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# Site Map: Nuclear Reactors

This page shows how the U.S. Nuclear Regulatory Commission (NRC) has organized the reactor-related information available through our public Web site. These links will take you directly to the indicated pages on our site.
        - Power Reactors           - Pressurized Water Reactors
          - Boiling Water Reactors
          - Advanced Manufacturing Technologies (AMTs)
          - Digital Twins
        - Operator Licensing           - Regulations, Guidance, and Communications
          - Licensing Process for Operators             - FAQs for New Reactor Operator Licensing
          - Oversight Program
          - Public Involvement in Operator Licensing
          - Related Documents and Other Resources
          - Program Feedback
          - Contact Us
        - Non-Power Facilities           - Event at the National Institute of Standards and Technology (NIST) Center for Neutron Research
          - New Facility Licensing             - MSRR – Abilene Christian University Application                - Application Documents
              - Project Status Dashboard
              - Abilene Christian University
            - Hermes – Kairos Application               - Application Documents
              - Project Status Dashboard
            - Hermes 2 – Kairos Application               - Application Documents
              - Project Status Dashboard
          - Program Management
          - Inspection Reports for Research and Test Reactors
        - Operating Reactors           - Map of Power Reactor Sites
          - Map of Research and Test Reactor Sites
          - Regulations, Guidance, and Communications
          - Operating Reactor Licensing             - Technical Specifications               - Standard Technical Specifications – Operating and New Reactors – Current Versions
              - Operability Guidance
              - Technical Specifications Task Force (TSTF) Travelers
            - License Transfers & Mergers
            - Power Uprates               - Background on Power Uprates
              - Types of Power Uprates
              - Regulatory Process for Submitting/Reviewing Requests
              - Regulations and Guidance                 - Generic Guidance for Power Uprates
                - Past Requests for Additional Information Concerning Power Uprates                   - Measurement Uncertainty Recapture Uprates for Boiling Water Reactors                     - LaSalle 1 & 2
                    - Cooper
                    - Edwin I. Hatch 1 & 2
                    - Pilgrim
                    - River Bend
                    - Peach Bottom 2 & 3
                    - Grand Gulf
                    - Hope Creek
                    - Susquehanna 1 & 2
                  - Measurement Uncertainty Recapture Uprates for Pressurized Water Reactors                     - Surry 1 & 2
                    - Prairie Island 1 & 2
                    - North Anna 1 & 2
                    - Calvert Cliffs 1 & 2
                    - Davis-Besse
                    - Vogtle 1 & 2
                    - Crystal River 3
                    - Seabrook
                    - Palisades
                    - Kewaunee
                    - Indian Point 2
                    - D.C. Cook 2
                    - D.C. Cook 1
                    - Point Beach 1 & 2
                    - Indian Point 3
                    - H.B. Robinson
                    - Sequoyah 1 & 2
                    - South Texas 1 & 2
                    - Waterford 3
                    - Comanche Peak 1 & 2
                    - Beaver Valley 1 & 2
                    - San Onofre 2 & 3
                    - Salem 1 & 2
                    - Watts Bar
                  - Stretch Uprates for Pressurized Water Reactors                     - Millstone 3
                    - Comanche Peak 1 & 2
                    - Palo Verde 1 & 3 (Combined Application)
                    - Indian Point 3
                    - Seabrook
                    - Indian Point 2
                    - Kewaunee
                    - Palo Verde 2
                    - Crystal River 3
                    - Shearon Harris
                    - Braidwood 1 & 2 and Byron 1 & 2 (Combined Application)
                    - Diablo Canyon
                  - Extended Uprates for Boiling Water Reactors                     - Approved Power Uprate Application Information For Duane Arnold
                    - Approved Power Uprate Application Information For Clinton Power Station, Unit 1
                    - Approved Power Uprate Application Information For Brunswick Steam Electric Plant, Unit Nos. 1 and 2
                    - Approved Power Uprate Application Information For Hope Creek
                    - Approved Power Uprate Application Information For Quad Cities 1 & 2
                    - Approved Power Uprate Application Information For Susquehanna 1 & 2
                    - Approved Power Uprate Application Information For Vermont Yankee
                    - Approved Power Uprate Application Information For Dresden Nuclear Power Station, Units 2 and 3
                  - Extended Uprates for Pressurized Water Reactors                     - Approved Power Uprate Application Information For Waterford
                    - Approved Power Uprate Application Information For Ginna
                    - Approved Power Uprate Application Information For Beaver Valley 1 & 2
                    - Approved Power Uprate Application Information For ANO-2
                - Recent Safety Evaluations for Power Uprates
              - Status of Power Uprate Applications                 - Approved Applications for Power Uprates
                - Expected Applications for Power Uprates
                - Pending Applications for Power Uprates
