Home/CFR/Title 10/Part 72
FEDERAL · 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

109 sections · Title 10: Energy

§ 72.1Purpose.
§ 72.2Scope.
§ 72.3Definitions.
§ 72.4Communications.
§ 72.5Interpretations.
§ 72.6License required; types of licenses.
§ 72.7Specific exemptions.
§ 72.8Denial of licensing by Agreement States.
§ 72.9Information collection requirements: OMB approval.
§ 72.10Employee protection.
§ 72.11Completeness and accuracy of information.
§ 72.12Deliberate misconduct.
§ 72.13Applicability.
§ 72.16Filing of application for specific license.
§ 72.18Elimination of repetition.
§ 72.20Public inspection of application.
§ 72.22Contents of application: General and financial information.
§ 72.24Contents of application: Technical information.
§ 72.26Contents of application: Technical specifications.
§ 72.28Contents of application: Applicant's technical qualifications.
§ 72.30Financial assurance and recordkeeping for decommissioning.
§ 72.32Emergency Plan.
§ 72.34Environmental report.
§ 72.40Issuance of license.
§ 72.42Duration of license; renewal.
§ 72.44License conditions.
§ 72.46Public hearings.
§ 72.48Changes, tests, and experiments.
§ 72.50Transfer of license.
§ 72.52Creditor regulations.
§ 72.54Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas.
§ 72.56Application for amendment of license.
§ 72.58Issuance of amendment.
§ 72.60Modification, revocation, and suspension of license.
§ 72.62Backfitting.
§ 72.70Safety analysis report updating.
§ 72.72Material balance, inventory, and records requirements for stored materials.
§ 72.74Reports of accidental criticality or loss of special nuclear material.
§ 72.75Reporting requirements for specific events and conditions.
§ 72.76Material status reports.
§ 72.78Nuclear material transaction reports.
§ 72.79Facility information and verification.
§ 72.80Other records and reports.
§ 72.82Inspections and tests.
§ 72.84Violations.
§ 72.86Criminal penalties.
§ 72.90General considerations.
§ 72.92Design basis external natural events.
§ 72.94Design basis external man-induced events.
§ 72.96Siting limitations.
§ 72.98Identifying regions around an ISFSI or MRS site.
§ 72.100Defining potential effects of the ISFSI or MRS on the region.
§ 72.102Geological and seismological characteristics for applications before October 16, 2003 and applications for other than dry cask modes of storage.
§ 72.103Geological and seismological characteristics for applications for dry cask modes of storage on or after October 16, 2003.
§ 72.104Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS.
§ 72.106Controlled area of an ISFSI or MRS.
§ 72.108Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation.
§ 72.120General considerations.
§ 72.122Overall requirements.
§ 72.124Criteria for nuclear criticality safety.
§ 72.126Criteria for radiological protection.
§ 72.128Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste, and other radioactive waste storage and handling.
§ 72.130Criteria for decommissioning.
§ 72.140Quality assurance requirements.
§ 72.142Quality assurance organization.
§ 72.144Quality assurance program.
§ 72.146Design control.
§ 72.148Procurement document control.
§ 72.150Instructions, procedures, and drawings.
§ 72.152Document control.
§ 72.154Control of purchased material, equipment, and services.
§ 72.156Identification and control of materials, parts, and components.
§ 72.158Control of special processes.
§ 72.160Licensee and certificate holder inspection.
§ 72.162Test control.
§ 72.164Control of measuring and test equipment.
§ 72.166Handling, storage, and shipping control.
§ 72.168Inspection, test, and operating status.
§ 72.170Nonconforming materials, parts, or components.
§ 72.172Corrective action.
§ 72.174Quality assurance records.
§ 72.176Audits.
§ 72.180Physical protection plan.
§ 72.182Design for physical protection.
§ 72.184Safeguards contingency plan.
§ 72.186Change to physical security and safeguards contingency plans.
§ 72.190Operator requirements.
§ 72.192Operator training and certification program.
§ 72.194Physical requirements.
§ 72.200Provision of MRS information.
§ 72.202Participation in license reviews.
§ 72.204Notice to States.
§ 72.206Representation.
§ 72.210General license issued.
§ 72.212Conditions of general license issued under § 72.210.
§ 72.214List of approved spent fuel storage casks.
§ 72.216§ 72.216 [Reserved]
§ 72.218Termination of licenses.
§ 72.220Violations.
§ 72.230Procedures for spent fuel storage cask submittals.
§ 72.232Inspection and tests.
§ 72.234Conditions of approval.
§ 72.236Specific requirements for spent fuel storage cask approval and fabrication.
§ 72.238Issuance of an NRC Certificate of Compliance.
§ 72.240Conditions for spent fuel storage cask renewal.
§ 72.242Recordkeeping and reports.
§ 72.244Application for amendment of a certificate of compliance.
§ 72.246Issuance of amendment to a certificate of compliance.
§ 72.248Safety analysis report updating.