NUREG-1350 Volume 33, 2021-2022 Information Digest
Text
AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material Non-NRC Reference Material As of November 1999, you may electronically access Documents available from public and special technical NUREG-series publications and other NRC records at the libraries include all open literature items, such as books, NRCs Library at www.nrc.gov/reading-rm.html. Publicly journal articles, transactions, Federal Register notices, released records include, to name a few, NUREG-series Federal and State legislation, and congressional reports.
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information notices; inspection and investigative reports; licensee event reports; and Commission papers and their Copies of industry codes and standards used in a attachments. substantive manner in the NRC regulatory process are maintained at NRC publications in the NUREG series, NRC regulations, The NRC Technical Library and Title 10, Energy, in the Code of Federal Regulations Two White Flint North may also be purchased from one of these two sources: 11545 Rockville Pike Rockville, MD 20852-2738
- 1. The Superintendent of Documents U.S. Government Publishing Office These standards are available in the library for reference Washington, DC 20402-0001 use by the public. Codes and standards are usually Internet: www.bookstore.gpo.gov copyrighted and may be purchased from the originating Telephone: (202) 512-1800 organization or, if they are American National Standards, Fax: (202) 512-2104 from American National Standards Institute
- 2. The National Technical Information Service 11 West 42nd Street 5301 Shawnee Road New York, NY 10036-8002 Alexandria, VA 22312-0002 Internet: www.ansi.org Internet: www.ntis.gov (212) 642-4900 1-800-553-6847 or, locally, (703) 605-6000 Legally binding regulatory requirements are stated only in A single copy of each NRC draft report for comment is laws; NRC regulations; licenses, including technical available free, to the extent of supply, upon written specifications; or orders, not in NUREG-series publications.
The views expressed in contractor prepared publications in request as follows:
this series are not necessarily those of the NRC.
Address: U.S. Nuclear Regulatory Commission The NUREG series comprises (1) technical and Office of Administration administrative reports and books prepared by the staff (NUREG-XXXX) or agency contractors (NUREG/CR-XXXX),
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Services Branch (3) reports resulting from international agreements Washington, DC 20555-0001 (NUREG/IA-XXXX),(4) brochures (NUREG/BR-XXXX), and E-mail: Reproduction.Resource@nrc.gov (5) compilations of legal decisions and orders of the Facsimile: (301) 415-2289 Commission and the Atomic and Safety Licensing Boards and of Directors decisions under Section 2.206 of the NRCs regulations (NUREG-0750).
Some publications in the NUREG series that are posted at the NRCs Web site address www.nrc.gov/reading-rm/ DISCLAIMER: This report was prepared as an account doc-collections/nuregs are updated periodically and may of work sponsored by an agency of the U.S. Government.
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NUREG-1350, Volume 33 Manuscript Completed: August 2021 Date Published: October 2021 U.S. Nuclear Regulatory Commission Office of Public Affairs Washington, DC 20555-0001 www.nrc.gov
ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) has published the Information Digest annually since 1989. The Digest provides information about agency activities and licensees from the various industries it regulates. It describes the agencys responsibilities and activities, and provides general information on nuclear-related topics. The Information Digest includes NRC and industry data in an easy-to-read format. Infographics help explain the information with visual aids.
The 2021-2022 Information Digest includes NRC data in the appendices and non-NRC data (e.g., International Atomic Energy Agency, Energy Information Administration, and U.S.
Department of Energy) that were updated as of August 10, 2021, including data in maps and graphics. The Digest is an annual publication, with updates to certain non-NRC data every 2 years.
The next Information Digest containing updated data will be published in September 2022.
The Information Digest will include links to the most current information.
The NRC reviews the information from industry and international sources but does not independently verify it. The Web Link Index provides sources for more information on major topics. The NRC is the source of all photographs, graphics, and tables unless otherwise noted.
All information is final unless otherwise noted. Any corrections and updates will appear in the digital version of the publication on the NRC Web site at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1350/.
The NRC welcomes comments or suggestions on the Information Digest. To submit comments, write to the Office of Public Affairs at U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or at opa.resource@nrc.gov.
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CONTENTS ABSTRACT..........................................................................................................................................iii NRC AT A GLANCE..........................................................................................................................xi ACCOMPLISHMENTS AND HIGHLIGHTS FOR 2020-2021...........................................xvii PHOTOS: THE NRC ON THE JOB.............................................................................................xxvi
- 1. NRC: AN INDEPENDENT REGULATORY AGENCY.........................................................1 About the NRC........................................................................................................................ 2 Mission Statement.................................................................................................................. 3 Major Activities........................................................................................................................ 5 Transforming the NRC............................................................................................................ 6 A Typical Rulemaking Process............................................................................................... 7 Organizations and Functions.................................................................................................. 9 Fiscal Year 2021 Budget....................................................................................................... 12
- 2. NUCLEAR ENERGY IN THE U.S. AND WORLDWIDE ..................................................15 Worldwide Electricity Generated by Commercial Nuclear Power........................................ 16 International Strategy 2021-2025........................................................................................ 17 International Activities........................................................................................................... 18
- 3. NUCLEAR REACTORS.............................................................................................................21 U.S. Electricity Generated by Commercial Nuclear Power.................................................. 22 U.S. Commercial Nuclear Power Reactors.......................................................................... 23 Oversight of U.S. Commercial Nuclear Power Reactors...................................................... 28 Reactor License Renewal..................................................................................................... 30 Nuclear Research and Test Reactors................................................................................... 33 New Commercial Nuclear Power Reactor Licensing........................................................... 34 New Licensing of Nonpower Production and Utilization Facilities....................................... 40 Nuclear Regulatory Research............................................................................................... 41
- 4. NUCLEAR MATERIALS............................................................................................................45 Materials Licenses................................................................................................................ 46 Medical and Academic.......................................................................................................... 47 Industrial................................................................................................................................ 48 v
Transportation....................................................................................................................... 49 Materials Security.................................................................................................................. 49 Nuclear Fuel Cycle................................................................................................................ 50 Fuel Cycle Facilities.............................................................................................................. 53
- 5. RADIOACTIVE WASTE.............................................................................................................57 Low-Level Radioactive Waste Disposal............................................................................... 58 High-Level Radioactive Waste Management....................................................................... 59 Transportation....................................................................................................................... 65 Decommissioning.................................................................................................................. 66
- 6. SECURITY AND EMERGENCY PREPAREDNESS.........................................................71 Facility Security..................................................................................................................... 72 Cybersecurity........................................................................................................................ 73 Materials Security.................................................................................................................. 74 Emergency Preparedness.................................................................................................... 74 Incident Response................................................................................................................ 76 Emergency Classifications.................................................................................................... 76 International Emergency Classifications............................................................................... 77
- 7. APPENDICES................................................................................................................................79 Abbreviations........................................................................................................................ 80 Quick-Reference Metric Conversion Tables......................................................................... 83 APPENDIX A: Commercial Nuclear Power Reactors..................................................... 85 APPENDIX B: New Nuclear Power Plant Licensing Applications................................. 102 APPENDIX C: Commercial Nuclear Power Reactors Undergoing Decommissioning and Permanently Shut Down Formerly Licensed To Operate............... 104 APPENDIX D: Canceled Commercial Nuclear Power Reactors................................... 108 APPENDIX E: Commercial Nuclear Power Reactors by Parent Company.................. 115 APPENDIX F: Commercial Nuclear Power Reactor Operating Licenses Issued by Year................................................................................... 117 APPENDIX G: Commercial Nuclear Power Reactor Operating Licenses Expiration by Year, 2024-2055........................................................ 117 APPENDIX H: Operating Nuclear Research and Test Reactors Regulated by the NRC........................................................................................... 118 APPENDIX I: Nuclear Research and Test Reactors under Decommissioning Regulated by the NRC........................................................................... 120 APPENDIX J: Radiation Doses and Regulatory Limits................................................ 120 vi
APPENDIX K: Commercial Nuclear Power Plant Licensing History 1955-2021.......... 121 APPENDIX L: Materials Licenses by State...................................................................123 APPENDIX M: Major U.S. Fuel Cycle Facility Sites....................................................... 124 APPENDIX N: Dry Spent Fuel Storage Designs: NRC-Approved for Use by General Licensees .................................................................... 125 APPENDIX O: Dry Cask Spent Fuel Storage Licensees............................................... 126 APPENDIX P: U.S. Low-Level Radioactive Waste Disposal Compact Membership.... 130 APPENDIX Q: NRC-Regulated Complex Materials Sites Undergoing Decommissioning............................................................... 131 APPENDIX R: Nuclear Power Units by Nation.............................................................. 132 APPENDIX S: Nuclear Power Units by Reactor Type, Worldwide................................ 133 APPENDIX T: Native American Reservations and Trust Lands within a 50-Mile Radius of an Operating Nuclear Power Plant............. 134 APPENDIX U: States with NRC Grant Recipients in Fiscal Year 2020......................... 135 APPENDIX V: Significant Enforcement Actions Issued, 2020...................................... 148 APPENDIX W: Fundamental Laws Governing the U.S. Nuclear Regulatory Commission................................................... 140 APPENDIX X: International Activities: Conventions and Treaties Pertaining to Nuclear Safety, Security, and International Safeguards........................ 141 APPENDIX Y: International Activities: List of Multilateral Organizations, Committees, and Working Groups in which the NRC Participates....... 142 APPENDIX Z: International Activities: List of Import and Export Licenses Issued for 2020...................................................................................... 144 APPENDIX AA: List of Some Major Uses of Radioisotopes in the United States........... 147
- 8. GLOSSARY (includes abbreviations, definitions, and illustrations)......................................151
- 9. WEB LINK INDEX......................................................................................................................181 FIGURES vii
FIGURES NRC: AN INDEPENDENT REGULATORY AGENCY Figure 1. How the NRC Regulates.................................................................................... 2 Figure 2. Transforming the NRC....................................................................................... 6 Figure 3. Typical Rulemaking Process............................................................................. 7 Figure 4. NRC Organizational Chart............................................................................... 10 Figure 5. NRC Regions................................................................................................... 11 Figure 6. NRC Total Authority, FYs 2011-2021.............................................................. 12 Figure 7. NRC FY 2021 Distribution of Budget Authority; Recovery of Enacted NRC Budget.................................................................. 13 NUCLEAR ENERGY IN THE U.S. AND WORLDWIDE Figure 8. Nuclear Share of Electricity Generated by Country........................................ 16 NUCLEAR REACTORS Figure 9. U.S. Gross Electricity Share by Energy Source, 2020.................................... 22 Figure 10. U.S. Electricity Generation by Energy Source, 2015-2020............................ 23 Figure 11. Gross Electricity Generated in Each State by Nuclear Power........................ 24 Figure 12. U.S. Operating Commercial Nuclear Power Reactors.................................... 25 Figure 13. Day in the Life of an NRC Resident Inspector................................................. 26 Figure 14. NRC Post-Fukushima Safety Enhancements................................................. 27 Figure 15. Reactor Oversight Action Matrix Performance Indicators............................... 29 Figure 16. Reactor Oversight Framework......................................................................... 29 Figure 17. License Renewals Granted for Operating Nuclear Power Reactors............... 31 Figure 18. U.S. Commercial Nuclear Power Reactors Years of Operation by the End of 2020....................................................... 31 Figure 19. License Renewal Process............................................................................... 32 Figure 20. Size Comparison of Commercial and Research Reactors.............................. 33 Figure 21. U.S. Nuclear Research and Test Reactors...................................................... 34 Figure 22. The Different NRC Classifications for Types of Reactors............................... 35 Figure 23. New Reactor Licensing Process...................................................................... 36 Figure 24. Locations of New Nuclear Power Reactor Active Applications and Approved Licenses................................................................................... 38 Figure 25. NRC Research Funding, Fiscal Year 2021...................................................... 42 viii
NUCLEAR MATERIALS Figure 26. U.S. Agreement States.................................................................................... 46 Figure 27. NRC Approach to Source Security.................................................................. 49 Figure 28. The Nuclear Fuel Cycle................................................................................... 50 Figure 29. The In Situ Uranium Recovery Process.......................................................... 51 Figure 30. Locations of NRC-Licensed Uranium Recovery Facility Sites........................ 52 Figure 31. Locations of NRC-Licensed Fuel Cycle Facilities............................................ 54 Figure 32. Simplified Fuel Fabrication Process................................................................ 54 RADIOACTIVE WASTE Figure 33. Low-Level Radioactive Waste Disposal.......................................................... 59 Figure 34. Spent Fuel Generation and Storage after Use................................................ 60 Figure 35. Dry Storage of Spent Nuclear Fuel.................................................................. 62 Figure 36. Licensed and Operating Independent Spent Fuel Storage Installations by State.......................................................................... 64 Figure 37. Ensuring Safe Spent Fuel Shipping Containers.............................................. 65 Figure 38. Reactor Phases of Decommissioning............................................................. 66 Figure 39. Power Reactor Decommissioning Status........................................................ 67 Figure 40. Locations of NRC-Regulated Sites Undergoing Decommissioning................ 69 SECURITY AND EMERGENCY PREPAREDNESS Figure 41. Security Components...................................................................................... 73 Figure 42. Emergency Planning Zones............................................................................ 75 Figure 43. The International Nuclear and Radiological Event Scale................................ 77 ix
NRC AT A GLANCE Mission Statement The NRC licenses and regulates the Nations civilian use of radioactive materials to provide reasonable assurance of adequate protection of public health and safety, and to promote the common defense and security, and to protect the environment.
Commission Chairman Christopher T. Hanson Term ends June 30, 2024 Commissioner Jeff Baran Term ends June 30, 2023 Commissioner David A. Wright Term ends June 30, 2025 Vacant Term ends June 30, 2022 Vacant Term ends June 30, 2026 Locations Headquarters:
U.S. Nuclear Regulatory Commission 301-415-7000 Rockville, MD 800-368-5642 Regional Offices:
Region IKing of Prussia, PA 610-337-5000 800-432-1156 Region IIAtlanta, GA 404-997-4000 800-577-8510 Region IIILisle, IL 630-829-9500 800-522-3025 Region IVArlington, TX 817-200-8100 800-952-9677 Headquarters Operations Center Rockville, MD 301-816-5100 The NRC maintains a staffed, 24-hour Operations Center that coordinates incident response with Federal, State, Tribal, and local agencies.
Training and Professional Development Technical Training Center 423-855-6500 Chattanooga, TN Professional Development Center 301-287-0556 Rockville, MD Resident Sites At least two NRC resident inspectors, who report to the appropriate regional office, are assigned at each operating nuclear power plant site.
NRC AT A GLANCE l xi
NRC Fiscal Year 2021 Budget
Total authority: $879 million ($844 million enacted budget and $35 million authorized carryover)
Total authorized staff: 2,868 full-time equivalents
Estimated fees to be recovered: $721.4 million
Separate appropriation for the Office of the Inspector General: $13.5 million
Total research budget: $77 million
- Reactor Program: $55 million
- New/Advanced Reactor Licensing: $18 million
- Materials and Waste: $4 million What Does the NRC Do?
Regulation and guidancerulemaking
Policymaking
Licensing, decommissioning, and certification
Research
Oversight and enforcement
Incident response
Emergency preparedness and response Nuclear Governing Legislation The NRC was established by the Energy Reorganization Act of 1974. The most significant laws that govern the regulatory process of the agency are in Appendix W of this Information Digest. The NRCs regulations are found in Title 10, Energy, of the Code of Federal Regulations (10 CFR). The text of many laws may be found in NUREG-0980, Nuclear Regulatory Legislation.
NRC BY THE NUMBERS U.S. Electricity Generated by Commercial Nuclear Power NRC-licensed nuclear reactors generate about 19 percent of U.S. gross electricity, or about 807 billion kilowatt-hours.
Nuclear Reactors
93 commercial nuclear power reactors operating in 28 States at 55 sites
62 pressurized-water reactors and 31 boiling-water reactors
Four reactor fuel vendors
21 parent operating companies
About 80 different designs
About 5,530 total inspection and assessment hours at each operating reactor in 2020
Licensees expected to shut down or not seek license renewal include the following:
- Palisades (Entergy) will close by May 31, 2022
- Diablo Canyon Units 1 and 2 (Pacific Gas and Electric) plan to close by November 2024 and August 2025, respectively xii l NRC AT A GLANCE
Reactor License Renewal Commercial power reactor operating licenses are valid for 40 years and may be renewed for additional 20-year terms.
94 reactors have been issued initial renewed licenses, including 9 reactors now permanently shut down.
Eight reactors operate under their original licenses.
Subsequent License Renewal This type of licensing would allow plants to operate from 60 to 80 years.
Six reactors at three sites have been issued subsequent renewed licenses.
Seven reactors at three sites have subsequent license renewal applications under review.
Two licensees with a total of five reactors have submitted letters of intent to request subsequent license renewals.
Early Site Permits for New Reactors
Six early site permits have been issued:
- System Energy Resources, Inc., for the Grand Gulf site in Mississippi
- Exelon Generation Co., LLC, for the Clinton site in Illinois
- Dominion Nuclear North Anna, LLC, for the North Anna site in Virginia
- Southern Nuclear Operating Co., for the Vogtle site in Georgia
- PSEG Power, LLC, and PSEG Nuclear, LLC, for a site in New Jersey
- Tennessee Valley Authority for two or more small modular reactor modules at the Clinch River Nuclear Site in Tennessee Combined License Construction and Operating License for New Reactors
Since June 2007, the NRC has received and docketed 18 combined license (COL) applications for 28 new, large light-water reactors. The NRC has received and docketed a COL application for the Oklo advanced reactor.
The NRC suspended or canceled 10 COL application reviews at the request of the applicants for Bell Bend, PA; Bellefonte, AL; Callaway, MO; Calvert Cliffs, MD; Comanche Peak, TX; Grand Gulf, MS; Nine Mile Point, NY; River Bend, LA; Shearon Harris, NC; and Victoria County Station, TX.
The NRC has issued COLs for 14 reactors at Fermi, MI; Levy County, FL; North Anna, VA; South Texas Project, TX; Turkey Point, FL; V.C. Summer, SC; Vogtle, GA; and W.S. Lee, SC.
At the licensees request, six COLs have been terminated at three sites: Levy County Units 1 and 2 (terminated on April 26, 2018); South Texas Project Units 3 and 4 (terminated on July 12, 2018); and V.C. Summer Units 2 and 3 (terminated on March 6, 2019).
Reactor Design Certification
Six reactor design certifications (DCs) have been issued:
- General Electric-Hitachi Nuclear Energys ABWR (Advanced Boiling-Water Reactor)
- Westinghouse Electric Companys System 80+
- Westinghouse Electric Companys AP600
- Westinghouse Electric Companys AP1000
- General Electric-Hitachi Nuclear Energys ESBWR (Economic Simplified Boiling-Water Reactor)
- Korean Electric Power Corporation APR1400 (Advanced Power Reactor)
NRC AT A GLANCEl xiii
One DC application review was completed by NRC staff for the NuScale small modular reactor design and issued a final safety evaluation report. The NRC staff published the proposed NuScale small modular reactor design certification rule for public comment on July 1, 2021.
The NRC completed review of one DC renewal application for the ABWR design. The final rule for the ABWR design is effective September 29. 2021.
Two DC applications for the U.S. EPR (Evolutionary Pressurized-Water Reactor) and US-APWR (Advanced Pressurized-Water Reactor) are suspended at the request of the applicants.
Nonpower Production and Utilization Facilities
Research and Test Reactors
- 31 licensed research and test (nonpower) reactors operate in 21 States.
Medical Radioisotope Facilities
- Two construction permits have been issued to SHINE Medical Technologies, LLC, in Janesville, WI, and Northwest Medical Isotopes, LLC, in Columbia, MO.
- One operating license application is under review (SHINE).
NUCLEAR MATERIALS Materials Licensing
The NRC and the Agreement States have more than 18,000 licensees for medical, academic, industrial, and general users of nuclear materials.
- The NRC regulates nearly 2,200 licenses.
- The 39 Agreement States regulate more than 16,000 licenses.
Connecticut and Indiana have submitted letters of intent to become Agreement States, a process that takes about 5 years to complete, including legislative action within the States.
The agency issues approximately 1,600 new licenses, renewals, or amendments for existing materials licenses annually. The NRC conducts approximately 600 to 800 safety, and security inspections of materials licensees each year.
Nuclear Fuel Cycle
Three uranium recovery sites are licensed by the NRC.
The NRC licenses nine active fuel cycle facilities:
- One uranium hexafluoride conversion facility (ready-idle status)
- Five uranium fuel fabrication facilities
- Two gas centrifuge uranium enrichment facilities (one operating and one under construction)
- One depleted uranium deconversion facility (construction decision pending)
The NRC issues about 45 fuel cycle facility licensing actions per year, including amendments; renewals; new licenses; and safety, environmental, and safeguards reviews.
National Source Tracking System The National Source Tracking System, also known as NSTS, tracks more than 76,000 sources held by about 1,100 NRC and Agreement State licensees. Of those sources, about 52 percent are Category 1 sources and 48 percent are Category 2. The majority are cobalt-60, the most widely used isotope in large sources.
xiv l NRC AT A GLANCE
Domestic Safeguards The NRC and the U.S. Department of Energy (DOE) use the Nuclear Materials Management and Safeguards System (NMMSS) to track transfers and inventories of source and special nuclear material.
Licensees must report their inventories, transfers, purchases, and sales (including import and export) of these materials to the NMMSS. More than 300 licensees report to the NMMSS database, verifying their inventories at least annually by reconciling their transactions against the previous years inventory. The database supports U.S. participation in the Treaty on the Non-Proliferation of Nuclear Weapons.
RADIOACTIVE WASTE Low-Level Radioactive Waste
10 regional compacts
Four State-licensed disposal facilities HIGH-LEVEL RADIOACTIVE WASTE MANAGEMENT Spent Nuclear Fuel Storage
The NRC has issued 81 licenses for independent spent fuel storage installations in 35 States:
- 16 site-specific licenses (two of these facilities are licensed but were never built or operated) this includes the Interim Storage Partners CISF license that was issued September 13, 2021
- 65 general licenses
An application is under review for consolidated interim storage facility for spent fuel in Lea County, NM.
