Source: http://www.law.cornell.edu/cfr/text/10/72?quicktabs_7=3
Timestamp: 2013-12-21 17:19:11
Document Index: 750511838

Matched Legal Cases: ['art 72', 'art 72', 'art 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', '§ 72', 'art 72', 'art 72', 'art 72', '§ 2021', '§ 2071', '§ 2073', '§ 2077', '§ 2092', '§ 2093', '§ 2095', '§ 2099', '§ 2111', '§ 2201', '§ 2232', '§ 2233', '§ 2234', '§ 2236', '§ 2238', '§ 2239', '§ 2282', '§ 4332', '§ 5841', '§ 5842', '§ 5846', '§ 5851', '§ 10101', '§ 10102', '§ 10103', '§ 10104', '§ 10105', '§ 10106', '§ 10107', '§ 10108', '§ 10137', '§ 10151', '§ 10152', '§ 10153', '§ 10154', '§ 10155', '§ 10157', '§ 10161', '§ 10162', '§ 10165', '§ 10168', '§ 10198', 'art 72', 'art 72', 'art 72', 'art 72']

10 CFR Part 72 - LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE | Title 10 - Energy | Code of Federal Regulations | LII / Legal Information Institute
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10 CFR Part 72 - LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE
There are 5 Updates appearing in the Federal Register for 10 CFR 72. Select the tab below to view, or View eCFR (GPOAccess)
SUBPART A — General Provisions (§§ 72.1 - 72.13)
SUBPART B — License Application, Form, and Contents (§§ 72.16 - 72.34)
SUBPART C — Issuance and Conditions of License (§§ 72.40 - 72.62)
SUBPART D — Records, Reports, Inspections, and Enforcement (§§ 72.70 - 72.86)
SUBPART E — Siting Evaluation Factors (§§ 72.90 - 72.108)
SUBPART F — General Design Criteria (§§ 72.120 - 72.130)
SUBPART G — Quality Assurance (§§ 72.140 - 72.176)
SUBPART H — Physical Protection (§§ 72.180 - 72.186)
SUBPART I — Training and Certification of Personnel (§§ 72.190 - 72.194)
SUBPART J — Provision of MRS Information to State Governments and Indian Tribes (§§ 72.200 - 72.206)
SUBPART K — General License for Storage of Spent Fuel at Power Reactor Sites (§§ 72.210 - 72.220)
SUBPART L — Approval of Spent Fuel Storage Casks (§§ 72.230 - 72.248)
Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183, 184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953, 954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C. 2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 2234, 2236, 2237, 2238, 2282); sec. 274, Pub. L. 86-373, 73 Stat. 688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88 Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846); Pub. L. 95-601, sec. 10, 92 Stat. 2951 as amended by Pub. L. 102-486, sec. 7902, 106 Stat. 3123 (42 U.S.C. 5851); sec. 102, Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332); secs. 131, 132, 133, 135, 137, 141, Pub. L. 97-425, 96 Stat. 2229, 2230, 2232, 2241, sec. 148, Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10151, 10152, 10153, 10155, 10157, 10161, 10168); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Pub. L. No. 109-58, 119 Stat. 549 (2005).
Section 72.44(g) also issued under secs. 142(b) and 148(c), (d), Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 10162(b), 10168(c), (d)).
Section 72.46 also issued under sec. 189, 68 Stat. 955 (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 2230 (42 U.S.C. 10154).
53 FR 31658, Aug. 19, 1988, unless otherwise noted.
Title 10 published on 2013-01-01The following are only the Rules published in the Federal Register after the published date of Title 10.For a complete list of all Rules, Proposed Rules, and Notices view the Rulemaking tab.2013-06-25; vol. 78 # 122 - Tuesday, June 25, 201378 FR 37927 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System
typeregulations.gov FR Doc.2013-15127 RIN3150-AJ22 NRC-2012-0308 NUCLEAR REGULATORY COMMISSION Final rule. The final rule is effective July 25, 2013. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. (NAC) Modular Advanced Generation Nuclear All-purpose Storage (MAGNASTOR®) Cask System listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 3 to Certificate of Compliance (CoC) No. 1031. Amendment No. 3 revises authorized contents to include: pressurized water reactor (PWR) damaged fuel contained in damaged fuel cans that are placed in a damaged fuel basket assembly; PWR fuel assemblies with nonfuel hardware per the expanded definition in the Amendment No. 3 application; and PWR fuel assemblies with up to five activated stainless steel fuel replacement rods at a maximum burnup/exposure of 32.5 gigawatt days per metric ton of uranium (GWd/MTU). Additionally, Amendment No. 3 revises paragraph 4.3.1(i) in Appendix A of the CoC Technical Specifications (TS) to clarify that the maximum design basis earthquake accelerations of 0.37g in the horizontal direction (without cask sliding) and 0.25g in the vertical direction at the independent spent fuel storage installation (ISFSI) pad top surface do not result in cask tip-over. Amendment No. 3 also makes additional changes to Appendix A, Technical Specifications and Design Features for the MAGNASTOR® System, and Appendix B, Approved Contents for the MAGNASTOR® System, of the CoC.
