Nuclear Energy Regulation

Nuclear energy regulation in the United States — governed by the Atomic Energy Act of 1954 (42 U.S.C. §§ 2011–2297) and administered by the Nuclear Regulatory Commission (NRC) — is one of the most stringent regulatory frameworks in American law, reflecting the unique hazards of nuclear fission: radiation exposure, meltdown risk, and radioactive waste that remains hazardous for thousands of years. The NRC licenses and inspects all 93 commercial nuclear reactors currently operating across 28 states, which generate approximately 19% of U.S. electricity (and roughly 50% of U.S. carbon-free electricity), under licenses that originally ran 40 years and can be renewed for 20-year extensions. The NRC's licensing process — requiring an operating license, periodic safety reviews, and detailed emergency planning for a 10-mile emergency planning zone — was designed for large light-water reactors and is now being reformed to accommodate advanced reactor designs including small modular reactors (SMRs), microreactors, and Generation IV reactor technologies that differ fundamentally from existing plants. The ADVANCE Act (2024) streamlined NRC licensing timelines and authorized the NRC to license U.S. reactors abroad. Nuclear power is experiencing a policy renaissance driven by climate goals: the Biden and Trump administrations both supported nuclear expansion, and companies including Microsoft, Google, and Amazon have signed power purchase agreements with existing nuclear plants and new SMR developers to meet data center electricity demand. The Price-Anderson Act (42 U.S.C. § 2210) caps nuclear liability at approximately $14 billion — a federal backstop essential for commercial nuclear investment.

Current Law (2026)

Legal Authority

• 42 U.S.C. § 2011-2013 — Congressional findings, purpose (development and utilization of atomic energy for peaceful purposes; program of federal regulation to protect health and safety and the common defense and security)
• 42 U.S.C. § 2073-2077 — Special nuclear material (NRC controls domestic distribution, licenses, and unauthorized dealings in special nuclear material — enriched uranium and plutonium; the materials used in nuclear reactors and weapons)
• 42 U.S.C. § 2131-2139 — Licensing of nuclear facilities (no person may construct or operate a nuclear utilization or production facility except under license from NRC; commercial licenses for power reactors; medical, industrial, and research licenses; antitrust review; operator licensing; classes of facilities; emergency suspension authority)
• 42 U.S.C. § 2201 — General duties of the Commission (NRC authority to establish standards for protection of health and minimize danger to life and property; inspect licensed facilities; issue regulations; conduct investigations; control possession and use of nuclear material)
• 42 U.S.C. § 2210 — Price-Anderson Act indemnification (establishes liability framework for nuclear incidents; operators must maintain private insurance + participate in retrospective assessment pool; total coverage ~$13.6 billion; federal government indemnifies beyond that amount; channeling of liability to the operator; limitation on liability)
• 42 U.S.C. § 2232 — License applications (applications for construction permits and operating licenses must be reviewed by NRC staff; Advisory Committee on Reactor Safeguards review; public notice and opportunity for hearing)
• 42 U.S.C. § 2239 — Hearings and judicial review (NRC must grant a hearing upon request for any proceeding on granting, suspending, or revoking a license; mandatory hearing for construction permits; judicial review in courts of appeals)
• 42 U.S.C. § 2282 — Civil penalties (NRC may impose civil penalties up to $399,120 per violation per day for any person who violates the Act, NRC regulations, or license conditions)

Implementing Regulations (10 CFR — NRC)

• 10 CFR Part 50 — Domestic licensing of production and utilization facilities: the core reactor licensing regulation — construction permits, operating licenses, technical specifications, safety standards, environmental qualification, fire protection, emergency planning

• 10 CFR Part 52 — Licenses, certifications, and approvals for nuclear power plants: Combined License (COL) process, Early Site Permits, Design Certifications, Standard Design Approvals — the streamlined licensing framework for new reactors

• 10 CFR Part 20 — Standards for protection against radiation: dose limits for workers (5 rem/year total effective dose equivalent) and the public (100 mrem/year), ALARA principle, monitoring, waste disposal, surveys

• 10 CFR Part 50.46 — Emergency core cooling system (ECCS) performance criteria: peak cladding temperature limits, maximum oxidation, coolable geometry — the technical safety requirements at the heart of light-water reactor design

• 10 CFR Part 54 — License renewal: requirements for extending reactor operating licenses from 40 to 60 years (initial renewal) and 60 to 80 years (subsequent renewal); aging management programs, environmental review

• 10 CFR Part 53 — Risk-informed, technology-inclusive framework for advanced reactors: new licensing pathway for non-light-water designs (SMRs, molten salt, gas-cooled); alternative to traditional deterministic requirements

• 10 CFR Part 70 — Domestic licensing of special nuclear material: possession, use, and transfer of enriched uranium and plutonium; criticality safety, material control and accounting

• 10 CFR Part 73 — Physical protection of plants and materials: security requirements for nuclear power plants, armed guard force, access authorization, cybersecurity, design basis threat

• 10 CFR Part 100 — Reactor site criteria: siting factors including seismology, geology, hydrology, meteorology, population density, and emergency planning zone requirements

• 10 CFR Part 1 — NRC organization: structure and functions of NRC offices including the Office of Nuclear Reactor Regulation (NRR), which oversees licensing and oversight of operating reactors, license renewals, and operator licensing

• 10 CFR Part 50 (expanded) — Domestic licensing of production and utilization facilities (additional requirements): personnel training and qualification programs for reactor operators; effluent control requirements limiting radioactive releases to the environment; combustible gas control inside containment following a loss-of-coolant accident; emergency core cooling system (ECCS) acceptance criteria (peak cladding temperature, maximum oxidation, coolable geometry); environmental qualification of electrical equipment important to safety; fracture prevention criteria for reactor coolant pressure boundary components; risk-informed categorization and treatment of structures, systems, and components; maintenance effectiveness requirements (Maintenance Rule); immediate notification requirements for significant events and emergencies

• 10 CFR Part 73 (expanded) — Physical Protection of Plants and Materials (47 sections): the full operational security rulebook for nuclear facilities and nuclear material in transit. Key provisions:

