal contactors for appendix. use in a plant for the reprocessing of Note: In the plasma separation process, a irradiated fuel. Solvent extractors must be plasma of uranium ions passes through an ■ 15. Revise appendix I to part 110 to resistant to the corrosive effect of nitric acid. electric field tuned to the 235U ion resonance read as follows: Solvent extractors are normally fabricated to frequency so that they preferentially absorb extremely high standards (including special energy and increase the diameter of their Appendix I to Part 110—Illustrative welding and inspection and quality corkscrew-like orbits. Ions with a large- List of Reprocessing Plant Components assurance and quality control techniques) out diameter path are trapped to produce a Under NRC Export Licensing Authority of low carbon stainless steels, titanium, product enriched in 235U. The plasma, made zirconium, or other high quality materials. by ionizing uranium vapor, is contained in a Note: Reprocessing irradiated nuclear fuel Solvent extractors both receive the solution vacuum chamber with a high-strength separates plutonium and uranium from of irradiated fuel from the dissolvers and the magnetic field produced by a intensely radioactive fission products and organic solution which separates the superconducting magnet. The main other transuranic elements. Different uranium, plutonium, and fission products. technological systems of the process include technical processes can accomplish this Solvent extraction equipment is normally the uranium plasma generation system, the separation. However, over the years Purex designed to meet strict operating parameters, separator module with superconducting has become the most commonly used and such as long operating lifetimes with no magnet, and metal removal systems for the accepted process. Purex involves the maintenance requirements or adaptability to collection of ‘‘product’’ and ‘‘tails.’’ dissolution of irradiated nuclear fuel in nitric easy replacement, simplicity of operation and (1) Microwave power sources and acid, followed by separation of the uranium, control, and flexibility for variations in antennae. plutonium, and fission products by solvent process conditions. Especially designed or prepared extraction using a mixture of tributyl (4) Chemical holding or storage vessels. microwave power sources and antennae for phosphate in an organic diluent. Especially designed or prepared holding or producing or accelerating ions having the Purex facilities have process functions storage vessels for use in a plant for the following characteristics: Greater than 30 similar to each other, including: Irradiated reprocessing of irradiated fuel. The holding GHz frequency and greater than 50 kW mean fuel element chopping, fuel dissolution, or storage vessels must be resistant to the power output for ion production. solvent extraction, and process liquor corrosive effect of nitric acid. The holding or (2) Ion excitation coils. storage. There may also be equipment for storage vessels are normally fabricated of Especially designed or prepared radio thermal denitration of uranium nitrate, materials such as low carbon stainless steels, frequency ion excitation coils for frequencies conversion of plutonium nitrate to oxide titanium or zirconium, or other high quality of more than 100 kHz and capable of metal, and treatment of fission product waste materials. Holding or storage vessels may be handling more than 40 kW mean power. liquor to a form suitable for long term storage designed for remote operation and (3) Uranium plasma generation systems. or disposal. However, the specific type and maintenance and may have the following Especially designed or prepared systems configuration of the equipment performing features for control of nuclear criticality: for the generation of uranium plasma for use these functions may differ between Purex (i) Walls or internal structures with a boron in plasma separation plants. facilities for several reasons, including the equivalent of at least 2 percent, or (4) Uranium metal ‘‘product’’ and ‘‘tails’’ type and quantity of irradiated nuclear fuel (ii) A maximum diameter of 175 mm (7 in) collector assemblies. to be reprocessed and the intended for cylindrical vessels, or

