Certification · license to practice
NRC Reactor Operator (RO) License
U.S. Nuclear Regulatory Commission (NRC) · United States (federal) · Individual license
Requires: Employed by an NRC-licensed facility; facility licensee certifies completion of a systems-approach-to-training program (typically INPO-accredited); pass NRC written examination and operating test per 10 CFR 55.41/55.45; physical and mental fitness certified on
Renewal: 6-year license term; renewal under 10 CFR 55.57 requires successful completion of the facility requalification program (
Certification · license to practice
NRC Senior Reactor Operator (SRO) License
U.S. Nuclear Regulatory Commission (NRC) · United States (federal) · Individual license
Requires: Same baseline as RO, plus demonstrated ability to direct the licensed activities of licensed operators (exam scope under 10 CFR 55.43); facility licensees typically require prior licensed-RO experience or an engineering degree plus experience per National Acad
Renewal: 6-year license term; renewal under 10 CFR 55.57 requires successful completion of the facility requalification program (
Certification · license to practice · flagship
PE Nuclear (NCEES Principles and Practice of Engineering - Nuclear)
NCEES; license issued by individual U.S. state/territory licensing boards · United States (state-level) · Professional license (discipline exam)
Requires: ABET-accredited engineering degree; pass FE exam; typically 4+ years post-college engineering experience; pass the PE Nuclear exam (computer-based, administered one day per year, 85 questions, 9.5-hour appointment, $400 NCEES fee)
Renewal: State-dependent, typically biennial renewal with continuing-education/PDH requirements
Certification · flagship
Certified Health Physicist (CHP)
American Board of Health Physics (ABHP) · United States · Professional certification
Requires: Bachelor's degree in physical science, engineering, or biological science with minimum 20 semester hours in physical science; 6 years professional health physics experience (advanced degrees may substitute up to 2 years); references including one currently-cer
Renewal: estimated: continuing certification on a ~5-year cycle with continuing education per third-party career guides — officia
Certification
Registered Radiation Protection Technologist (NRRPT)
National Registry of Radiation Protection Technologists (NRRPT) · United States · Technician registration
Requires: Age 21+; high school diploma minimum; at least 5 years of operational (hands-on) radiation protection experience (advanced degrees may waive a portion); pass the NRRPT examination
Renewal: estimated: registry maintained with renewal fees/continuing education — renewal cadence not verified
Certification
INPO Training Program Accreditation (National Nuclear Accrediting Board)
Institute of Nuclear Power Operations (INPO) / National Academy for Nuclear Training · United States · Program-level (not individual)
Requires: Utility member training programs (nonlicensed/licensed operator, shift supervisor, shift technical advisor, I&C, electrical/mechanical maintenance, radiological protection, chemistry, onsite technical staff) undergo comprehensive self-assessment plus INPO peer
Renewal: Accrediting board decision every 4 years: renewed, placed on probation, or withdrawn (board includes one NRC-nominated m
Standard · flagship
ASME BPVC Section III — Rules for Construction of Nuclear Facility Components
ASME · International; incorporated into U.S. regulation via 10 CFR 50.55a · Code
Requires: Applies to design/construction of Class 1, 2, 3 components (NB/NCD), Class MC, supports (NF), core support structures (NG), concrete containments (Div 2), spent-fuel transport/storage containments (Div 3), fusion devices (Div 4), high-temperature reactors (Div
Renewal: n/a; code editions issued on cycle — 2025 edition lists Section III Divisions 1-5
Standard · flagship
ASME BPVC Section XI — Rules for Inservice Inspection of Nuclear Power Plant Components
ASME · International; incorporated into U.S. regulation via 10 CFR 50.55a · Code
Requires: Applies after construction-code requirements are satisfied; governs examination, inservice testing/inspection, and repair/replacement of components in operating light-water plants (Div 1) and reliability/integrity management programs (Div 2)
Renewal: n/a; mandatory program of scheduled examinations, testing, and inspections over plant operating life
Standard · flagship
ASME NQA-1 — Quality Assurance Requirements for Nuclear Facility Applications
ASME · International (U.S. adoption via NRC endorsement) · Quality standard
Requires: n/a; 18 requirements in Part I organized to implement the 18 criteria of 10 CFR 50 Appendix B, plus Parts II-IV supplemental/guidance material (e.g., commercial-grade dedication)
Renewal: n/a; editions periodically (1979, 1983, 1986, 1989, 1994, 1997, 2000, 2004, 2008, 2012...)