  • § 73.15 — Enhanced weapons and preemption of state firearms laws: under Section 161A of the Atomic Energy Act, NRC may authorize nuclear power plant and fuel cycle facility security forces to use "enhanced weapons" — weapons that would otherwise be prohibited under state law, including select-fire automatic weapons, large-capacity magazines, and suppressors; this federal authorization preempts state firearms laws for authorized security personnel at designated facilities; this is one of the few federal statutes that explicitly displaces state gun laws for a defined class of users; licensees must apply for enhanced weapons authorization and demonstrate adequate need and safeguards
  • § 73.17 — Firearms background checks: all security personnel whose duties require access to enhanced weapons must pass a firearms background check under Section 161A of the AEA; background checks are more stringent than the standard NICS check used for commercial gun purchases; NRC can deny or revoke authorization based on disqualifying factors
  • § 73.21 — Safeguards Information protection: "Safeguards Information" (SI) is a category of sensitive nuclear security information that is not classified under the Atomic Energy Act but is protected from disclosure because release could enable nuclear theft or sabotage; SI includes security plans, vulnerability assessments, the design basis threat, and details about protective measures; licensees must restrict SI to persons with a need to know, mark and store it appropriately, and protect it against unauthorized disclosure; SI is distinct from Restricted Data (classified nuclear weapons information)
  • § 73.45 — Fixed site physical protection performance capabilities: nuclear plant security systems must be capable of protecting against the Design Basis Threat (DBT) — a classified specification of the adversary characteristics (number of attackers, weapons, tactics) the security force must be able to defeat; systems must detect unauthorized access early enough to allow armed response; the security perimeter must have multiple barriers; communication systems must work under attack conditions
  • § 73.54 — Cybersecurity: each nuclear power reactor licensee must have a Commission-approved cyber security plan protecting digital control systems and networks from cyberattack; the plan must address all critical digital assets (systems whose failure could affect nuclear safety or security functions); required by 2009 rulemaking following recognition that control system cyberattacks (like Stuxnet) represent credible sabotage vectors
  • § 73.55 — Physical protection against radiological sabotage: specific requirements for nuclear power plant security — armed response force (minimum staffing, training, qualifications), detection systems, communication systems, access control to vital areas, on-site response capability able to defend against the DBT without waiting for off-site law enforcement
  • § 73.56 — Personnel access authorization: every person seeking unescorted access to a nuclear power plant must undergo a background investigation — personal history (education, employment, military service), criminal history records check, credit history check, psychological evaluation, and drug testing; access authorization must be maintained by continuous behavioral observation
  • § 73.1200 — Security event notifications: licensees must notify the NRC Headquarters Operations Center within 15 minutes of detecting a physical security event (intrusion, theft, hostile action attempt, loss of security system); initial notification is by phone; written follow-up reports are required within 60 days (§ 73.1205)
  • § 73.1215 — Suspicious activity reports: licensees must report "suspicious activities" — indicators of surveillance, hostile reconnaissance, or attack planning — to local law enforcement, the FBI, and NRC; this provision recognizes that terrorist planning phases often precede attacks by months and creates an early warning obligation

• 10 CFR Part 50 — Domestic Licensing of Production and Utilization Facilities (NRC reactor licensing: construction permits, operating licenses, technical specifications, safety analysis, environmental review, decommissioning; 89 sections — the foundational reactor licensing framework)

• 10 CFR Part 52 — Licenses, Certifications, and Approvals for Nuclear Power Plants (combined licenses, early site permits, standard design certifications — the modern streamlined licensing pathway for new nuclear construction; 93 sections)

• 10 CFR Part 20 — Standards for Protection Against Radiation (occupational dose limits, public dose limits, radiation monitoring, ALARA principle, waste disposal, reporting; 70 sections)

• 10 CFR Part 835 — Occupational Radiation Protection (DOE contractor facilities — parallel to NRC Part 20 but covering DOE-owned national laboratories, weapons facilities, and research sites): DOE's radiation protection framework applies to federal employees and contractors at DOE-operated facilities such as Oak Ridge, Los Alamos, Sandia, Savannah River, Hanford, and the Nevada Test Site. Key provisions:

  • § 835.101 — Radiation Protection Programs (RPP): every DOE activity involving radiation must be conducted under a documented RPP approved by DOE; the RPP must describe the facility's implementation of ALARA (As Low As Reasonably Achievable) — the principle that doses should be reduced to the lowest level practical, not just kept below legal limits; internal audits of the RPP are required annually (§ 835.102)
  • § 835.202 — Occupational dose limits for general employees: annual limits are (a) 5 rem (0.05 Sv) total effective dose (whole-body external + committed effective dose from internal radiation); (b) 50 rem (0.5 Sv) equivalent dose to any organ or tissue; (c) 50 rem equivalent dose to the lens of the eye; (d) 50 rem equivalent dose to skin and extremities — the same numerical limits as NRC Part 20; the limits are based on ICRP recommendations and represent levels below which significant excess cancer risk has not been demonstrated
  • § 835.203 — Combining internal and external doses: total effective dose is the sum of external dose (measured by dosimeters) plus committed effective dose from internally deposited radionuclides; internals must be tracked through bioassay and air sampling programs, making Part 835 compliance more complex than external-radiation-only workplaces
  • § 835.204 — Planned special exposures (PSE): for operations where dose limits would otherwise be exceeded (e.g., emergency repairs in high-dose environments), DOE may authorize a PSE for up to 5 rem in a single year and 10 rem lifetime beyond the standard limits; PSEs require advance DOE approval, written informed consent from the worker, and documentation; they may not be used routinely to circumvent dose limits
  • § 835.206 — Embryo/fetus limits: a declared pregnant worker's embryo/fetus may receive no more than 0.5 rem (5 mSv) equivalent dose during the entire gestational period; declaration of pregnancy is voluntary; once declared, the licensee must ensure fetal dose tracking and may need to reassign the worker
  • § 835.207 — Minors: occupational dose limits for workers under 18 are one-tenth (10%) of the adult limits — 0.5 rem total effective dose annually
  • § 835.402 — Individual monitoring: personnel dosimeters (film badges or TLDs) must be provided to and used by workers likely to receive 100 mrem (1 mSv) or more in a year from external sources; air monitoring required where workers may inhale 40+ DAC-hours annually (§ 835.403)
  • §§ 835.501–835.502 — Radiological area classifications: areas are classified by dose rate and contamination level — controlled areas, radiological areas, high radiation areas, very high radiation areas (>500 R/hr at 30 cm), and airborne radioactivity areas; each classification triggers specific entry controls, monitoring, and postings; entry into a very high radiation area requires supervisor authorization and continuous attendant
  • §§ 835.601–835.606 — Posting and labeling: all access points to radiological areas must be posted with the standard radiation warning symbol (trefoil); radioactive material containers must be labeled; temporary exceedances (< 8 hours) may be managed by worker control rather than posting
  • § 835.901 — Radiation safety training: all workers who enter controlled areas must receive initial radiation safety training before entry and refresher training annually; training must cover the classification and labeling system, ALARA principles, dose limits, proper use of dosimeters, and emergency procedures; records must be maintained

