Nuclear Reactor Regulation

On this Page:

• Office of Nuclear Reactor Regulation
• Division of Engineering and External Hazards (DEX)
• Division of Advanced Reactors and Non-Power Production and Utilization Facilities (DANU)
• Division of Risk Assessment (DRA)
• Division of Safety Systems (DSS)
• Division of New and Renewed Licenses (DNRL)
• Division of Reactor Oversight (DRO)
• Division of Operating Reactor Licensing (DORL)
• Embark Venture Studio
• Division of Resource Management and Administration (DRMA)

Office of Nuclear Reactor Regulation

Director (A): Michael King
Deputy Director for Engineering: Michael Franovich
Deputy Director for New Reactors: Gregory Bowman
Deputy Director for Reactor Safety Programs and Mission Support (A): Jeremy Groom

The Office of Nuclear Reactor Regulation (NRR) is responsible for accomplishing key components of the NRC's nuclear reactor safety mission.  NRR conducts a broad range of regulatory activities in support of the Commission's safety and security strategic goals.  These activities encompass licensing, oversight, siting, rulemaking, and incident response for operating commercial nuclear power reactors, new commercial nuclear power reactors, advanced reactor technologies, and non-power production and utilization facilities.  NRR collaborates with other headquarters and regional offices to accomplish the NRC mission.

Division of Engineering and External Hazards (DEX)

Director (A): Tania Martinez Navedo
Deputy Director (A): Jonathan Evans

Provides technical expertise to support the licensing, oversight, and rulemaking goals of the Office of Nuclear Reactor Regulation.  The division has responsibility for the following technical subject areas:  electrical engineering and electrical power systems, instrumentation and controls (both analog and digital), structural engineering, civil engineering, geotechnical engineering, mechanical engineering, external hazards (hydrology, meteorology, and seismology), in-service testing, and equipment qualification.  Additional functions include:  leadership of the digital instrumentation and controls steering committee, ownership of the dam safety program, and technical liaison with standards committees and international counterparts. 

Electrical Engineering Branch (EEEB)

EEEB reviews and evaluates the functional performance requirements, design, and operation of electrical power systems for operating reactors, new reactors, and advanced reactor design certifications.

Instrumentation & Controls Branch  (EICB)

EICB reviews the functional performance requirements, design, and operation of instrumentation and control systems for operating reactors, new and advanced reactors, and non-power production and utilization facilities. EICB supports licensing, inspection, guidance development, and rulemaking efforts associated with the use of instrumentation and controls in nuclear facilities.

Long Term Operations and Modernization Branch (ELTB)

ELTB leads strategic enhancement of electrical and I&C infrastructure and licensing projects to support new, operating, and long-term operations for operating reactors, including resolution of subsequent license renewal issues and topical reports, enabling implementation of new technologies. Provide technical expertise and enhance domestic and international partnerships for electrical and I&C activities, including participation in domestic and international consensus standards activities. Review relevant operating experience, explore data analytics opportunities, and support issuance of generic communications.

Mechanical Engineering and Inservice Testing Branch (EMIB)

EMIB reviews and evaluates the design, qualification, operation, and in-service testing of mechanical systems and components in operating and new nuclear power plants to provide reasonable assurance that those systems and components are capable of performing their intended functions in accordance with NRC requirements and guidance.

Structural, Civil, Geotech Engineering Branch (ESEB)

ESEB provides technical expertise in the review of light-water reactor and advanced reactor designs. The branch provides technical support and expertise for regional assistance, including regional construction inspection activities, topical reports, rulemakings, allegations, operating experience assessments, development of Generic Communications, and infrastructure development concerning aging effects and license renewals. The branch develops and implements review guidance and infrastructure in the assigned review areas, including seismic analysis of structures, design of safety-related structures, and aging management for structures; ESEB also includes staff that cover geotechnical engineering and human-induced external hazards reviews under 10 CFR Parts 50, 52, 70, 72, and 100.

External Hazards Branch (EXHB)

EXHB provides hydrologic, geologic, seismologic, and meteorological safety reviews. These areas of responsibility include a wide variety of physical science and engineering issues and requirements in 10 CFR Parts 50, 52, 70, 72, and 100 that are used to determine the suitability of sites for prospective nuclear power plants and other nuclear facilities. In addition, the branch is responsible for assessing new information related to natural hazards through the Process for Ongoing Assessment of Natural Hazards Information that may significantly impact operating nuclear power plants and other nuclear facilities. EXHB staff are members of the agency's External Hazard Center of Expertise (EHCOE) which includes the Agency’s Dam Safety Program and geotechnical and human- induced external hazard reviewers DEX and EXHB and in ESEB.

