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

Authority:

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).

Section 72.96(d) also issued under sec. 145(g), Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10165(g)).

Subpart J also issued under secs. 2(2), 2(15), 2(19), 117(a), 141(h), Pub. L. 97-425, 96 Stat. 2202, 2203, 2204, 2222, 2224 (42 U.S.C. 10101, 10137(a), 10161(h)).

Subparts K and L are also issued under sec. 133, 98 Stat. 2230 (42 U.S.C. 10153) and sec. 218(a), 96 Stat. 2252 (42 U.S.C. 10198).

Source:

53 FR 31658, Aug. 19, 1988, unless otherwise noted.

Title 10 published on 2013-01-01

The 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.

2013-04-16; vol. 78 # 73 - Tuesday, April 16, 2013

78 FR 22411 - List of Approved Spent Fuel Storage Casks: HI-STORM 100, Amendment No. 8; Corrections

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2013-08889
RIN	3150-AJ05
	NRC-2011-0221

NUCLEAR REGULATORY COMMISSION

Final rule; correcting amendments.

This rule is effective May 16, 2013.

10 CFR Part 72

Summary

On 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'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, 2013

78 FR 16601 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2013-06015
RIN	3150-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

Summary

The 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.

2013-01-04; vol. 78 # 3 - Friday, January 4, 2013

78 FR 663 - Decommissioning Planning During Operations

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2012-31705
RIN	3150-AI55
	NRC-2011-0286

NUCLEAR REGULATORY COMMISSION

Regulatory guide; issuance.

10 CFR Parts 20, 30, 40, 50, 70, and 72

Summary

The U.S. Nuclear Regulatory Commission (NRC) is issuing a new regulatory guide (RG) 4.22, “Decommissioning Planning During Operations.” The guide describes a method that the NRC staff considers acceptable for use by holders of licenses in complying with the NRC's Decommissioning Planning Rule (DPR) (76 FR 35512; June 17, 2011). The DPR went into effect on December 17, 2012, and is intended to minimize the likelihood of new “legacy sites,” which are NRC-licensed facilities with insufficient resources to complete decommissioning activities and termination of a license at the end of operations.

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

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

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

United States Code

U.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

USC : Title 44 - PUBLIC PRINTING AND DOCUMENTS

§ 3504 note - Authority and functions of Director

Statutes at Large

119 Stat. 594

Title 10 published on 2013-01-01

The following are ALL rules, proposed rules, and notices (chronologically) published in the Federal Register relating to 10 CFR 72 after this date.

2013-04-16; vol. 78 # 73 - Tuesday, April 16, 2013

78 FR 22411 - List of Approved Spent Fuel Storage Casks: HI-STORM 100, Amendment No. 8; Corrections

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2013-08889
RIN	3150-AJ05
	NRC-2011-0221

NUCLEAR REGULATORY COMMISSION

Final rule; correcting amendments.

This rule is effective May 16, 2013.

10 CFR Part 72

Summary

On 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'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.

2013-03-29; vol. 78 # 61 - Friday, March 29, 2013

78 FR 19148 - Shielding and Radiation Protection Review Effort and Licensing Conditions for Dry Storage Applications

GPO FDSys XML | Text

Additional Documents

type	regulations.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

Summary

The 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.”

2013-03-18; vol. 78 # 52 - Monday, March 18, 2013

78 FR 16601 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2013-06015
RIN	3150-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

Summary

The 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.

78 FR 16619 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2013-06016
RIN	3150-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

Summary

The 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, 2013

78 FR 8050 - Spent Fuel Cask Certificate of Compliance Format and Content

GPO FDSys XML | Text

Additional Documents

type	regulations.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

Summary

The 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.”

2013-01-17; vol. 78 # 12 - Thursday, January 17, 2013

78 FR 3853 - Retrievability, Cladding Integrity and Safe Handling of Spent Fuel at an Independent Spent Fuel Storage Installation and During Transportation

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2013-00478
RIN
	NRC-2013-0004

NUCLEAR REGULATORY COMMISSION

Request for comments for potential rulemaking.

Submit comments by March 18, 2013. Comments received after the comment period deadline will be considered if it is practical to do so, but the NRC is only able to ensure consideration of comments received on or before the end of the public comment period.

10 CFR Parts 71 and 72

Summary

The regulations for packaging and transport of spent nuclear fuel are separate from requirements for storage of spent nuclear fuel. Because these regulatory schemes are separate, there is no requirement that loaded storage casks also meet transportation requirements. Integration of storage and transport regulations could enable a more predictable transition from storage to transport by potentially minimizing future handling of spent fuel and uncertainty as to whether loaded storage casks may be transported from the storage location. As part of its evaluation of integration and compatibility between storage and transportation regulations, the U.S. Nuclear Regulatory Commission (NRC) staff is reviewing its policies, regulations, guidance, and technical needs in several key areas, such as: retrievability, cladding integrity, and safe handling of spent fuel; criticality safety features and requirements for spent fuel transportation; and aging management and qualification of dual-purpose canisters and components after long-term storage. The NRC staff is reviewing the potential policy issues and requirements related to retrievability, cladding integrity, and safe handling of spent fuel as the lead issue for evaluating compatibility of storage and transportation regulations. As part of its evaluation of integration and compatibility between NRC's storage regulations and transportation regulations, the NRC is issuing this request for comment (available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML12293A434) as the staff begins its review of NRC policies, guidance, and technical needs related to retrievability, cladding integrity, and safe handling of spent fuel.

2013-01-04; vol. 78 # 3 - Friday, January 4, 2013

78 FR 663 - Decommissioning Planning During Operations

GPO FDSys XML | Text

Additional Documents

type	regulations.gov
FR Doc.	2012-31705
RIN	3150-AI55
	NRC-2011-0286

NUCLEAR REGULATORY COMMISSION

Regulatory guide; issuance.

10 CFR Parts 20, 30, 40, 50, 70, and 72

Summary

The U.S. Nuclear Regulatory Commission (NRC) is issuing a new regulatory guide (RG) 4.22, “Decommissioning Planning During Operations.” The guide describes a method that the NRC staff considers acceptable for use by holders of licenses in complying with the NRC's Decommissioning Planning Rule (DPR) (76 FR 35512; June 17, 2011). The DPR went into effect on December 17, 2012, and is intended to minimize the likelihood of new “legacy sites,” which are NRC-licensed facilities with insufficient resources to complete decommissioning activities and termination of a license at the end of operations.

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

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