  The DOE Part 835 framework parallels but is distinct from NRC's Part 20. NRC Part 20 applies to licensed facilities (commercial power reactors, fuel cycle facilities, research reactors, medical facilities); DOE Part 835 applies to DOE-owned facilities operated by contractors. At most DOE sites, contractors manage day-to-day operations while DOE retains regulatory authority through site-specific contracts and oversight — meaning the private contractor's radiation workers are regulated by DOE rather than NRC. ALARA is the unifying principle: meeting the numerical dose limits is the legal floor, but the actual goal is continuous reduction, with facilities required to demonstrate that doses are being driven as low as practicable through engineering controls, administrative controls, and shielding — not just kept below the limit ceiling.

• 40 CFR Part 194 — Criteria for Certification and Re-Certification of the Waste Isolation Pilot Plant's Compliance with the 40 CFR Part 191 Disposal Regulations — EPA's certification framework for the Waste Isolation Pilot Plant (WIPP), the world's only currently operating deep geological repository for transuranic (TRU) nuclear waste. WIPP is located 2,150 feet underground in ancient Permian salt formations near Carlsbad, New Mexico; it has received TRU waste from nuclear weapons production at national laboratories (Los Alamos, Savannah River, Oak Ridge, Hanford) since March 1999. EPA — not NRC — is the regulatory authority for WIPP; EPA certifies that WIPP's disposal system complies with the long-term performance standards in 40 CFR Part 191 over a 10,000-year compliance period. Key provisions:

  • § 194.1 — Scope and applicability: Part 194 applies specifically to the WIPP facility operated by DOE; EPA must certify WIPP before waste disposal can begin and must re-certify under the WIPP Land Withdrawal Act (WIPP LWA, Public Law 102-579) to authorize continued operations; re-certification submissions must be made every 5 years
  • § 194.14 — Compliance certification application content: DOE's application to EPA must include (a) a description of the natural and engineered features of the disposal system that may affect performance (the salt geology, room-and-pillar mine configuration, engineered barriers); (b) performance assessments (PAs) — probabilistic computer models projecting radioactive waste migration under thousands of possible scenarios over 10,000 years; (c) complementary cumulative distribution functions (CCDFs) — statistical representations of the probability distribution of all possible release scenarios; (d) a waste characterization program documenting the chemical, radiological, and physical composition of all waste proposed for disposal; (e) quality assurance documentation for all models and data
  • § 194.22 — Quality assurance: DOE must adhere to a quality assurance program meeting ASME NQA-1 standards for all data, models, and analyses used in compliance applications; this peer-review-level rigor is required because EPA's certification depends on trusting complex computational models projecting behavior over geologic time scales — the QA program provides the auditable record of how those models were developed and validated
  • § 194.23 — Models and computer codes: compliance applications must describe all conceptual models and scenarios used in performance assessments; computer codes must be verified and validated; EPA reviews the theoretical underpinnings of the models and their predictions against available analogues (natural salt formations with ancient uranium deposits that show minimal migration over millions of years, such as the Cigar Lake uranium deposit)
  • § 194.24 — Waste characterization: all waste sent to WIPP must be characterized before shipment — chemical composition, radioactive isotope inventory, and physical form (no free liquids, limits on organic materials that could generate gas from microbial degradation); characterization errors are among the most common compliance issues at WIPP
  • § 194.21 — EPA inspection authority: EPA has unfettered and unannounced access to all areas of WIPP, all related DOE facilities where waste is characterized, and all supporting contractors; EPA inspectors may observe any activity, review any records, and collect samples; this broad inspection authority reflects EPA's role as independent regulatory overseer of a DOE-operated facility
  • §§ 194.32–194.34 — Performance assessments and regulatory standards: EPA certifies that WIPP's calculated probability of exceeding the Part 191 release limits is at or below the specified levels — the core 10,000-year containment standard; performance assessments must account for undisturbed performance, human intrusion scenarios (future drilling into the repository for oil/gas exploration), and disturbed scenarios combining natural processes with human intrusion

  WIPP's 2014 radiological release incident — the first such event in the repository's history — resulted from a container of organic cat litter substituted for inorganic clay in waste packaging at Los Alamos, causing a chemical reaction that ruptured the container underground and released small amounts of radioactive material; the repository closed for approximately 3 years while DOE assessed and repaired the damage. The incident exposed gaps in DOE's waste characterization and quality assurance programs. Post-2014 reforms tightened waste characterization requirements at all generator sites. WIPP's continued operation is essential to DOE's ability to clean up legacy TRU waste from Cold War weapons production — Hanford, Savannah River, and other sites cannot complete their cleanup missions without WIPP as a disposal path. EPA's most recent re-certification (2024) confirmed continued compliance with the 10,000-year containment standards.