Division of Advanced Reactors and Non-Power Production and Utilization Facilities (DANU)

Director: Jeremy Bowen
Deputy Director: Jonathan Greives
Deputy Director: Mehdi Reisi Fard

Develops and implements risk-informed and performance-based approaches to licensing and oversight of advanced reactors and non-power production and utilization facilities (NPUF), including research reactors, testing facilities, and medical radioisotope facilities.  Conducts the design reviews and initial licensing reviews for advanced reactors and NPUFs submitted under 10 CFR Parts 50 and 52.  Applies insights from engineering, systems analysis, and consequence analysis to the reviews of licensing actions, preparation of regulatory guidance documents, resolution of policy issues, development of operator licensing examinations, and conduct of safety and security inspections.  Supports international coordination programs for the oversight of advanced reactors and NPUFs and consults on the export and import of nuclear technology and material.

Advanced Reactor Policy Branch (UARP)

Leads the development and resolution of policy issues for all activities involving the licensing of advanced reactors.  Institutes transformational change to enable the efficient and effective licensing of advanced reactors. 

Advanced Reactor Licensing Branch (UAL) 1 and 2

Issues permits and licenses to advanced non-light water reactors through the management of pre-application document reviews and reviews of license applications.  Works closely with technical reviewers to conduct right-sized safety focused assessments of the pre-application documents and license applications.

Advanced Reactor Technical Branch (UTB) 1, 2, and 3

Efficiently performs right-sized safety focused assessments of pre-application documents and license applications.  Develops the risk-informed, performance-based regulatory infrastructure for advanced non-LWR reactors.

Non-Power Production and Utilization Facility Oversight (UNPO)

Implements the NRC’s safety and security inspection and operator licensing oversight programs for non-power production and utilization facilities from initial licensing to decommissioning.

Non-Power Production and Utilization Facility Licensing (UNPL)

Implements the policy, programs, and activities, including performing and coordinating licensing and technical reviews, associated with the overall project management for NPUFs.

Division of Risk Assessment (DRA)

Director (A): Meena Khanna
Deputy Director (A): Shilp Vasavada

Develops and implements policies and guidance for the use of probabilistic risk assessments and other risk-informed approaches in regulatory decision-making for light-water reactors. Performs and evaluates probabilistic risk assessments and review of risk-informed licensee programs and approaches to support licensing and oversight activities, evaluates fire protection programs and systems performance, and evaluates severe accident issues as they relate to current generation plants and licensing of new light water reactor designs.  Develops and implements rules, standards, plans, and policy for accident radiological consequence analysis and health physics and provides oversight support of radiation protection programs.  Provides domestic and international expertise for other risk significant activities such as specific safety issue resolution, special inspections, and event and incident response.

PRA Licensing Branch – A  (APLA)

Provides leadership for development and implementation of risk-informed approaches to the NRC’s Part 50 regulations and regulatory processes to support efficient and reliable licensing. Develops guidance for the use of probabilistic risk assessments (PRA) and associated analyses in regulatory decision-making, primarily for operating reactors. Performs efficient and reliable licensing reviews of major risk-informed licensing actions and license applications that have the potential to provide significant flexibility to plant operations (e.g., risk-informed categorization under 10 CFR 50.69 and risk-informed completion times).

PRA Licensing Branch – B  (APLB)

Performs efficient and reliable licensing reviews of license amendment requests and advanced reactor applications primarily related to fire protection, fire safe shutdown, and fire risk for operating and new reactors. Supports reviews of other risk-informed LARs and non-risk-informed LARs for risk insights. Performs fire protection safety review of license renewal, subsequent license renewal, and power uprate applications for operating reactors. Develops and implements risk-informed and performance-based fire protection, fire safe shutdown, fire analysis, and fire risk assessment guidance for use in regulatory decision-making. Reviews operating experience involving fires or fire protection systems and disseminates information on significant issues. Supports consistent application of the fire protection regulations at the Regional Offices.