2013-04-16; vol. 78 # 73 - Tuesday, April 16, 201378 FR 22411 - List of Approved Spent Fuel Storage Casks: HI-STORM 100, Amendment No. 8; Corrections
typeregulations.gov FR Doc.2013-08889 RIN3150-AJ05 NRC-2011-0221 NUCLEAR REGULATORY COMMISSION Final rule; correcting amendments. This rule is effective May 16, 2013. 10 CFR Part 72 SummaryOn February 17, 2012 (77 FR 9515), the U.S. Nuclear Regulatory Commission (NRC) published a direct final rule amending its spent fuel storage regulations by revising the Holtec International, Inc. (Holtec) HI-STORM 100 Cask System listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 8 to Certificate of Compliance (CoC) No. 1014. The direct final rule was effective on May 2, 2012 (77 FR 24585; April 25, 2012). The NRC has made non-substantive corrections to the technical specifications (TS) and the NRC&apos;s Safety Evaluation Report (SER) for the Holtec HI-STORM 100 Cask System, Amendment No. 8. The purpose of this document is to provide notification that the NRC is amending its regulations by revising the Holtec HI-STORM 100 Cask System listing within the “List of Approved Spent Fuel Storage Casks” to include notification that Amendment No. 8 to CoC No. 1014 was corrected on November 16, 2012.
2013-03-18; vol. 78 # 52 - Monday, March 18, 201378 FR 16601 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System
typeregulations.gov FR Doc.2013-06015 RIN3150-AJ22 NRC-2012-0308 NUCLEAR REGULATORY COMMISSION Direct final rule. The final rule is effective June 3, 2013, unless significant adverse comments are received by April 17, 2013. If the rule is withdrawn as a result of such comments, timely notice of the withdrawal will be published in the Federal Register . Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. (NAC) Modular Advanced Generation Nuclear All-purpose Storage (MAGNASTOR®) System listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 3 to Certificate of Compliance (CoC) No. 1031. Amendment No. 3 revises authorized contents to include: Pressurized water reactor (PWR) damaged fuel contained in damaged fuel (DF) cans that are placed in a damaged fuel basket assembly; PWR fuel assemblies with nonfuel hardware per the expanded definition in the Amendment No. 3 application; and PWR fuel assemblies with up to five activated stainless steel fuel replacement rods at a maximum burnup/exposure of 32.5 gigawatt days per metric ton of uranium (GWd/MTU). Additionally, Amendment No. 3 revises paragraph 4.3.1(i) in appendix A of the CoC Technical Specifications (TS) to clarify that the maximum design basis earthquake accelerations of 0.37g in the horizontal direction (without cask sliding) and 0.25g in the vertical direction at the independent spent fuel storage installation (ISFSI) pad top surface do not result in cask tip-over. Amendment No. 3 also makes additional changes to appendix A, Technical Specifications and Design Features for the MAGNASTOR® System, and appendix B, Approved Contents for the MAGNASTOR® System, of the CoC.