TransportationPrincipal Licensing and Inspection Activities
Approximately 1,000 safety inspections of fuel, reactor, and materials licensees are conducted annually.
Annually, 50-70 new, renewed, or amended container-design applications for the transport of nuclear materials are reviewed.
Approximately 150 license applications for the import and export of nuclear materials from the United States are reviewed annually.
More than 3 million packages of radioactive materials are shipped each year in the United States by road, rail, air, or water. This represents less than 1 percent of the Nations yearly hazardous material shipments.
Decommissioning
Approximately 100 materials licenses are terminated each year. The NRCs materials decommissioning program focuses on the termination of licenses that are not routine and that require complex activities.
25 nuclear power reactors are in various stages of decommissioning (DECON or SAFSTOR).
Three research and test reactors are permanently shut down and in various stages of decommissioning.
11 complex materials sites are in various stages of decommissioning.
Two fuel cycle facilities are in partial decommissioning, and one is undergoing decommissioning.
Five NRC-licensed uranium recovery facilities are in various stages of decommissioning.
NRC AT A GLANCE l xv
SECURITY AND EMERGENCY PREPAREDNESS
Every 2 years, each operating nuclear power plant performs a full-scale emergency preparedness exercise inspected by the NRC and evaluated by the Federal Emergency Management Agency.
Plants conduct additional emergency drills between full-scale exercises to maintain their preparedness and proficiency in responding to emergencies.
The NRC spends about 15,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> a year scrutinizing security at nuclear power plants, including 8,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of force-on-force inspections. These inspections include mock combat drills, which are conducted at each site every 3 years.
The NRC has implemented a comprehensive cybersecurity oversight program for power reactors, which includes routine inspections and requires licensees to isolate critical systems from the Internet.
The NRC Operations Center, located in the agencys Three White Flint North headquarters building, serves as the center when an emergency occurs or when the agency conducts exercises.
xvi l NRC AT A GLANCE
ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021 COVID-19 In March 2020, the NRC formed a task force to lead a coordinated agencywide response to the COVID-19 pandemic. The primary goals were to maintain the agencys important safety and security mission while also protecting employees and mitigating the spread of the virus at NRC worksites.
By April 2020, approximately 98 percent of the agency workforce, including its inspectors, were successfully working remotely.
The task force oversaw the implementation of Federal requirements in response to the pandemic; engaged with other Federal agencies on their COVID response; developed agencywide guidance and protocols; and communicated on related NRC activities with internal and external stakeholders through virtual meetings, collaboration tools, social media, and dedicated internal and external Web pages.
Key NRC actions related to COVID-19 include the following:
Developing COVID-19 guidance for nuclear power plant licensees and nuclear materials licensees
Communicating regularly with nuclear facilities to discuss current activities and future plans, including staffing, reactor operator licensing, reductions in nonessential maintenance, fire brigade staff requirements, and other matters
Providing the nuclear industry with information to facilitate the expedited review of requests for temporary exemptions, such as to work-hour limits, to allow flexibility in maintaining an appropriate workforce to meet the NRCs minimum reactor operator and security staffing requirements
Deferring licensee invoicing for annual fees (10 CFR Part 171) and user fees (10 CFR Part 170) normally due in the third quarter of Fiscal Year (FY) 2020
Informing licensees how to request extensions to requirements to account for special nuclear materials and request temporary relief from some agency requirements while maintaining safety
Providing information to NRC licensees to facilitate expedited review of requests for temporary exemptions from some biennial emergency preparedness exercise requirements
Completing full implementation inspections and engaging stakeholders during development of a draft baseline cyber inspection procedure that will be used in CY 2022.
Approving more than 250 licensing actions seeking temporary flexibilities to maintain the safe and secure operation of reactor licensees during the pandemic
Issuing general enforcement guidance on how the agency will examine potential violations of NRC regulations related to COVID-19
Adjusting inspection plans and schedules to safeguard the health and safety of NRC and licensee staff while effectively implementing the Reactor Oversight Program
Adjusting security and emergency preparedness inspections schedules related to COVID-19
Performing a lessons-learned and best practices review, resulting in recommendations to address information technology and changes to remote oversight when site access may be restricted
Extending public comment deadlines to afford additional opportunities for public involvement during the pandemic
Creating a new NRC eLearning initiative to help parents with children attending school virtually and for adults who want to know more about science, nuclear technology, and the NRC ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021 l xvii
Power Reactors
Completed more than 1,350 licensing actions and other licensing tasks that support operating, new, and advanced reactors, including numerous actions related to the adoption of risk-informed initiatives, topical reports, and the safe transition of operating plants to decommissioning
Provided a revision of NUREG-1409, Backfitting Guidelines, to the Commission
Issued a memorandum to the Commission describing the status of the NRCs review of construction tests and analysis, inspection, and licensing activities for Vogtle Unit 3
Continued preparation for the end of Vogtle construction by risk-informing the baseline inspection program for AP1000 reactors and finalizing plans to transition Vogtle Units 3 and 4 from construction to the operating reactor oversight process
Rolled out a new Web-based portal for licensee submission of proposed alternatives to codes and standards per 10 CFR 50.55a(z)
Provided to the Commission several rulemakings such as the ABWR design certification (DC) renewal, NuScale small modular reactor DC, AP1000 DC extension
Completed several key activities related to accident tolerant fuel (ATF) including issuance of a report by Energy Research, Inc. that covers the performance of the reactor during severe accidents for the current ATF concepts, higher burnup fuel, and fuel with enrichment above five weight percent; redesigning the ATF public Web site; and hosting two large workshops on licensing of higher burnup and increased enrichment fuel
Granted subsequent license renewals for Surry Units 1 and 2, authorizing reactor operation from 60 to 80 years
Accepted for review two subsequent license renewal applications for North Anna Units 1 and 2 and Point Beach Units 1 and 2
Accepted for review the first digital instrumentation and control (DI&C) pilot application for Waterford using the new DI&C licensing process providing for an earlier licensing decision on the safety of the design
Issued a revision to staff guidance regarding the evaluation of defense-in-depth and diversity to address a potential common-cause failure in digital safety systems
Published technology-inclusive guidance for use by the NRC staff in reviewing the instrumentation and controls portions of non-light-water reactor applications
Developed preliminary proposed rule language and held multiple public workshops regarding the safety and security requirements for the 10 CFR Part 53, Licensing and regulation of advanced nuclear reactors, rulemaking on a risk-informed, technology-inclusive regulatory framework for advanced reactors, with a publication target of October 2024
Completed reviews of several topical reports and continued various other preapplication engagement activities with reactor vendors and applicants, including those selected by the Department of Energy, to construct and operate advanced nuclear power reactors under the Advanced Reactor Demonstration Program
Issued several guidance and policy documents to support future licensing of advanced reactors on topics such as fuel qualification methodology; policy, licensing, and environmental considerations associated with micro-reactors; and instrumentation and controls systems
Finalized guidance on a risk-informed process for evaluations to establish a more efficient means to review licensing actions that address issues of low safety significance within the licensing basis
Issued revised guidance to enhance regulatory efficiencies by enabling licensee peer review of newly developed methods for use in probabilistic risk assessments
Completed reviews on all seismic probabilistic risk assessments and external flooding submittals in response to the agencys post-Fukushima actions resulting in safety enhancements and an improved ability to cope with the reevaluated hazards xviii l ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021
Approved multiple applications for the adoption of advanced risk management programs (such as 15 Risk-Informed Completion Times applications and the last National Fire Protection Agency 805 application)
Completed 99 percent of calendar year 2020 required inspection and assessment activities of the Reactor Oversight Process, despite significant challenges due to COVID-19
Issued a new Inspection Manual chapter to assist staff in reviewing licensee evaluations of changes to facility design, procedures, tests, or experiments in instances where a license amendment is not required to make the change
Developed and began implementing an operating experience dashboard to provide staff with centralized access to information and ability to view, search, and use relevant operating experience data and trends
Implemented various data analysis initiatives to enhance and modernize new and operating reactor workload and financial management across multiple business lines
Prepared a rulemaking plan to update and transform the NRCs environmental review process
Published an Advance Notice of Proposed Rulemaking for Alternatives to the Use of Credit Ratings
Issued Interim Staff Guidance, Micro-Reactor Applications, COL-ISG-029, Environmental Considerations Associated with Micro-Reactors
Published proposed rule for the NuScale small modular reactor DC
Issued orders approving the transfers of Indian Point Units 1, 2, and 3 and Three Mile Island Unit 2 licenses for the purpose of decommissioning
Provided technical expertise to the U.S. Navy for decommissioning of the Surface Ship Support Barge under an interagency agreement
Completed 61 force-on-force inspections, testing licensees abilities to protect against the Design Basis Threat during the COVID-19 public health emergency
Reviewed and accepted three industry-proposed revisions to current cybersecurity guidance to enhance the identification and protection of the critical digital assets associated with the safety-related and emergency preparedness functions
Conducted 154 baseline security inspections at operating power reactors and Category I fuel cycle facilities
Issued Revision 6 of Regulatory Guide 1.101, Emergency Planning and Preparedness for Nuclear Power Reactors, which describes and endorses acceptable methods for implementing the emergency preparedness regulations
Issued Revision 1 of NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate Studies, resulting in significant enhancements for use by licensees when analyzing 2020 decennial census data
Continued to synchronize physical security inspections of Vogtle Units 1 and 2 with Unit 3, improving efficiency in the oversight program
Signed a memorandum of understanding with Cooper Nuclear Station to participate in the RAPBack Program, which allows both parties to receive notification of activity on individuals who hold positions of trust or who are under criminal justice supervision or investigation Nonpower Reactors
Granted SHINE Medical Technologies, LLC, an exemption that provides flexibility to procure facility-specific and other components for the construction of the SHINE medical isotope production facility ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021 l xix
Nuclear Materials and Waste
Completed approximately 1,400 radioactive materials licensing actions
Transitioned inspection activities, Integrated Materials Performance Evaluation Program (IMPEP) activities, and public meetings to a remote environment in response to the COVID-19 pandemic to minimize impact to the agencys oversight programs and stakeholder engagement
Completed six IMPEP reviews, including the first consolidated IMPEP of NRC licensing and oversight programs
Issued a revision to Management Directive 5.1, Consultation and Coordination with Governments and Indian Tribes, in July 2020 to ensure that written communications are provided to Federally recognized Indian Tribes for providing input on NRC regulatory actions after the agencys final decision
Completed the revisions of 13 State Agreement procedures to implement the revised Management Directive 5.6, Integrated Materials Performance Evaluation Program
Issued revisions to five State Agreement and State Liaison procedures to support NRC Agreement States and enhance joint oversight of the National Materials Program
Issued a technical evaluation report for Exubrion Therapeutics proposed license application template for the use by the NRC and Agreement States applicants and licensees for use of a tin-117m colloid to treat osteoarthritis in large dogs
Issued five Approved Spent Fuel Storage Casks Certificates of Compliance
Issued Centrus Energy Corp./American Centrifuge Operatings license amendment for the High-Assay Low-Enriched Uranium Demonstration Program
Issued reports for the fuel cycle smarter inspection program and the independent spent fuel storage installation (ISFSI) oversight enhancement initiatives to ensure safety as well as provide for a comprehensive and consistent inspection program
Issued NUREG-2224, Dry Storage and Transportation of High Burnup Spent Nuclear Fuel, which includes approaches for enhancing the effectiveness and efficiency of licensing and certification of high burnup spent nuclear fuel in transportation and dry storage
Endorsed the ISFSI License and Cask CoC Format Content, and Selection Criteria document to improve the dry storage licensing process by applying risk insights to clarify the information required in certificates of compliance and technical specifications and removing or relocating details that are not risk significant
Renewed the license for the Honeywell International uranium conversion plant in Metropolis, IL, after concluding that renewing the license will not pose an undue risk to public health and safety and will not significantly affect the quality of the environment
Renewed the license for the Humboldt Bay ISFSI for an additional 40 years; the renewed license includes implementation of an aging management program to ensure that important-to-safety structures, systems, and components will continue to perform their intended functions during the extended storage period authorized by the renewal
Terminated the materials license for the General Atomics facility in San Diego, CA
Submitted a report to Congress identifying best practices for establishing and operating local community decommissioning advisory boards, as required by the Nuclear Energy Innovation and Modernization Act
Signed a memorandum of understanding with the Environmental Protection Agency to improve coordination and cooperation in the regulation of the in situ recovery process of uranium extraction xx l ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021
Used pre-recorded radio broadcasts both in English and the Navajo Diné language to communicate on NRC activities during the public comment period for the United Nuclear Corporation Church Rock Project Draft Environmental Impact Statement
Issued a license on Sept. 13 to Interim Storage Partners LLC to construct and operate a consolidated interim storage facility for spent nuclear fuel in Andrews, Texas.
Agencywide
Continued to oversee the safe and secure operation of nuclear power plants and fuel cycle facilities, as well as the possession and use of radioactive materials
Made significant progress toward the transformation vision of being a modern, risk-informed regulator, particularly in the areas of innovation; employee retention, recruitment, and development; use of risk insights; and technology adoption
Launched the internal agencywide innovation platform, and collected more than 480 innovation success stories and hosted approximately 20 innovation challenge campaigns
Established a framework to incorporate risk considerations across all business lines and platforms, which was used to help determine certain licensing actions in response to COVID-19 considerations
Provided technology infrastructure and training to allow 98 percent of the NRC workforce to transition to mandatory telework within days due to the COVID-19 pandemic, and increased the use of dashboards to enhance the automated use of data for decisionmaking and data analysis
Established two career development platforms for NRC employees
Overall achievements that contributed to the agencys desired culture efforts:
- Administered three Culture and Climate Surveys to 1,200 employees in March 2020, which created a baseline for culture improvement efforts
- Developed an Agencywide Improvement Strategy and Implementation Plan and delivered presentations to staff.
- Administered the Federal Employee Viewpoint Survey to all employees in September 2020 with 83 percent participation. The results showed 4 percent increase in employee engagement index (78 percent positive) and 3 percent increase in global satisfaction (75 percent positive).
- Conducted discussions with management and champions in 22 offices and regions to review office/region-level culture improvement plans and identify best practices to share more broadly
- Administered a culture pulse survey to all employees in April 2021 with 57 percent participation.
The culture pulse survey showed a slight increase in constructive behavior; a significant decrease in defensive behavior; and increases in perceptions of employee involvement, communication, and adaptability.
- Held three Executive Director for Operations Town Hall meetings to create a dialogue between staff and senior management about emergent topics of wide interest
- Held 17 Leader Behavior Check-In sessions with groups of senior managers in June 2021 to create forums for leadership to model constructive behaviors in the agencys desired culture
Continued implementing innovative solutions via EMBARK Venture Studio to enable and promote a risk-informed mindset within the nuclear reactor safety program and other business lines
Pursued substantial rulemaking activities on topics including American Society of Mechanical Engineers codes and code cases; licensing of advanced reactors; categorical exclusions from environmental reviews; and petitions for rulemaking submitted by members of the public
Implemented Fiscal Year (FY) 2020 eBilling, a public facing, Web-based application for use by NRC licensees, that provides immediate delivery of NRC invoices, customizable e-mail notifications, the capability to view and analyze invoice details, and the convenience to access U.S. Treasury systems to pay invoices ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021 l xxi
Issued 61 escalated enforcement actions under traditional enforcement, the Reactor Oversight Process, and the Construction Reactor Oversight Process; processed 15 enforcement actions that involved civil penalties (14 proposed, 1 imposed) totaling $1,586,413 proposed and $606,942 imposed; 9 were enforcement orders without a proposed civil penalty, and 37 were escalated notices of violation without a proposed civil penalty
Published research results on a variety of topics related to operating facility safety, safety analysis, severe accident analysis, improved methods for risk assessment, embedded digital devices, flood hazard assessment, advanced manufacturing, and fire modeling
Continued collaboration with the DOE under the Nuclear Energy Innovation Capabilities Act through signing a technical addendum on light-water reactor sustainability and MELCOR source term evaluation, and through a separate agreement with DOE on operating experience and data analysis sharing
Continued collaboration with the DOE under the Nuclear Energy Innovation Capabilities Act through signing technical addenda for the National Reactor Innovation Center, on light-water reactor sustainability, and MELCOR source term evaluation, and through a separate agreement with DOE on operating experience and data analysis sharing.
Received 88 educational proposals and 160 research and development (R&D) proposals under the Integrated University Program Funding Opportunity Announcements, grants awarded included 45 educational grants and 15 R&D grants totaling $17.9 million in grants to 33 academic institutions.
International Activities
Represented the NRC as part of U.S. delegations, negotiating agreements for civil nuclear cooperation (Section 123 Agreements) and participating in activities such as meetings of the Nuclear Suppliers Group, International Atomic Energy Agency (IAEA) Board of Governors, and Group of Seven Nuclear Safety and Security Group
Issued 60 licenses to export nuclear materials and equipment
Supported the development of enhanced regulatory infrastructure for radiological sources, research reactors, and nuclear power plant safety and security around the world through the provision of technical expertise and assistance funding thereby reinforcing U.S. Government national security and foreign policy objectives
Participated in a U.S. Government delegation to international meetings addressing the implementation of treaties and conventions, including the Technical Meeting of Representatives to the Convention on the Physical Protection of Nuclear Materials (CPPNM) and its Amendment (A/CPPNM), and the meeting of the Preparatory Committee for the Conference of the Parties to the Amended CPPNM
Participated in hundreds of virtual meetings with regulatory counterparts after international travel was suspended due to COVID-19
Continued work under a first-of-a-kind memorandum of cooperation with the Canadian Nuclear Safety Commission to increase regulatory effectiveness through collaboration on the technical reviews of advanced reactors and small modular reactors
Supported establishment of the Framework for Irradiation Experiments with the Organization for Economic Co-operation and Development/Nuclear Energy Agency to provide testing and examination capabilities for fuels and materials research to support new reactor technologies xxii l ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021
Administration
Processed 288 Freedom of Information Act (FOIA) requests and 24 appeals in FY 2020, with 81 FOIA requests and 3 FOIA appeals pending by the end of FY 2020
Conducted 155 investigation cases by the Office of Investigations for FY 2020 including 110 investigations, 60 of which were carried over from FY 2019, and also 45 assists to staff, 5 of which were carried over from FY 2019
Conducted agency outreach to audiences interested in NRC activities, including through the use of social media
Awarded and administered the agencys acquisition portfolio with obligations estimated more over $255 million in FY 2020 Public Meetings and Involvement
Revised the agencys public meeting policy and defined new public meeting categories to interact more effectively with stakeholders and the public
During calendar year 2020 conducted approximately 639 open public meetings addressing a full range of NRC issues to support transparency with agency stakeholders and conducted 31 closed meetings
Conducted 10 full committee meetings of the Advisory Committee on Reactor Safeguards and approximately 47 subcommittee meetings in fiscal year 2021; all of the ACRS meetings during the fiscal year were conducted virtually in response to COVID-19
Held four public meetings of the Advisory Committee on the Medical Uses of Isotopes in calendar year 2020
Hosted the first ever, all-virtual Regulatory Information Conference, which was also the highest attended to date with more than 4,300 people attending and 50 countries represented
Created a new NRC eLearning initiative for children and adults who would like to know more about science, nuclear technology, and the NRC News and Information
Maintained the NRC Web site and free listserv subscription services at https://www.nrc.gov/
public-involve/listserve.html to post and distribute NRC news releases
Shared information with the public using social media through platforms that address the major categories of social communication, with a focus on social networking and microblogging (Facebook, LinkedIn and Twitter, respectively)
In calendar year 2020, gained 960 followers on Twitter and sent 470 tweets; gained more than 880 page likes and published approximately 280 posts on Facebook; gained more than 3,000 followers and published approximately 100 posts on LinkedIn.
Issued 146 news releases in FY 2020 For more information on the agencys accomplishments, go to https://www.nrc.gov/reading-rm/
doc-collections/congress-docs/.
ACCOMPLISHMENTS AND HIGHLIGHTS 2020-2021 l xxiii
CONTACT US U.S. Nuclear Regulatory Commission 800-368-5642 301-415-7000 Hearing Impaired Access TTY:
240-428-3217 https://www.nrc.gov Public Affairs 301-415-8200 fax: 301-415-3716 e-mail: opa.resource@nrc.gov Public Document Room 800-397-4209 fax: 301-415-3548 Employment Human Resources: 301-415-7400 General Counsel Intern Program Honor Law Graduate Program or 2-Year Judicial Clerkship Program:
301-415-1515 Contracting Opportunities Small Business:
800-903-7227 License Fee Help Desk 301-415-7554 e-mail: fees.resource@nrc.gov Mailing Address U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Delivery Address NRC Storage and Distribution Facility 4934 Boiling Brook Parkway Rockville, MD 20852 xxiv
REPORT A CONCERN Emergency Report an emergency involving a nuclear facility or radioactive materials, including the following:
any accident involving a nuclear reactor, nuclear fuel facility, or radioactive materials
lost or damaged radioactive materials
any threat, theft, smuggling, vandalism, or terrorist activity involving a nuclear facility or radioactive materials Call the NRCs 24-Hour Headquarters Operations Center: 301-816-5100.
The NRC accepts collect calls. The agency records all calls to this number.
Non-Emergency This includes any concern involving a nuclear reactor, nuclear fuel facility, or radioactive materials.
You may send an e-mail to allegations@nrc.gov. However, because e-mail transmission may not be completely secure, if you are concerned about protecting your identity, it is preferable that you contact us by telephone or in person. You may contact any NRC employee (including a resident inspector) or call:
The NRCs Toll-Free Safety Hotline: 800-695-7403 Calls to this number are not recorded between the hours of 7 a.m. and 5 p.m. eastern time. However, calls received outside these hours are answered by the Headquarters Operations Center on a recorded line.
Some materials and activities are regulated by Agreement States, and concerns should be directed to the appropriate State radiation control program, a list of which can be found at https://scp.nrc.gov/
allegations.html.
THE NRCS OFFICE OF THE INSPECTOR GENERAL The Office of the Inspector General (OIG) at the NRC established the OIG Hotline to provide NRC employees, other government employees, licensee and utility employees, contractor employees, and the public with a means of confidentially reporting suspicious activity to OIG concerning fraud, waste, abuse, and employee or management misconduct. Mismanagement of agency programs or danger to public health and safety may also be reported through the hotline.