PRA Licensing Branch – C  (APLC)

Develops and implements guidance for the use of PRA for first-of-a-kind and new reactor licensing applications. Enables efficient and reliable licensing reviews by championing and coordinating the use of risk information to focus resources on areas of greatest safety significance and providing training and technical assistance to other offices and divisions and sharing best practices with other members of the PRA community. For operating reactors, APLC performs efficient and reliable licensing reviews of first-of-a-kind licensing applications, external hazard risk assessments for risk-informed LARs, and other emergent or innovative risk-informed analyses. For advanced reactors, APLC performs efficient and reliable licensing reviews of PRA and severe accident information in licensing applications and uses risk insights to support reviews related to plant security, the reliability assurance program, technical specifications, regulatory treatment of non-safety systems, and inspections, tests, analysis, and acceptance criteria (ITAAC).

PRA Oversight Branch (APOB)

Enabling the safe and secure use of the operating reactor fleet by supporting timely and risk-informed decision making on emergent issues by performing risk assessments to inform the regulatory decision. Specifically supports HQ oversight to allow for efficient and reliable oversight through the effective execution of various aspects of the risk-informed Reactor Oversight Process (ROP), for example, Notice of Enforcement Discretions, Significance Determinations Process, MD 8.3. Including interfaces with other stakeholders such as the Regions, RES and others to solicit feedback and to obtain diverse opinions that could impact the overall significance of an issue. Support and enable specific licensing and inspection issues by leading programs related to PRA, 50.69 risk-informed categorization, and Risk-informed process for evaluations (RIPE). Seeks to improve the infrastructure and tools (e.g., guidance documents, SPAR models, training) necessary for the agency to improve efficiency of oversight and licensing actions via effective risk-informed decisions.

Radiation Protection & Consequence Branch (ARCB)

Establishes standards and guidance in the areas of health physics and radiological accident consequences. Performs efficient and reliable technical evaluations, safety reviews, and development of licensing guidance for health physics, reactor design basis accident radiological consequences assessment, severe accident mitigation alternatives, and related meteorology. Performs these technical evaluations for license amendments and license renewal applications using both deterministic and risk-informed approaches. Supports efficient and reliable oversight by providing guidance to the regional inspectors on the health physics portion of the ROP. Evaluates operating experience to assess the significance of reportable events involving health physics, radiological consequences assessment, and control room habitability.

Division of Safety Systems (DSS)

Director (A): Vic Cusumano
Deputy Director: Vacant

Provides nuclear plant systems-related analysis to assess changes to operating reactor licenses, new reactor applications for design certifications and combined licenses, and generic nuclear plant system methodologies.  This analysis focuses on plant safety-related and non-safety-related systems, core physics, and core thermal hydraulics performance.  Provides technical expertise for other related purposes such as licensing, oversight, event response, rulemaking, and international programs.  Develops programs and guidelines to improve generic technical specifications and provides interpretations of technical specification requirements.

Technical Specifications Branch (STSB)

Implements, interprets, and develops plant Technical Specifications (TS), ensuring that the regulatory approach to plant licensing embodied in the Standard Technical Specifications (STS) is appropriately applied to plant TS, while considering plant-specific licensing bases and the requirements of 10 CFR 50.36, “Technical Specifications.” Provides project management for technical specification development activities.

Nuclear Methods and Fuels Branch (SFNB)

Reviews topical reports and license applications related to the review of nuclear and thermal hydraulic aspects of the reactor core (e.g. core physics, fuel behavior, the reactivity control system, control rod design, and core thermal hydraulic design). Reviews and evaluates policy decisions related to nuclear fuel performance. Reviews spent fuel pool criticality safety and provides support to regional inspectors for spent fuel pool inspections. Reviews advanced fuel and fluence methods, including supporting international meetings related to advance light water reactor fuel concepts international meetings related to advance light water reactor fuel concepts.

Containment and Plant Systems (SCPB)

Reviews and evaluates licensing applications involving auxiliary, support, balance of plant systems, HVAC systems, containment systems, new and spent fuel storage, load handling systems, and cranes. Reviews and evaluates plant methods of addressing internal and external flooding, internally and externally generated missiles, high energy line breaks outside containment, and reactor coolant leakage detection. Performs scoping and screening reviews for containment and balance-of-plant systems to support license renewal and provides support to regional inspection activities.

Nuclear Systems Performance (SNSB)

Reviews nuclear and thermal hydraulic aspects of reactor systems. Reviews changes to operating reactor’s licensing basis including power uprates, supporting safety analyses for fuel transitions, topical report implementation, and changes to plant operation that impact primary plant system performance or supporting analyses. Reviews containment response and methods for both operating and new light-water reactor designs.