Standard
IEEE 603 — Standard Criteria for Safety Systems for Nuclear Power Generating Stations
IEEE · International (U.S. adoption via NRC endorsement) · Standard
Requires: n/a; sets criteria for safety systems including single-failure criterion application and system-level design requirements
Renewal: n/a; periodic revisions (603-1991 cited in NRC guidance; 603-2018 is the current edition — estimated)
Standard
IEEE 344 / IEC/IEEE 60980-344 — Seismic Qualification of Equipment for Nuclear Facilities
IEEE / IEC · International · Recommended practice / international standard
Requires: n/a; establishes procedures (test, analysis, or experience-based evaluation) to demonstrate Class 1E / equipment-important-to-safety can perform its safety function during/after a safe-shutdown earthquake preceded by operating-basis earthquakes
Renewal: n/a
Standard · flagship
IAEA SSR-2/1 (Rev.1) — Safety of Nuclear Power Plants: Design
International Atomic Energy Agency (IAEA) · International (IAEA Member States) · Safety Requirements
Requires: n/a; binding-style safety requirements (not a certifiable standard) covering NPP design, defence in depth, design extension conditions, practical elimination of early/large releases
Renewal: n/a; Rev.1 published Vienna 2016 (post-Fukushima amendments)
Standard · flagship
IAEA SSR-2/2 (Rev.1) — Safety of Nuclear Power Plants: Commissioning and Operation
International Atomic Energy Agency (IAEA) · International (IAEA Member States) · Safety Requirements
Requires: n/a; safety requirements for commissioning programs, operating/maintenance procedures validation, periodic safety review, emergency preparedness, accident management, operating-experience feedback
Renewal: n/a; Rev.1 published Vienna 2016
Standard
IAEA GSR Part 1 — Governmental, Legal and Regulatory Framework for Safety
International Atomic Energy Agency (IAEA) · International (IAEA Member States) · Safety Requirements
Requires: n/a; requirements for national regulatory bodies — independence, legal authority, licensing/authorization, inspection, enforcement
Renewal: n/a
Standard
ISO 19443:2018 — Quality management systems for the nuclear supply chain (ITNS)
ISO · International · Certifiable QMS standard
Requires: n/a; builds on ISO 9001 with nuclear-specific requirements (safety culture, traceability, risk management, regulatory compliance) for organizations supplying products/services Important To Nuclear Safety (ITNS); certification awarded by accredited bodies (e.g.
Renewal: n/a; certification subject to surveillance/recertification audits per the certification body
Standard
ANSI/ANS-8.26 — Criticality Safety Engineer Training and Qualification Program
American Nuclear Society (ANS) / ANSI · United States (DOE sites; international reference) · Consensus standard
Requires: n/a; defines training subject-matter areas and qualification requirements for Nuclear Criticality Safety Engineers (NCSEs) — invoked as the requirements basis for site CSE qualification cards
Renewal: n/a
Standard
ANSI/ANS-8.1 — Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors
American Nuclear Society (ANS) / ANSI · United States (DOE/NRC fuel-cycle facilities) · Consensus standard
Requires: n/a; fundamental criticality-safety practices for handling, storing, and processing fissionable material outside reactors
Renewal: n/a
Regulation
10 CFR Part 55 — Operators' Licenses
U.S. Nuclear Regulatory Commission (NRC) · United States (federal) · Federal regulation
Requires: n/a; establishes procedures and criteria for issuance, modification, maintenance, and renewal of RO, SRO (and legacy special senior operator) licenses
Renewal: n/a; licenses issued for 6-year terms with requalification
Regulation · flagship
10 CFR Part 50 — Domestic Licensing of Production and Utilization Facilities
U.S. Nuclear Regulatory Commission (NRC) · United States (federal) · Federal regulation
Requires: n/a; two-step licensing: Construction Permit then Operating License; includes Appendix B QA criteria, 50.59 change process, 50.55a codes/standards incorporation