It is not OIG policy to attempt to identify people contacting the OIG Hotline. People may contact OIG by telephone, through an online form, or by mail. There is no caller identification feature associated with the hotline or any other telephone line in the Inspector Generals office. No identifying information is captured when you submit an online form. You may provide your name, address, or telephone number, if you wish.
Call the OIG Hotline:
800-233-3497 7 a.m. - 4 p.m. (eastern time)
After hours, please leave a message.
xxv
NRC inspectors keep a close eye on construction NRC Office of Nuclear Security and Incident Response activities to ensure NRC regulations are being Director Mirela Gavrilas observes new construction met at Vogtle Units 3 and 4, in Georgia. activities at Vogtle Units 3 and 4, in Georgia.
PHOTOS:
NRC ON THE JOB NRC inspectors (left to right) Katherine Warner, Liz Region IV Health Physicist Linda Gersey (right)
Andrews and Mark Henrion observe workers preparing conducts radiological surveys and collects soil samples and pouring concrete for a dry cask storage pad on at the Sequoyah Fuels plant near Gore, Oklahoma.
the Three Mile Island plant site in Pennsylvania. This site is undergoing decommissioning.
xxvi
Jared Nadel, NRC senior resident inspector at the Oconee Nuclear Station in South Carolina, tracks outage work on a licensee-provided iPad, checks work email on his NRC tablet, reviews his latest inspection report on his home computer and keeps his NRC laptop ready for the next virtual meeting.
Using Microsoft Teams, Ryan Craffey, a Region III materials inspector, successfully conducts a virtual inspection, observing in real-time the licensees preparations and assessing the effectiveness of their safety practices.
xxvii
Chairman Christopher T. Hanson (left) observes plant operations, including a stop in the control room during his visit to the Salem and Hope Creek nuclear power plants in New Jersey.
NRC Senior Instructor Jeff Griffis teaches a virtual class from the agencys Technical Training Center in Chattanooga, Tennessee.
xxviii
NRC Division Director Chris Miller observes new construction activities at Vogtle Units 3 and 4, in Georgia.
Nuclear Regulator Apprenticeship Network participant Hayden Page visits the plants condenser containment system at the Sequoyah nuclear power plant in Tennessee.
xxix
NRC Commissioner David Wright (purple shirt) tours Arkansas Nuclear One in Russellville, Arkansas, with Entergy and NRC staff before observing a security exercise. Photo courtesy of Entergy.
NRC Region I Inspector Juan Ayala in Wilmington, Region IV health physicist Rob Evans completes Delaware, conducts an inspection to ensure a nuclear his inspection at the 600-acre site in Gore, gauge is being properly handled and secured. Oklahoma, where the Sequoyah Fuels Corporation operated a uranium conversion facility.
xxx
Indian Point nuclear power plant control room operators prepare for the final insertion of control rods in the Unit 3 reactor, part of the permanent shutdown of the site in New York. Not pictured NRC inspectors watching operations.
The reactor vessel and vessel head arrive at the V.C. Summer site South Carolina. The parts traveled by rail from the Port of Charleston by rail and on a Schnabel cara specialized freight car designed to carry heavy and oversized loads. Courtesy of SCANA/SCE&G.
xxxi
NRC Office of Nuclear Reactor Regulation Director Andrea Veil observes new construction activities at Vogtle Units 3 and 4, in Georgia.
NRC Region II Inspector Nick Peterka pauses for a moment during an inspection of the Keowee Hydro Station near the Oconee Nuclear Station in South Carolina.
xxxii
Edison Fernandez (left), a Region III specialist in refueling outage activities and welding, makes an unannounced inspection at the Palisades nuclear power plant to observe some emergent repair work and conduct final examinations on a nozzle weld during a refueling outage.
NRC staff participate in a hybrid incident response exercise with some staff online and others working from the Headquarters Operations Center in Rockville, Maryland.
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1 NRC: AN INDEPENDENT REGULATORY AGENCY
ABOUT THE NRC The U.S. Nuclear Regulatory Commission (NRC) is an independent agency created by Congress.
The NRC regulates the Nations civilian commercial, industrial, academic, and medical uses of nuclear materials.
The NRCs scope of responsibility includes regulating commercial nuclear power plants; nonpower production and utilization facilities including research and test reactors (RTRs); nuclear fuel cycle facilities; medical, academic, and industrial uses of radioactive materials; the decommissioning of licensed facilities and sites; and the transport, storage, and disposal of radioactive materials and wastes. The agency issues licenses for and oversees the use of radioactive materials and certifies nuclear reactor designs, spent fuel storage casks, and transportation packages. The agency also licenses the import and export of radioactive materials, and works closely with its international counterparts to enhance nuclear safety and security worldwide. To fulfill its responsibilities, the NRC performs five principal regulatory functions, as seen in Figure 1. How the NRC Regulates.
Figure 1. How the NRC Regulates How We Regulate 1 Regulations and Guidance
- Rulemaking
- Guidance Development
- Generic Communications
- Standards Development 4 Operational 5 Support for Decisions 2 Licensing,
- Research Activities Decommissioning, Experience and Certification
- Risk Assessment
- Events Assessment
- Performance Assessment
- Licensing
- Generic Issues
- Advisory Committee Activities
- Decommissioning
- Adjudication
- Certification 3 Oversight
- Inspection
- Assessment of Performance
- Enforcement
- Allegations
- Investigations
- Incident Response
- 1. Develop regulations and guidance for applicants and licensees.
- 2. License or certify applicants to use nuclear materials, operate nuclear facilities, and decommission facilities.
- 3. Inspect and assess licensee operations and facilities to ensure licensees comply with NRC requirements, respond to incidents, investigate allegations of wrongdoing, and take appropriate followup or enforcement actions when necessary.
- 4. Evaluate operational experience of licensed facilities and activities.
- 5. Conduct research, hold hearings, and obtain independent reviews to support regulatory decisions.
2 l NRC: AN INDEPENDENT REGULATORY AGENCY
MISSION STATEMENT The NRC licenses and regulates the Nations civilian use of radioactive materials to provide reasonable assurance of adequate protection of public health and safety, to promote the common defense and security, and to protect the environment.
Vision Demonstrate the Principles of Good Regulation in performing the agencys mission.
To be successful, the NRC must not only excel in carrying out its mission but must do so in a manner that engenders the trust of the public and stakeholders. The Principles of Good Regulation independence, openness, efficiency, clarity, and reliabilityguide the agency. They affect how the NRC reaches decisions on safety, security, and the environment; how the NRC performs administrative tasks; and how its employees interact with each other as well as with external stakeholders. By adhering to these principles, the NRC maintains its regulatory competence, conveys that competence to stakeholders, and promotes trust in the agency. The agency puts these principles into practice with effective, realistic, and timely actions.
Principles of Good Regulation Independence: Nothing but the highest possible standards of ethical performance and professionalism should influence regulation.
Openness: Nuclear regulation is the publics business, and it must be transacted publicly and candidly.
Efficiency: The highest technical and managerial competence is required and must be a constant agency goal.
Clarity: Regulations should be coherent, logical, and practical. Agency positions should be readily understood and easily applied.
Reliability: Regulations should be based on the best available knowledge from research and operational experience.
Strategic Goals Safety: Ensure the safe use of radioactive materials.
Security: Ensure the secure use of radioactive materials.
Statutory Authority The Energy Reorganization Act of 1974 created the NRC from a portion of the former Atomic Energy Commission. The new agency was to independently overseebut not promotethe commercial nuclear industry so the United States could benefit from the use of radioactive materials while also protecting people and the environment. The agency began operations on January 18, 1975. The NRCs regulations can be found in Title 10, Energy, of the Code of Federal Regulations (10 CFR).
The principal statutory authorities that govern the NRCs work can be found on its Web site (see the Web Link Index for more information).
See the complete list of the NRCs authorizing legislation in Appendix W.
NRC: AN INDEPENDENT REGULATORY AGENCY l 3
The NRC, its licensees (those licensed by the NRC to use radioactive materials), and the Agreement States (States that assume regulatory authority over certain nuclear materials) share responsibility for protecting public health and safety and the environment. Federal regulations and the NRCs regulatory program play a key role. Ultimately, however, the licensees bear the primary responsibility for safely handling and using radioactive materials.
On September 28, 2018, the Nuclear Energy Innovation Capabilities Act of 2017 was signed into law. The Act requires the U.S. Department of Energy (DOE) and the NRC to enter into a memorandum of understanding (MOU) on certain topics related to advanced reactors and authorizes them to enter into an MOU on additional topics in this area. The NRC and DOE signed an MOU to implement provisions of the Act in October 2019.
On January 14, 2019, the Nuclear Energy Innovation and Modernization Act (NEIMA) was signed into law. NEIMAs provisions are varied and have impacts across the agency.
NEIMA has three stated objectives:
- 1. To provide a revised framework for fee recovery by the NRC to ensure the availability of resources to meet industry needs without burdening existing licensees unfairly for inaccurate workload projections or premature existing reactor closures.
- 2. To support the development of expertise and regulatory infrastructure necessary to allow innovation and the commercialization of advanced nuclear reactors.
- 3. To foster more efficient regulation of uranium recovery.
The NRC is in the process of implementing the various provisions of NEIMA. The agency has already submitted multiple reports to Congress establishing performance metrics and milestone schedules for requested activities of the Commission. The NRC is also taking actions related to the licensing process for commercial advanced reactors and research and test reactors. The NRC is committed to meeting the requirements of NEIMA and is working diligently to do so.
NRC regulations are contained in Title 10, Energy, of the Code of Federal Regulations, Chapter 1, Parts 1 to 199.
4 l NRC: AN INDEPENDENT REGULATORY AGENCY
MAJOR ACTIVITIES The NRC fulfills its responsibilities by doing the following:
licensing the design, and overseeing construction, operation, and decommissioning of commercial nuclear power plants and other nuclear facilities
licensing the possession, use, processing, handling, exporting, and importing of nuclear materials
establishing national policy and standards for the safe disposal of low-level radioactive waste
certifying the design, and overseeing construction, and operation of commercial transportation casks for radioactive materials and waste
licensing the design, and overseeing construction, and operation of spent fuel storage casks and interim storage facilities for spent fuel and high-level radioactive waste
licensing nuclear reactor operators
licensing uranium enrichment facilities
conducting research to support regulatory framework and to address potential reactor and other nuclear facility safety issues
collecting, analyzing, and disseminating information about the operation of commercial nuclear power reactors and certain nonreactor activities
issuing safety and security regulations, policies, goals, and orders that govern nuclear activities
interacting with other Federal agencies, foreign governments, and international organizations on safety, security, and nonproliferation issues
conducting investigations of alleged violations by NRC licensees that may result in criminal, civil, or administrative penalties
inspecting NRC licensees to ensure adequate performance of safety and security, programs
enforcing NRC regulations and the conditions of NRC licenses and imposing, when necessary, civil sanctions and penalties
conducting public hearings on nuclear and radiological safety, security, and environmental concerns
implementing international legal commitments made by the U.S. Government in treaties and conventions
developing working relationships with State and Tribal governments
maintaining an incident response program and overseeing required emergency response activities at NRC-licensed facilities
implementing lessons learned from the March 2011 nuclear accident in Japan to enhance safety at U.S. commercial nuclear facilities
transforming the agency one decision at a time into a modern, risk-informed regulator that promotes and embraces innovative approaches to achieve the agency mission (see Figure 2.
Transforming the NRC)
involving the public in the regulatory process through meetings, conferences, and workshops; providing opportunities for commenting on proposed new regulations, petitions, guidance documents, and technical reports; offering multiple ways to report safety concerns; and providing documents under the Freedom of Information Act and through the NRCs Web site (see Figure 3. A Typical Rulemaking Process)
engaging and informing the public through social media platforms and by providing interactive, high-value datasets (data in a form that allows members of the public to search, filter, or repackage information)
NRC: AN INDEPENDENT REGULATORY AGENCY l 5
TRANSFORMING THE NRC Figure 2. Transforming the NRC How is the NRC transforming into a modern, risk-informed regulator?
Be riskSMARTmaking sound decisions while accepting well-managed risks in decisionmaking.
Focus on Our Peoplemaintaining an engaged and highly skilled workforce now and in the future.
Innovatemaking timely decisions that take into account different viewpoints and fully explored options.
Use Technologyworking smarter, including using data analytics to highlight areas for regulatory attention and improvement.
The NRCs Transformation Journey Over the past several years, the NRC has been transforming to realize its vision of becoming a modern, risk-informed regulator and be in the best position to continue meeting its important safety and security mission well into the future. Transformation will help the agency keep pace with the highly dynamic, interconnected environment in which it operates and regulate an innovative industry that has new technologies. Transforming also provides the NRC an opportunity to re-evaluate the way it conducts business to streamline processes and procedures and maximize efficiencies to better serve the American public.
The NRCs transformation vision is supported by the four focus areas outlined above. Each of the four focus areas is supported by initiatives aimed at streamlining work processes, advancing the use of new information technology, systematizing the appropriate consideration of risk in decisionmaking and encouraging innovative solutions to agency challenges.
The NRC anticipates that the efficiencies gained by transformation will allow the staff to make more timely and better quality decisions vital for accomplishing the agencys safety and security mission.
As the agency continues its transformation journey, stakeholder engagement is important, and the agency is communicating its progress through public meetings and conferences, as well as through the NRC Web site. For more information on the agencys transformation journey, visit https://www.nrc.gov/about-nrc/plans-performance/modern-risk-informed-reg.html.
6 l NRC: AN INDEPENDENT REGULATORY AGENCY
A TYPICAL RULEMAKING PROCESS The process of developing regulations is called rulemaking. The NRC initiates a new rule or a change to an existing rule when there is a need to do so to protect public health and safety.
Additionally, any member of the public may petition the NRC to develop, change, or rescind a rule.
The Commission directs the staff to begin work on a new rulemaking activity through approval of a staff rulemaking plan.
Figure 3. A Typical Rulemaking Process A TYPICAL RULEMAKING PROCESS RULEMAKING TRIGGERS COMMISSION
- Congress/Executive order REVIEW AND APPROVAL OF
- Commission/EDO direction DRAFT FINAL
- Staff-identified need RULE
- Petition for rulemaking COMMISSION PUBLIC INVOLVEMENT/
- Commission issues REVIEW AND START STAKEHOLDER INPUT staff requirements APPROVAL OF RULEMAKING
- Advance notice of memorandum proposed rulemaking
- Staff resolves PLAN
- Regulatory basis Commission
- Preliminary proposed comments rule language
- Public meeting STAKEHOLDER INPUT STAFF EVALUATES PUBLIC COMMENTS PUBLISH FINAL RULE RULE TAKES
- Final environmental EFFECT PUBLISH PROPOSED assessment RULE FOR COMMENT
- Final regulatory
- Draft environmental analysis
- Final guidance RULE assessment COMPLIANCE
- Draft regulatory COMMISSION REVIEW AND APPROVAL OF DRAFT PROPOSED RULE DEADLINE analysis (cost-benefit)
- Commission issues staff
- Draft guidance requirements memorandum
- Public meeting
- Staff resolves Commission comments Regulatory Basis A regulatory basis document is an analysis that describes the technical, legal, and policy information that supports changes to the NRCs regulations. It describes why the current regulation needs to be updated, explains how a change in the regulations will resolve the problem, and discusses other regulatory options to potentially address the problem. It provides a high-level discussion of the costs and benefits of each option, and identifies any backfitting and forward fitting considerations. For each rulemaking, the NRC determines whether development of a regulatory basis is necessary based on the regulatory issues involved. If development of a regulatory basis is warranted, it is generally published for public comment. Any comments received on the regulatory basis would be considered in the development of the proposed rule.
NRC: AN INDEPENDENT REGULATORY AGENCY l 7
Proposed Rules Each proposed rule that involves significant matters of policy is sent to the NRC Commission for approval. Less significant rules may, with Commission approval, be signed by an NRC staff manager.
If approved, the proposed rule is published in the Federal Register and usually contains the following items:
the background information about the proposed rule
an address for submitting comments
the date by which comments must be submitted to ensure consideration by the NRC
an explanation indicating why the rule change is thought to be needed
the proposed text to be changed Usually, the public is given 30 to 90 days to provide written comments, although not all rules are issued for public comment. Generally, the agency does not collect comments on rules that concern agency organization, procedure, practice, or rules for which delaying their publication to receive comments would be contrary to the public interest and not practical.
Final Rules Once the public comment period has closed for the proposed rule, the staff analyzes the comments, makes any needed changes, and prepares a final rule for approval by the Commission or delegated NRC manager. Upon approval, the final rule is published in the Federal Register and usually becomes effective 30 days later.
Direct Final Rulemakings When appropriate, the NRC can shorten the traditional rulemaking process by using a direct final rulemaking process. This process is used only for regulatory changes that the NRC believes are noncontroversial. In a direct final rule, a companion proposed rule is published at the same time as the direct final rule. If there are no significant and adverse comments on the proposed rule, the direct final rule becomes effective. If there are significant and adverse comments, the direct final rule is withdrawn and the rulemaking proceeds as a typical final rule addressing public comment.
Advance Notice of Proposed Rulemaking For especially important or complex rules, the NRC may engage the public at the earliest stages of rulemaking to define the scope and content of the rule. One way of doing this is through an Advance Notice of Proposed Rulemaking. The notice requests public comment well in advance of the proposed rulemaking stage. The notice describes the need for the proposed action but discusses only broad concepts. The NRC may also conduct public meetings at this stage to gather direct input on the rulemaking.
Rulemaking Information The public can access a centralized, Web-based tracking and reporting system, which provides near-real-time updates on all NRC rulemaking activities on the NRC Web site at https://www.nrc.gov/
about-nrc/regulatory/rulemaking/rules-petitions.html.
8 l NRC: AN INDEPENDENT REGULATORY AGENCY
ORGANIZATIONS AND FUNCTIONS The NRCs Commission has five members nominated by the President of the United States and confirmed by the U.S. Senate for 5-year terms. The members terms are staggered so one Commissioners term expires on June 30 of each year. The President designates one member to serve as Chairman. The Chairman is the principal executive officer and spokesperson of the agency.
No more than three Commissioners can belong to the same political party. The Commission as a whole formulates policies and regulations governing the safety and security of nuclear reactors and materials, issues orders to licensees, and adjudicates legal matters brought before it. The Executive Director for Operations carries out the policies and decisions of the Commission and directs the activities of the program and regional offices (see Figure 4. NRC Organizational Chart).
Commissioner Term Expiration*
Christopher T. Hanson Jeff Baran David A. Wright Vacant Vacant Chairman June 30, 2023 June 30, 2025 June 30, 2022 June 30, 2026 June 30, 2024
- Commissioners listed by seniority.
The NRC is headquartered in Rockville, MD, and has four regional offices. They are located in King of Prussia, PA; Atlanta, GA; Lisle, IL; and Arlington, TX.
The NRCs corporate offices provide centrally managed activities necessary for agency programs to operate and achieve goals. Corporate support is needed for a successful regulatory program that include such as Administration, Office of General Council and Office of Chief Information Officer et. al. The NRC has the following major program offices:
The Office of Nuclear Reactor Regulation handles all licensing and inspection activities for existing nuclear power reactors and research and test reactors. It also oversees the design, siting, licensing, and construction of new commercial nuclear power reactors.
The Office of Nuclear Regulatory Research provides independent expertise and information for making timely regulatory judgments, anticipating potentially significant safety problems, and resolving safety issues. It helps develop technical regulations and standards and collects, analyzes, and disseminates information about the safety of commercial nuclear power plants and certain nuclear materials activities.
The Office of Nuclear Material Safety and Safeguards regulates the production of commercial nuclear fuel; uranium recovery activities; decommissioning of nuclear facilities; and the use of radioactive materials in medical, industrial, academic, and commercial applications.
It regulates safe storage, transportation, and disposal of low- and high-level radioactive waste and spent nuclear fuel. The office also works with other Federal agencies, States, and Tribal and local governments on regulatory matters.
The Office of Nuclear Security and Incident Response initiates and oversees the implementation of agency security policy for nuclear facilities and users of radioactive material and coordinates with other Federal agencies and international organizations on security issues. This office also maintains the NRCs emergency preparedness and incident response programs.
NRC: AN INDEPENDENT REGULATORY AGENCY l 9
The NRC regional offices conduct inspections and investigations; take enforcement actions (in coordination with the Office of Enforcement); and maintain incident response programs for nuclear reactors, fuel facilities, and materials licensees. In addition, the regional offices carry out licensing for certain materials licensees (see Figure 5. NRC Regions).
The agency has two advisory committees, the Advisory Committee on Reactor Safeguards (ACRS) and the Advisory Committee on the Medical Uses of Isotopes (ACMUI), which are independent of the NRC staff. The ACRS reports directly to the Commission, which appoints its members. The advisory committees are structured to provide a forum where experts representing many technical perspectives can provide independent advice that is factored into the Commissions decision-making process. Most committee meetings are open to the public, and any member of the public may request an opportunity to make an oral statement during committee meetings.
NRC ORGANIZATION CHART Figure 4. NRC Organizational Chart The Commission Commissioner Commissioner Chairman Commissioner Commissioner Executive Director, General Counsel Advisory Committee Director, Office of Director, Office of on Reactor Safeguards Congressional Affairs Public Affairs Director, Office of International Programs Director, Office of Commission Appellate Adjudication Inspector General Secretary of the Commission Chief Administrative Judge (Chairman), Atomic Safety Chief Financial and Licensing Board Panel Office Executive Director for Operations Deputy Executive Director Deputy Executive Director for Materials, Waste, Assistant for for Reactor and Research, State, Tribal, Compliance, Operations Preparedness Programs Administration, and Human Capital Programs Regional Administrator Director, Office of Chief Information Region I Nuclear Regulatory Officer Research Regional Administrator Director, Office of Region II Director, Office of Small Business Enforcement and Civil Rights Regional Administrator Region III Director, Office of Nuclear Material Safety and Safeguards Regional Administrator Region IV Director, Office of Investigations Director, Office of Nuclear Security and Incident Response Director, Office of Administration Director, Office of Nuclear Reactor Chief Human Regulation Capital Officer Note: For the most recent information, go to the NRC Organization Chart at https://www.nrc.gov/about-nrc/organization.html.