              - Public Involvement
              - Public Meetings
              - Contact Us
            - Reactor License Renewal               - Overview
              - Process
              - Regulations
              - Guidance                 - Schedule and Background For Guidance Updates
              - Public Involvement
              - Commission Papers
              - Status of Initial License Renewal Applications and Industry Initiatives                 - Arkansas Nuclear One, Unit 1
                - Arkansas Nuclear One, Unit 2
                - Beaver Valley Power Station
                - Browns Ferry Nuclear Plant (Initial Renewal)
                - Browns Ferry Nuclear Plant (Subsequent Renewal)
                - Brunswick Steam Electric Plant
                - Calvert Cliffs
                - Catawba
                - Clinton Power Station, Unit 1
                - Columbia
                - Comanche Peak
                - D.C. Cook
                - Cooper
                - Crystal River
                - Davis-Besse
                - Diablo Canyon
                - Dresden
                - Duane Arnold
                - Joseph M. Farley
                - James A. FitzPatrick
                - Fort Calhoun
                - R.E. Ginna
                - Shearon Harris 
                - Edwin I. Hatch
                - Hope Creek
                - Indian Point
                - Kewaunee
                - McGuire
                - Millstone
                - Monticello (Initial Renewal)
                - Monticello (Subsequent Renewal)
                - Nine Mile Point
                - North Anna (Initial Renewal)
                - North Anna (Subsequent Renewal)
                - Oconee (Initial Renewal)
                - Oconee (Subsequent Renewal)
                - Oyster Creek
                - Palisades
                - Palo Verde
                - Peach Bottom (Initial Renewal)
                - Perry
                - Pilgrim
                - Point Beach (Initial Renewal)
                - Point Beach (Subsequent Renewal)
                - Prairie Island
                - Quad Cities
                - Robinson
                - Salem
                - Seabrook
                - South Texas Project
                - St. Lucie (Initial Renewal)
                - St. Lucie (Subsequent Renewal)
                - V.C. Summer (Initial Review)
                - V.C. Summer (Subsequent Renewal)
                - Surry (Initial Renewal)
                - Susquehanna
                - Three Mile Island
                - Turkey Point (Initial Renewal)
                - Vermont Yankee
                - Vogtle
                - Wolf Creek
              - Introduction                 - Environmental Impact of Reactor License Renewal                   - Additional Information on Environmental
                - Reactor License Renewal Decision                   - Continuation of CLB and Conditions of Renewed License
                - Reactor License Renewal Hearing
                - Reactor License Renewal Inspections                   - Frequently Asked Questions (FAQs) About License Renewal Inspection Procedure (IP) 71003, "Post-Appro
                  - License Renewal Inspection Guidance Documents
                - Reactor License Renewal Orientation                   - Additional Information on Orientation
                - Reactor License Renewal Review
                - Reactor License Renewal Safety                   - Additional Information on Safety
                  - Safety Guidance Documents
              - License Renewal Generic Environmental Review
              - Light Water Reactor Sustainability Program                 - Plant Modernization
                - Flexible Plant Operation and Generation
                - Risk-Informed Systems Analysis
                - Materials Research
                - Physical Security
                - Contact Us About Light Water Reactor Sustainability
                - References
            - Resource Estimator for Operating Reactor Licensing               - Estimates for Types of License Amendment Requests
              - Resource Estimates for License Amendment Requests to Adopt Approved Travelers
              - Estimates for Types of Relief Requests
              - Estimates for Exemptions
              - Estimates for COVID-19-Related Licensing Actions
              - Key Influencing Factors 
              - Vignettes
          - Reactor Oversight Process (ROP)             - ROP Framework               - Inspection Manual by Cornerstone
            - Performance Indicators               - Data Dictionary
              - PI Summary Raw Data
            - Inspection Reports for Operating Power Reactors               - List of Inspection Reports (Last 12 months)
              - Data Dictionary
            - ROP Evaluation
            - Plant Summaries
            - Inspection Findings
            - Action Matrix
            - Assessment Letters
            - Cross Cutting Issues
            - ROP References
            - Operating Reactor Analytics
            - Contact Us About Operating Reactor Analytics
          - Reactor Safety Information Topics             - Access Authorization Programs               - Contact Us About Access Authorization
              - Frequently Asked Questions About Access Authorization
            - Baffle-Former Bolts
            - Concrete Degradation at Seabrook Nuclear Power Plant
            - Davis-Besse Reactor Vessel Head Degradation               - Completion Of Requirements Of 2004 Confirmatory Order Modifying License (EA-03-214)
              - Davis-Besse Lessons Learned Task Force                 - Lessons Learned Task Force Report
                - Action Plans
                - Status of Recommendations
                - Meetings for Davis-Besse Lessons Learned Task Force