This is a list of United States Code sections, Statutes at Large, Public Laws, and Presidential Documents, which provide rulemaking authority for this CFR Part.This list is taken from the Parallel Table of Authorities and Rules provided by GPO [Government Printing Office].It is not guaranteed to be accurate or up-to-date, though we do refresh the database weekly. More limitations on accuracy are described at the GPO site.United States CodeU.S.C. : Title 42 - THE PUBLIC HEALTH AND WELFARE§ 2021 - Cooperation with States§ 2071 - Determination of other material as special nuclear material; Presidential assent; effective date§ 2073 - Domestic distribution of special nuclear material§ 2077 - Unauthorized dealings in special nuclear material§ 2092 - License requirements for transfers§ 2093 - Domestic distribution of source material§ 2095 - Reports§ 2099 - Prohibitions against issuance of license§ 2111 - Domestic distribution§ 2201 - General duties of Commission§ 2232 - License applications§ 2233 - Terms of licenses§ 2234 - Inalienability of licenses§ 2236 - Revocation of licenses§ 2238 - Continued operation of facilities§ 2239 - Hearings and judicial review§ 2282 - Civil penalties§ 4332 - Cooperation of agencies; reports; availability of information; recommendations; international and national coordination of efforts§ 5841 - Establishment and transfers§ 5842 - Licensing and related regulatory functions respecting selected Administration facilities§ 5846 - Compliance with safety regulations§ 5851 - Employee protection§ 10101 - Definitions§ 10102 - Separability§ 10103 - Territories and possessions§ 10104 - Ocean disposal§ 10105 - Limitation on spending authority§ 10106 - Protection of classified national security information§ 10107 - Applicability to atomic energy defense activities§ 10108 - Applicability to transportation§ 10137 - Consultation with States and affected Indian tribes§ 10151 - Findings and purposes§ 10152 - Available capacity for interim storage of spent nuclear fuel§ 10153 - Interim at-reactor storage§ 10154 - Licensing of facility expansions and transshipments§ 10155 - Storage of spent nuclear fuel§ 10157 - Transportation§ 10161 - Monitored retrievable storage§ 10162 - Authorization of monitored retrievable storage§ 10165 - Site selection§ 10168 - Construction authorization§ 10198 - Research and development on spent nuclear fuel
Title 10 published on 2013-01-01The following are ALL rules, proposed rules, and notices (chronologically) published in the Federal Register relating to 10 CFR 72 after this date.2013-06-25; vol. 78 # 122 - Tuesday, June 25, 201378 FR 37927 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System
2013-03-29; vol. 78 # 61 - Friday, March 29, 201378 FR 19148 - Shielding and Radiation Protection Review Effort and Licensing Conditions for Dry Storage Applications
typeregulations.gov FR Doc.2013-06387 RIN NRC-2013-0051 NUCLEAR REGULATORY COMMISSION Draft interim staff guidance; request for public comment. Submit comments by May 13, 2013. Comments received after this date will be considered, if it is practical to do so; however, the NRC staff is only able to ensure consideration of comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) requests public comment on Draft Spent Fuel Storage and Transportation Interim Staff Guidance No. 26A (SFST-ISG-26A), Revision 0, “Shielding and Radiation Protection Review Effort and Licensing Conditions for 10 CFR Part 72 Applications.”
78 FR 16619 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System
typeregulations.gov FR Doc.2013-06016 RIN3150-AJ22 NRC-2012-0308 NUCLEAR REGULATORY COMMISSION Proposed rule. Submit comments by April 17, 2013. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the NAC International, Inc., Modular Advanced Generation Nuclear All-purpose Storage (MAGNASTOR®) Cask System listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 3 to Certificate of Compliance (CoC) No. 1031. Amendment No. 3 includes changes that would revise authorized contents to include: pressurized water reactor (PWR) damaged fuel contained in damaged fuel cans that are placed in a damaged fuel basket assembly; PWR fuel assemblies with nonfuel hardware per the expanded definition in the Amendment No. 3 application; and PWR fuel assemblies with up to five activated stainless steel fuel replacement rods at a maximum burnup/exposure of 32.5 gigawatt days per metric ton of uranium (GWd/MTU). Additionally, Amendment No. 3 would revise paragraph 4.3.1(i) in appendix A of the CoC Technical Specifications (TS), to clarify that the maximum design basis earthquake accelerations of 0.37g in the horizontal direction (without cask sliding) and 0.25g in the vertical direction at the independent spent fuel storage installation pad top surface do not result in cask tip-over. Amendment No. 3 would make additional changes to appendix A, Technical Specifications and Design Features for the MAGNASTOR® System, and appendix B, Approved Contents for the MAGNASTOR® System, of the CoC TS.
2013-02-05; vol. 78 # 24 - Tuesday, February 5, 201378 FR 8050 - Spent Fuel Cask Certificate of Compliance Format and Content
typeregulations.gov FR Doc.2013-02477 RIN Docket No.PRM-72-7 NRC-2012-0266 NUCLEAR REGULATORY COMMISSION Petition for rulemaking; receipt and request for comment. Submit comments by April 22, 2013. Comments received after this date will be considered if it is practical to do so, but the NRC is able to assure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is publishing for public comment a notice of receipt for a petition for rulemaking (PRM), dated October 3, 2012, which was filed with the NRC by Anthony R. Pietrangelo on behalf of the Nuclear Energy Institute (NEI or the petitioner). The petition was docketed by the NRC on October 18, 2012, and assigned Docket No. PRM-72-7. The petitioner requests that the NRC add a new rule that governs the format and content of spent fuel storage cask Certificates of Compliance (CoCs), extend the backfit rule to CoCs, and make other improvements that result in “more efficient and effective NRC oversight of dry cask storage activities as well as improved implementation of dry cask storage requirements by industry.”