10 l NRC: AN INDEPENDENT REGULATORY AGENCY
Figure 5. NRC Regions NRC REGIONS Region IV Region III Region I NRC Lisle NRC King of Prussia NRC HQ Rockville NRC Chattanooga Region II NRC Atlanta NRC Arlington Region I Region II Region III Region IV Technical Training Ctr.
King of Prussia, PA Atlanta, GA Lisle, IL Arlington, TX Chattanooga, TN Nuclear Power Plants
- Each regional office oversees the plants in its regionexcept for the Callaway plant in Missouri, which Region IV oversees.
Materials Licensees
- Region I oversees licensees and Federal facilities located in Region I and Region II.
- Region III oversees licensees and Federal facilities located in Region III.
- Region IV oversees licensees and Federal facilities located in Region IV.
Nuclear Fuel Processing Facilities
- Region II oversees all the fuel processing facilities in all regions.
- Region II also handles all construction inspection activities for new nuclear power plants and fuel cycle facilities in all regions.
NRC: AN INDEPENDENT REGULATORY AGENCY l 11
FISCAL YEAR 2021 BUDGET For fiscal year (FY) 2021 (October 1, 2020, through September 30, 2021), the NRCs budget is
$879 million. The NRC has 2,868 full-time equivalents (FTEs) in FY 2021; including the Office of the Inspector General (see Figure 6. NRC Total Authority, FYs 2011-2021). The Office of the Inspector General received its own appropriation of $13.5 million, which is included in the total NRC budget.
The breakdown of the budget is shown in Figure 7. NRC FY 2021 Distribution of Budget Authority; Recovery of Enacted NRC Budget. The Nuclear Energy Innovation and Modernization Act, known as NEIMA (Public Law 115-439), requires the NRC to recover, to the maximum extent practicable, approximately 100 percent of its total budget authority for a fiscal year, less the budget authority for excluded activities. The NRC collects fees each year by September 30 and transfers them to the U.S. Treasury. The agency estimates that it will recover $721.4 million in fees in FY 2021.
Figure 6. NRC Total NRC Authority, TotalFYs 2011-2021 FYs 2011-2021 Authority, 34 23 15 20 1,054 1,056 40 35 1,038 1,015 986 1,002 917 922 911 856 879 3,992 3,953 3,931 3,815 3,779 3,595 3,396 3,186 3,106 2,970 2,868 11 12 13 14 15 16 17 18 19 20 21 Total Authority Authorized Carryover Full-Time Dollars in Millions Dollars in Millions Equivalents (FTEs)
Note: Dollars are rounded to the nearest million.
12 l NRC: AN INDEPENDENT REGULATORY AGENCY
Figure 7. NRC FY 2021 Distribution of Budget Authority;
NRC FY2021Recovery Distribution of EnactedofBudgetBudget Authority; Recovery of Enacted Budget Nuclear Reactor Safety Program:
77% ($667.6 Million)
Nuclear Materials and Waste Safety Total Program: 21% ($182.3 Million)
Budget: University Nuclear Leadership Program Funded by Carryover: 1% ($16 Million)
$879 Inspector General: 1% ($13.5 Million)
Million Nuclear Reactor Safety Program 78% (2,220 FTEs)
Headquarters Nuclear Materials 74% (2,128 FTEs) Total FTE: and Waste Safety Program:
2,867 20% (584 FTEs)
Regions 26% (740 FTEs) Inspector General:
2% (63 FTEs)
Reactor Fees:
$661.3 Million Recovery Nuclear Materials Fees:
$60.1 Million of Enacted Budget Budget Not Recovered by Fees:
FY 2021 $123 Million Estimated Fees To Be Recovered*
by FY 2021: $721.4 Million
- Recovered fees do not include the use of prior-year carryover where fees were previously collected.
After Part 171 billing adjustments the amount to be recovered is $708 Million.
Notes: The NRC incorporates corporate and administrative costs proportionately within programs. Also, the spread of corporate FTE is included in Reactor and Material fees. Numbers may not add due to rounding.
Enacted budget for FY 2021. More budget information available in the Congressional Budget Justification at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1100.
NRC: AN INDEPENDENT REGULATORY AGENCY l 13
2 NUCLEAR ENERGY IN THE U.S. AND WORLDWIDE
WORLDWIDE ELECTRICITY GENERATED BY COMMERCIAL NUCLEAR POWER Nuclear reactor technology was first developed in the 1940s, initially for producing weapons, but President Dwight D. Eisenhowers Atoms for Peace program shifted the focus to power generation, scientific research, and the production of medical and industrial isotopes. Today, nuclear technology is global, and nuclear-generated power is a part of the worldwide energy portfolio.
As of June 2021, there were 444 operating reactors in 30 countries with a total net capacity of 394,229 megawatts electric (MWe). In addition, 51 reactors were under construction. Based on data from 2020, France had the highest portion (70.6 percent) of total domestic energy generated by nuclear power. Share of Electricity Generated by Country Nuclear Figure 8. Nuclear Share of Electricity Generated by Country.
France Slovakia Ukraine Hungary Bulgaria Belgium Slovenia Czech Rep.
70.6% 53.1% 51.2% 48% 40.8% 39.1% 37.8% 37.3%
Armenia Finland Switzerland Sweden Rep. Korea Spain Russia Romania 34.5% 33.9% 32.9% 29.8% 29.6% 22.2% 20.6% 19.9%
U.S.A. Canada United Kingdom Germany Argentina Pakistan S. Africa Japan 19.7% 14.6% 14.5% 11.3% 7.5% 7.1% 5.9% 5.1%
China Mexico India Netherlands Brazil Iran UAE 4.9% 5.9% 3.3% 3.2% 2.1% 1.7% 1.7%
In addition to generating electricity, nuclear materials and technology are used worldwide for many Note: Each countrys short-form name is used.
other peaceful Source: IAEA, purposes, such Power as theInformation Reactor following: System database, as of June 2021 for 2020
Radioactive isotopes help diagnose and treat medical conditions
Irradiation makes food safer and last longer, and assists in making pest-resistant seed varieties with higher yields
Nuclear gauges maintain quality control in industry
Radioactive isotopes date objects and identify elements The NRC engages in international activities to exchange regulatory information to enhance the safe and secure civilian use of nuclear materials and technologies.
See Appendix R for the number of nuclear power reactor units by nation; Appendix S for nuclear power reactor units by reactor type, worldwide; and Appendices X, Y, and Z for lists of international activities, including conventions and treaties, bilateral information exchange and cooperation agreements, multilateral organizations in which the NRC participates, and list of export and import licenses.
16 l NUCLEAR ENERGY IN THE U.S. AND WORLDWIDE
INTERNATIONAL STRATEGY 2021-2025 The NRC is well-respected internationally in nuclear safety and security regulation. The agencys International Strategy builds directly on the Commissions 2014 International Policy Statement and has two primary aims:
Leverage this reputation to positively influence the development of new, and maintenance of existing, nuclear safety and security regimes around the world; and
Target the staffs international engagement to opportunities that will directly inform the agencys domestic mission objectives.
The strategy consists of five objectives to guide the agencys international engagement and ensure that the agencys activities positively influence global nuclear safety and security, align with U.S. Government policy priorities, and promote strong cooperation with international regulatory partners. The objectives are as follows:
EXCEL Maintain excellence in executing the NRCs statutory and legally mandated activities.
Successfully execute the U.S. Governments export and import mandate for nuclear equipment, components, and materials and contribute to meeting U.S. obligations under nuclear safety, security, and nonproliferation conventions, treaties, and U.S.
Government commitments.
INTEGRATE Integrate the agencys international activities with broader U.S. Government foreign policy and national security objectives.
Frequent engagement with the Executive Branch about how the NRC can complement U.S. foreign policy or national security objectives, recognizing the NRCs nonpromotional status and independence and areas where policy restrictions may influence the direction of the agencys work.
PARTNER Build and maintain partnerships in specific regions of strategic importance to the United States that will support governmentwide objectives and enable the agency to learn from its counterparts and advance its domestic mission.
Establish and maintain strategic global partnerships in all regions in targeted ways; promote domestic and global nuclear safety and security by creating and taking advantage of opportunities to increase cooperation; and gain valuable information to use as a benchmark for the agencys domestic activities.
LEAD Demonstrate leadership in the international community through involvement in key bilateral and multilateral forums in areas of strategic importance to the NRC and U.S. Government.
Positively influence the global nuclear safety and security regime to develop regulatory frameworks that emphasize safety and security as a foremost objective, in a manner that promotes or is consistent with the NRCs domestic regulatory approach.
ASSIST Advance nuclear safety and security worldwide by providing regulatory assistance to countries with emerging regulatory programs, with a focus on countries of strategic importance to the broader U.S. Government.
Countries receiving NRC capacity-building support will make advances in developing a sound, independent, technically competent, adequately resourced nuclear safety and security regulatory infrastructure that mirrors key tenets of the NRCs regulatory infrastructure and approach.
NUCLEAR ENERGY IN THE U.S. AND WORLDWIDE l 17
INTERNATIONAL ACTIVITIES The NRCs international activities support the agencys domestic mission, as well as broader U.S.
domestic and international interests. The wide-ranging activities include the following:
convention and treaty implementation
nuclear nonproliferation
export and import licensing for nuclear materials and equipment
international nuclear safety, security, and safeguards cooperation and assistance
cooperative safety research The NRC works with multinational organizations, such as the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA), and bilaterally with regulators in other countries through cooperation and research agreements. These interactions allow the NRC to share and acquire regulatory safety and security best practices. In addition, joint research projects give the NRC access to research facilities not available in the United States.
Conventions and Treaties All countries that ratify nuclear-related conventions and treaties must take actions to implement them. Their actions help ensure high levels of safety and security. For example, the NRC actively participates in and provides leadership for the implementation of the Convention on Nuclear Safety.
The objectives of the Convention are to maintain a high level of nuclear safety worldwide, to prevent accidents with radiological consequences, and to mitigate such consequences should they occur.
In addition, the NRCs international cooperation and assistance activities, as well as import and export licensing of nuclear materials and equipment, fulfill U.S. obligations undertaken under the treaty on the Non-Proliferation of Nuclear Weapons, which says that all parties to the Treaty have the right to participate in the fullest possible exchange of equipment, materials, and scientific and technological information for the peaceful uses of nuclear energy, provided that they meet their nonproliferation obligations. The NRC therefore participates in review meetings and associated activities under this treaty.
The NRC also actively participates in meetings and activities for the following conventions:
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Convention on the Physical Protection of Nuclear Material and Its Amendment
Convention on Early Notification of a Nuclear Accident
Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency Export and Import Licensing The NRC reviews applications to license exports and imports of nuclear materials and equipment to ensure that such exports and imports will not be inimical to the safety and security of the United States and will be consistent with applicable agreements for the peaceful use of nuclear materials.
The NRCs export and import regulations are found in Title 10 of the Code of Federal Regulations Part 110, Export and import of nuclear equipment and material.
The NRC participates in meetings of the Nuclear Suppliers Group and the Code of Conduct on the Safety and Security of Radioactive Sources (see the Web Link Index for the Code of Conduct) to ensure that U.S. export and import controls are appropriate.
Bilateral Cooperation and Assistance The NRC has information-sharing agreements with more than 45 countries, as well as Taiwan and the European Atomic Energy Community (see Appendix X for the list of the NRCs bilateral information exchange and cooperation agreements).
18 l NUCLEAR ENERGY IN THE U.S. AND WORLDWIDE
Cooperation The NRC participates in a wide range of programs that enhance the safety and security of peaceful nuclear activities worldwide. With countries that have mature nuclear power or radioactive materials programs, the NRC focuses on sharing information and best practices.
Some of the benefits of consulting with mature regulatory programs include the following:
awareness of reactor construction activities that could apply to new reactors being built in the United States
prompt notification to foreign partners of U.S. safety issues and vice versa
sharing of safety and security information Assistance The NRC provides bilateral and regional capacity-building support, training, workshops, and peer reviews to assist countries as they develop or enhance their national nuclear regulatory infrastructures and programs.
Foreign Assignee Program The NRC provides long-term, on-the-job assignments to foreign regulators at the NRC through its Foreign Assignee Program. This helps both organizations better understand each others regulatory programs, capabilities, and commitments. It also helps to enhance the expertise of both foreign assignees and the NRC staff. The program also fosters relationships between the NRC and key officials in other countries. Since the programs inception in 1975, the NRC has hosted more than 400 foreign assignees.
Foreign Trainee Program The NRC provides opportunities for engineers, scientists, and regulatory personnel from other countries to attend NRC training courses at the Technical Training Center and Professional Development Center.
Multilateral Cooperation and Assistance The NRC plays an active role in the different programs and committee work of multilateral organizations. The agency works with multiple regulatory counterparts through the IAEA, OECD/NEA, and other multilateral organizations on issues related to
safety research and development of standards
radiation protection
risk assessment
waste management
transportation
safeguards, physical protection, and security
training, communications, and public outreach International Cooperative Research The NRC participates in international cooperative research programs to share U.S. operating experience and to learn from the experiences of other countries. This helps leverage access to foreign research data and test facilities otherwise unavailable to the United States.
NUCLEAR ENERGY IN THE U.S. AND WORLDWIDE l 19
3 NUCLEAR REACTORS
U.S. ELECTRICITY GENERATED BY COMMERCIAL NUCLEAR POWER According to the U.S. Energy Information Administration (EIA), in 2020, preliminary estimates show that 4,009 billion kilowatt-hours (kWh) (or 4 trillion kWh) of electricity were generated at utility-scale electricity generation facilities in the United States. About 60.3 percent of this electricity generation was from fossil fuels (coal, natural gas, petroleum, and other gases). Nuclear energy provided 19.7 percent (790 billion kWh), and about 19.8 percent came from renewable energy sources (see Figure 9. U.S. Gross Electricity Share by Energy Source, 2020, and Figure 10. U.S. Electricity Generation by Energy Source, 2015-2020).
Since the 1970s, the Nations utilities have asked permission to generate more electricity from existing nuclear plants. The NRC regulates how much heat a commercial nuclear reactor may generate. This heat, or power level, is used with other data in many analyses that demonstrate the safety of the nuclear power plant. Because this power level is included in the plants license and technical specifications, the NRC must review and approve any licensees requested change to it, as it would for any license or technical specification change. Increasing a commercial nuclear power plants maximum operational power level is called a power uprate.
The NRC has approved power uprates that have collectively added the equivalent of seven new reactors worth of electrical generation to the power grid. See the Glossary for information on the electric power grid.
According to the EIA, in 2019, each of the following States generated more than 40,000 megawatt-hours of electricity from nuclear power: Illinois, Pennsylvania, South Carolina, New York, Alabama, North Carolina, and Texas. Illinois ranked first in the Nation in both generating capacity and net electricity generation from nuclear power. Illinois nuclear power plants accounted for 12 percent of the Nations nuclear power generation. The 2019 data cited reflect the total net electricity generation from nuclear sources in each of these States. See Figure 11. Gross Electricity Generated in Each State by Nuclear Power. In 2019, 30 of the 50 States generated electricity from nuclear power plants.
Figure U.S. 9. U.S. Gross Electricity Net Electricity Generation Share by by Energy Source, Selected Energy2020 Source, 2020 Petroleum Natural Gas 0.4%
40%
Coal 19.3%
Nuclear 19.6% Renewable 19.8%
Wind Solar 8.4%
2.3%
Hydropower 7.3%
Note: Figures are preliminary and rounded.
Source: DOE/EIA at https://www.eia.govTable 7.2a Electricity Net Generation: Total (All Sectors) data released as of June 24, 2021, annual total for 2020.
22 l NUCLEAR REACTORS
FigureU.S. 10. Electricity U.S. Electricity Net Generation Generationby byEnergy EnergySource, Source, 2015-2020*
2015-2020 Thousand Megawatt-Hours
- 2020 data are preliminary. Note: Figures are rounded.
Source: DOE/EIA, https://www.eia.govElectricity Data Browser; Electricity Net Generation: Total (All SectorsAnnually 2015-2020) released as of June 2021 for 2020 data.
U.S. COMMERCIAL NUCLEAR POWER REACTORS Power plants convert heat into electricity using steam. At nuclear power plants, the heat to boil water into steam is created when atoms split apart in a process called fission. When the process is repeated over and over, it is called a chain reaction. The reactions heat creates steam to turn a turbine. As the turbine spins, the generator turns, and its magnetic field produces electricity.
Nuclear power plants are very complex. There are many buildings at the site and many different systems. Some of the systems work directly to make electricity, while others keep the plant working correctly and safely. All nuclear power plants have a containment structure with reinforced concrete about 4 feet (1.2 meters) thick that houses the reactor. To keep reactors performing efficiently, operators remove about one-third of the fuel every year or two and replace it with fresh fuel. Used fuel is stored and cooled in deep pools of water located on site. The process of removing used fuel and adding fresh fuel is known as refueling.
See Appendix E for a list of parent companies of U.S. commercial operating nuclear power reactors, Appendix A for a list of reactors and their general licensing information, Appendix T for Native American Reservations and Trust lands near nuclear power plants, and Appendix J for radiation doses and regulatory limits.
The United States has two types of commercial nuclear reactors. Pressurized-water reactors are known as PWRs. They keep water in the reactor under pressure, so it heats to over 500 degrees Fahrenheit (260 degrees Celsius) but does not boil. Water from the reactor and the water that is turned into steam are in separate pipes and never mix. In boiling-water reactors,called BWRs, the water heated in the reactor actually boils and turns into steam, which then turns a turbine generator to produce electricity. In both types of plants, the steam is turned back into water and reused.
NUCLEAR REACTORS l 23
The NRC regulates commercial nuclear power plants that generate electricity. There are several operating companies and vendors and many different types of reactor designs. Of these designs, only PWRs and BWRs are currently in commercial operation in the United States. See Glossary for typical PWR and BWR designs. Although commercial U.S. reactors have many similarities, each one is considered unique (see Figure 12. U.S. Operating Commercial Nuclear Power Reactors).
Figure 11. Gross Electricity Generated in Each State by Nuclear Power U.S. Gross Electricity Generated in Each State by Nuclear Power RI ALASKA HAWAII PUERTO RICO GUAM AMERICAN SAMOA NORTHERN MARIANAS Total Nuclear Power Generated (in thousand megawatt-hours)
None < less than 20,000 20,001 to 40,000 40,001 to 60,000 > more than 60,001+
0 States 16 States 8 States 4 States 2 States Total Nuclear Power Generated by State (in megawatt-hours)
Total Nuclear % of Nuclear Total Nuclear % of Nuclear State Generated Electricity State Generated Electricity Illinois 98,735,488 53% California 16,165,384 8%
Pennsylvania 83,229,652 36% Connecticut 16,733,398 42%
S. Carolina 56,103,043 56% Maryland 15,012,922 38%
New York 44,865,018 34% Minnesota 14,104,547 24%
Alabama 43,656,862 30% Louisiana 13,981,335 14%
N. Carolina 41,915,605 32% Arkansas 13,574,947 21%
Texas 41,298,007 8% Mississippi 11,032,514 17%
Tennessee 35,720,405 43% New Hampshire 10,906,923 60%
Georgia 33,591,181 26% Wisconsin 10,030,305 16%
Michigan 32,909,275 28% Kansas 9,247,734 18%
Arizona 31,920,368 28% Missouri 9,189,863 12%
Virginia 29,497,516 30% Washington 8,866,499 8%
Florida 29,108,066 12% Nebraska 6,951,600 19%
New Jersey 26,637,324 37% Iowa 5,235,716 8%
Ohio 17,010,561 14% Massachusetts 2,177,204 10%
Source: DOE/EIA, State Historical Tables for 2019, Released September 2020, Revised February 2021, https://eia.gov/state.
24 l NUCLEAR REACTORS
Figure 12. U.S. Operating Commercial Nuclear Power Reactors U.S. Operating Commercial Nuclear Power Reactors RI REGION I REGION II REGION III REGION IV CONNECTICUT ALABAMA ILLINOIS ARKANSAS Millstone 2 and 3 Browns Ferry 1, 2, Braidwood 1 and 2 Arkansas Nuclear 1 and 2 and 3 Byron 1 and 2 MARYLAND Clinton ARIZONA Farley 1 and 2 Palo Verde 1, 2, and 3 Calvert Cliffs 1 and 2 Dresden 2 and 3 FLORIDA LaSalle 1 and 2 CALIFORNIA NEW HAMPSHIRE St. Lucie 1 and 2 Seabrook Quad Cities 1 and 2 Diablo Canyon 1 and 2 Turkey Point 3 and 4 MICHIGAN KANSAS NEW JERSEY GEORGIA Cook 1 and 2 Hope Creek Wolf Creek Hatch 1 and 2 Fermi 2 Salem 1 and 2 Vogtle 1 and 2 Palisades LOUISIANA River Bend 1 NEW YORK NORTH CAROLINA MINNESOTA Waterford 3 FitzPatrick Brunswick 1 and 2 Monticello Ginna McGuire 1 and 2 Prairie Island 1 and 2 MISSISSIPPI Nine Mile Point 1 and 2 Harris 1 Grand Gulf OHIO PENNSYLVANIA SOUTH CAROLINA Davis-Besse MISSOURI Beaver Valley 1 and 2 Catawba 1 and 2 Perry Callaway Limerick 1 and 2 Oconee 1, 2, and 3 NEBRASKA Robinson 2 WISCONSIN Peach Bottom 2 and 3 Point Beach 1 and 2 Cooper Susquehanna 1 and 2 Summer TENNESSEE TEXAS Sequoyah 1 and 2 Comanche Peak 1 and 2 Watts Bar 1 and 2 South Texas Project 1 and 2 VIRGINIA WASHINGTON North Anna 1 and 2 Columbia Surry 1 and 2 Note: NRC-abbreviated reactor names are listed. Data are current as of June 2021. For the most recent information, go to the NRC facility locator page at https://www.nrc.gov/info-finder/reactors/index.html.