                - Press Releases
                - Reports to the Commission
              - Undercut Area Toward Nozzle Eleven
              - News and Correspondence
              - Petition Related Documents
              - Public Meetings for Reactor Vessel Head Degradation
              - Transporting New Head to Davis Besse
              - Undervessel Pre-Cleaning - View 3
              - Undervessel Pre-Cleaning - View 2
              - Undervessel Pre-Cleaning Center Incore Nozzle - View 1
              - Overview of the Davis Besse Reactor Head Inspection Area
              - Nozzle Eleven Perspective
              - Looking Up at the Davis Besse Reactor Head Inspection Area
              - Looking Toward Nozzle Eleven
              - Looking Down (second angle) at the Davis Besse Reactor Head Inspection Area
              - Looking Down at the Davis Besse Reactor Head Inspection Area
              - Looking Back Toward Nozzle Three
              - Underneath the Davis Besse Reactor Head
              - Davis Besse Reactor Vessel Head Insulation Top View with Nozzle #3 Removed (Overhead View)
              - Davis Besse Reactor Vessel Insulation Head Top View with Nozzle #3 Removed (Overhead View)
              - Davis Besse Control Rod Drive Open Access Hatch View
              - Containment Access Location
              - Close Up View of Cavity Looking Toward Nozzle Eleven
              - Cavity Looking Toward Nozzle Eleven
              - Downward View of Reactor Vessel Head Cutout Hole - View 3
              - Downward View of Reactor Vessel Head Cutout Hole - View 1
              - 17 Inch Cutout - View 2
              - 17 Inch Cutout - View 1
              - Underneath View of Cutout - Closeup View
              - Underneath View of Cutout
              - Davis-Besse Correspondence Related to NRC Bulletin 2002-01
              - Davis-Besse Correspondence Related to NRC Order EA-03-009
              - References
              - Downward View of Reactor Vessel Head Cutout Hole - View 2
            - Fire Protection Program
            - Fitness-for-Duty Programs               - Part 26 Requirements
              - Industry  Guidance for Reactor Construction FFD (NEI 06-06, Rev. 5) 
              - Frequently Asked Questions
              - Performance Reports
              - History
              - Submitting Fitness for Duty Reports
              - Related Documents and Other Resources
              - Contact Us
            - Human Factors
            - Open Phase Conditions in Electric Power Systems
            - Operating Reactor Maintenance Effectiveness               - Regulations and Guidance
              - Related Documents and Other Resources
              - Maintenance Rule Frequently Asked Questions
            - Point Beach 2003-2006 - Multiple/Repetitive Degraded Cornerstone Column               - Point Beach Summary
              - Public Meetings for Multiple/Repetitive Degraded Cornerstone
              - Supplemental Inspection
              - Related Documents
            - PWR Sump Performance               - Description of the Safety Concern
              - Discovery of Sump Performance Issue
              - Function of the Containment Sump
              - Technical References
            - Reactor Pressure Boundary Integrity Issues for Pressurized Water Reactors               - Overview of Reactor Pressure Boundary Integrity Issues
              - Reactor Coolant System Weld Issues                 - News and Correspondence About Reactor Coolant System Weld Issues
                - Plant-Specific Correspondence About Reactor Coolant System Weld Issues
                - Public Meetings About Reactor Coolant System Weld Issues
                - Correspondence Related to NRC Regulations in 10 CFR 50.55a(g)(6)(ii)(E) and 10 CFR 50.55a(g)(6)(ii)(
              - Pressurizer Issues                 - News and Correspondence
                - References
                - Correspondence Related to NRC Bulletin 2004-01
              - RPV Upper Head Issues                 - News and Correspondence
                - Public Meetings                   - 2019
                - Images
                - Bulletin 2002-01 Plant Specific Information
                - Bulletin 2001-01 Plant Specific Information
                - Bulletin 2002-02 Plant Specific Information
                - NRC Order EA-03-009 Plant Specific Information
                - References
              - RPV Bottom Head Issues                 - Correspondence Related to NRC Bulletin 2003-02
                - Images
                - News and Correspondence
                - Public Meetings
                - References
            - Reactor Vessel Integrity               - Reactor Vessel Integrity Database Version 2.0.1
            - Safety Enhancements After Fukushima
            - Operating Reactor Scram Trending
            - Process for the Ongoing Assessment of Natural Hazard Information (POANHI)               - Seismic Activities Related to the Process for the Ongoing Assessment of Natural Hazard Information (
          - List of Power Reactor Units
          - NRC Contacts for Power and Research & Test Reactors
        - New Reactors           - Advanced Reactors (non-LWR designs)             - Get Involved               - Stakeholder Meetings
              - Stakeholder Position Papers
            - How We're Executing               - Licensing Dashboards
              - Advanced Reactor Ready - By the Numbers
              - Integrated Review Schedule Dashboard                 - Integrated Review Schedule - Deliverable Details
            - Who We're Working With               - Pre-Application Activities                 - General Atomics
                - Kairos Power LLC
                - Natrium
                - eVinci
                - Terrestrial Energy USA Inc.