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(iii) A maximum width of 75 mm (3 in) for A. The GS process is based upon the utilizing either the water-hydrogen sulphide either a slab or annular vessel. exchange of hydrogen and deuterium exchange process or the ammonia-hydrogen (5) Neutron measurement systems for between water and hydrogen sulphide within exchange process: process control. a series of towers which are operated with (i) Water-hydrogen Sulphide Exchange Neutron measurement systems especially the top section cold and the bottom section Towers. designed or prepared for integration and use hot. Water flows down the towers while the Exchange towers with diameters of 1.5 m with automated process control systems in a hydrogen sulphide gas circulates from the or greater and capable of operating at plant for the reprocessing of irradiated fuel bottom to the top of the towers. A series of pressures greater than or equal to 2 MPa (300 elements. These systems involve the perforated trays are used to promote mixing psi) especially designed or prepared for capability of active and passive neutron between the gas and the water. Deuterium heavy water production utilizing the water- measurement and discrimination in order to migrates to the water at low temperatures and hydrogen sulphide exchange process. determine the fissile material quantity and to the hydrogen sulphide at high (ii) Blowers and Compressors. composition. The complete system is temperatures. Gas or water, enriched in Single stage, low head (i.e., 0.2 MPa or 30 composed of a neutron generator, a neutron deuterium, is removed from the first stage psi) centrifugal blowers or compressors for detector, amplifiers, and signal processing towers at the junction of the hot and cold hydrogen-sulphide gas circulation (i.e., gas electronics. sections and the process is repeated in containing more than 70 percent H2S). The The scope of this entry does not include subsequent stage towers. The product of the blowers or compressors have a throughput neutron detection and measurement last stage, water enriched up to 30 percent in capacity greater than or equal to 56 m3/ instruments that are designed for nuclear deuterium, is sent to a distillation unit to second (120,000 standard cubic feet per material accountancy and safeguarding or produce reactor grade heavy water; i.e., 99.75 minute) while operating at pressures greater any other application not related to percent deuterium oxide. than or equal to 1.8 MPa (260 psi) suction integration and use with automated process B. The ammonia-hydrogen exchange and have seals designed for wet H2S service. control systems in a plant for the process can extract deuterium from synthesis (iii) Ammonia-Hydrogen Exchange Towers. reprocessing of irradiated fuel elements. gas through contact with liquid ammonia in Ammonia-hydrogen exchange towers (6) Plutonium nitrate to plutonium oxide the presence of a catalyst. The synthesis gas greater than or equal to 35 m (114.3 ft) in conversion systems. Complete systems is fed into exchange towers and then to an height with diameters of 1.5 m (4.9 ft) to 2.5 especially designed or prepared for the ammonia converter. Inside the towers the gas m (8.2 ft) capable of operating at pressures conversion of plutonium nitrate to plutonium flows from the bottom to the top while the greater than 15 MPa (2225 psi). The towers oxide, in particular adapted so as to avoid liquid ammonia flows from the top to the have at least one flanged, axial opening of the criticality and radiation effects and to bottom. The deuterium is stripped from the same diameter as the cylindrical part through minimize toxicity hazards. hydrogen in the synthesis gas and which the tower internals can be inserted or (7) Plutonium metal production systems. concentrated in the ammonia. The ammonia withdrawn. Complete systems especially designed or then flows into an ammonia cracker at the (iv) Tower Internals and Stage Pumps Used prepared for the production of plutonium bottom of the tower while the gas flows into in the Ammonia-hydrogen Exchange Process. metal, in particular adapted so as to avoid an ammonia converter at the top. Further Tower internals include especially criticality and radiation effects and to enrichment takes place in subsequent stages designed stage contactors which promote minimize toxicity hazards. and reactor-grade heavy water is produced (8) Process control instrumentation through final distillation. The synthesis gas intimate gas/liquid contact. Stage pumps specially designed or prepared for feed can be provided by an ammonia plant include especially designed submersible monitoring or controlling the processing of that can be constructed in association with a pumps for circulation of liquid ammonia material in a reprocessing