NUCLEAR REACTORS l 25
Resident Inspectors Since the late 1970s, the NRC has maintained its own sets of eyes and ears at the Nations nuclear power plants. These onsite NRC personnel are referred to as resident inspectors. Each plant has at least two resident inspectors, and their work is at the core of the agencys reactor inspection program. These highly trained and qualified professionals scrutinize activities at the plants and verify adherence to Federal safety requirements. The inspectors visit the control room and review operator logbook entries, visually assess areas of the plant, observe tests of (or repairs to) important systems or components, interact with plant employees, and check corrective action documents to ensure that problems have been identified and appropriate fixes implemented.
Resident inspectors promptly notify plant operators of any safety-significant issues they find so they are corrected, if necessary, and communicated to NRC management. If problems are significant enough, the NRC will consider whether enforcement action is warranted. More information about the NRCs Reactor Oversight Process and the resident inspector program is available on the agencys Web site (see Figure 13. Day in the Life of an NRC Resident Inspector).
Figure 13. Day in the Life of an NRC Resident Inspector 1 An NRC resident inspector is a specially trained START expert who lives in the community around the plant.
Each plant has at least two inspectors.
3 2 Each morning, the inspector visits the reactors control room, gets information on the plant status, and relays As with everyone at the plant, this information to NRC offices.
the inspector passes through security checkpoints.
As As 4 The inspector attends the plan-of-the-day meeting with plant 5 officials to understand what activities are planned.
As part of their routine, inspectors proceed with inspection 7 activities, observe 6 Inspectors routinely inspect Resident inspectors play safety systems, discuss safety issues plant workers, a very important role for with plantLorem ipsumand submit employees, make sure publicly available reports. the NRC. They are the the plant is agencys on-the-ground following eyes and ears.
NRC rules, and report concerns.
Have a safe day!
Learn more about resident inspectors. Watch the videos on the NRC YouTube Channel at https://www.youtube.com/user/NRCgov.
26 l NUCLEAR REACTORS
Post-Fukushima Safety Enhancements On March 11, 2011, a 9.0-magnitude earthquake, followed by a 45-foot (13.7-meter) tsunami, heavily damaged the nuclear power reactors at Japans Fukushima Dai-ichi facility. Following this accident, the NRC required significant enhancements to U.S. commercial nuclear power plants. At the front lines of this effort were the agencys resident inspectors and regional staff. They inspected and monitored U.S. reactors as the plants worked on these enhancements.
The enhancements included adding capabilities to maintain key plant safety functions following any kind of severe event, updating evaluations of potential impacts from seismic and flooding events, installing new equipment to better handle potential reactor core damage events, and strengthening emergency preparedness capabilities. These actions ensure the nuclear industry and the NRC are prepared for the unexpected. The NRC continues to inspect plants efforts to ensure they have the required resources, plans, and training (see Figure 14. NRC Post-Fukushima Safety Enhancements NRC Post-Fukushima Safety Enhancements and the Web Link Index).
Figure 14. NRC Post-Fukushima Safety Enhancements Mitigation Strategies Seismic FLEX Defense Equipment Hardened Vents Spent Fuel Pool Instrumentation Emergency Preparedness FLEX Offsite Flooding Equipment Defense Note: FLEX refers to the industrys term for mitigation strategy equipment.
Principal Licensing, Inspection, and Enforcement Activities The NRCs commercial reactor licensing and inspection activities include the following:
reviewing separate license change requests, called amendments, from power reactor licensees
performing inspections at each operating reactor site
conducting initial reactor operator licensing examinations
ensuring NRC-licensed reactor operators maintain their knowledge and skills current by passing rigorous requalification exams every 2 years and obtaining an NRC license renewal every 6 years
reviewing applications for proposed new reactors
inspecting construction activities
reviewing operating experience items each year and sharing lessons learned that could help licensed facilities operate more effectively
issuing notices of violation, civil penalties, or orders to operating reactors for significant violations of NRC safety and security regulations NUCLEAR REACTORS l 27
investigating allegations of inadequacy or impropriety associated with NRC-regulated activities
incorporating independent advice from the Advisory Committee on Reactor Safeguards (ACRS), which holds both full committee meetings and subcommittee meetings each year to examine potential safety issues for existing or proposed reactors OVERSIGHT OF U.S. COMMERCIAL NUCLEAR POWER REACTORS The NRC establishes requirements for the design, construction, operation, and security of U.S.
commercial nuclear power plants. The agency ensures plants operate safely and securely within these requirements by licensing the plants to operate, licensing control room personnel, establishing technical specifications for operating each plant, and inspecting plants daily.
Reactor Oversight Process The NRCs Reactor Oversight Process (ROP) verifies that U.S. reactors are operating in accordance with NRC rules, regulations, and license requirements. If reactor performance declines, the NRC increases its oversight to protect public health and the environment. This can range from conducting additional inspections to shutting a reactor down.
The NRC staff uses the ROP to evaluate NRC inspection findings and performance records for each reactor and applies this information to assess the reactors safety performance and security measures. Every 3 months, the NRC places each reactor in one of five categories. The top category is fully meeting all safety cornerstone objectives, while the bottom is unacceptable performance (see Figure 15. Reactor Oversight Action Matrix Performance Indicators).
NRC inspections start with detailed baseline-level activities for every reactor. As the number of issues at a reactor increases, the NRCs inspections increase. The agencys supplemental inspections and other actions (if needed) ensure licensees promptly address significant performance issues. The latest reactor-specific inspection findings and historical performance information can be found on the NRCs Web site (see the Web Link Index).
The ROP is informed by 50 years of improvements in nuclear industry performance. The process continues to improve approaches to inspecting and evaluating the safety and security performance of NRC-licensed nuclear plants. More ROP information is available on the NRCs Web site and in NUREG-1649, Revision 6, Reactor Oversight Process, issued July 2016 (see Figure 16. Reactor Oversight Framework).
NRC Commissioner Jeff Baran observes the reactor vessel head inside Unit 4 containment, currently under construction at the Vogtle site in Georgia.
28 l NUCLEAR REACTORS
Figure 15. Reactor OversightAction Reactor Oversight Action Matrix Matrix Performance Performance Indicators Indicators Performance Indicators GREEN WHITE YELLOW RED INCREASING SAFETY SIGNIFICANCE Inspection Findings GREEN WHITE YELLOW RED INCREASING SAFETY SIGNIFICANCE Figure 16. Reactor Oversight Framework Mission Protect Public Health and Safety in the Use of Nuclear Power Strategic Performance Reactor Safety Radiation Safety Safeguards Areas Initiating Mitigating Barrier Emergency Public Occupational Security Cornerstones Events Systems Integrity Preparedness Radiation Radiation Cross-Cutting Human Problem Identification Safety-Conscious Areas Performance and Resolution Work Environment See Appendix C for a list of reactors undergoing decommissioning and permanently shutdowns; Appendix V for list of significant enforcement actions; and Appendices F and G for power reactor operating licenses issued and expiring by year.
NUCLEAR REACTORS l 29
REACTOR LICENSE RENEWAL The Atomic Energy Act of 1954, as amended, authorizes the NRC to issue 40-year initial licenses for commercial power reactors. The Act also allows the NRC to renew licenses. Under the NRCs current regulations, the agency can renew reactor licenses for 20 years at a time. Congress set the original 40-year term after considering economic and antitrust issues, as opposed to nuclear technology issues. Some parts of a reactor, however, may have been engineered based on an expected 40-year service life. These parts must be maintained and monitored during the additional period of operation, and licensees may choose to replace some components (see Figure 17.
License Renewals Granted for Operating Nuclear Power Reactors). For current reactors grouped by how long they have operated, see Figure 18. U.S. Commercial Nuclear Power ReactorsYears of Operation by the End of 2020. Nuclear power plant owners typically seek license renewal based on a plants economic situation and on whether it can continue to meet NRC requirements in the future (see Figure 19. License Renewal Process).
The NRC reviews a license renewal application on two tracks: safety and environmental impacts.
The safety review evaluates the licensees plans for managing aging plant systems during the renewal period. For the environmental review, the agency uses the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (NUREG-1437, Revision 1, issued June 2013) to evaluate impacts common to all nuclear power plants, then prepares a supplemental environmental impact statement for each individual plant. The supplement examines impacts unique to the plants site. The public has two opportunities to contribute to the environmental reviewat the beginning and when the draft report is published.
The NRC considered the environmental impacts of the continued storage of spent nuclear fuel during rulemaking activities and published its final continued storage rule and supporting generic environmental impact statement in 2014. The rule addresses the environmental impacts of the continued storage of spent nuclear fuel beyond a reactors licensed operating life before ultimate disposal (previously referred to as waste confidence). The environmental impacts of continued storage of spent nuclear fuel are incorporated into each environmental review for license renewal.
Subsequent License Renewal The NRC staff developed guidance and a standard review plan for subsequent license renewals that would allow plants to operate for more than 60 years (the 40 years of the original license plus 20 years in the initial license renewal).
The Commission determined that the agencys existing regulations are adequate for subsequent license renewals. Nevertheless, the Commission asked the staff to develop new guidance to better help licensees develop aging management programs for the 60-year to 80-year period. The staff issued this guidance (NUREG-2191 and NUREG-2192) in July 2017.
Public Involvement The public plays an important role in the license renewal process. Members of the public have several opportunities to contribute to the environmental review. The NRC shares information provided by the applicant, holds public meetings, and publicly documents the results of its technical and environmental reviews. In addition, the ACRS reviews license renewal applications and discusses them at its meetings.
Individuals or groups can raise legal arguments against a license renewal application in an Atomic Safety and Licensing Board hearing if they would be affected by the renewal and meet basic requirements for requesting a hearing. (For more information, see the Web Link Index.)
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Figure 17. License Renewals Granted for Operating Nuclear U.S. Operating Power Reactors Commercial Nuclear Power Reactors RI Original License (8)
License Renewal Granted (79)
Subsequent License Renewal Granted (6)
Licensed to Operate (93)
Note: The NRC has issued a total of 94 initial license renewals: 9 of these units have permanently shut down.
Data are as of July 2021. For the most recent information, go to NRC Web page at https://www.nrc.gov/info-finder.html Figure 18. U.S. Commercial Nuclear Power Reactors Years of Operation by the End of 2020 U.S. Commercial Nucelar Reactors --Years of Operation by the End of 2021 1 2 44 43 4 reactor reactors reactors reactors reactors 1-19 years 20-29 years 30-39 years 40-49 years >50 years Note: Ages are based on operating license issued date and have been rounded up to the end of the year.
For the most recent information, go to the NRC Web page at https://www.nrc.gov/info-finder.html NUCLEAR REACTORS l 31
License Figure 19.Renewal Process Process License Renewal Not applicable to the subsequent license renewal process Opportunities for public interaction Onsite If a request for a hearing is granted Safety Review Inspection(s) Availlable at https://www.nrc.gov 10 CFR Part 54 Safety Inspection Evaluation Reports Audit/Review Issued**
License Renewal Safety Evaluation Process and Report Issued**
Environmental Scoping Meeting Advisory Committee on START Environmental Review Reactor Safeguards 10 CFR Part 51 (ACRS) Review License ACRS Renewal Letter Application** Issued**
Draft Site Environmental Supplement Audit to Generic DECISION Environmental Draft Hearings*
Impact Supplemental Statement Environmental (GEIS) Issued** Impact Statement Public Comment/ Final Supplement NRC Decision Meeting to GEIS Issued** on Application**
Turkey Point nuclear power plant in Florida was the first U.S. plant to be approved by the NRC for Subsequent License Renewal, or an additional 20 years of operation, for a total lifespan of 80 years.
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NUCLEAR RESEARCH AND TEST REACTORS Nuclear research and test reactors (RTRs), also called nonpower reactors, are a type of Nonpower Production and Utilization Facility (NPUF). RTRs are primarily used for research, training, and development to support science and education in nuclear engineering, physics, chemistry, biology, anthropology, medicine, materials sciences, and related fields. These reactors do not produce electricity. Most U.S. RTRs are at universities or colleges.
The largest U.S. RTR (which operates at 20 megawatts thermal (MWt) is approximately 80 times smaller than the smallest U.S. commercial power nuclear reactor (which operates at 1,677 MWt).
The NRC regulates a wide variety of RTRs located across the country (see Figure 20. Size Comparison of Commercial and Research Reactors and Figure 21. U.S. Nuclear Research and Test Reactors). DOE also uses nonpower nuclear research reactors, but they are not regulated by the NRC.
NRC inspectors visit each RTR facility about once a year to provide varying levels of oversight. RTRs licensed to operate at 2 MWt or more receive a full NRC inspection every year. Those licensed to operate at less than 2 MWt receive a full inspection every 2 years.
Principal Licensing and Inspection Activities The NRCs RTR licensing and inspection activities include:
licensing new and current operating sites, including license renewals and license amendments
overseeing decommissioning
licensing operators
overseeing operator relicensing programs
conducting inspections each year, based on inspection frequency and procedures for operating RTRs
overseeing facility security and emergency preparedness programs Figure 20. Size Comparison of Commercial and Research Reactors Size Comparison Commercial Power and Nonpower Reactor SMALLEST LARGEST 1,677 MWt 20 MWt COMMERCIAL RESEARCH and POWER TEST REACTOR 80 1,677 megawatts 20 megawatts thermal thermal For the most recent information, go to NRC Web page at https://www.nrc.gov/info-finder.html NUCLEAR REACTORS l 33
Figure U.S. 21. U.S. Nuclear Nuclear Nonpower Research and ResearchTest Reactorsand Test Reactors RI RTRs Licensed and Currently Operating (31)
Note: RTRs are also referred to as nonpower facilities. For the most recent information, go to NRC Web page at https://www.nrc.gov/info-finder.html See Appendices H and I for a list of RTRs regulated by the NRC that are operating or are in the process of decommissioning.
NEW COMMERCIAL NUCLEAR POWER REACTOR LICENSING New reactors are any reactors proposed in addition to the current fleet of operating reactors (see Figure 22. The Different NRC Classifications for Types of Reactors).
The NRCs current review of new power reactor license applications improves on the process used through the 1990s (see Figure 23. New Reactor Licensing Process). In 2012, the NRC issued the first combined construction permit and operating license (called a combined license, or COL) under the new licensing process. The NRC continues to review applications submitted by prospective licensees and (when appropriate) issues standard design approvals, standard design certifications, early site permits (ESPs), limited work authorizations, construction permits, operating licenses, and COLs for facilities in a variety of projected locations throughout the United States. The NRC has implemented the Commissions policies on new reactor safety through rules, guidance, staff reviews, and inspection.
The NRCs ongoing design certification, COL, and ESP reviews are incorporating lessons learned from the Fukushima accident. The environmental impacts of continued storage of spent nuclear fuel are incorporated into each environmental review for new reactor licensing. The NRC considered these impacts in a rulemaking and published its final continued storage rule and supporting generic environmental impact statement in September 2014. Section 5 discusses the continued storage rule in more detail.
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Figure 22. The Different NRC Classifications for Types of Reactors Operating Reactors Design: The U.S. fleet consists mainly of large reactors that use regular water (light water, as opposed to heavy water that has a different type of hydrogen than commonly found in nature) for both cooling the core and facilitating the nuclear reaction.
Capacity: The generation base load of these plants is 1,677 MWt (approximately 570 MWe) or higher.
Safety: These reactors have active safety systems powered by alternating current (ac) and require an operator to reach a safe shutdown state.
Fuel: These reactors require enriched uranium.
Advanced Reactors Design: Advanced reactors are a new generation of nonlight-water reactors.They use coolants including molten salts, liquid metals, and even gases such as helium.
Capacity: These plants range in power from very small reactors to a power level comparable to existing operating reactors.
Safety: These reactors are expected to provide enhanced margins of safety and use simplified, inherent, and passive means to ensure safety.
They may not require an operator to shut down.
Fuel: These reactors could use enriched uranium, thorium, or used nuclear fuel.
Small Modular Reactors Design: Small modular reactors (SMRs) are similar to large light-water reactors but are smaller, compact designs. These factory-fabricated reactors can be transported by truck or rail to a nuclear power site. Additional SMRs can be installed on site to scale or to meet increased energy needs.
Capacity: These reactors are about one-third the size of typical reactors with a generation base load of 1,000 MWt (300 MWe) or less.
Safety: These reactors can be installed underground, providing more safety and security. They are built with passive safety systems and can be shut down without an operator.
Fuel: These reactors require enriched uranium.
Research and Test Reactors Design: Research and test reactorsalso called nonpower reactorsare primarily used for research, training, and development. They are classified by their moderator, the material used to slow down the neutrons, in the nuclear reaction. Typical moderators include water (H2O), heavy water (D2O), polyethylene, and graphite.
Capacity: These current licensed facilities range in size from 5 watts (less than a night light) to 20 MWt (equivalent to 20 standard medical x-ray machines).
Safety: All NRC-licensed research and test reactors have a built-in safety feature that reduces reactor power during potential accidents before an unacceptable power level or temperature can be reached.
Fuel: Reactors may also be classified by the type of fuel used, such as MTR (plate-type fuel) or TRIGA fuel. TRIGA fuel is unique in that a moderator (hydrogen) is chemically bonded to the fuel.
See Appendix B for a list of new nuclear power plant licensing applications in the United States.
NUCLEAR REACTORS l 35
Figure 23. New Reactor Licensing Process 10 CFR Part 50Two-Step Licensing Process STEP ONE:
Construction Permit Review START STEP 1 Application submitted to NRC Preliminary Safety Analysis Review Report by ACRS Environmental Safety Review Review Possible Contested Mandatory Hearing Hearing START PART 2 DECISION STEP 1 Commission Decision Construction Construction on Permit Permit and Further Design Construction Final Safety Complete Analysis Report STEP TWO: Operating License Operating License Application Application Review Submitted to NRC Review by ACRS Environmental Safety Review Review Possible NRC Operating Contested Hearing License Decision Plant Operation DECISION STEP 2 36 l NUCLEAR REACTORS
10 CFR Part 52Combined License Application Review Process Safety Review START Combined License Application Public Involvement Final Safety Evaluation Report Public Comments Notice of Environmental Hearing Review DECISION Hearings Final Environmental Impact Commission Statement Decision on Application Combined License ApplicationsConstruction and Operating By issuing a COL, the NRC authorizes the licensee to construct and (with specified conditions) operate a nuclear power plant at a specific site, in accordance with established laws and regulations. If the Commission finds that the acceptance criteria are met, a COL is valid for 40 years. A COL can be renewed for additional 20-year terms (see Figure 24. Locations of New Nuclear Power Reactor Applications). For the current review schedule for active licensing applications, consult the NRCs Web site (see the Web Link Index).
Public Involvement Even before the NRC receives an application, the agency holds a public meeting to talk to the community near the proposed reactor location. The agency explains the review process and outlines how the public may participate. After the application is submitted, the NRC asks the public to comment on which factors the agency should consider in its environmental review under the National Environmental Policy Act.
The NRC later posts a draft environmental evaluation on its Web site and asks for public input.
There is no formal opportunity for public comment on the staffs safety evaluation, but members of the public are welcome to attend public meetings and make comments. Individuals or groups can raise legal arguments against a new reactor application in an Atomic Safety and Licensing Board hearing if they would be affected by the new reactor and meet basic requirements for requesting a hearing. The NRC announces opportunities to request these hearings in news releases, in the Federal Register, and on its Web site.
NUCLEAR REACTORS l 37
Figure Locations24. Locations of New of Nuclear New Nuclear Power Power ReactorActive Reactor Active Applications Applications and Approved and Approved Licenses Licenses Oklo Fermi RI PSEG (ESP) 2 North Anna 2
Shearon Harris*
2 Clinch River (ESP)
William States Lee 2
= A proposed new reactor at or near an existing nuclear plant Vogtle
= A proposed reactor at a site that has Comanche Peak* 2 Turkey Point not previously produced nuclear power
= Approved reactor = 1 unit 2 = 2 units
- Review suspended Note: Alaska and Hawaii are not pictured, but have no sites. On July 31, 2017, South Carolina Electric and Gas announced its decision to cease construction on V.C. Summer Units 2 and 3, and the licensee has requested that the COLs be withdrawn.
As of October 2017, Duke Energy has announced plans to cancel reactors at Levy County, FL, and William States Lee, SC.
Applications were withdrawn for Calvert Cliffs, Grand Gulf, Nine Mile Point, Victoria County, and Callaway (COL and ESP).
In June 2018, Nuclear Innovation North America submitted a letter requesting that the COLs for South Texas Project Units 3 and 4 be withdrawn. NRC-abbreviated reactor names are listed. Data are current as of August 2021.
For the most recent information, go to the NRC Web site at https://www.nrc.gov.
Early Site Permits An ESP review examines whether a piece of land is suitable for a nuclear power plant. The review covers site safety, environmental protection, and emergency preparedness. The ACRS reviews safety-related portions of an ESP application. As with COL reviews, the public participates in the environmental portion of the NRCs ESP review, and the public can challenge an application in a hearing.
Design Certifications The NRC issues standard design certifications through rulemaking for reactor designs that meet basic requirements for ensuring safe operation. Utilities can cite a certified design when applying for a nuclear power plant construction permit, COL, ESP, or manufacturing license. The certification is valid for 15 years from the date issued and can be renewed for an additional 15 years. The NRC staff has also issued standard design approvals upon completion of the final SER for the design.
Standard design approvals may be referenced by a construction permit, combined license, or manufacturing license. The new reactor designs under review incorporate new elements such as passive safety systems and simplified system designs. The six certified designs are
GE-Hitachi Nuclear Energys Advanced Boiling-Water Reactor (ABWR)
Westinghouse Electric Companys System 80+
Westinghouse Electric Companys AP600
Westinghouse Electric Companys AP1000
GE-Hitachi Economic Simplified Boiling-Water Reactor (ESBWR)
Korean Electric Power Corporation APR 1400 (Advanced Power Reactor) 38 l NUCLEAR REACTORS
Design Certification Renewals The NRC staff has completed its review of GE-Hitachis application to renew the ABWR design certification. The direct final rule renewing this design certification was published on July 1, 2021, and was effective September 29, 2021.