                - X-Energy LLC
                - TerraPower, LLC
                - Fast Modular Reactor
                - ARC-100
                - Oklo Aurora Powerhouse
                - University of Illinois at Urbana-Champaign
                - Radiant Kaleidos
              - International Cooperation                 - Collaborative Projects with Canada
                - Memorandum of Cooperation Between the Canadian Nuclear Safety Commission (CNSC), the United Kingdom                    - Joint Reports
            - Modernizing How We Regulate               - Rulemaking and Guidance                 - Part 53 – Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors
                - Physical Security Rulemaking
                - Emergency Preparedness Rulemaking
                - Regulatory Review Roadmap For Non-Light Water Reactors
                - Industry-Led Licensing Modernization Project
                - Advanced Reactor Content of Application Project
                - Advanced Nuclear Reactor Generic Environmental Impact Statement (GEIS)
                - NRC-DOE Joint Initiative - Non-LWR Design Criteria
                - Testing Needs and Prototype Plants
                - Fuel Qualification                   - TRi-structural ISOtropic (TRISO) Fuel
                  - Metal Fuel
                  - Molten Salt Fuel
                  - Silicon Carbide Composite Clad Uranium Carbide Fuel
                - Fuel Cycle
                - Endorsement Review of ASME B&PV Code Section III, Division 5, "High Temperature Reactors"
                - Endorsement of ASME/ANS RA-S-1.4 Probabilistic Risk Assessment Standard for Advanced Non-Light Water
                - Digital I&C
              - Policy Development                 - Related Commission Papers
            - References and Training               - NEIMA/Vision and Strategy
              - Nuclear Power Reactor Source Term
              - Reference Materials
              - Training Materials
            - Advanced Reactor Highlights               - 2024
          - Large Light Water Reactors             - Design Certification Applications for New Reactors               - ABWR
              - ABWR Amendment                 - Project Overview for the Design Certification Application Review - ABWR Amendment
                - Design Certification Documents for the ABWR Amendment
                - Review Schedule for the Design Certification Application Review - ABWR Amendment
              - AP1000
              - ESBWR
              - U.S. EPR                 - U.S. EPR Pre-Application Review
                - U.S. EPR Application Documents                   - U.S. EPR Advanced Safety Evaluations
                  - U.S. EPR Final Safety Evaluations
                  - U.S. EPR Safety Evaluations with Open Items
                - U.S. EPR Project Overview
                - U.S. EPR Application Review Schedule
              - US-APWR                 - Correspondence and Public Meetings Related to the US-APWR Design Certification Application
                - US-APWR Design Control Document and Environmental Report
                - US-APWR Pre-Application Review
                - Supplemental Reports Related to the US-APWR Design Certification Application
                - US-APWR Application Review Schedule
              - ABWR Renewal Toshiba
              - ABWR Renewal GE-Hitachi
              - Design Certification Application Review - AP1000 Amendment
            - Early Site Permit Applications for New Reactors               - Clinton Site ESP
              - Grand Gulf Site ESP
              - North Anna Site ESP
              - Vogtle Site ESP
              - PSEG Site ESP
              - Victoria County Station ESP Site
            - Combined License Applications for New Reactors               - Locations of New Nuclear Power Reactor Applications
              - Bell Bend                 - Public Meetings for Bell Bend Nuclear Power Plant Application
                - Combined License Application Documents for Bell Bend Nuclear Power Plant Application
                - Requests for Additional Information Regarding the Combined License Application for Bell Bend Nuclear
                - Application Review Schedule for the Combined License Application for Bell Bend Nuclear Power Plant
              - Bellefonte, Units 3 & 4                 - Public Meetings for Bellefonte Nuclear Station, Units 3 and 4 Application
                - Combined License Application Documents for Bellefonte Nuclear Station, Units 3 and 4                   - Advanced Safety Evaluations for Bellefonte Nuclear Station, Units 3 and 4 Application
                  - Final Safety Evaluations for Bellefonte Nuclear Station, Units 3 and 4 Application
                  - Safety Evaluations with Open Items for Bellefonte Nuclear Station, Units 3 and 4 Application
                - Requests for Additional Information Regarding the Combined License Application for Bellefonte Nuclea