• 48 CFR Part 950 — Extraordinary Contractual Actions and the Safety Act (DOE Acquisition Regulation — DEAR): the DOE contracting regulation implementing the nuclear indemnification provisions of the Price-Anderson Act (42 U.S.C. § 2210) specifically for DOE contractors rather than NRC-licensed reactor operators. The distinction matters: the Price-Anderson framework has two tracks — NRC-licensed commercial reactor operators participate in the retrospective assessment pool (described above at 42 U.S.C. § 2210); DOE's own contractors at national laboratories, weapons production facilities, and remediation sites are indemnified through a separate contractual mechanism under the Atomic Energy Act § 170d and § 2201. Key provisions of Subpart 950.70 — Nuclear Indemnification of DOE Contractors:

  • § 950.7000 — Scope: this subpart governs DOE's policy of indemnifying contractors against public liability for nuclear incidents arising out of or in connection with the contract activity; "public liability" means third-party claims for bodily injury, property damage, or other costs — not claims by the contractor's own employees
  • § 950.7001 — Applicability: the indemnification policies apply to any DOE contractor whose work involves "the risk of public liability for a nuclear incident or precautionary evacuation"; this covers not just weapons production contractors but laboratory contractors handling radioactive materials, environmental remediation contractors at contaminated sites, and research contractors operating nuclear facilities
  • § 950.7002 — Indemnification agreements: DOE enters into nuclear indemnification agreements with qualifying contractors as part of the contract; the agreement specifies the scope of covered nuclear incidents and the extent of DOE's indemnification obligation; unlike the NRC reactor track (which uses private insurance plus a retrospective assessment pool), DOE contractor indemnification is backed directly by the federal government's authority under 42 U.S.C. § 2210(d)
  • § 950.7003–950.7006 — Indemnification conditions and limits: the indemnification is subject to conditions including contractor cooperation with incident investigation, insurance maintenance requirements (to the extent reasonably available), and limitations on willful misconduct coverage; amounts are governed by the Price-Anderson liability cap framework

  The DOE contractor track of Price-Anderson covers a remarkably broad range of activities: Hanford Site cleanup contractors managing millions of gallons of radioactive tank waste; Los Alamos and Lawrence Livermore laboratory contractors conducting weapons physics research; Oak Ridge and Savannah River contractors processing plutonium and tritium; and smaller contractors at university research reactors operated under DOE grants. Without the indemnification agreement, private contractors could not obtain commercial insurance at commercially reasonable rates for nuclear operations of this type and scale — the federal indemnification is an essential enabler of the contractor-operated model that has characterized DOE's national laboratory and production complex since the Manhattan Project.

• 40 CFR Part 190 — Environmental Radiation Protection Standards for Nuclear Power Operations: EPA's public dose limits for the entire uranium fuel cycle — from mining and milling through enrichment, fuel fabrication, reactor operation, and spent fuel storage. Part 190 complements NRC's occupational dose limits (10 CFR Part 20, which protects workers at 5 rem/year) by setting limits on what the general public may receive from all fuel-cycle sources combined. Key provisions:

  • § 190.01 — Applicability: Part 190 applies to the entire nuclear fuel cycle associated with the production of electrical power — uranium mining and milling, conversion, enrichment, fuel fabrication, reactor operation, spent fuel reprocessing, and radioactive waste disposal; it does not cover medical uses of radiation or military nuclear activities
  • § 190.10 — Standards for normal operations: annual dose limits for any member of the public from the entire uranium fuel cycle are (a) 25 millirem (0.25 mSv) whole body; (b) 75 millirem (0.75 mSv) to the thyroid; (c) 25 millirem to any other organ; these are public dose limits — not worker dose limits — and are substantially lower than NRC's general public limit in 10 CFR Part 20 (100 mrem/year) because they represent EPA's judgment on acceptable aggregate exposure from all fuel-cycle contributions to any single individual; facilities must conduct environmental monitoring around nuclear sites to demonstrate compliance
  • § 190.11 — Variances for unusual operations: the § 190.10 annual limits may be exceeded only if a regulatory agency grants a variance based on a finding that the unusual operation is necessary, temporary, and that the expected doses remain below levels of concern; the variance mechanism addresses one-time events such as emergency maintenance requiring additional releases or unusual facility conditions — it is not a general relaxation of the standard

  The 25 mrem/year whole-body limit is one of EPA's foundational radiation standards and has governed the nuclear power industry since 1977. It is considerably more stringent than the NRC's 100 mrem/year general public dose limit — reflecting EPA's "all pathways" approach: the 25 mrem limit covers dose from drinking water, air, food, and direct radiation combined, summed across all stages of the fuel cycle. This means a community near both a uranium enrichment facility and a nuclear power plant can only receive 25 mrem total from both sources combined, not 100 mrem from each. The practical effect is that nuclear facilities conduct detailed environmental monitoring (air, water, soil, foodstuffs) and environmental dose assessments annually to demonstrate compliance. No major rulemakings since the rule's 1977 promulgation — EPA has maintained the 25 mrem standard while the industry has dramatically reduced actual emissions well below the limit; NRC-regulated facilities routinely demonstrate actual public doses a fraction of a millirem per year.

• 10 CFR Part 75 — Safeguards on Nuclear Material — Implementation of Safeguards Agreements Between the United States and the International Atomic Energy Agency (34 sections — the NRC's operational rulebook for implementing U.S. nuclear material accounting obligations under the IAEA safeguards system):

  The United States is party to two IAEA safeguards agreements: the Voluntary Offer Agreement (VOA) (1980) — under which the U.S. offers to place certain civilian nuclear facilities and nuclear material under IAEA inspection, though the U.S. may exclude material necessary for national security; and the Additional Protocol (2008) — a supplementary agreement that requires broader declarations of nuclear activities and facilities and grants the IAEA expanded inspection rights ("complementary access"). Part 75 translates these treaty obligations into NRC compliance requirements that bind domestic licensees and certificate holders.