Advanced Reactor Designs Several companies are considering advanced reactor designs and technologies and are conducting preapplication activities with the NRC. These reactors are cooled by liquid metals, molten salt mixtures, or inert gases. Advanced reactors can also consider fuel materials and designs that differ radically from todays enriched-uranium dioxide (UO2) pellets with zirconium cladding. While developing the regulatory framework for advanced reactor licensing, the NRC is examining policy issues in areas such as security and emergency preparedness.
Small Modular Reactors Small modular reactors (SMRs) use water to cool the reactor core in the same way as todays large light-water reactors. SMR designs also use the same enriched uranium fuel as todays reactors. However, SMR designs are considerably smaller. Each SMR module generates 300 megawatts electric (MWe) (1,000 MWt) or less, compared to todays large designs that can generate 1,000 MWe (3,300 MWt) or more per reactor. The NRCs discussions to date with SMR designers involve modules generating less than 200 MWe (660 MWt).
New Reactor Construction Inspections NRC inspectors based in the agencys Region II office in Atlanta, GA, monitor reactor construction activities. These expert staff members ensure licensees carry out construction according to NRC license specifications and related regulations.
The NRC staff examines the licensees operational programs in areas such as security, radiation protection, and operator training and qualification. Inspections at a construction site verify that a licensee has completed required inspections, tests, and analyses and has met associated acceptance criteria. The NRCs onsite resident construction inspectors oversee day-to-day licensee and contractor activities.
In addition, specialists in NRC Region IIs Division of Construction Oversight periodically visit the sites to ensure the facilities are being constructed using the approved design.
The NRCs Construction Reactor Oversight Process assesses all of these activities. Before the agency will allow a new reactor to start up, NRC inspectors must confirm that the licensee has met all the acceptance criteria in its COL.
The agency also inspects domestic and overseas factories and other vendor facilities. This ensures new U.S. reactors receive high-quality products and services that meet the NRCs regulatory requirements. The NRCs Web site has more information on new reactor licensing activities (see the Web Link Index).
NRC senior leaders observe new construction activities to ensure NRC regulations are being met at Vogtle Units 3 and 4, in Georgia.
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NEW LICENSING OF NONPOWER PRODUCTION AND UTILIZATION FACILITIES Research reactors, testing facilities, and other nonpower facilities can be used to produce medical radioisotopes and demonstrate advanced reactor technologies. These research and test reactors are used to demonstrate new reactor technologies to meet future energy needs, promote training and education, and support needed medical care. To support these efforts, the NRC staff conducts safety and environmental reviews of construction permit and operating license applications, which are also subject to regulatory requirements for hearings and an independent review by the ACRS.
Doctors worldwide rely on a steady supply of molybdenum-99 (Mo-99) to produce technetium-99m in hospitals, which is used in a radiopharmaceutical applied in approximately 50,000 medical diagnostic procedures daily in the United States. The NRC supports the national policy objective of establishing a reliable, domestically available supply of this medical radioisotope by reviewing license applications for these facilities submitted in accordance with the provisions of 10 CFR Part 50. Since 2013, the NRC staff has received two construction permit applications and one operating license application for these facilities. The proposed facilities would irradiate low-enriched uranium targets in utilization facilities, then separate Mo-99 from other fission products in hot cells contained within a production facility. The NRC approved the construction permits for SHINE Medical Technologies, LLC (SHINE), in February 2016 and for Northwest Medical Isotopes, LLC, in May 2018. The staff is reviewing SHINEs application for a license to operate its facility.
The NRC is also engaged in pre-application topical report reviews for Atomic Alchemy and Abilene Christian University, which have proposed to construct nonpower reactors for radioisotope production and molten salt reactor technology demonstration, respectively.
The NRC anticipates receiving additional topical reports, construction permit applications, operating license applications, materials license applications, and license amendment requests in the coming years from other potential Mo-99 producers and advanced nonpower reactor applicants.
The NRC continues to develop the necessary infrastructure programs for these facilities, including inspection procedures for construction and operation. The agency provides updates on the status of these licensing reviews through NRC-hosted public meetings, Commission meetings, and interagency interactions.
Technetium-99m is produced by the decay of molybdenum-99 and is used in diagnostic nuclear medical imaging procedures 40 l NUCLEAR REACTORS
NUCLEAR REGULATORY RESEARCH The NRCs Office of Nuclear Regulatory Research supports the agencys mission by providing technical advice, tools, methods, data, and information. This research can identify, explore, and resolve safety issues, as well as provide information supporting licensing decisions and new regulations and guidance. The NRCs research includes the following:
independently confirming other parties work through experiments and analyses
developing technical support for agency safety decisions
preparing for the future by evaluating the safety implications of new technologies and designs for nuclear reactors, materials, waste, and security The research program reflects the challenges of an evolving industry. The NRCs research covers the light-water reactor technology developed in the 1960s and 1970s, todays advanced light-water reactor designs, and fuel cycle facilities. The agency has longer term research plans for more advance reactor concepts, such as those cooled by high-temperature gases or molten salts. The NRCs research programs examine a broad range of subjects, such as the following:
material performance (for example, environmentally assisted degradation and cracking of metallic alloys, aging management of reactor components and materials, boric-acid corrosion, radiation effects on concrete, and embrittlement of reactor pressure vessel steels)
events disrupting heat transfer from a reactor core, criticality safety, severe reactor accidents, how radioactive material moves through the environment, and how that material could affect human health (sometimes using NRC-developed computer codes for realistic simulations)
computer codes used to analyze fire conditions in nuclear facilities, to examine how reactor fuel performs, and to assess nuclear power plant risk
new and evolving technologies such as additive manufacturing, accident tolerant fuel, and advanced control and automation
experience gained from operating reactors
digital instrumentation and controls, including analyzing digital system components, security aspects of digital systems, and probabilistic assessment of digital system performance
enhanced risk-assessment methods, tools, and models to support the increased use of probabilistic risk assessment in regulatory applications
earthquake, flooding, and high-wind hazards
ultrasonic testing and other nondestructive means of inspecting reactor components and dry cask storage systems and developing and accessing ultrasonic testing simulation tools to optimize examination procedure variables
the human side of reactor operations, including safety culture, and computerization and automation of control rooms The Office of Nuclear Regulatory Research also plans, develops, and manages research on fire safety and risk, including modeling, and evaluates potential security vulnerabilities and possible solutions (see the Web Link Index for more information on specific NRC research projects and activities).
NUCLEAR REACTORS l 41
NRC Research Funding The NRCs research program involves about 5 percent of the agencys personnel and uses about 7 percent of its contracting funds. The NRCs $77 million research budget for Fiscal Year (FY) 2021 includes contracts with national laboratories, universities, research organizations, and other Federal agencies (e.g., the National Institute of Standards and Technology, the U.S. Army Corps of Engineers, and the U.S. Geological Survey). NRC research funds support access to a broader group of experts and international research facilities. Figure 25. NRC Research Funding, FY 2021, illustrates the primary areas of research.
The majority of the NRCs research budget supports maintaining operating reactor safety and security, while the remainder supports regulatory activities for new and advanced reactors, industrial and medical use of nuclear materials, and nuclear fuel cycle and radioactive waste programs. The NRC cooperates with universities and nonprofit organizations on research for the agencys specific interests.
The NRCs international cooperation in research areas leverages agency resources, facilitates work on advancing existing technologies, and determines any safety implications of new technologies.
The agencys leadership role in international organizations such as IAEA and OECD/NEA helps guide the agencys collaborations.
The NRC maintains international cooperative research agreements with more than two dozen foreign governments. This work covers technical areas from severe accident research and computer code development to materials degradation, nondestructive examination, fire risk, and human-factors research. Cooperation under these agreements is more efficient than conducting research independently.
Figure 25. NRC Research Funding, Fiscal Year 2021 NRC Research Funding, FY2021 TOTAL $77 MILLION Reactor Program$55 Million New/Advanced Reactor Licensing$18 Million Materials and Waste$4 Million Note: Totals may not equal sum of components because of rounding.
See Appendix U for States with NRC Grant Award Recipients in Fiscal Year 2020 42 l NUCLEAR REACTORS
A group observes the Annular Core Research Reactor. The reactor has been in operation since 1979 at Sandia National Laboratories in New Mexico.
NRC Chairman Christopher T. Hanson tours the NIST Center for Neutron Research in Maryland, learning about some of the research conducted using the largest NRC-regulated nonpower reactor in the U.S.
NUCLEAR REACTORS l 43
4 NUCLEAR MATERIALS
The NRC regulates each phase of the nuclear fuel cyclethe steps needed to turn uranium ore into fuel for nuclear power plantsas well as storing and disposing of the fuel after it is used in a reactor. In some States, the NRC also regulates nuclear materials used for medical, industrial, and academic purposes. Work includes reviewing applications for and issuing new licenses, license renewals, and amendments to existing licenses. The NRC also regularly conducts safety and security inspections.
MATERIALS LICENSES States have the option to regulate certain radioactive materials under agreements with the NRC.
Those that do are called Agreement States (see Figure 26. U.S. Agreement States). These Agreement States then develop regulations consistent with the NRCs and appoint officials to ensure nuclear materials are used safely and securely. Only the NRC regulates nuclear reactors, fuel fabrication facilities, consumer product distribution, and certain amounts of what is called special nuclear materialthat is, radioactive material that can fission or split apart.
Radioactive materials, or radionuclides, are used for many purposes. They are used in civilian and military industrial applications; basic and applied research; the manufacture of consumer products; academic studies; and medical diagnosis, treatment, and research. They can be produced in a reactor or an acceleratora machine that propels charged particles. The NRC does not regulate accelerators but does license the use of radioactive materials produced in accelerators.
Figure 26. U.S. Agreement States U.S. Agreement States RI ALASKA HAWAII PUERTO RICO GUAM Letter of Intent AMERICAN SAMOA Agreement States NORTHERN MARIANAS Non-Agreement States Note: Data are current as of June 2021. For the most recent information, go to the NRC facility locator page https://www.nrc.gov/info-finder/reactors/index.html.
See Appendix L for a list of the number of materials licenses by State.
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MEDICAL AND ACADEMIC The NRC and Agreement States review the facilities, personnel, program controls, and equipment involved in using radioactive materials in medical and academic settings. These reviews ensure the safety of the public, patients, and workers who might be exposed to radiation from those materials. The NRC regulates only the use of radioactive material, which is why it does not regulate x-ray machines or other devices that produce radiation without using radioactive materials.
Medical The NRC and Agreement States license hospitals, physicians, veterinarians, health physicists, and radiopharmacists to use radioactive materials in medical treatments and diagnoses. The NRC also develops guidance and regulations for licensees.
These regulations require licensees to have experience and special training, focusing on operating equipment safely, controlling the radioactive material, and keeping accurate records.
To help the NRC stay current, the Advisory Committee on the Medical Uses of Isotopes advises the NRC staff on policy and technical issues that arise in the regulation of the medical uses of radioactive material in diagnosis and therapy. This expert committee includes scientists, physicians, and other health care professionals who have experience with medical radionuclides.
Nuclear Medicine Doctors use radioactive materials to diagnose or treat about one-third of all patients admitted to hospitals. This branch of medicine is known as nuclear medicine, and the radioactive materials are called radiopharmaceuticals.
Two types of radiopharmaceutical tests can diagnose medical problems. In vivo tests (within the living) administer radiopharmaceuticals directly to patients. In vitro tests (within the glass) add radioactive materials to lab samples taken from patients.
Radiation Therapy Doctors also use radioactive materials and radiation-producing devices to treat medical conditions. They can treat hyperthyroidism and some cancers, for example, and can also ease the pain caused by bone cancer. Radiation therapy aims to deliver an accurate radiation dose to a target site while protecting surrounding healthy tissue. To be most effective, treatments often require several exposures over a period of time. When used to treat malignant cancers, radiation therapy is often combined with surgery or chemotherapy.
There are three main categories of radiation therapy:
External beam therapy (also called teletherapy) is a beam of radiation directed to the target tissue. Several different types of machines are used in external beam therapy.
Treatment machines regulated by the NRC contain high-activity radioactive sources (usually cobalt-60) that emit photons to treat the target site.
Brachytherapy treatments use sealed radioactive sources placed near or even directly in cancerous tissue. The radiation dose is delivered at a distance of up to an inch (2.54 centimeters) from the target area.
Therapeutic radiopharmaceuticals deliver a large radiation dose inside the body. Different radioactive materials can be given to patients and will concentrate in different regions or organ systems.
Academic The NRC and the Agreement States issue licenses to academic institutions for education and research. For example, qualified instructors may use radioactive materials in classroom demonstrations. Scientists in many disciplines use radioactive materials for laboratory research.
NUCLEAR MATERIALS l 47
INDUSTRIAL The NRC and Agreement States issue licenses that specify the type, quantity, and location of radioactive materials to be used. Radionuclides can be used in industrial radiography, gauges, well logging, and manufacturing. Radiography uses radiation sources to find structural defects in metal and welds. Gas chromatography uses low-energy radiation sources to identify the chemical elements in an unknown substance. For example, gas chromatography devices are used to analyze air pollutants, blood alcohol content, essential oils, and food products. They are also used in biological and medical research to identify the parts that make up complex proteins and enzymes. Well-logging devices use radioactive sources and detection equipment to make a record of geological formations from within a well. This process is used extensively for oil, gas, coal, and mineral exploration.
Nuclear Gauges Nuclear gauges are used to measure the physical properties of products and industrial processes nondestructively as a part of quality control. Gauges use radiation sources to determine the thickness of paper products, fluid levels in oil and chemical tanks, and the moisture and density of soils and materials at construction sites. Gauges may be fixed or portable.
A gauge has shielding to protect the operator while the radioactive source is exposed. When the measuring process is completed, the source is retracted or a shutter closes, minimizing exposure from the source. A fixed gauge has a radioactive source shielded in a container. When the user opens the containers shutter, a beam of radiation hits the material or product being processed or controlled. A detector mounted opposite the source measures the radiation passing through the product. The gauge readout or computer monitor shows the measurement. The material and process being monitored dictate the type, energy, and strength of radiation used.
Fixed fluid gauges are used by the beverage, food, plastics, and chemical industries. Installed on a pipe or the side of a tank, these gauges measure the density, flow rate, level, thickness, and weights of a variety of materials and surfaces. A portable gauge uses both a shielded radioactive source and a detector. The gauge is placed on the object to be measured. Some gauges rely on radiation from the source to reflect back to the gauge. Other gauges insert the source into the object. The detector in the gauge measures the radiation either directly from the inserted source or from the reflected radiation.
The moisture density gauge is a portable device that places a gamma source under the surface of the ground through a tube. Radiation is transmitted directly to the detector on the bottom of the gauge, allowing accurate measurements of compaction. Industry uses such gauges to monitor the structural integrity of roads, buildings, and bridges. Airport security uses nuclear gauges to detect explosives in luggage.
Commercial Irradiators The U.S. Food and Drug Administration and other agencies have approved the irradiation of food.
Commercial irradiators expose food and spices, as well as products such as medical supplies, blood, and wood flooring, to gamma radiation. This process can be used to eliminate harmful germs and insects or for hardening or other purposes. The gamma radiation does not leave radioactive residue or make the treated products radioactive. The radiation can come from radioactive materials (e.g., cobalt-60), an x-ray, or an electron beam.
The NRC and Agreement States license about 50 commercial irradiators. Up to 10 million curies of radioactive material can be used in these types of irradiators. NRC regulations protect workers and the public from this radiation.
Two main types of commercial irradiators are used in the United States: underwater and wet-source-storage panoramic models. Underwater irradiators use sealed sources (radioactive material encased inside a capsule) that remain in the water at all times, providing shielding for workers and the public. The product to be irradiated is placed in a watertight container, lowered into the pool, irradiated, and then removed.
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Wet-source-storage panoramic irradiators also store radioactive sealed sources in water. However, the sources are raised into the air to irradiate products that are automatically moved in and out of the room on a conveyor system. Sources are then lowered back into the pool when not in use. For this type of irradiator, thick concrete walls and ceilings or steel barriers protect workers and the public when the sources are lifted from the pool.
TRANSPORTATION More than 3 million packages of radioactive materials are shipped each year in the United States by road, rail, air, or water. This represents less than 1 percent of the Nations yearly hazardous material shipments.
The NRC and the U.S. Department of Transportation (DOT) share responsibility for regulating the safety of radioactive material shipments. The vast majority of these shipments consist of small amounts of radioactive materials used in industry, research, and medicine. The NRC requires such materials to be shipped in accordance with DOTs safety regulations.
MATERIALS SECURITY To monitor the manufacture, distribution, and possession of the most high-risk sources, the NRC set up the National Source Tracking System (NSTS) in January 2009. Sources tracked in the system are known as Category 1 and Category 2 sources. They have the potential to cause permanent injury and even death if they are not handled safely and securely, in compliance with NRC requirements. The majority of these sources are cobalt-60.
Licensees use this secure Web-based system to enter information on the receipt or transfer of tracked radioactive sources (see Figure 27. NRC Approach to Source Security). The NRC and the Agreement States use the system to monitor where high-risk sources are made, shipped, and used.
The NRC and the Agreement States have increased controls on the most safety-significant radioactive materials. Stronger physical security requirements and stricter limits on who can access the materials give the NRC and the Agreement States added confidence in their security. The NRC has also joined with other Federal agencies, such as the U.S. Department of Homeland Security (DHS) and DOEs National Nuclear Security Administration, to set up an additional layer of voluntary protection. Together, these activities help make potentially dangerous radioactive sources even more secure and less vulnerable to malevolent uses.
Figure 27. NRC Approach to Source Security NUCLEAR MATERIALS l 49
NUCLEAR FUEL CYCLE The typical nuclear fuel cycle uses uranium in different chemical and physical forms. Figure 28. The Nuclear Fuel Cycle illustrates the stages, which include uranium recovery, conversion, enrichment, and fabrication, to produce fuel for nuclear reactors. Uranium is recovered or extracted from ore, converted, and enriched. Then the enriched uranium is manufactured into pellets, which are placed into fuel assemblies to power nuclear reactors.
TheFigure 28. The Nuclear Fuel Cycle Nuclear Fuel Cycle Fuel Fabrication Enriched Uranium Fresh UO2 UO2 Depleted Fresh Uranium MOX MOX Deconversion of Depleted Uranium-Plutonium Reactor Enrichment Mixture Dry Cask Uranium Pool Storage Conversion Spent Reprocessed MOX Milling Uranium Spent Reprocessing UO2 Uranium Recovery Facility*
Heap In Situ Mining Leach Disposal Natural Uranium
- Reprocessing of spent nuclear fuel, including mixed-oxide (MOX) fuel, is not practiced in the United States.
Note: The NRC has no regulatory role in mining uranium.
Uranium Recovery The NRC does not regulate conventional mining but does regulate the processing of uranium ore, known as milling. This processing can be done at three types of uranium recovery facilities:
conventional mills, in situ recovery facilities, and heap leach facilities. Once the milling is completed, the uranium is in a powder form known as yellowcake, which is packed into 55-gallon (208-liter) drums and transported to a fuel cycle facility for further processing. The NRC has an established regulatory framework for uranium recovery facilities. This framework ensures they are licensed, operated, decommissioned, and monitored to protect the public and the environment.
Conventional Uranium Mill A conventional uranium mill is a chemical plant that extracts uranium from ore. Most conventional mills are located away from population centers and within about 30 miles (50 kilometers) of a uranium mine. In a conventional mill, the process of uranium extraction from ore begins when ore is hauled to the mill and crushed. Sulfuric acid dissolves and removes 90 to 95 percent of the uranium from the ore. The uranium is then separated from the solution, concentrated, and dried to form yellowcake.
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In Situ Recovery In situ recovery is another way to extract uraniumin this case, directly from underground ore. In this process, a solution of ground water, typically mixed with oxygen or hydrogen peroxide and sodium bicarbonate or carbon dioxide, is injected into the ore to dissolve the uranium. The solution is then pumped out of the rock and the uranium separated to form yellowcake (see Figure 29. The In Situ Uranium Recovery Process).
The In Situ Uranium Recovery Process Figure 29. The In Situ Uranium Recovery Process Central Processing Plant Injection Well Recovery Well Underlying Monitoring Well Overlying Monitoring Well Perimeter Monitoring Well typically 500 Perimeter Monitoring Well Header Monitoring House Well From Processing Plant To Processing Plant Monitoring Well Recovery Aquifer (Sands, Well Clays, and Gravel)
Confining Layer Perimeter (Upper Clay) Injection Monitoring Well Well Uranium-Bearing Aquifer (Sand)
Confining Layer Injection (Lower Clay) Well Aquifer (Sand/Gravel)
Submersible Pump Injection wells pump a solution of native ground water, typically mixed with oxygen or hydrogen peroxide and sodium bicarbonate or carbon dioxide, into the aquifer (ground water) containing uranium ore. The solution dissolves the uranium from the deposit in the ground and is then pumped back to the surface through recovery wells , all controlled by the header house. From there, the solution is sent to the processing plant. Monitoring wells are checked regularly to ensure the injection solution is not escaping from the wellfield. Confining layers keep ground water from moving from one aquifer to another.
NUCLEAR MATERIALS l 51
Heap Leach Facility Heap leach facilities also extract uranium from ore. At these facilities, the ore is placed in piles or heaps on top of liners. The liners prevent uranium and other chemicals from moving into the ground.
Sulfuric acid is dripped onto the heap and dissolves uranium as it moves through the ore. The uranium solution drains into collection basins, where it is piped to a processing plant. At the plant, uranium is extracted, concentrated, and dried to form yellowcake. There are no licensed uranium heap leach facilities in operation in the United States.
Licensing Uranium Recovery Facilities The NRC currently regulates an in situ uranium recovery facility in Nebraska, which suspended operations in 2016. Two in situ recovery facilities, one in South Dakota and another in New Mexico, have been licensed but not constructed. Nine in situ recovery facilities are operating in Wyoming under State regulations, as Wyoming became an NRC Agreement State in 2018. The NRC considers the views of stakeholders, including Native American Tribal governments, to address their concerns with licensing new uranium recovery facilities. (See the Web Link Index for more information on uranium recovery and Agreement States. See the Glossary for the definition and an illustration of the heap leach recovery process.)