                - Application Review Schedule for the Combined License Application for Bellefonte Nuclear Station, Uni
              - Callaway, Unit 2                 - Public Meetings for Callaway, Unit 2 Application
                - Combined License Application Documents for Callaway, Unit 2 Application
                - Requests for Additional Information Regarding the Combined License Application for Callaway, Unit 2
                - Application Review Schedule for the Combined License Application for Callaway, Unit 2
              - Calvert Cliffs, Unit 3                 - Public Meetings for Calvert Cliffs, Unit 3 Application
                - Combined License Application Documents for Calvert Cliffs, Unit 3 Application                   - Advanced Safety Evaluations for Calvert Cliffs, Unit 3 Application
                  - Final Safety Evaluations for Calvert Cliffs, Unit 3 Application
                  - Safety Evaluations with Open Items for Calvert Cliffs, Unit 3 Application
                - Requests for Additional Information Regarding the Combined License Application for Calvert Cliffs, U
                - Application Review Schedule for the Combined License Application for Calvert Cliffs, Unit 3
              - Comanche Peak Units, 3 & 4                 - Public Meetings for Comanche Peak Nuclear Power Plant, Units 3 and 4 Application
                - Combined License Application Documents for Comanche Peak Nuclear Power Plant, Units 3 and 4 Applicat
                - Requests for Additional Information Regarding the Combined License Application for Comanche Peak Nuc
                - Application Review Schedule for the Combined License Application for Comanche Peak Nuclear Power Pla
              - Fermi, Unit 3                 - Public Meetings for Fermi, Unit 3 Application
                - Combined License Application Documents for Fermi, Unit 3 Application
                - Requests for Additional Information Regarding the Combined License Application for Fermi, Unit 3
                - Application Review Schedule for the Combined License Application for Fermi, Unit 3
              - Grand Gulf, Unit 3                 - Public Meetings for Grand Gulf, Unit 3 Application
                - Combined License Application Documents for Grand Gulf, Unit 3 Application
                - Requests for Additional Information Regarding the Combined License Application for Grand Gulf, Unit 
                - Application Review Schedule for the Combined License Application for Grand Gulf, Unit 3
              - Levy County, Units 1 and 2                 - Public Meetings for Levy County, Units 1 and 2 Application
                - Combined License Application Documents for Levy Nuclear Plant, Units 1 and 2                   - Advanced Safety Evaluations for Levy County, Units 1 and 2 Application
                  - Final Safety Evaluations for Levy County, Units 1 and 2 Application
                - Requests for Additional Information Regarding the Combined License Application for Levy County, Unit
                - Application Review Schedule for the Combined License Application for Levy County, Units 1 and 2
              - Nine Mile Point, Unit 3                 - Public Meetings
                - Application Documents
                - Application Review Schedule
                - Requests for Additional Information
              - North Anna, Unit 3                 - Public Meetings for North Anna, Unit 3 Application
                - Combined License Application Documents for North Anna, Unit 3 Application
                - Requests for Additional Information Regarding the Combined License Application for North Anna, Unit 
                - Application Review Schedule for the Combined License Application for North Anna, Unit 3
              - River Bend Station, Unit 3                 - Public Meetings for River Bend Station, Unit 3 Application
                - Combined License Application Documents for River Bend Station, Unit 3 Application
                - Requests for Additional Information Regarding the Combined License Application for River Bend Statio
                - Application Review Schedule for the Combined License Application for River Bend Station, Unit 3
              - Shearon Harris, Units 2 & 3                 - Public Meetings for Shearon Harris Nuclear Site, Units 2 and 3 Application
                - Combined License Application Documents for Shearon Harris Nuclear Site, Units 2 and 3 Application                   - Advanced Safety Evaluations for Shearon Harris Nuclear Site, Units 2 and 3 Application
                  - Final Safety Evaluations for Shearon Harris Nuclear Site, Units 2 and 3 Application
                - Requests for Additional Information Regarding the Combined License Application for Shearon Harris Nu
                - Application Review Schedule for the Combined License Application for Shearon Harris Nuclear Site, Un