plant. heavy water ammonia-hydrogen exchange within a contacting stage internal to the stage (9) Any other components especially plant. The ammonia-hydrogen exchange towers. designed or prepared for use in a process can also use ordinary water as a feed (v) Ammonia Crackers Utilizing the reprocessing plant or in any of the source of deuterium. Ammonia-hydrogen Exchange Process. components described in this appendix. C.1. Much of the key equipment for heavy Ammonia crackers with operating pressures greater than or equal to 3 MPa (450 ■ water production plants using either the GS 16. In appendix J to part 110, add a process or the ammonia-hydrogen exchange psi) especially designed or prepared for new paragraph (c) to read as follows: process are common to several segments of heavy water production utilizing the the chemical and petroleum industries; ammonia-hydrogen exchange process. Appendix J to Part 110—Illustrative (vi) Ammonia Synthesis Converters or List of Uranium Conversion Plant particularly in small plants using the GS process. However, few items are available Synthesis Units. Equipment and Plutonium Conversion ‘‘off-the-shelf.’’ Both processes require the Ammonia synthesis converters or synthesis Plant Equipment Under NRC Export handling of large quantities of flammable, units especially designed or prepared for Licensing Authority corrosive, and toxic fluids at elevated heavy water production utilizing the pressures. Therefore, in establishing the ammonia-hydrogen exchange process. * * * * * These converters or units take synthesis (c) Any other components especially design and operating standards for plants and equipment using these processes, careful gas (nitrogen and hydrogen) from an designed or prepared for use in a uranium ammonia/hydrogen high-pressure exchange conversion plant or plutonium conversion attention to materials selection and specifications is required to ensure long column (or columns), and the synthesized plant or in any of the components described ammonia is returned to the exchange column in this appendix. service life with high safety and reliability factors. The choice is primarily a function of (or columns). ■ 17. Revise appendix K to part 110 to economics and need. Most equipment, (vii) Infrared Absorption Analyzers. read as follows: therefore, is prepared to customer Infrared absorption analyzers capable of requirements. ‘‘on-line’’ hydrogen/deuterium ratio analysis Appendix K to Part 110—Illustrative In both processes, equipment which where deuterium concentrations are equal to List of Equipment and Components individually is not especially designed or or greater than 90 percent. Under NRC Export Licensing Authority prepared for heavy water production can be (viii) Catalytic Burners Used in the for Use in a Plant for the Production of assembled into especially designed or Ammonia-hydrogen Exchange Process. Heavy Water, Deuterium and prepared systems for producing heavy water. Catalytic burners for the conversion of enriched deuterium gas into heavy water Deuterium Compounds Examples of such systems are the catalyst production system used in the ammonia- especially designed or prepared for heavy Note: Heavy water can be produced by a hydrogen exchange process and the water water production utilizing the ammonia- variety of processes. However, two processes distillation systems used for the final hydrogen exchange process. have proven to be commercially viable: The concentration of heavy water to reactor-grade (ix) Complete Heavy Water Upgrade water-hydrogen sulphide exchange process in either process. Systems or Columns. (GS process) and the ammonia-hydrogen C.2. Equipment especially designed or Complete heavy water upgrade systems or exchange process. prepared for the production of heavy water columns especially designed or prepared for

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the upgrade of heavy water to reactor-grade 99.75 percent deuterium oxide) from heavy ■ 18. Revise appendix M to part 110 to deuterium concentration. These systems, water feedstock of lesser concentration. read as follows: which usually employ water distillation to D. Any other components especially separate heavy water from light water, are designed or prepared for use in a plant for Appendix M to Part 110— especially designed or prepared to produce the production of heavy water, deuterium, Categorization of Nuclear Material and deuterium compounds or in any of the reactor-grade heavy water (i.e., typically components described in this appendix.