The NRC is also overseeing the decommissioning of five uranium recovery facilities: three in New Mexico, one in Oklahoma, and another in Wyoming that was not transferred to the State under its agreement with the NRC. See Figure 30. Locations of NRC-Licensed Uranium Recovery Facility Sites. See Glossary for information on mill tailings.
Figure 30. Locations of NRC-Licensed Uranium Recovery Facility Sites Locations of NRC-Licensed Uranium Recovery Facilities Sites (Includes sites undergoing decommissioning)
RI States with authority to license uranium recovery facility sites States where the NRC has retained authority to license uranium recovery facilities NRC-licensed uranium recovery facility sites (8)
Note: Alaska and Hawaii are not pictured here and do not have sites.
For the most recent information, go to the NRC facility locator page at https://www.nrc.gov/info-finder/reactors/index.html.
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The NRC is also responsible for the following actions:
inspecting and overseeing both active and inactive uranium recovery facilities
ensuring the safe management of mill tailings (waste) at facilities that the NRC requires to be located and designed to minimize radon release and disturbance by weather or seismic activity
enforcing requirements to ensure cleanup of active and closed uranium recovery facilities
applying stringent financial requirements to ensure funds are available for decommissioning
ensuring licensees monitor ground water for contamination
providing oversight of decommissioned uranium recovery facilities FUEL CYCLE FACILITIES The NRC licenses all commercial fuel cycle facilities involved in conversion, enrichment, and fuel fabrication (see Figure 31. Locations of NRC-Licensed Fuel Cycle Facilities, and Figure 32. Simplified Fuel Fabrication Process).
The NRC reviews applications for licenses, license amendments, and renewals. The agency also routinely inspects licensees safety, safeguards, security, and environmental protection programs.
These facilities turn the uranium that has been removed from ore and made into yellowcake into fuel for nuclear reactors. In this process, the conversion facility converts yellowcake into uranium hexafluoride (UF6). Next, an enrichment facility heats the solid UF6 enough to turn it into a gas, which is enriched, or processed to increase the concentration of the isotope uranium-235. The UF6 gas is then cooled back into solid UF6 for shipment to a fuel fabrication facility.
Once at a fuel fabrication facility, the UF6 is mechanically and chemically processed back into a solid UO2 powder. The powder is blended, milled, pressed, and fused into ceramic fuel pellets about the size of a fingertip. The pellets are stacked into tubes or rods that are about 14 feet (4.3 meters) long and made of material such as zirconium alloys; this material is referred to as cladding. These fuel rods are made to maintain both their chemical and physical properties under the extreme conditions of heat and radiation present inside an operating reactor.
The fuel rods are bundled into fuel assemblies for use in reactors. The assemblies are washed, inspected, and stored in a special rack until ready for shipment to a nuclear power plant. The NRC inspects these operations to ensure they are conducted safely.
Domestic Safeguards Program The NRCs domestic safeguards program for fuel cycle facilities and transportation is aimed at ensuring that special nuclear material (such as plutonium or enriched uranium) is not stolen and does not pose a risk to the public from sabotage or terrorism. Through licensing and inspections, the NRC verifies that licensees apply safeguards to protect special nuclear material.
The NRC and DOE developed the Nuclear Materials Management and Safeguards System (NMMSS) to track transfers and inventories of special nuclear material, source material from abroad, and other material.
These licensees verify and document their inventories in the NMMSS database. The NRC and Agreement States have licensed several hundred additional sites that possess special nuclear material in smaller quantities. Licensees possessing small amounts of special nuclear material must confirm their inventories annually in the NMMSS database.
See Appendix M for major U.S. fuel cycle facility sites and Glossary for more information on the enrichment process.
NUCLEAR MATERIALS l 53
Figure 31. Locations of NRC-Licensed Fuel Cycle Facilities Locations of NRC-Licensed Fuel Cycle Facilities RI Uranium Fuel Fabrication Facility (5) Depleted Uranium Deconversion Facility (1)
Gas Centrifuge Uranium Enrichment Facility (2) Uranium Hexafluoride Conversion Facility (1)
Note: Alaska and Hawaii are not pictured here and do not have sites. On January 5, 2021, the NRC issued a letter terminating the license for the GLE Laser Separation Enrichment Facility. For the most recent information, go to the NRC facility locator page at https://www.nrc.gov/info-finder/reactors/index.html.
Figure 32. Simplified Fuel Fabrication Process Incoming UO2 Powder Fuel Rod/Bundle/Transport to UF6 UF6 Powder Processing/Pellet Assembly/ Nuclear Cylinders Vaporization Production Manufacturing Quality Check Reactors Fabrication of commercial light-water reactor fuel consists of the following three basic steps:
- 1. the chemical conversion of UF6 to UO2 powder
- 2. a ceramic process that converts UO2 powder to small ceramic pellets
- 3. a mechanical process that loads the fuel pellets into rods and constructs finished fuel assemblies 54 l NUCLEAR MATERIALS
A Bexxar Automated-Inspection unit placing a vial containing radiopharmaceutical into a lead pot. Courtesy of the Noridan Corporation.
A moisture density gauge indicates whether a foundation is suitable for constructing a building or roadway. Courtesy of APNGA NUCLEAR MATERIALS l 55
5 RADIOACTIVE WASTE
LOW-LEVEL RADIOACTIVE WASTE DISPOSAL Low-level radioactive waste (LLW) includes items contaminated with radioactive material or exposed to neutron radiation. This waste typically consists of contaminated protective shoe covers and clothing, wiping rags, mops, filters, reactor water treatment residues, equipment and tools, medical waste, and laboratory animal carcasses and tissue. Some LLW is quite low in radioactivityeven as low as just above background levels found in nature. Some licensees, notably hospitals, store such waste on site until it has decayed and lost most of its radioactivity.
Then it can be disposed of as ordinary trash. Other LLW, such as parts of a reactor vessel from a nuclear power plant, is more radioactive and requires special handling.
Waste that does not decay fairly quickly is stored until amounts are large enough for shipment to an LLW disposal site in containers approved by DOT and the NRC. Commercial LLW can be disposed of in facilities licensed by either the NRC or Agreement States. The facilities are designed, constructed, and operated to meet NRC and State safety standards. The facility operator analyzes how the facility will perform in the future based on the environmental characteristics of the site. Current LLW disposal uses shallow land disposal sites with or without concrete vaults (see Figure 33. Low-Level Radioactive Waste Disposal).
Determining the classification of waste can be a complex process. The NRC classifies LLW based on its potential hazards. The NRC has specified disposal and waste requirements for three classes of wasteClass A, B, and Cwith progressively higher concentrations of radioactive material.
Class A waste, the least radioactive, accounts for approximately 96 percent of the total volume of LLW in the United States. A fourth class of LLW, called greater-than-Class-C waste, must be disposed of in a geological repository licensed by the NRC unless the Commission approves an alternative proposal. Under the Low-Level Radioactive Waste Policy Amendments Act of 1985, DOE is responsible for disposal of greater-than-Class-C waste.
The volume and radioactivity of waste vary from year to year. Waste volumes currently include several million cubic feet each year from operating and decommissioning reactor facilities and from cleanup of contaminated sites.
The Low-Level Radioactive Waste Policy Amendments Act gave the States responsibility for LLW disposal. The Act authorized States to do the following:
form regional compacts, with each compact to provide for LLW disposal site access
manage LLW imported to, and exported from, a compact
exclude waste generated outside a compact The States have licensed four active LLW disposal facilities:
EnergySolutions Barnwell facility, located in Barnwell, SCPreviously, Barnwell accepted LLW from all U.S. generators of LLW. Barnwell now accepts waste only from the Atlantic Compact States (Connecticut, New Jersey, and South Carolina). The State of South Carolina licensed Barnwell to receive Class A, B, and C waste.
EnergySolutions Clive facility, located in Clive, UTClive accepts waste from all States of the United States. The State of Utah licensed Clive for Class A waste only.
US Ecologys Richland facility, located in Richland, WA, on the Hanford SiteRichland accepts waste from the Northwest Compact States (Alaska, Hawaii, Idaho, Montana, Oregon, Utah, Washington, and Wyoming) and the Rocky Mountain Compact States (Colorado, Nevada, and New Mexico). The State of Washington licensed Richland to receive Class A, B, and C waste.
Waste Control Specialists Andrews facility, located in Andrews County, TX Andrews accepts waste from the Texas Compact States (Texas and Vermont). It also accepts waste from out-of-compact generators on a case-by-case basis. The State of Texas licensed Andrews to receive Class A, B, and C waste.
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Low-Level Radioactive Waste Disposal Figure 33. Low-Level Radioactive Waste Disposal Impermeable Top Soil Clay-Reinforced Low-Level Concrete Vaults Waste Canisters Impermeable Backfill Drainage System The LLW disposal site accepts waste from States participating in a regional disposal agreement.
See Appendix P for regional compacts and closed LLW sites, Appendices N and O for information about dry spent fuel storage and licensees, and Glossary for information on fuel reprocessing (recycling).
HIGH-LEVEL RADIOACTIVE WASTE MANAGEMENT Spent Nuclear Fuel Storage Commercial spent nuclear fuel, although highly radioactive, is stored safely and securely throughout the United States. Spent fuel is stored in pools and in dry casks at sites with operating nuclear power reactors, decommissioning or decommissioned reactors, and some other sites.
Waste can be stored safely in pools or casks for 100 years or more. The NRC licenses and regulates the storage of spent fuel, both at commercial nuclear power plants and at separate storage facilities.
Most reactor facilities were not designed to store the full amount of spent fuel that the reactors would generate during their operational licenses. Originally planned to store spent fuel temporarily in deep pools of continuously circulating water, which cools the spent fuel assemblies. After a few years, they were expected to send the spent fuel to a reprocessing plant. However, in 1977, the U.S. Government declared a moratorium on reprocessing spent fuel Although the Government later lifted the restriction, reprocessing has not resumed in the United States.
Facilities then expanded their storage capacity by using high-density storage racks in their spent fuel pools. For additional storage, some fuel assemblies are stored in dry casks on site (see Figure
- 34. Spent Fuel Generation and Storage after Use) in independent spent fuel storage installations (ISFSIs). These large casks are licensed by the NRC and are typically made of leak tight, welded, and bolted steel and concrete surrounded by another layer of steel or concrete.
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The spent fuel sits in the center of the cask in an inert gas. Dry cask storage shields people and the environment from radiation and keeps the spent fuel inside dry and nonreactive (see Figure 35.
Dry Storage of Spent Nuclear Fuel). Another type of ISFSI is called a consolidated interim storage facility, which would store spent fuel from multiple commercial reactors, including those that have ceased operation, on an interim basis until a permanent disposal option is available. Additional information on consolidated interim storage is available on the NRCs Web site (see the Web Link Index).
Figure 34. Spent Fuel Generation and Storage after Use Spent Fuel Generation and Storage after Use 1 A nuclear reactor is powered by enriched uranium-235 fuel. Nuclear Fission (splitting of atoms) Reactor generates heat, which produces steam that turns turbines to produce electricity. A reactor rated at several hundred megawatts may contain 100 or more tons of fuel in the form of Fuel bullet-sized pellets loaded Rods into long metal rods that are bundled together into fuel assemblies. Pressurized-water Coolant Fuel Uranium reactors (PWRs) contain Rod Fuel Pellets between 120 and 200 fuel assemblies. Boiling-water reactors (BWRs) contain between 370 and 800 fuel assemblies.
Fuel Assembly 2 After 5-6 years, spent fuel assemblies (which are typically 14 feet [4.3 meters]
long and which contain nearly 200 fuel rods for PWRs and 80-100 fuel rods for BWRs) are removed from the reactor and allowed to cool in storage pools.
At this point, the 900-pound (409-kilogram) assemblies contain only about one-fifth the original amount of uranium-235.
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Spent Fuel Generation and Storage after Use 3 Commercial light-water nuclear reactors store spent radioactive fuel in a steel-lined, seismically designed concrete pool under about 40 feet (12.2 meters) of water that provides shielding from radiation.
Pumps supply continuously flowing water Bundle of to cool the spent fuel. Extra water for Spent Fuel the pool is provided by other pumps Assemblies that can be powered from an onsite emergency diesel generator. Support features, such as water-level monitors and radiation detectors, are also in the pool.
Spent fuel is stored in the pool until it is transferred to dry casks on site or transported off site for interim storage or disposal.
Canister Storage Cask The NRC regulates facilities that store spent fuel in two different ways, either through a specific or general license. Site-specific licenses are issued after a safety review of the technical requirements and operating conditions for an ISFSI.
The agency has issued a general license authorizing nuclear power reactor licensees to store spent fuel on site in dry storage casks that the NRC has certified. Following a similar safety review, the NRC may issue a certificate of compliance and add the cask to a list of approved systems through a rulemaking. The agency issues licenses and certificates for terms not to exceed 40 years, but they can be renewed for up to an additional 40 years (see Figure 36.
Licensed and Operating Independent Spent Fuel Storage Installations by State).
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Figure 35. Dry Storage of Spent Nuclear Fuel Dry Storage of Spent Nuclear Fuel At nuclear reactors across the country, spent fuel is kept on site, typically above ground, in systems basically similar to the ones shown here. The NRC reviews and approves the designs of these spent fuel storage systems before they can be used.
1 Once the spent fuel has sufficiently cooled, it is loaded into special canisters that are designed to hold nuclear fuel assemblies. Water and air are removed. The canister is filled with inert gas, welded shut, and rigorously tested for leaks.
It is then placed in a cask for storage or transportation.
The dry casks are then loaded onto concrete pads.
2 The canisters can also be stored in aboveground concrete bunkers, each of which is about the size of a one-car garage.
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Public Involvement The public can participate in decisions about spent nuclear fuel storage, as it can in many licensing and rulemaking decisions. The Atomic Energy Act of 1954, as amended, and the NRCs own regulations call for public meetings about site-specific licensing actions and allow the public to comment on certificate of compliance rulemakings. Members of the public may also file petitions for rulemaking. Additional information on ISFSIs is available on the NRCs Web site (see the Web Link Index).
Spent Nuclear Fuel Disposal The current U.S. policy governing permanent disposal of high-level radioactive waste is defined by the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992. These acts specify that high-level radioactive waste will be disposed of underground in a deep geologic repository licensed by the NRC. Because the timing of repository availability is uncertain, the NRC looked at potential environmental impacts of storing spent fuel over three possible timeframes: the short term, which includes 60 years of continued storage after a reactors operating license has expired; the medium term, or 160 years after license expiration; and indefinite, which assumes a repository never becomes available. The NRCs findingsthat any environmental impacts can be managedappear in the 2014 report NUREG-2157, Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel.
The NRC adopted those findings into NRC regulations in a continued storage rule. This rule provides an important basis for issuing new or renewed licenses for nuclear power plants and spent fuel storage facilities.
Massive containers hold spent nuclear fuel at safe and secure dry storage facilities. This photo shows, at right, dry cask recently loaded with spent fuel being lifted from a horizontal transporter to be placed vertically on a specially-designed storage pad. Courtesy of Sandia National Laboratories.
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Figure 36. Licensed and Operating Independent Spent Fuel Storage Licensed Installations and Operating by State Independent Spent Fuel Storage Installations by State RI ISFSI site-specific license (16)
ISFSI general license (65) 35 States have at least one ISFSI ALABAMA IDAHO MASSACHUSETTS NEW JERSEY SOUTH CAROLINA Browns Ferry DOE: Three Mile Island 2 Pilgrim Hope Creek Catawba (Fuel Debris) Yankee Rowe Oyster Creek Oconee Farley DOE: Idaho Spent Salem Robinson ARIZONA Fuel Facility
- MICHIGAN Summer Palo Verde Big Rock Point NEW YORK ILLINOIS FitzPatrick TENNESSEE ARKANSAS Braidwood Cook Fermi 2 Ginna Sequoyah Arkansas Nuclear Byron Indian Point Watts Bar Clinton Palisades CALIFORNIA Nine Mile Point Dresden MINNESOTA TEXAS Diablo Canyon NORTH CAROLINA WCS Consolidated Interim Humboldt Bay GEH Morris (Wet) Monticello Storage Facility (CISF)
LaSalle Brunswick Rancho Seco Prairie Island McGuire Comanche Peak San Onofre Quad Cities South Texas Project MISSISSIPPI OHIO COLORADO Zion Grand Gulf Davis-Besse UTAH Fort St. Vrain IOWA Perry Private Fuel Storage*
CONNECTICUT Duane Arnold MISSOURI Callaway OREGON VERMONT Haddam Neck Millstone LOUISIANA Trojan Vermont Yankee NEBRASKA River Bend Cooper VIRGINIA FLORIDA Waterford PENNSYLVANIA Crystal River Ft. Calhoun North Anna Beaver Valley St. Lucie MAINE NEW HAMPSHIRE Limerick Surry Turkey Point Maine Yankee Seabrook Peach Bottom WASHINGTON GEORGIA MARYLAND Susquehanna Columbia Hatch Calvert Cliffs Three Mile Island WISCONSIN Vogtle Kewaunee La Crosse Point Beach
- Facility licensed only, never built or operated.
Note: Alaska and Hawaii are not pictured and have no sites. NRC-abbreviated reactor names are listed. Data are current as of Sept.13, 2021.
For the most recent information, go to the NRC facility locator page at https://www.nrc.gov/info-finder/reactors/index.hml.
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TRANSPORTATION The NRC regulates the transportation of spent nuclear fuel. The NRC establishes safety and security requirements in collaboration with the U.S. Department of Transportation, certifies transportation cask designs, and conducts inspections to ensure that requirements are being met. Spent nuclear fuel transportation casks are designed to meet the following safety criteria under both normal and accident conditions:
prevents the loss or dispersion of radioactive contents
shields everything outside the cask from the radioactivity of the contents
dissipates the heat from the contents
prevents nuclear criticality (a self-sustaining nuclear chain reaction) from occurring inside the cask Transportation casks must be designed to survive a sequence of tests, including a 30-foot (9.14-meter) drop onto an unyielding surface, a puncture test, a fully engulfing fire at 1,475 degrees Fahrenheit (800 degrees Celsius) for 30 minutes, and immersion under water.
This very severe test sequence, akin to the cask striking a concrete pillar along a highway at high speed and being engulfed in a severe and long-lasting fire and then falling into a river, simulates conditions more severe than 99 percent of vehicle accidents (see Figure 37. Ensuring Safe Spent Fuel Shipping Containers).
Ensuring Safe Spent Fuel Shipping Containers Figure 37. Ensuring Safe Spent Fuel Shipping Containers The impact (free drop and puncture), fire, and water immersion tests are considered in sequence to determine their cumulative effects on a given package.
To ensure the safe transportation of spent nuclear fuel and other nuclear materials, each year the NRC takes the following actions:
conducts transportation safety inspections of fuel, reactor, and materials licensees
reviews, evaluates, and certifies new, renewed, or amended transportation package design applications
inspects cask vendors and manufacturers to ensure the quality of dry cask design and fabrication Additional information on materials transportation is available on the NRCs Web site (see the Web Link Index).
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DECOMMISSIONING Decommissioning is the safe removal of a nuclear facility from service and the reduction of residual radioactivity to a level that permits release of the property and termination of the license. NRC rules establish site-release criteria and provide for unrestricted and under certain conditions restricted release of a site. The NRC also requires licensees to maintain financial assurance that funds will be available when needed for decommissioning.
The NRC regulates the decontamination and decommissioning of nuclear power plants, materials and fuel cycle facilities, research and test reactors, and uranium recovery facilities, with the ultimate goal of license termination (see Figure 38. Reactor Phases of Decommissioning, and Figure 39.
Power Reactor Decommissioning Status).
Figure 38. Reactor Phases of Decommissioning Reactor Phases of Decommissioning TRANSITION FROM OPERATION 0-2 years Fuel Removed TO DECOMMISSIONING Shutdown Activities 1. Permanent Cessation of Operations
- 2. Certification of Permanent Cessation of Operations
- 3. Certification of Permanent Fuel Removal Decommissioning Plans to the NRC MAJOR DECOMMISSIONING PSDAR MILESTONES Public 4. Post Shutdown Decommissioning Meeting Activity Report (PSDAR) Submittal*
NRC 5. PSDAR Public Meeting*
SAFSTOR Inspections 6. Major Decommissioning Activities Preparations for Storage and Dismantlement
- SAFSTOR DECON
- DECON up to 60 years Dry CasksSafely stored and monitored until disposal LICENSE TERMINATION ACTIVITIES License Termination Plan
- 7. License Termination Plan (LTP)
Public Submitted License Terminated Meeting 8. LTP Public Meeting Site released for public or other use NRC Conducts 9. Final Status Survey Survey 10. License Termination LAND REUSE Under SAFSTOR, a nuclear power plant is maintained and monitored in a condition that allows the radioactivity to decay; SAFSTOR afterwards, the plant shifts to DECON as the facility is dismantled and the property decontaminated.
Under DECON, equipment, structures, and portions of the facility containing radioactive contaminants are removed or DECON decontaminated to a level that permits release of the property and termination of the NRC license.
- Under DECON, some licensees have submitted the PSDAR before shutdown (license transfer model).
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Figure 39. Power Power Reactor Reactor Decommissioning Decommissioning Status Status I
I I
D D S I D T D S RI T
S I S S S S
I D D S T SS I D D
D S SAFSTOR D DECON Decommissioning Completed I Only ISFSI (Independent Spent Fuel Storage Installation)
T License Terminated (no fuel on site)
CALIFORNIA FLORIDA MASSACHUSETTS NEW YORK VERMONT S GE EVERSR D Crystal River D Pilgrim S Indian Point 1, 2, and 3 D Vermont Yankee S GE VBWR ILLINOIS I Yankee Rowe T Shoreham WISCONSIN D Humboldt Bay 3* S Dresden OREGON MICHIGAN S Kewaunee I Rancho Seco D Zion 1 and 2* I Trojan I Big Rock Point D La Crosse*
D San Onofre 1,2, and 3 IOWA S Fermi 2 PENNSYLVANIA COLORADO S Duane Arnold S Peach Bottom I Fort St. Vrain NEBRASKA MAINE T Saxton D Ft. Calhoun CONNECTICUT I Maine Yankee S Three Mile Island 1 and 2 I Haddam Neck NEW JERSEY MARYLAND SOUTH DAKOTA S Millstone D Oyster Creek D N.S. Savannah T Pathfinder
- The NRC is in the final stages of the license termination process with the reviews of the final status survey reports at Zion 1 and 2, La Crosse, and Humboldt Bay.
