10 CFR Part 50 - DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
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General Provisions
- § 50.1 — Basis, purpose, and procedures applicable.
- § 50.2 — Definitions.
- § 50.3 — Interpretations.
- § 50.4 — Written communications.
- § 50.5 — Deliberate misconduct.
- § 50.7 — Employee protection.
- § 50.8 — Information collection requirements: OMB approval.
- § 50.9 — Completeness and accuracy of information.
- Requirement of License, Exceptions
- Classification and Description of Licenses
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Applications for Licenses, Certifications, and Regulatory Approvals; Form; Contents; Ineligibility of Certain Applicants
- § 50.30 — Filing of application; oath or affirmation.
- § 50.31 — Combining applications.
- § 50.32 — Elimination of repetition.
- § 50.33 — Contents of applications; general information.
- § 50.34 — Contents of applications; technical information.
- § 50.34a — Design objectives for equipment to control releases of radioactive material in effluents—nuclear power reactors.
- § 50.35 — Issuance of construction permits. 1
- § 50.36 — Technical specifications.
- § 50.36a — Technical specifications on effluents from nuclear power reactors.
- § 50.36b — Environmental conditions.
- § 50.37 — Agreement limiting access to Classified Information.
- § 50.38 — Ineligibility of certain applicants.
- § 50.39 — Public inspection of applications.
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Standards for Licenses, Certifications, and Regulatory Approvals
- § 50.40 — Common standards.
- § 50.41 — Additional standards for class 104 licenses.
- § 50.42 — Additional standard for class 103 licenses.
- § 50.43 — Additional standards and provisions affecting class 103 licenses and certifications for commercial power.
- § 50.44 — Combustible gas control for nuclear power reactors.
- § 50.45 — Standards for construction permits, operating licenses, and combined licenses.
- § 50.46 — Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors.
- § 50.46a — Acceptance criteria for reactor coolant system venting systems.
- § 50.47 — Emergency plans.
- § 50.48 — Fire protection.
- § 50.49 — Environmental qualification of electric equipment important to safety for nuclear power plants.
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Issuance, Limitations, and Conditions of Licenses and Construction Permits
- § 50.50 — Issuance of licenses and construction permits.
- § 50.51 — Continuation of license.
- § 50.52 — Combining licenses.
- § 50.53 — Jurisdictional limitations.
- § 50.54 — Conditions of licenses.
- § 50.55 — Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses.
- § 50.55a — Codes and standards.
- § 50.56 — Conversion of construction permit to license; or amendment of license.
- § 50.57 — Issuance of operating license. 1
- § 50.58 — Hearings and report of the Advisory Committee on Reactor Safeguards.
- § 50.59 — Changes, tests, and experiments.
- § 50.60 — Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation.
- § 50.61 — Fracture toughness requirements for protection against pressurized thermal shock events.
- § 50.61a — Alternate fracture toughness requirements for protection against pressurized thermal shock events.
- § 50.62 — Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants.
- § 50.63 — Loss of all alternating current power.
- § 50.64 — Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.
- § 50.65 — Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
- § 50.66 — Requirements for thermal annealing of the reactor pressure vessel.
- § 50.67 — Accident source term.
- § 50.68 — Criticality accident requirements.
- § 50.69 — Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
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Inspections, Records, Reports, Notifications
- § 50.70 — Inspections.
- § 50.71 — Maintenance of records, making of reports.
- § 50.72 — Immediate notification requirements for operating nuclear power reactors.
- § 50.73 — Licensee event report system.
- § 50.74 — Notification of change in operator or senior operator status.
- § 50.75 — Reporting and recordkeeping for decommissioning planning.
- § 50.75 — Reporting and recordkeeping for decommissioning planning.
- § 50.76 — Licensee's change of status; financial qualifications.
- US/IAEA Safeguards Agreement
- Transfers of Licenses - Creditors' Rights—Surrender of Licenses
- § 50.83 — Release of part of a power reactor facility or site for unrestricted use.
- Amendment of License or Construction Permit at Request of Holder
- Revocation, Suspension, Modification, Amendment of Licenses and Construction Permits, Emergency Operations by the Commission
- Backfitting
- Enforcement
- Additional Standards for Licenses, Certifications, and Regulatory Approvals
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.
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.
§ 2131 - License required
§ 2132 - Utilization and production facilities for industrial or commercial purposes
§ 2133 - Commercial licenses
§ 2134 - Medical, industrial, and commercial licenses
§ 2135 - Antitrust provisions governing licenses
§ 2138 - Suspension of licenses during war or national emergency
§ 2152 - Policies contained in international arrangements
§ 2201 - General duties of Commission
§ 2232 - License applications
§ 2233 - Terms of licenses
§ 2234 - Inalienability of licenses
§ 2236 - Revocation of licenses
§ 2237 - Modification of license
§ 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
§ 5844 - Office of Nuclear Safety and Safeguards
§ 5846 - Compliance with safety regulations
§ 3504 note - Authority and functions of Director
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 50 after this date.
GPO FDSys XML | Text type regulations.gov FR Doc. 2013-08216 RIN 3150-AJ08 NRC-2011-0299 NUCLEAR REGULATORY COMMISSION Draft regulatory basis and draft rule concepts; request for comment. Submit comments by May 28, 2013. Comments received after this date 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 this date. 10 CFR Parts 50 and 52 The U.S. Nuclear Regulatory Commission (NRC) is requesting comment on the draft regulatory basis document to support the potential amendment of its regulations concerning nuclear power plant licensees' station blackout mitigation strategies. Appendix A of the draft regulatory basis provides a discussion of rule language concepts that the NRC staff is considering for this potential rulemaking. In addition, Appendix A contains a set of questions soliciting stakeholder feedback in areas that would support the NRC staff in developing a proposed rule. The issuance of this draft regulatory basis document is one of the actions stemming from the NRC's lessons-learned efforts associated with the March 2011 Fukushima Dai-ichi Nuclear Power Plant accident in Japan.
GPO FDSys XML | Text type regulations.gov FR Doc. 2012-31706 RIN 3150-AJ11 NRC-2012-0031 NUCLEAR REGULATORY COMMISSION Draft regulatory basis. Submit comments by February 22, 2013. Comments received after this date 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 this date. 10 CFR Parts 50 & 52 The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing a draft regulatory basis document to support the potential amendment of its regulations concerning nuclear power plant licensees' onsite emergency response capabilities. The NRC is seeking public comments on this document. The issuance of this draft regulatory basis document is one of the actions stemming from the NRC's lessons-learned efforts associated with the March 2011 Fukushima Dai-ichi Nuclear Power Plant accident in Japan.
GPO FDSys XML | Text 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 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.