CATEGORIZATION OF NUCLEAR MATERIAL [From IAEA INFCIRC/225/Revision 5]

Material Form Category I Category II Category III 3

1. Plutonium1 ...... Unirradiated 2 ...... 2 kg or more ...... Less than 2 kg but more 500 g or less but more than than 500 g. 15 g. 2. Uranium-235 Unirradiated 2: (235U). —Uranium enriched to 5 kg or more ...... Less than 5 kg but more 1 kg or less but more than 20 percent 235U or than 1 kg. 15 g. more. —Uranium enriched to ...... 10 kg or more ...... Less than 10 kg but more 10 percent 235U but than 1 kg. less than 20 percent 235U. —Uranium enriched ...... 10 kg or more. above natural, but less than 10 percent 235U. 3. Uranium-233 Unirradiated 2 ...... 2 kg or more ...... Less than 2 kg but more 500 g or less but more than (233U). than 500 g. 15 g. 4. Irradiated Fuel ...... Depleted or natural uranium, (The categoriza- thorium or low enriched tion of irradiated fuel (less than 10 percent fuel in the table fissile content) 45 is based on international transport consid- erations. The State may assign a different cat- egory for domes- tic use, storage and transport taking all rel- evant factors into account). 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 pru- dent 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 dif- ferent 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 Appendix O to Part 110—Illustrative equipment to extremely high standards is new paragraph c. to read as follows: List of Fuel Element Fabrication Plant necessary in order to ensure predictable and Equipment and Components Under safe fuel performance. Appendix N to Part 110—Illustrative NRC’s Export Licensing Authority (a) Items that are considered especially List of Lithium Isotope Separation designed or prepared for the fabrication of Facilities, Plants and Equipment Under Note: Nuclear fuel elements are fuel elements include equipment that: manufactured from source or special nuclear (1) Normally comes in direct contact with, NRC’s Export Licensing Authority material. For oxide fuels, the most common or directly processes or controls, the * * * * * type of fuel equipment for pressing pellets, production flow of nuclear material; c. Any other components especially sintering, grinding and grading will be (2) Seals the nuclear material within the cladding; designed or prepared for use in a present. Mixed oxide fuels are handled in glove boxes (or equivalent containment) until (3) Checks the integrity of the cladding or reprocessing plant or in any of the they are sealed in the cladding. In all cases, the seal; components described in this appendix. the fuel is hermetically sealed inside a (4) Checks the finished treatment of the suitable cladding which is designed to be the sealed fuel; or ■ 20. Revise appendix O to part 110 to primary envelope encasing the fuel so as to (5) Is used for assembling reactor fuel read as follows: provide suitable performance and safety elements. during reactor operation. Also, in all cases, (b) This equipment or systems of precise control of processes, procedures and equipment may include, for example:

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(1) Fully automatic pellet inspection rear spar web in the area of rear spar (ACO), 1601 Lind Avenue SW., Renton, stations especially designed or prepared for station (RSS) 224.14, which could grow WA 98057–3356; phone: 425–917–6440; checking final dimensions and surface and result in a fuel leak and possible fax: 425–917–6590; email: defects of fuel pellets; fire. [email protected]. (2) Automatic welding machines especially designed or prepared for welding end caps DATES: This AD is effective July 25, SUPPLEMENTARY INFORMATION: onto the fuel pins (or rods); 2014. Discussion (3) Automatic test and inspection stations The Director of the Federal Register especially designed or prepared for checking approved the incorporation by reference On January 18, 2014, we issued AD the integrity of completed fuel pins (or rods). of a certain publication listed in this AD 2014–03–06, Amendment 39–17743 (79 This item typically includes equipment for: as of April 9, 2014 (79 FR 12368, March FR 12368, March 5, 2014), for all the (i) X-ray examination of pin (or rod) end Boeing Company Model 737–100, –200, cap welds; 5, 2014). (ii) Helium leak detection from pressurized We must receive any comments on –200C, –300, –400, and –500 series pins (or rods); and this AD by August 25, 2014. airplanes. AD 2014–03–06 required (iii) Gamma-ray scanning of the pins (or ADDRESSES: You may send comments, repetitive inspections for cracking of the rods) to check for correct loading of the fuel using the procedures found in 14 CFR aft support fitting for the main landing pellets inside. 