Part 72 — Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste
Subpart A — General Provisions
- § 72.1— Purpose.
- § 72.2— Scope.
- § 72.3— Definitions.
- § 72.4— Communications.
- § 72.5— Interpretations.
- § 72.6— License required; types of licenses.
- § 72.7— Specific exemptions.
- § 72.8— Denial of licensing by Agreement States.
- § 72.9— Information collection requirements: OMB approval.
- § 72.10— Employee protection.
- § 72.11— Completeness and accuracy of information.
- § 72.12— Deliberate misconduct.
- § 72.13— Applicability.
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.
- § 72.32— Emergency Plan.
- § 72.34— Environmental report.
Subpart C — Issuance and Conditions of License
- § 72.40— Issuance of license.
- § 72.42— Duration of license; renewal.
- § 72.44— License conditions.
- § 72.46— Public hearings.
- § 72.48— Changes, tests, and experiments.
- § 72.50— Transfer of license.
- § 72.52— Creditor regulations.
- § 72.54— Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas.
- § 72.56— Application for amendment of license.
- § 72.58— Issuance of amendment.
- § 72.60— Modification, revocation, and suspension of license.
- § 72.62— Backfitting.
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.
- § 72.82— Inspections and tests.
- § 72.84— Violations.
- § 72.86— Criminal penalties.
Subpart E — Siting Evaluation Factors
- § 72.90— General considerations.
- § 72.92— Design basis external natural events.
- § 72.94— Design basis external man-induced events.
- § 72.96— Siting limitations.
- § 72.98— Identifying regions around an ISFSI or MRS site.
- § 72.100— Defining potential effects of the ISFSI or MRS on the region.
- § 72.102— Geological and seismological characteristics for applications before October 16, 2003 and applications for other than dry cask modes of storage.
- § 72.103— Geological and seismological characteristics for applications for dry cask modes of storage on or after October 16, 2003.
- § 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, high-level radioactive waste, or reactor-related greater than Class C waste transportation.
Subpart F — General Design Criteria
- § 72.120— General considerations.
- § 72.122— Overall requirements.
- § 72.124— Criteria for nuclear criticality safety.
- § 72.126— Criteria for radiological protection.
- § 72.128— Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste, and other radioactive waste storage and handling.
- § 72.130— Criteria for decommissioning.
Subpart G — Quality Assurance
- § 72.140— Quality assurance requirements.
- § 72.142— Quality assurance organization.
- § 72.144— Quality assurance program.
- § 72.146— Design control.
- § 72.148— Procurement document control.
- § 72.150— Instructions, procedures, and drawings.
- § 72.152— Document control.
- § 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.
- § 72.162— Test control.
- § 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.
- § 72.172— Corrective action.
- § 72.174— Quality assurance records.
- § 72.176— Audits.
Subpart H — Physical Protection
Subpart I — Training and Certification of Personnel
Subpart J — Provision of MRS Information to State Governments and Indian Tribes
Subpart K — General License for Storage of Spent Fuel at Power Reactor Sites
Subpart L — Approval of Spent Fuel Storage Casks
- § 72.230— Procedures for spent fuel storage cask submittals.
- § 72.232— Inspection and tests.
- § 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.