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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Subpart A—General Provisions
Sec.
72.6 License required; types of licenses.
72.8 Denial of licensing by Agreement States.
72.9 Information collection requirements: OMB approval.
72.11 Completeness and accuracy of information.
Subpart B—License Application, Form, and Contents
72.16 Filing of application for specific license.
72.18 Elimination of repetition.
72.20 Public inspection of application.
72.22 Contents of application: General and financial information.
72.24 Contents of application: Technical information.
72.26 Contents of application: Technical specifications.
72.28 Contents of application: Applicant's technical qualifications.
72.30 Financial assurance and recordkeeping for decommissioning.
Subpart C—Issuance and Conditions of License
72.42 Duration of license; renewal.
72.48 Changes, tests, and experiments.
72.56 Application for amendment of license.
72.60 Modification, revocation, and suspension of license.
Subpart D—Records, Reports, Inspections, and Enforcement
72.70 Safety analysis report updating.
72.72 Material balance, inventory, and records requirements for stored materials.
72.74 Reports of accidental criticality or loss of special nuclear material.
72.75 Reporting requirements for specific events and conditions.
72.76 Material status reports.
72.78 Nuclear material transaction reports.
72.79 Facility information and verification.
72.80 Other records and reports.
Subpart E—Siting Evaluation Factors
72.92 Design basis external natural events.
72.94 Design basis external man-induced events.
72.98 Identifying regions around an ISFSI or MRS site.
72.100 Defining potential effects of the ISFSI or MRS on the region.
72.104 Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.
72.106 Controlled area of an ISFSI or MRS.
72.108 Spent fuel for high-level radioactive waste transportation.
Subpart F—General Design Criteria
72.120 General considerations.
72.124 Criteria for nuclear criticality safety.
72.126 Criteria for radiological protection.
72.130 Criteria for decommissioning.
Subpart G—Quality Assurance
72.140 Quality assurance requirements.
72.142 Quality assurance organization.
72.144 Quality assurance program.
72.148 Procurement document control.
72.150 Instructions, procedures, and drawings.
72.154 Control of purchased material, equipment, and services.
72.156 Identification and control of materials, parts, and components.
72.158 Control of special processes.
72.160 Licensee and certificate holder inspection.
72.164 Control of measuring and test equipment.
72.166 Handling, storage, and shipping control.
72.168 Inspection, test, and operating status.
72.170 Nonconforming materials, parts, or components.
72.174 Quality assurance records.
Subpart H—Physical Protection
72.180 Physical protection plan.
72.182 Design for physical protection.
72.184 Safeguards contingency plan.
72.186 Change to physical security and safeguards contingency plans.
Subpart I—Training and Certification of Personnel
72.192 Operator training and certification program.
Subpart J—Provision of MRS Information to State Governments and Indian Tribes
72.200 Provision of MRS information.
72.202 Participation in license reviews.
Subpart K—General License for Storage of Spent Fuel at Power Reactor Sites
72.210 General license issued.
72.212 Conditions of general license issued under § 72.210.
72.214 List of approved spent fuel storage casks.
72.218 Termination of licenses.
Subpart L—Approval of Spent Fuel Storage Casks
72.230 Procedures for spent fuel storage cask submittals.
72.234 Conditions of approval.
72.236 Specific requirements for spent fuel storage cask approval and fabrication.
72.238 Issuance of an NRC Certificate of Compliance.
72.240 Conditions for spent fuel storage cask renewal.
72.242 Recordkeeping and reports.
72.244 Application for amendment of a certificate of compliance.
72.246 Issuance of amendment to a certificate of compliance.
72.248 Safety analysis report updating.
Authority: Atomic Energy Act secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C. 2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy Reorganization Act sec. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); National Environmental Policy Act sec. 102 (42 U.S.C. 4332); Nuclear Waste Policy Act secs. 131, 132, 133, 135, 137, 141, 148 (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. 109–58, 119 Stat. 549 (2005).
Section 72.44(g) also issued under secs. Nuclear Waste Policy Act 142(b) and 148(c), (d) (42 U.S.C. 10162(b), 10168(c), (d)). Section 72.46 also issued under Atomic Energy Act sec. 189 (42 U.S.C. 2239); Nuclear Waste Policy Act sec. 134 (42 U.S.C. 10154). Section 72.96(d) also issued under Nuclear Waste Policy Act sec. 145(g) (42 U.S.C. 10165(g)). Subpart J also issued under Nuclear Waste Policy Act secs. 117(a), 141(h) (42 U.S.C. 10137(a), 10161(h)). Subpart K is also issued under sec. 218(a) (42 U.S.C. 10198).
Source: 53 FR 31658, Aug. 19, 1988, unless otherwise noted.
[73 FR 32463, Jun. 9, 2008; 73 FR 78607, Dec. 23, 2008; 73 FR 63572, Oct. 24, 2008; 76 FR 8891, Feb. 16, 2011; 77 FR 39908, Jul. 6, 2012]