Renewal: n/a
Regulation · flagship
10 CFR Part 52 — Licenses, Certifications, and Approvals for Nuclear Power Plants
U.S. Nuclear Regulatory Commission (NRC) · United States (federal) · Federal regulation
Requires: n/a; one-step alternative: early site permits (ESPs), standard design approvals/certifications (DCs), manufacturing licenses (MLs), combined licenses (COLs); applies to LWRs and non-LWRs
Renewal: n/a; NuScale standard design certified under Part 52 (final rule Jan 2023)
Regulation
10 CFR Part 100 — Reactor Site Criteria
U.S. Nuclear Regulatory Commission (NRC) · United States (federal) · Federal regulation
Requires: n/a; site suitability evaluation factors — exclusion area, low-population zone, population-center distance, atmospheric dispersion, geologic/seismic siting (100.23), meteorology, hydrology, man-related hazards
Renewal: n/a
Regulation · flagship
10 CFR Part 810 — Assistance to Foreign Atomic Energy Activities
U.S. Department of Energy / National Nuclear Security Administration (NNSA) · United States (federal, extraterritorial reach) · Federal export-control regulation
Requires: n/a; implements Atomic Energy Act §57b(2): specific DOE authorization required before transferring unclassified nuclear technology or assistance abroad (enrichment, reprocessing, plutonium fuel fabrication, heavy water, production reactors/accelerators, sensit
Renewal: n/a; authorizations are activity/country specific
Regulation
10 CFR Part 830 — Nuclear Safety Management
U.S. Department of Energy (DOE) · United States (federal, DOE sites) · Federal regulation
Requires: n/a; requires documented safety basis (safety analysis) for DOE hazard category 1, 2, and 3 nuclear facilities; DOE management official approves safety basis
Renewal: n/a
Regulation
10 CFR Part 835 — Occupational Radiation Protection
U.S. Department of Energy (DOE) · United States (federal, DOE sites) · Federal regulation
Requires: n/a; DOE-worker counterpart to NRC Part 20 — occupational dose limits, monitoring, internal dosimetry, ALARA, contamination control, radiation safety training, nuclear accident dosimetry
Renewal: n/a
Regulation
DOE Order 420.1C — Facility Safety
U.S. Department of Energy (DOE) · United States (federal, DOE sites) · DOE Order (directive)
Requires: n/a; DOE facility-safety requirements for nuclear and non-nuclear facilities (natural-phenomena hazards, fire protection, criticality safety interfaces)
Renewal: n/a
Regulation
IAEA Comprehensive Safeguards Agreements (INFCIRC/153) + Additional Protocol (INFCIRC/540)
International Atomic Energy Agency (IAEA) · International (NPT non-nuclear-weapon states) · International safeguards regime
Requires: n/a; states accept safeguards on all source/special fissionable material in peaceful activities and must establish a State System of Accounting for and Control of nuclear material (SSAC); Additional Protocol extends declarations, access, and import/export repo
Renewal: n/a
Regulation
Euratom Treaty Safeguards (Chapter VII) + Commission Regulation (Euratom) No 302/2005
European Commission (Euratom) · European Union · Supranational safeguards regulation
Requires: n/a; Treaty Article 77 safeguards cover all civilian nuclear material in the EU — broader than IAEA (also covers proper use per supply contracts); operators must declare basic technical characteristics, keep operating records, submit nuclear-material accounts;
Renewal: n/a
Regulation
NRC Agreement State Program (Atomic Energy Act §274)
U.S. Nuclear Regulatory Commission + Agreement States · United States (state) · Federal-state regulatory program
Requires: n/a; NRC relinquishes regulatory authority over certain byproduct, source, and limited special nuclear material to states that demonstrate compatible radiation-control programs; licensees then hold state-issued radioactive-materials licenses instead of NRC lic
Renewal: n/a
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