              - South Texas Project, Units 3 & 4                 - Public Meetings for South Texas Project, Units 3 and 4 Application
                - Combined License Application Documents for South Texas Project, Units 3 and 4 Application                   - Advanced Safety Evaluations for South Texas Project, Units 3 and 4 Application
                  - Final Safety Evaluations for South Texas Project, Units 3 and 4 Application
                  - Safety Evaluations with Open Items for South Texas Project, Units 3 and 4 Application
                - Requests for Additional Information Regarding the Combined License Application for South Texas Proje
                - Application Review Schedule for the Combined License Application for South Texas Project, Units 3 an
              - Turkey Point, Units 6 & 7                 - Public Meetings for Turkey Point, Units 6 and 7 Application
                - Combined License Application Documents for Turkey Point, Units 6 and 7 Application                   - Advanced Safety Evaluations for Turkey Point, Units 6 and 7 Application
                  - Final Safety Evaluations for Turkey Point, Units 6 and 7 Application
                - Requests for Additional Information Regarding the Combined License Application for Turkey Point, Uni
                - Application Review Schedule for the Combined License Application for Turkey Point, Units 6 and 7
              - Victoria County Station, Units 1 & 2                 - Public Meetings
                - Application Documents
                - Application Review Schedule
                - Requests for Additional Information
              - Virgil C. Summer, Units 2 & 3
              - Vogtle, Units 3 & 4
              - William States Lee III, Units 1 & 2                 - Public Meetings
                - Application Documents                   - Advanced Safety Evaluations for William States Lee III Nuclear Station, Units 1 and 2 Application
                  - Final Safety Evaluations for William States Lee III Nuclear Station, Units 1 and 2 Application
                - Application Review Schedule
                - Requests for Additional Information
          - How We Regulate             - Regulations, Guidance, and Communications
            - Regulatory Oversight               - Construction Inspection Program for New Reactors                 - Public Meetings and Workshops
                - Inspection Manual
                - Commission Documents
              - Construction Reactor Oversight Process (cROP)                 - Construction Action Matrix Deviations
                - List of Construction Inspection Reports
                - cROP Historical Performance from Previous Quarters
                - Frequently Asked Questions About the Construction Assessment Program
                - Frequently Asked Questions About the Reactor Construction Inspection Program
                - Construction Assessment Reports/Inspection Plans
                - 2023Q2 Construction Action Matrix Summary and Current Regulatory Oversight
                - cROP 2019Q2 Cross Cutting Issues Summary
                - Detailed cROP Description
              - Quality Assurance for New Reactors                 - Regulations, Standard Review Plan, SECY Paper, and NUREG-1055
                - Safety Evaluation Reports Concerning the Revised Basis for QA Programs
                - QA Inspections for New Reactor Licensing                   - 2024
                  - 2021
                - Vendor QA Inspections                   - NRO SECY Paper on Enhancements to the Vendor Inspection Program for New Reactors
                  - Inspection Procedures
                  - Generic Letters
                  - Information Notices
                  - Regulatory Information Summaries
                  - Commercial-Grade Dedication
                  - NUREG-0302, Revision 1 (10 CFR Part 21)
                  - Inspection Reports                     - 2024
                    - 2023
                    - 2022
                    - 2021
                - Nuclear Procurement Issues Corporation (NUPIC) and Industry Interactions
                - Town Hall Meetings on Vendor Oversight                   - 2021
                  - 2023
                - Workshops on Vendor Oversight                   - 2022
                  - 2020
                - Guidance on Implementation of 10 CFR Part 21 Requirements
              - Radiation Protection for New Reactors                 - Public Meetings Regarding Radiation Protection for New Reactors
                - Generic Communications Regarding Radiation Protection for New Reactors
                - Regulations and Standard Review Plan Concerning Radiation Protection for New Reactors
                - Guidance Regarding Radiation Protection for New Reactors
              - Aircraft Impact Assessment (AIA) Inspections

Page Last Reviewed/Updated Wednesday, November 25, 2020

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Page Last Reviewed/Updated Wednesday, November 25, 2020