Nuclear Methods, Systems, and New Reactors (SNRB)

Reviews new light-water reactor designs and the fuel and systems designs, methodologies and topical reports related to the review of these designs and initial licenses. Reviews nuclear and thermal hydraulic aspects of the reactor core. Reviews changes to licensed passive and small modular reactor licensing bases, and changes or renewals of certified designs that impact the branch’s areas of responsibility. Reviews and evaluates policy decisions related to new light-water reactor designs, fuels and methods.

Division of New and Renewed Licenses (DNRL)

Director: Michele Sampson
Deputy Director: Samuel Lee

Responsible for program management and technical review activities associated with license renewal, new light-water and small modular reactor licensing, and reactor materials engineering issues.  Conducts safety evaluations focused on vessels and internals, piping and head penetrations, and corrosion and steam generators.  Provides technical expertise to support regional activities, special projects, international programs, rulemaking, standards committees, and regulatory and policy activities.  Leads, manages, and facilitates design certification, early site permit, combined license, and license renewal applications review for light-water power reactors. Develops and maintains the necessary programmatic and technical support for new light-water power reactor licensing, license renewal, and reactor materials engineering activities. 

New Reactor Licensing Branch (NRLB)

NRLB provides project management for reviews of new light water reactor design certifications (DC), standard design applications (SDA), early site permits (ESP), construction permits (CP) and combined license (COL) applications, including associated pre-application activities and support to international forums.

License Renewal Projects Branch (NLRP)

NLRP provides project management for the safety review of license renewal and subsequent license renewal applications for operating reactors and coordination with NMSS for the environmental review.

Vessels and Internals Branch (NVIB)

NVIB provides review and evaluation of the design, inspection, evaluation, and repair of vessels and reactor pressure vessel internals, including individual licensing actions, topical reports, ASME Section XI code changes, and license renewal.

Piping and Head Penetrations Branch (NPHP)

NPHP provides review and evaluation of the design, fabrication, inspection, and repair of pumps and valves (pressure boundary aspects), piping and reactor vessel head penetrations, including individual licensing actions, topical reports, ASME code changes, and license renewal.

Corrosion and Steam Generator Branch (NCSG)

NCSG provides chemical, materials, and corrosion engineering review and evaluation of design, fabrication, inspection, and repair issues for neutron absorbing materials, coatings, and steam generators, including individual licensing actions, topical reports, ASME code changes, and license renewals.

Licensing and Regulatory Infrastructure Branch (NLIB)

NLIB provides project management of new light water reactor design certifications (DC), standard design applications (SDA), early site permits (ESP), construction permits (CP), and combined license (COL) applications, including associated pre-application activities, DC and ESP renewal activities, licensing support infrastructure development, and support to international forums.

Division of Reactor Oversight (DRO)

Director: Russell Felts
Deputy Director: Phillip McKenna

Responsible for leading activities associated with inspecting and assessing licensee performance at light-water power reactors and vendors.  Reviews quality assurance programs for operating power reactor licensees, vendors, applicants, and construction licensees.  Verifies effective implementation of commercial-grade dedication programs, systems for reporting defects under 10 CFR Part 21, and processes to prevent use of counterfeit and fraudulent items.  Leads and audits the implementation of the operator licensing program for light-water power reactors and provides oversight of industry training accreditation and establishes policy for design and testing of control room simulators. Evaluates human factors safety and security issues.  Evaluates plant events, communicates lessons learned to cognizant domestic and international groups, and maintains operating experience data collection and coordination. Develops and issues generic communications. 

Reactor Oversight Process (ROP) Inspection Branch (IRIB)

IRIB supports NRR's mission to protect public health, safety and the environment by providing the infrastructure for inspecting and evaluating licensee compliance with regulatory requirements and other standards in an open manner that is risk-informed, objective, predictable and understandable.

Reactor Assessment Branch (IRAB)

IRAB supports NRR’s mission to protect public health, safety and the environment by providing tools for assessing licensee performance. We do this in an open manner that is risk-informed, objective, predictable, and understandable. We will seek to continually improve the ROP, and its associated procedures and policies, learning lessons from its implementation and by soliciting feedback from both internal and external stakeholders.

Generic Communications and Operating Experience Branch (IOEB)

IOEB supports NRR's mission to protect public health, safety and the environment by administering an effective generic communications program as well as an operating experience program that collects, evaluates, and communicates domestic and international reactor operating experience, and applies the lessons learned.

Operating Licensing and Human Factors Branch (IOLB)

IOLB supports NRR's mission to protect public health, safety and the environment by establishing rules, standards, plans, and policy in the areas of operator licensing, as well as evaluating human factors safety and security issues by conducting licensing reviews of human factors engineering and organizational structure, and supporting rulemaking, policy development and implementation, and the development and implementation of program documents concerning human factors engineering.