  • § 75.2 — Scope: Part 75 applies to all NRC licensees or certificate holders who are notified by NRC that their facility has been identified under the VOA or that information about their activities is required for the Additional Protocol; this covers commercial nuclear power plants, research reactors, fuel cycle facilities (enrichment plants, fuel fabrication facilities), and possessors of nuclear material outside facilities
  • § 75.10 — Facility information: licensees selected under the VOA must provide NRC with detailed facility information — design information, operational data, and material flow data — in the NRC/DOC forms specified; NRC then transmits this to the IAEA; the IAEA uses this information to design safeguards inspection procedures (the Safeguards Approach) specific to that facility
  • § 75.21 — Material accounting: designated facilities must maintain detailed nuclear material accounting records in IAEA Material Balance Areas (MBAs); records must track all inventory changes (receipts, shipments, removals, losses) to permit a determination of the nuclear material "book inventory" at any time; these accounting records are the foundation of the IAEA's ability to verify that no material has been diverted from the declared inventory
  • § 75.26 — IAEA exemptions: small quantities of nuclear material (below defined thresholds) may be requested for exemption from IAEA safeguards by the U.S. Government; the exemption process reflects the practical reality that accounting for every gram of naturally occurring uranium in an academic chemistry laboratory would be administratively burdensome without meaningful nonproliferation benefit

  The practical significance of Part 75 is at the intersection of domestic nuclear regulation and international nonproliferation law. IAEA inspectors conduct both scheduled and short-notice inspections at designated U.S. facilities — the same inspection regime applied to nuclear programs in Iran, Japan, and other countries applies to U.S. commercial nuclear sites covered by the VOA. The IAEA's ability to verify that civilian U.S. nuclear material is not diverted to weapons purposes enhances U.S. nonproliferation credibility: the U.S. cannot credibly demand Iran accept full-scope safeguards while exempting its own civilian program. As of 2024, the IAEA has inspected more than 20 U.S. facilities under the VOA, including nuclear power plants and fuel cycle facilities, confirming that material accounting matches declared inventories.

• 10 CFR Part 74 — Material Control and Accounting of Special Nuclear Material. NRC regulations implementing 42 U.S.C. § 2073 that require all NRC licensees possessing special nuclear material (SNM) — enriched uranium, plutonium, or uranium-233 — to maintain rigorous inventory control, accounting records, and theft/loss reporting systems. The Part's requirements scale with the strategic significance of the material held: "low strategic significance" (research-grade quantities, power reactor fuel), "moderate strategic significance" (enough for a crude improvised device), and "formula quantities of strategic SNM" (Category I — sufficient for a sophisticated weapon). Key provisions:

  • § 74.11 — Immediate loss/theft reporting: any licensee possessing ≥1 gram of contained U-235, U-233, or plutonium must notify the NRC Operations Center within 1 hour of discovering any loss, theft, attempted theft, or unlawful diversion; a follow-up written report is required within 24 hours; the 1-hour phone notification is non-negotiable — it feeds directly into NRC's SECY alert chain and FBI notification (NRC immediately notifies FBI of all SNM loss/theft reports)
  • § 74.13 — Material status reports: licensees report their SNM inventory semi-annually using the Nuclear Materials Management and Safeguards System (NMMSS); the reports enable NRC to track the location and quantity of all licensed SNM in the U.S. materials accountability system
  • § 74.15 — Nuclear material transaction reports: every transfer or receipt of ≥1 gram of contained SNM requires a transaction report to NMMSS; the shipper and receiver both submit independent reports — any shipper-receiver difference (SRD) above defined thresholds triggers immediate investigation and possible loss report
  • § 74.31 — Low strategic significance SNM (Subpart C): facilities holding reactor-grade enriched uranium in amounts above 1 effective kilogram must maintain a nuclear material control and accounting (MC&A) system meeting defined performance objectives; physical inventory must be taken annually; records must be maintained to account for all SNM receipts, production, transfers, removals, and losses; amended at 91 FR 15877 (March 30, 2026) to update accountability thresholds
  • § 74.41 — Moderate strategic significance SNM (Subpart D): facilities holding quantities potentially useful for an improvised nuclear device (but below Category I thresholds) must conduct semi-annual physical inventories (twice the frequency of Subpart C); internal controls must be capable of detecting an abrupt loss of 15 kg of contained U-235 (or equivalent) within the inventory period; amended at 91 FR 15878 (March 30, 2026)
  • §§ 74.51–74.59 — Formula quantities of strategic SNM (Subpart E, Category I): the most stringent tier — applies to weapons-usable amounts of plutonium, highly enriched uranium (HEU), or U-233; licensees must implement either Near-Real-Time Accounting (NRTA) or Item Control System (ICS) to detect any loss within hours; physical inventories every 12 months; automated access control and material control technology required; any SRD exceeding a statistically derived threshold triggers immediate investigation and potential FBI/NRC Operations Center notification; Subpart E facilities include DOE/NNSA nuclear weapons component plants that also hold NRC licenses for civilian-origin material

  Part 74's material accountability system is the domestic regulatory complement to the IAEA safeguards obligations implemented by Part 75 — together, they form the U.S.'s two-layer material accounting framework. The domestic layer (Part 74) catches diversion from any licensed facility; the international layer (Part 75/IAEA) catches diversion at the national level, including possible DOE-to-NRC material flow anomalies. The 2024 amendment cycle updated the statistical detection capability requirements for Subpart E to reflect modern measurement technology improvements.

• 10 CFR Part 712 — DOE Human Reliability Program (HRP). DOE regulations implementing 42 U.S.C. § 2201 and 50 U.S.C. § 2401, establishing a continuous physical and psychological fitness program for individuals with access to the most sensitive nuclear materials and weapons. The HRP applies to DOE, NNSA, and contractor employees in designated positions — a program distinct from standard security clearances because it targets behavioral reliability, not loyalty or foreign influence. Key provisions:

  • § 712.1 — Purpose: the HRP ensures that individuals who occupy positions affording access to certain materials, nuclear explosive devices, facilities, and programs "meet the highest standards of reliability and physical and mental suitability" — accomplished through a system of continuous evaluation that identifies impairment from physical disorders, mental/personality disorders, alcohol abuse, illegal drug use, or other conditions of security or safety concern
  • § 712.10 — HRP positions: HRP certification is required for positions that afford access to Category I special nuclear material (SNM) (large quantities of weapons-usable plutonium or enriched uranium); involve nuclear explosive duties or responsibility for protecting or transporting nuclear devices; afford access to information about vulnerabilities in protective systems for nuclear transportation; or have significant national security impact (by special designation)
  • § 712.11 — General requirements: HRP candidates must hold a DOE "Q" access authorization (the highest-level DOE security clearance); sign releases and waivers authorizing access to medical, psychological, financial, and criminal records; and complete the HRP evaluation process before accessing HRP positions
  • § 712.14 — Medical assessment: a Designated Physician evaluates each HRP candidate and certified individual for physical or mental conditions that may prevent reliable HRP duty performance or represent a security concern; conditions reviewed include cardiovascular disease, neurological disorders, substance dependence, and prescribed medications that could impair judgment; a Designated Psychologist separately assesses psychological fitness
  • § 712.15 — Management evaluation: the HRP management official reviews the results of the medical assessment, security review, and supervisor evaluations before certifying or recertifying an individual; the management official has authority to initiate temporary removal (§ 712.19) whenever behavioral or medical concerns emerge between certification cycles
  • § 712.16 — Security review: a personnel security specialist reviews the personnel security file (including polygraph results, financial disclosures, and reported incidents) for every HRP candidate at each certification cycle; the security review feeds into the management evaluation
  • § 712.17 — Annual instruction: each DOE site with HRP positions must run an annual HRP training program covering self-reporting obligations, behavioral indicators, and supervisor responsibilities; unlike standard security awareness training, HRP instruction focuses on the behavioral and medical warning signs of reliability impairment
  • § 712.19 — Removal and revocation: the management official must temporarily remove an HRP-certified individual when impairment is identified or when behavior creates reasonable doubt about reliability; revocation follows a more formal process with due process protections; the revocation does not automatically remove a security clearance, but NNSA typically initiates access authorization review in parallel
  • § 712.20 — Appeal: an individual whose HRP certification is revoked may request reconsideration or a formal certification review hearing before DOE's Office of Hearings and Appeals; the hearing is conducted by an Administrative Judge with at least a "Q" clearance; the final decision rests with the cognizant DOE Under Secretary (§ 712.24)
  • §§ 712.30–712.35 — Medical standards: Subpart B defines the qualifications for the Designated Physician (occupational medicine background, DOE "Q" clearance) and Designated Psychologist (clinical psychology doctorate, "Q" clearance); the Site Occupational Medical Director (SOMD) nominates both and oversees the site's HRP medical assessment function

  The HRP operates as a layer on top of — not a substitute for — the standard DOE security clearance process. Where clearance investigations focus on foreign contacts, loyalty, and financial vulnerability, the HRP's ongoing supervisory evaluation and annual medical assessment target behavioral reliability: an HRP-certified individual who develops a substance dependence problem, receives a new psychiatric diagnosis, or exhibits concerning on-the-job behavior can be removed immediately — without waiting for the next scheduled security review. The program covers approximately 5,000–6,000 positions at DOE's 17 national laboratory sites and NNSA's nuclear weapons production complex (Los Alamos, Sandia, Lawrence Livermore, Pantex, Y-12, and Savannah River). Recent rulemakings: 88 FR 41292 (June 2023) — comprehensive HRP rule revision updating medical standards and adding clarifications to the removal and appeal procedures.

• 10 CFR Part 950 — Standby Support for Certain Nuclear Plant Delays (28 sections across 4 subparts): implements Energy Policy Act of 2005 § 638 (42 U.S.C. § 16014) — a federal risk insurance program designed to incentivize construction of the first six new advanced nuclear power plants in the United States by protecting investors against specific types of delays attributable to the NRC regulatory process. Part 950 was promulgated in recognition that first-of-a-kind construction risk — including regulatory uncertainty — was a primary barrier to private capital committing to new nuclear construction after the 1970s–80s era of abandoned projects and cost overruns.

  Program structure (§§ 950.1–950.2): DOE enters into Standby Support Contracts with "sponsors" (nuclear power plant developers) of new advanced nuclear facilities — defined as any facility with a reactor design approved by NRC after December 31, 1993 (covering Generation III+ and advanced designs). The program covers the first six advanced nuclear plants to reach eligibility (reflecting Congressional intent to subsidize early movers, not the entire industry); once six contracts are in place, no additional plants may enter the program. DOE has entered into conditional agreements with plants using the AP1000 reactor design (Vogtle Units 3 and 4 in Georgia; VC Summer Units 2 and 3 in South Carolina) — the only four units to have reached late-stage construction under the program.

  Conditional Agreement and Standby Support Contract (§§ 950.10–950.13):

  • § 950.10 — Conditional Agreement: the preliminary commitment between DOE and the sponsor; the Department will execute a Standby Support Contract once the sponsor demonstrates it has received all required federal and state licenses, permits, and approvals and begun construction; the Conditional Agreement reserves the plant's place among the first six eligible projects
  • § 950.12 — Standby Support Contract conditions precedent: before DOE executes the contract, the sponsor must demonstrate (a) receipt of an NRC Combined License authorizing construction and operation; (b) commencement of actual construction; and (c) compliance with all applicable legal and regulatory requirements; once these conditions are met, DOE is obligated to execute the Standby Support Contract
  • § 950.13 — General provisions: the Standby Support Contract obligates DOE to compensate the sponsor for covered costs incurred during covered delay periods; the compensation structure differs for the first two plants (Plants 1–2) vs. Plants 3–6 — the tiered structure provides more favorable terms for the earliest movers to offset their first-mover disadvantage

  Covered events and financial caps (§ 950.14):