11.43 and 11.45, by any of the following gear (MLG) beam, and the rear spar (4) Systems especially designed or methods: upper chord and rear spar web in the prepared to manufacture nuclear fuel • Federal eRulemaking Portal: Go to area of rear spar station (RSS) 224.14; cladding. http://www.regulations.gov. Follow the and repair if necessary. AD 2014–03–06 (c) Any other components especially resulted from reports of cracks found in designed or prepared for use in a fuel instructions for submitting comments. • Fax: 202–493–2251. the aft support fitting, the rear spar element fabrication plant or in any of the • components described in this appendix. Mail: U.S. Department of upper chord, and the rear spar web. We Transportation, Docket Operations, M– issued AD 2014–03–06 to detect and Dated at Rockville, Maryland, this 18th day 30, West Building Ground Floor, Room correct cracking of the aft support fitting of June, 2014. W12–140, 1200 New Jersey Avenue SE., for the main landing gear (MLG) beam, For the Nuclear Regulatory Commission. Washington, DC 20590. and the rear spar upper chord and rear Mark A. Satorius, • Hand Delivery: U.S. Department of spar web in the area of rear spar station Executive Director for Operations. Transportation, Docket Operations, M– (RSS) 224.14, which could grow and [FR Doc. 2014–15828 Filed 7–9–14; 8:45 am] 30, West Building Ground Floor, Room result in a fuel leak and possible fire. BILLING CODE 7590–01–P W12–140, 1200 New Jersey Avenue SE., Actions Since AD 2014–03–06 Was Washington, DC 20590, between 9 a.m. Issued and 5 p.m., Monday through Friday, DEPARTMENT OF TRANSPORTATION except Federal holidays. Since we issued AD 2014–03–06, For service information identified in Amendment 39–17743 (79 FR 12368, Federal Aviation Administration this AD, contact Boeing Commercial March 5, 2014), two incorrect paragraph Airplanes, Attention: Data & Services references were found. The references to 14 CFR Part 39 Management, P.O. Box 3707, MC 2H–65, paragraphs (g) and (g)(1) in paragraph [Docket No. FAA–2014–0341; Directorate Seattle, WA 98124–2207; telephone (h)(2) of AD 2014–03–06 are incorrect. Identifier 2014–NM–102–AD; Amendment 206–544–5000, extension 1; fax 206– The correct reference should be to the 39–17874; AD 2014–12–13] 766–5680; Internet https:// introductory text of paragraph (h) and www.myboeingfleet.com. You may view paragraph (h)(1) of AD 2014–03–06. RIN 2120–AA64 this referenced service information at Paragraph (h)(2) of AD 2014–03–06 is Airworthiness Directives; the Boeing the FAA, Transport Airplane the corrective action for the inspections Company Airplanes Directorate, 1601 Lind Avenue SW., required by the introductory text of Renton, WA. For information on the paragraph (h) and paragraph (h)(1) of AGENCY: Federal Aviation availability of this material at the FAA, this AD. In order to mandate the Administration (FAA), DOT. call 425–227–1221. corrective actions for the inspections ACTION: Final rule; request for Examining the AD Docket required by the introductory text of comments. paragraph (h) and paragraph (h)(1) of You may examine the AD docket on this AD, we have revised the references SUMMARY: We are superseding the Internet at http:// in paragraph (h)(2) of this AD. Airworthiness Directive (AD) 2014–03– www.regulations.gov by searching for FAA’s Determination 06 for all the Boeing Company Model and locating Docket No. FAA–2014– 737–100, –200, –200C, –300, –400, and 0341; or in person at the Docket We are issuing this AD because we –500 series airplanes. AD 2014–03–06 Management Facility between 9 a.m. evaluated all the relevant information required repetitive inspections for and 5 p.m., Monday through Friday, and determined the unsafe condition cracking of the aft support fitting for the except Federal holidays. The AD docket described previously is likely to exist or main landing gear (MLG) beam, and the contains this AD, the regulatory develop in other products of these same rear spar upper chord and rear spar web evaluation, any comments received, and type designs. in the area of rear spar station (RSS) other information. The street address for AD Requirements 224.14; and repair if necessary. This AD the Docket Office (phone: 800–647– clarifies two paragraph references. This 5527) is in the ADDRESSES section. This AD requires repetitive AD was prompted by a determination Comments will be available in the AD inspections for cracking of the aft that two paragraph references were in docket shortly after receipt. support fitting for the MLG beam, and error. We are issuing this AD to detect FOR FURTHER INFORMATION CONTACT: the rear spar upper chord and rear spar and correct cracking of the aft support Nancy Marsh, Aerospace Engineer, web in the area of RSS 224.14; and fitting for the main landing gear (MLG) Airframe Branch, ANM–120S, FAA, repair if necessary. This AD corrects beam, and the rear spar upper chord and Seattle Aircraft Certification Office these paragraph references.

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