Quality Assurance and Vendor Inspection Branch (IQVB)

IQVB supports NRR's mission to protect public health, safety and the environment by reviewing and inspecting the implementation of QA programs of applicants for Parts 50 and 52 certifications, permits, and licenses; nuclear steam system suppliers; architect-engineering firms; suppliers of safety-related and commercial-grade products and services; calibration and testing laboratories; and holders of NRC construction permits, operating licenses, and combined licenses. Consistent with the goals of the Vendor Inspection Program Plan, IQVB outreach activities improve communication with our stakeholders which enhances the NRC’s commitment to openness, efficiency, and clarity.

Division of Operating Reactor Licensing (DORL)

Director (A): Jamie Pelton
Deputy Director: Vacant
Deputy Director: Aida Rivera-Varona

Implements the policy, programs, and activities, including coordinating licensing and technical reviews, associated with the overall project management for operating light-water power reactors.  Manages the areas of workload planning for the office's operating and new reactor workload, the beyond-design-basis event assessments, and the operating and new reactor licensing processes, such as topical reports and other special support services.  Serves as point-of-contact and provides an overall liaison with vendors, owner's groups, the Nuclear Energy Institute, and the Electric Power Research Institute.  Develops processes for, and provides the interoffice interface function with RES, NSIR, and NMSS, for NRR Continuity of Operations activities, and other special projects of critical importance to the NRC.

Licensing Data Analytics, Tools, and Assessments Branch (LDATA)

Identifies patterns in data to assist the Office of Nuclear Reactor Regulation (NRR) leadership in effective decision-making and the development of strategies. Implements NRR leadership strategies and vision, with effective performance monitoring, project tracking, and collaborative decision-making across the office. Uses data to improve and optimize licensing processes.

Licensing Projects Branch  (LLPB)

LLPB serves as the agency’s owner of the Topical Report Program which enables efficiency of licensing amendment requests to reduce the burden of licensees. The branch serves as point-of-contact and provides an overall liaison with nuclear vendors, owner's groups, and trade organizations, such as, the Nuclear Energy Institute (NEI), and the Electric Power Research Institute (EPRI). The branch also provides NRR interoffice interface function with Nuclear Regulatory Research (RES), Nuclear Security and Incident Response (NSIR), and Nuclear Material Safety and Safeguards (NMSS), and other special projects of critical importance, to the NRC.

Plant Licensing Branch (LPL) 1, 2-1, 2-2, 3, and 4

The plant licensing branches manages the review and processing of license amendments and other requests requiring NRC approval, and serves as headquarters contact with licensees, the Regions and other stakeholders in matters pertaining to assigned facilities. Project Manager Assignments are based on plants by region.

LPL1: Beaver Valley, Calvert Cliffs, FitzPatrick, Hope Creek, Indian Point, Limerick, Millstone, Nine Mile Point, Peach Bottom, R.E. Ginna, Salem, Seabrook, and Susquehanna 

LPL2-1: Catawba, Farley, Hatch, McGuire, North Anna, Oconee, Summer, Surry, and Vogtle 

LPL2-2: Browns Ferry, Brunswick, Robinson, Sequoyah, Shearon Harris, St. Lucie, Turkey Point, and Watts Bar 

LPL3: Braidwood, Byron, Clinton, TMI/Crane Clean Energy Center, Davis-Besse, D.C. Cook, Dresden, Duane Arnold, Fermi, LaSalle, Monticello, Palisades, Perry, Point Beach, Prairie Island, and Quad Cities

LPL4: Arkansas Nuclear One, Calloway, Columbia, Comanche Peak, Cooper, Diablo Canyon, Grand Gulf, Palo Verde, River Bend, South Texas, Waterford, and Wolf Creek

Embark Venture Studio

Director (A): Undine Shoop

Responsible for the leadership and resource management of core teams dedicated to implementing innovation projects and serving as a focal point for other NRC offices (program and corporate) regarding innovation initiatives that will benefit the nuclear reactor safety program, as well as other NRC business lines.

Division of Resource Management and Administration (DRMA)

Director: Damaris Marcano

Provides mission and program support to the Office of Nuclear Reactor Regulation (NRR) and the Operating Reactor and New Reactor Business Lines. Enables NRR to operate efficiently and effectively by overseeing administrative services, human capital management, information management, financial management, performance management, internal controls, and coordinates the annual Regulatory Information Conference.