  • Covered events: any NRC action (or inaction) — including rulemaking delays, additional NRC hearings, licensing proceedings initiated by intervenors, or NRC-directed construction holds — that delays the scheduled commercial operation date beyond the date attributable to the NRC regulatory process; delays caused by construction defects, contractor failures, weather, or the sponsor's own decisions are excluded from coverage
  • Financial limits: for Plants 1–2, DOE covers 100% of the first $500 million of covered delay costs; for Plants 3–6, DOE covers 50% of the first $250 million; coverage is available only for delays occurring within the first 6 years of the Standby Support Contract; covered costs include the carrying costs (interest and opportunity costs) of delayed cost recovery — not construction costs themselves
  • § 950.25 — Calculation: covered costs are calculated based on the increased financing costs the sponsor incurs because delayed commercial operation pushes back the date at which the plant begins generating revenue to recover construction investment; DOE does not cover lost revenue directly — it covers the incremental borrowing cost attributable to the delay

  Claims process (§§ 950.20–950.28): when a covered event occurs, the sponsor files a notification with DOE's Claims Administrator within a specified window; the Claims Administrator has 30 days to review the notification for completeness; DOE then makes a Covered Event Determination (was this a regulatory delay within the program's scope?); upon attaining full power operation, the sponsor files a Certification of Covered Costs; DOE has 30 days to issue a Claim Determination; disputes go to mediation, then to Summary Binding Decision by a neutral expert.

  The Part 950 program has had limited practical application: Vogtle Units 3 and 4 (Georgia Power/Southern Nuclear) are the only new nuclear units in the United States to reach commercial operation in the program era (Unit 3 in July 2023, Unit 4 in April 2024 — both years behind schedule and billions over budget). The VC Summer project in South Carolina was cancelled in 2017 after $9 billion was spent. DOE's standby support for Vogtle was triggered by NRC-related delays but the primary cost drivers were construction management failures outside the program's coverage scope. The program's fiscal exposure was much smaller than feared; its greater significance was providing confidence to lenders and investors that a backstop existed for regulatory risk. No rulemakings since original 2007 promulgation (72 FR 15004, March 2007).

• 10 CFR Part 719 — DOE Contractor Legal Management Requirements (35 sections — the Department of Energy's rules governing how DOE's large management and operating (M&O) contractors manage legal affairs, control litigation costs, and obtain DOE approval before settling significant cases): DOE's national laboratory and weapons production complex is operated almost entirely by private contractors — Boeing, Bechtel, Battelle, University of California, and other consortium managers operate Los Alamos, Savannah River, Oak Ridge, Lawrence Livermore, Sandia, Hanford, and dozens of other sites under cost-reimbursement M&O contracts. Because DOE reimburses contractors for legal costs, Part 719 creates cost-control and transparency requirements. The regulation covers all M&O contracts, non-M&O contracts over $100 million with significant legal cost exposure, and any contract the contracting officer designates. Key provisions:

  • §§ 719.10–719.17 — Legal Management Plan (LMP): each covered contractor must submit a written LMP to DOE within 60 days of contract award; the LMP must describe in-house counsel resources, criteria for retaining outside counsel (conflicts checks, billing rate controls, specialty expertise), and the system for managing and tracking all legal matters; contractors must revise annually; DOE Counsel reviews for adequacy within 30 days
  • §§ 719.15–719.16 — Staffing and Resource Plan: for "significant matters in litigation," retained outside counsel must prepare a matter-specific Staffing and Resource Plan within 30 days of retention, covering billing rates, staffing, anticipated tasks, and a budget estimate; this creates pre-approved budgets for major litigation before significant costs are incurred
  • § 719.17 — Annual legal budget: contractors must submit an annual legal budget to DOE Counsel covering all projected legal matters; this allows DOE to monitor contractor legal spending as part of its M&O cost oversight function
  • §§ 719.30–719.35 — Litigation approval requirements: contractors may not initiate litigation, appeal adverse decisions, or enter settlement agreements without advance DOE approval; § 719.33 requires DOE Counsel permission before any settlement; executed settlement copies must be delivered to DOE within 7 days; this prevents contractors from resolving disputes against DOE's interests without agency awareness
  • §§ 719.40–719.46 — Cost allowability: compliance with Part 719 is a prerequisite for allowability of legal costs; costs incurred without required DOE approval, or through outside counsel selected without following the LMP, are unallowable and cannot be charged to DOE; all covered costs are auditable by DOE, its representatives, or the GAO

  Part 719 reflects DOE's unusual position as a government agency that reimburses contractor legal costs — including litigation costs that can run into hundreds of millions of dollars at Hanford remediation and other complex sites. Original rule: 74 FR 36363 (July 2009).

• 10 CFR Part 709 — DOE Counterintelligence Evaluation Program (21 sections — DOE's mandatory polygraph and CI screening requirements for personnel with access to the most sensitive nuclear weapons information): DOE operates one of the broadest federal polygraph programs, mandatory for personnel with access to nuclear weapons design information, Special Access Programs, and Top Secret/SCI material. The program exists because DOE national laboratories — the sites of U.S. nuclear weapons R&D — are primary targets of foreign intelligence services. Authority: 42 U.S.C. § 2011 (AEA), 50 U.S.C. § 2401 (NNSA). Key provisions:

  • § 709.3 — Covered persons: mandatory CI evaluation (including polygraph) applies to: persons with access to Top Secret or SCI nuclear weapons information; DOE/NNSA employees and contractors in "critical nuclear weapons design information" positions; persons assigned to Intelligence Community activities at DOE; and other persons designated by the Secretary of Energy or Secretary of Defense
  • § 709.10 — Scope: a CI evaluation combines a review of the covered person's personnel security file and available intelligence data with a polygraph examination focused on foreign nexus issues — contacts with foreign nationals, foreign travel, foreign financial interests, and past disclosures of classified information; this is a CI-scope (not full-scope) polygraph
  • §§ 709.11–709.12 — Polygraph topics: questions cover unauthorized disclosure of classified information, deliberate damage to nuclear systems, and suspected espionage contacts; the examiner develops specific question wording in a pretest interview
  • § 709.13–709.14 — Refusal consequences: covered persons may refuse the polygraph, but refusal results in discontinuation of CI evaluation processing — and therefore denial or revocation of the access authorization required for the position; applicants who refuse cannot be hired; current employees who refuse may lose their access and thus their position
  • § 709.22–709.23 — Procedural rights: covered persons may consult with an attorney before and after (not during) the examination, at their own expense; DOE must obtain written informed consent before administering the polygraph, acknowledging that participation is required for the access authorization
  • § 709.25 — Limits on adverse action: DOE may not take an adverse personnel action based solely on an ambiguous polygraph result ("Significant Response" or "No Opinion") without further investigation and CI Evaluation Review Board review; the restriction acknowledges that polygraph results are not conclusive
  • § 709.16 — CI Evaluation Review Board: unresolved CI evaluation findings go to an agency Review Board composed of senior CI, security, and program officials; the Board reviews the full record and recommends to the DOE Director of Intelligence and Counterintelligence; final disposition rests with the relevant program office (§ 709.17)

  DOE's polygraph program has been controversial since its post-Wen Ho Lee expansion in the late 1990s. The National Academy of Sciences' 2002 report found polygraph evidence unreliable as a security screening tool, and Congress has periodically sought to limit DOE's authority. DOE argues the program deters hostile intelligence recruitment even if it is not a reliable lie-detection tool. The program covers approximately 5,000–6,000 positions at NNSA weapons laboratories and production sites.

How It Works

Nuclear energy regulation is one of the most intensive regulatory regimes in the world — reflecting the unique hazards of radioactive materials and the catastrophic potential of nuclear accidents.

No one may build or operate a nuclear reactor without an NRC license. The traditional two-step process required a Construction Permit followed by a separate Operating License; since 1989, applicants can also use the Combined License (COL) process — a single license authorizing both construction and operation at a specific site with a specific design, with post-construction verification conditions. NRC has also established Early Site Permits (banking a site for future construction) and Design Certifications (approving a reactor design independent of any site). The licensing process involves extensive safety review, NEPA environmental review, public hearings, and Advisory Committee on Reactor Safeguards (ACRS) review. NRC regulations in 10 CFR Parts 1–199 cover design criteria, radiation protection standards, emergency preparedness, security, quality assurance, and operator licensing. Continuous oversight runs through resident inspectors stationed at every operating reactor (2–3 per plant, present daily), regional inspection programs, reactor performance indicators, and significance determination processes. Enforcement ranges from non-cited violations to plant modification orders, civil penalties, and license revocation.

The Price-Anderson Act created a unique liability framework essential to commercial nuclear power's development. Each licensed reactor carries maximum available private insurance (~$500 million); beyond that, all operators participate in a retrospective assessment pool of approximately $140 million per reactor per incident — creating a total pool of ~$13.6 billion. Congress would address anything beyond that. Price-Anderson channels all liability to the operator (no suits against designers, suppliers, or contractors), applies strict liability (no negligence proof required), and bars punitive damages; it has been extended through 2045. The unresolved challenge is spent nuclear fuel: commercial reactors have generated approximately 90,000 metric tons, currently stored at reactor sites in spent fuel pools and dry cask storage. The Nuclear Waste Policy Act of 1982 directed DOE to build a permanent geological repository; Yucca Mountain was designated in 1987 but politically blocked since 2010, leaving ~$47 billion in the Nuclear Waste Fund (from $0.001/kWh utility fees) unused while fuel accumulates at 70+ reactor sites. A new generation of Small Modular Reactors (SMRs), molten salt reactors, and high-temperature gas reactors is moving through NRC review; the Nuclear Energy Innovation and Modernization Act (NEIMA, 2019) directed NRC to develop a risk-informed, technology-neutral licensing framework for advanced designs.

How It Affects You

State Variations

Nuclear safety regulation is exclusively federal (NRC), but states retain significant authority:

Pending Legislation

• S 1757 (Sen. Scott, R-SC) — Efficient Nuclear Licensing Hearings Act: lets NRC skip licensing hearings unless requested, favors informal hearings. Status: Introduced.
• S 101 (Sen. Cortez Masto, D-NV) — Nuclear Waste Informed Consent Act: requires state/local/tribal agreements before DOE spends on waste repository. Status: Introduced.
• HR 1757 — Efficient Nuclear Licensing Hearings Act: would let the NRC skip licensing hearings unless requested and favor informal proceedings. Status: Introduced.
• HR 1762 — NEDD Act: would expand DOE authority to regulate and defend nuclear sites against covered drones from foreign entities. Status: Introduced.

Recent Developments

• The ADVANCE Act (2024) reformed NRC licensing processes, reduced fees for advanced reactor applications, established pre-licensing milestones, and directed NRC to develop regulatory frameworks for fusion energy
• Renewed interest in nuclear power as a climate solution has led to bipartisan support for extending existing plant licenses and deploying new reactor designs
• Several previously retired nuclear plants are exploring restart — Palisades (Michigan) received DOE loan guarantees for restart in 2025
• AI data center electricity demand is driving interest in on-site small modular reactors, with several tech companies exploring nuclear-powered data centers
• Spent fuel storage remains at reactor sites indefinitely — the Yucca Mountain political impasse continues with no resolution in sight
• NRC finalizes landmark Part 53 advanced reactor licensing pathway (March 2026): NRC published its Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (10 CFR Part 53) — the most significant NRC regulatory modernization since the 1970s. Part 53 creates a performance-based, technology-neutral licensing pathway that does not require advanced reactors to conform to the light-water-reactor-specific rules in 10 CFR Part 50 and Part 52. The new pathway is designed to enable small modular reactors (SMRs), molten salt, and other Generation IV designs to seek NRC approval faster, with regulatory requirements scaled to the actual safety risks of the specific design rather than one-size-fits-all LWR rules. SMR developers including NuScale, X-energy, and TerraPower are expected to file Part 53 applications.
• Trump administration accelerates nuclear permitting (2025-2026): The administration has identified nuclear energy expansion as a national security and energy dominance priority, directing DOE and NRC to expedite permitting for both new reactors and license extensions for existing plants. DOE proposed amendments to worker safety regulations to speed advanced reactor testing and deployment. The White House circulated executive order drafts to further streamline NRC licensing timelines and authorize DOE to directly fund construction of demonstration reactors on federal sites. Microsoft, Google, and Amazon have all announced agreements to purchase nuclear power from new SMR projects or reactor restarts.