Notes: Fort St. Vrain ISFSI NRC SNM-2504 license was transferred to the DOE on June 4, 1999. ISFSIs are also located at all sites undergoing decommissioning or in SAFSTOR. GE Bonus, Hallam, and Piqua decommissioned reactor sites are part of the DOE nuclear legacy. For more information, visit DOEs Office of Legacy Management Sites Web page at https://www.energy.gov/lm/sites/. CVTR, Elk River, and Shippingport decommissioned reactor sites were either decommissioned before the formation of the NRC or were not licensed by the NRC. Licensees have announced their intention to permanently cease operations for Byron (2021), Dresden (2021), Palisades (2022), and Diablo Canyon (2024 and 2025).
NRC-abbreviated reactor names are listed. Alaska and Hawaii are not pictured and have no sites.
For the most recent information, go to the NRC facility locator page at https://www.nrc.gov/info-finder/reactors/index.html.
Data are current as of August 2021.
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Reactor Decommissioning When a nuclear power plant operator decides to cease operations, it must submit to the NRC a post-shutdown decommissioning activities report (PSDAR). This may be submitted before shutting down, or no later than 2 years following permanent cessation of operations. It includes detailed plans for decommissioning the facility, as well as a cost estimate.
The first stage of decommissioning for a nuclear power plant is to transition from operating status to a permanently shutdown condition. The licensee must certify to the NRC that it has permanently ceased operation and that it has permanently removed the fuel from the reactor. At this point, the license no longer authorizes the plant to operate or load fuel in the reactor.
Licensees typically then apply for several exemptions from NRC requirements that apply to operating reactors but are no longer appropriate after permanent shutdown because a reactor accident can no longer occur. The exemptions are implemented through license amendments that change the plants licensing basis to reflect its decommissioning status. These changes are in areas such as personnel, spent fuel management, physical and cybersecurity, emergency preparedness, and incident response. The NRC is developing new regulations to make this transition from operations to decommissioning more efficient.
The NRC allows a licensee up to 60 years to decommission a nuclear power plant. This may include extended periods of inactivity (called SAFSTOR), during which residual radioactivity is allowed to decay, making eventual cleanup easier and more efficient. A facility is said to be in DECON when active demolition and decontamination are underway. Active decommissioning of a nuclear power plant takes about 10 years on average.
NRC oversight and inspection continue throughout the entire process. Two years before cleanup is completed, the plant operator must submit a license termination plan, detailing procedures for the final steps. The NRC inspects and verifies that the site is sufficiently decontaminated before terminating the license and releasing the site for another use.
Public Involvement NEIMA required the NRC to provide a report to Congress identifying best practices for establishing and operating local community advisory boards, including lessons learned from existing boards.
These boards try to foster communication and information exchange between NRC licensees and members of the communities around decommissioning nuclear power plants.
In developing the report, the NRC hosted 11 public meetings in the vicinity of reactors and two webinars to consult with host States, local government organizations, communities within the emergency planning zone of a nuclear power reactor, existing local community advisory boards associated with decommissioning nuclear power plants, and similar external stakeholders. The public meeting locations were selected to ensure geographic diversity across the United States, with priority given to States that have a nuclear power reactor undergoing the decommissioning process.
The report, issued to Congress in July 2020, includes a discussion of the composition of local community advisory boards and best practices, such as logistical considerations, frequency of meetings, and the selection of board members.
See Appendices C, I and Q for licensees undergoing decommissioning 68 l RADIOACTIVE WASTE
Decommissioning of Materials Licenses The NRC terminates approximately 100 materials licenses each year. Most of these license terminations are routine, and the sites require little or no cleanup to meet the NRCs criteria for unrestricted access. The decommissioning program focuses on the termination of licenses for research and test reactors, uranium recovery facilities, fuel cycle facilities, and sites involving more complex decommissioning activities.
These facilities typically were manufacturing or industrial sites that processed uranium, radium, or thorium or were military bases. They are required to begin decommissioning within 2 years of ending operations, unless the NRC approves an alternative schedule. (See Figure 40. Locations of NRC-Regulated Sites Undergoing Decommissioning.)
SECY-20-0108, Status of the Decommissioning Program2020 Annual Report, dated November 30, 2020, contains additional information on the decommissioning programs of the NRC and Agreement States. More information is on the NRCs Web site (see the Web Link Index).
Figure Locations
- 40. Locations of NRC-Regulated of NRC-Regulated SitesSitesUndergoing Undergoing Decommissioning Decommissioning U 3 RI 2
2 2
F UU U U
3 Power Reactors (26)
Complex Materials (11)
F Fuel Cycle Facilities (1) = 1 unit Research and Test Reactors (3) 2 = 2 units
= 3 units Uranium Recovery (5) 3 U
Note: Alaska and Hawaii are not pictured and have no sites. The NRC is in the final stages of the licensing termination process with the reviews of the final status survey results at Zion 1 and 2, La Crosse, and Humboldt Bay, and it expects to terminate the two research reactor licenses at General Atomics by the end of 2020. Data are current as of June 2021. For the most recent information, go to the NRC facility locator page at https://www.nrc.gov/info-finder/reactors/index.html.
RADIOACTIVE WASTE l 69
6 SECURITY AND EMERGENCY PREPAREDNESS
Nuclear security and emergency preparedness and response are high priorities for the NRC. For decades, effective NRC regulation and strong partnerships with Federal, State, Tribal, and local authorities have ensured effective implementation of security programs at nuclear facilities and radioactive materials sites across the country. In fact, nuclear power plants are likely the best protected and prepared private sector facilities in the United States. However, given todays threat environment, the agency recognizes the need for continued vigilance and high levels of security (see Figure 41. Security Components).
Since 9/11, the NRC has required many enhancements to the security of nuclear power plants.
Because they are inherently robust structures, these additional security upgrades largely focus on the following:
well-trained and armed security officers
high-tech equipment and physical barriers
greater standoff distances for vehicle checks
intrusion detection and surveillance systems
tested emergency preparedness and response plans
restrictive site-access control, including background checks and fingerprinting of workers
controls to protect physical security, emergency preparedness, and safety systems from a cyber attack The NRC also coordinates and shares threat information with the Department of Defense, DHS, the FBI, intelligence agencies, and local law enforcement.
The NRC is moving toward a risk-informed, performance-based, technology-inclusive regulatory framework for emergency preparedness. As with security, the NRCs approach to emergency preparedness is graded, using a risk-informed process in which the safety requirements and criteria are matched to the risk of the facility. This approach provides an appropriate level of protection to public health and safety without creating undue regulatory burden.
In 2020, the NRC published a proposed rule for emergency preparedness for small modular reactors and other new technologies. Major provisions of the proposed rule include the following:
an alternative performance-based framework for emergency preparedness
a required hazard analysis of nearby facilities that would adversely impact emergency preparedness
a scalable approach for determining the size of the emergency planning zone
a requirement to describe ingestion response capabilities and resources FACILITY SECURITY Under NRC regulations, nuclear power plants and fuel facilities that handle highly enriched uranium must be able to defend successfully against a set of threats the agency calls the design-basis threat (DBT). The details of the DBT are not public because of security concerns, but it includes threats to a facilitys physical security, personnel security, and cybersecurity and is based on realistic assessments of the tactics, techniques, and procedures used by terrorist groups.
The NRC continually evaluates the threat environment and assesses the need to change the DBT.
The NRC verifies that licensees are complying with security requirements through its baseline inspection program. This includes force-on-force inspections designed to test a facilitys defenses against the DBT. Force-on-force inspections are held at each nuclear power plant once every 3 years, employing a highly trained mock adversary force to attack a nuclear facility.
Publicly available portions of security-related inspection reports are on the NRCs Web site (see the Web Link Index). For security reasons, inspection reports are not available for the NRC-licensed fuel facilities that handle highly enriched uranium.
72 l SECURITY AND EMERGENCY PREPAREDNESS
Figure 41. Security Components Security Components Intrusion Detection System/Fenceline Water Barriers Guard Tower Security Roving Officers Patrols Access Controls CYBERSECURITY Protecting nuclear facilities requires all of the security features to come together and work as one.
Nuclear facilities use digital and analog systems to monitor and operate various types of equipment, as well as to obtain and store vital information. Protecting these systems and the information they contain from sabotage or malicious use is called cybersecurity. All nuclear power plants licensed by the NRC must have an approved cybersecurity plan to guard against malevolent cyber acts against these facilities.
For this reason, computer systems at nuclear power plants that monitor and operate safety and security systems are isolated from external communications, including the Internet.
In 2017, the NRC began inspections of nuclear power plants full cybersecurity programs. The NRCs cybersecurity inspections provide reasonable assurance that nuclear power plant licensees adequately protect digital computers, communication systems, and networks associated with safety, security, and emergency preparedness. The experience that the NRC gained in developing the cybersecurity requirements for the current fleet of nuclear power plants provided a basis for developing cybersecurity requirements for nonreactor licensees and future advanced reactor licensees.
The NRCs cybersecurity oversight team includes technology and threat experts who evaluate and identify emerging cyber-related issues that could endanger plant systems. The team also makes recommendations to other NRC offices and programs on cybersecurity oversight issues. The NRC has established working relationships with Federal agencies such as the DHSs U.S. Cybersecurity and Infrastructure Security Agency; DOEs Office of Cybersecurity, Energy Security, and Emergency Response; and the FBI; as well as with international organizations such as the IAEA and the International Electrotechnical Commission. Such relationships are intended not only to promote information sharing but also to ensure effective coordination among Federal agencies if there were a cyber incident at a nuclear facility.
SECURITY AND EMERGENCY PREPAREDNESS l 73
MATERIALS SECURITY Radioactive materials must be secured to reduce the possibility that terrorists could use them to make a radiological dispersal device, sometimes called an RDD or dirty bomb. The NRC has established rules to require the physical protection of certain types and quantities of radioactive material. Additionally, the NRC works with the Agreement States, other Federal agencies, the IAEA, and licensees to protect radioactive materials from theft and malicious use.
In 2009, the NRC deployed the National Source Tracking System, designed to track the most risk-sensitive radioactive materials in sources. Other improvements allow U.S. Customs and Border Protection agents to promptly validate whether radioactive materials coming into the United States are properly licensed by the NRC or an Agreement State. In addition, the NRC improved and upgraded the joint NRC-DOE database tracking the movement and location of certain forms and quantities of special nuclear material.
EMERGENCY PREPAREDNESS Operators of nuclear facilities are required to develop and maintain effective emergency plans and procedures to protect the public in the unlikely event of an emergency. Emergency preparedness plans include public information, preparations for evacuation, instructions for sheltering, and other actions to protect the residents near nuclear power plants in the event of a serious incident.
The NRC conducts inspections and monitors performance indicators associated with emergency preparedness programs. At least once every 2 years, nuclear power plant operators must conduct full-scale exercises in coordination with State and local officials, under evaluation by the NRC and the Federal Emergency Management Agency. Once during every 8-year exercise cycle, these exercises include hostile-action-based scenarios. These exercises test and maintain the skills of the emergency responders and identify areas that need to be addressed. Nuclear power plant operators also conduct their own emergency response drills.
Emergency Planning Zones The NRC defines two emergency planning zones (EPZs) around each nuclear power plant. The exact size and configuration of the zones vary from plant to plant, based on local emergency response needs and capabilities, population, land characteristics, access routes, and jurisdictional boundaries. The zone boundaries are flexible, and emergency response actions may be expanded during an emergency if circumstances warrant.
For a typical EPZ around a nuclear plant, see Figure 42. Emergency Planning Zones. The two types of EPZs are the plume-exposure pathway and the ingestion pathway.
The plume-exposure pathway covers a radius of about 10 miles (16 kilometers) from the plant and is the area of greatest concern for the publics exposure to and inhalation of airborne radioactive contamination. Research has shown the most significant impacts of an accident would be expected in the immediate vicinity of a plant, and any initial protective actions, such as evacuations or sheltering in place, should be focused there.
The ingestion pathway, or food safety sampling area, extends to a radius of about 50 miles (80 kilometers) from the plant and is the area of greatest concern for the ingestion of food and liquid that may be contaminated by radioactive material.
Protective Actions During an actual nuclear power plant accident, the NRC would use radiation dose projection models to predict the nature and extent of a radiation release. The dose calculations would account for weather conditions to project the extent of radiation exposure to the nearby population. The NRC would confer with appropriate State and county governments on its assessment results.
Plant personnel would also provide assessments. State and local officials in communities within the EPZ have detailed plans to protect the public during a radiation release. These officials make their protective action decisions, including whether to order evacuations, based on these and other assessments.
74 l SECURITY AND EMERGENCY PREPAREDNESS
Figure 42. Emergency Planning Zones 50-mile food sampling area 2-mile radius 5 miles downwind 10-mile plume-exposure pathway Note: A 2-mile (3.2-kilometer) ring around the plant is identified for evacuation, along with a 5-mile (8-kilometer) zone downwind of the projected release path.
Evacuation, Sheltering, and the Use of Potassium Iodide Protective actions considered for a radiological emergency include evacuation, sheltering, and the preventive use of potassium iodide (KI) supplements to protect the thyroid from radioactive iodine, which can cause thyroid cancer.
Under certain conditions, it may be preventative to evacuate the public away from further exposure to radioactive material. However, a complete evacuation of the 10-mile (16-kilometer) zone around a nuclear power plant is not likely to be needed in most cases. The release of radioactive material from a plant during a major incident would move with the wind, not in all directions surrounding the plant. The release would also expand and become less concentrated as it traveled away from a plant. For these reasons, evacuations can be planned based on the anticipated path of the release.
Under some conditions, people may be instructed to take shelter in their homes, schools, or office buildings. Depending on the type of structure, sheltering can significantly reduce someones dose when compared to staying outside. It may be appropriate to shelter when the release of radioactive material is known to be short term or is controlled by the nuclear power plant operator. In certain situations, KI may be used as a supplement to either sheltering in place or evacuation.
The risk of an offsite radiological release is significantly lower and the types of possible accidents significantly fewer at a nuclear power reactor that has permanently ceased operations and removed fuel from the reactor vessel. Nuclear power plants that have begun decommissioning may therefore apply for exemptions from certain NRC emergency planning requirements. If the exemptions are granted, State and local agencies may apply their comprehensive emergency plansknown as all-hazards plansto respond to incidents at the plant. Additional information on emergency preparedness is available on the NRCs Web site (see Web Link Index).
SECURITY AND EMERGENCY PREPAREDNESS l 75
INCIDENT RESPONSE Quick and accurate communication among the NRC, other Federal and State agencies, and the nuclear industry is critical when responding to any incident. The NRC Headquarters Operations Center, located in the agencys headquarters in Rockville, MD, is staffed around the clock to disseminate information and coordinate response activities. The NRC also reviews intelligence reports and assesses suspicious activity to keep licensees and other agencies up to date on current threats.
The NRC works within the National Response Framework to respond to events. The framework guides the Nation in its response to complex events that might involve a variety of agencies and hazards. Under this framework, the NRC retains its independent authority and ability to respond to emergencies involving NRC-licensed facilities or materials. The NRC may request support from DHS in responding to an emergency at an NRC-licensed facility or involving NRC-licensed materials.
In response to an incident involving possible radiation releases, the NRC activates its incident response program at its Headquarters Operations Center and one of its regional Incident Response Centers. Teams of specialists at these centers evaluate event information, independently assess the potential impact on public health and safety, and evaluate possible recovery strategies.
The NRC response staff provides expert consultation, support, and assistance to State and local public safety officials and keeps the public informed of agency actions. Meanwhile, other NRC experts evaluate the effectiveness of protective actions the licensee has recommended to State and local officials. If needed, the NRC will dispatch a team of technical experts from the responsible regional office to the site. This team would assist the NRCs resident inspectors who work at the plant and provide licensee event information to the technical experts at the region and Headquarters.
EMERGENCY CLASSIFICATIONS Emergencies at nuclear facilities are classified according to the risk posed to the public. These classifications help guide first responders on the actions necessary to protect the population near the site. Nuclear power plants use these four emergency classifications:
- 1. Notification of Unusual Event: Events that indicate a potential degradation in the level of safety or indicate a security threat to the plant are in progress or have occurred. No release of radioactive material requiring offsite response or monitoring is expected unless further degradation occurs.
- 2. Alert: Events that involve an actual or potential substantial degradation in the level of plant safety or security events that involve probable life-threatening risk to site personnel or damage to site equipment are in progress or have occurred. Any releases of radioactive material are expected to be limited to a small fraction of the limits set forth by the U.S.
Environmental Protection Agency (EPA).
- 3. Site Area Emergency: Events that may result in actual or likely major failures of plant functions needed to protect the public or hostile actions that result in intentional damage or malicious acts are in progress or have occurred. Any releases of radioactive material are not expected to exceed the limits set by EPA except near the site boundary.
- 4. General Emergency: Events that involve actual or imminent substantial core damage or melting of reactor fuel with the potential for loss of containment integrity or hostile actions that result in an actual loss of physical control of the facility are in progress or have occurred.
Radioactive releases can be expected to exceed the limits set forth by EPA for more than the immediate site area.
76 l SECURITY AND EMERGENCY PREPAREDNESS
Nuclear materials and fuel cycle facility licensees use these emergency classifications:
- 1. Alert: Events that could lead to a release of radioactive materials are in progress or have occurred.
The release is not expected to require a response by an offsite response organization to protect residents near the site.
- 2. Site Area Emergency: Events that could lead to a significant release of radioactive materials are in progress or have occurred. The release could require a response by offsite response organizations to protect residents near the site.
INTERNATIONAL EMERGENCY CLASSIFICATIONS The IAEA uses the International Nuclear and Radiological Event Scale (INES) as a tool for promptly and consistently communicating to the public the safety significance of reported nuclear and radiological incidents and accidents worldwide (see Figure 43. The International Nuclear and Radiological Event Scale).
The scale can be applied to any event associated with nuclear facilities, as well as to the transport, storage, and use of radioactive material and radiation sources. Licensees are not required to classify events or provide offsite notifications using the INES. However, the NRC has a commitment to transmit to the IAEA an INES-based rating for an applicable U.S. events rated at Level 2 or above, or for events attracting international public interest.
Figure 43. The International Nuclear and Radiological Event Scale The International Nuclear and Radiological Event Scale 7 Major Accident 6 Serious Accident nt Accident with ide 5 Wider Consequences Acc Accident with 4 Local Consequences 3 Serious Incident nt ide Inc 2 Incident 1 Anomaly Below Scale/Level 0 INES events are classified on the scale at seven levels. Levels 1-3 are called incidents, and Levels 4-7 are called accidents. The scale is designed so that the severity of an event is about 10 times greater for each increase in level on the scale. Events without safety significance are called deviations and are classified as Below Scale or at Level 0.
Source: https://www.iaea.org/topics/emergency-preparedness-and-response-epr/international-nuclear-radiological-event-scale-ines SECURITY AND EMERGENCY PREPAREDNESS l 77
7 APPENDICES 79
Abbreviations ABWR Advanced Boiling-Water Reactor DHS Department of Homeland Security AC Allis Chalmers (U.S.)
ac alternating current DI&C digital instrumentation and control ACMUI Advisory Committee on the DOE Department of Energy (U.S.)
Medical Uses of Isotopes DOT Department of Transportation (U.S.)
ACRS Advisory Committee on Reactor DUKE Duke Power Company Safeguards EDO Executive Director for Operations ADAMS Agencywide Documents Access EBSO Ebasco and Management System EIA Energy Information Administration ADR alternative dispute resolution (DOE)
AEC Atomic Energy Commission (U.S.) EPA Environmental Protection Agency AEP American Electric Power Company (U.S.)
AGN Aerojet-General Nucleonics EPZ emergency planning zone AP1000 Advanced Passive 1000 Megawatt ESBWR Economic Simplified Boiling-Water (Westinghouse pressurized-water Reactor reactor) ESP early site permit AP600 Advanced Passive 600 Megawatt EVESR ESADA (Empire States (Westinghouse pressurized-water reactor) Atomic Development Associates)
APR1400 Advanced Power Reactor Vallecitos Experimental Superheat Reactor ASLB Atomic Safety and Licensing Board Exp. Date expiration date of operating license AFT accident tolerant fuel FBR fast breeder reactor B&R Burns & Roe FDA Food and Drug Administration B&W Babcock & Wilcox FEMA Federal Emergency Management BALD Baldwin Associates Agency BECH Bechtel FERC Federal Energy Regulatory BRRT Brown & Root Commission BWR boiling-water reactor FLUR Fluor Pioneer CE Combustion Engineering FOIA Freedom of Information Act CFR Code of Federal Regulations FR Federal Register COL combined license FTE full-time equivalent Comm. Op. date of commercial operation FW Foster Wheeler Con Type containment type FY fiscal year DRYAMB dry, ambient pressure G&H Gibbs & Hill DRYSUB dry, subatmospheric GA General Atomics ICECND wet, ice condenser GCR gas-cooled reactor MARK 1 wet, MARK I GE General Electric MARK 2 wet, MARK II GEH General Electric-Hitachi Nuclear MARK 3 wet, MARK III Energy CP construction permit GEIS generic environmental impact statement CP civil penalty GETR General Electric Test Reactor CP Issued date of construction permit issuance GIL Gilbert Associates CPPNM Convention on the Physical Protection of Nuclear Material GL general license CT computerized tomography GPC Georgia Power Company CVTR Carolinas Virginia Tube Reactor GW gigawatt CWE Commonwealth Edison Company GWh gigawatt-hour(s)
DANI Daniel International Gy gray DBDB Duke & Bechtel HLW high-level radioactive waste DBT design-basis threat HTG high-temperature gas DC design certification (reactor) 80 l APPENDICES
Abbreviations (continued)
HWR heavy-water reactor NSSS nuclear steam system IAEA International Atomic Energy Agency supplier and design type IMPEP Integrated Materials Performance GE 2 GE Type 2 Evaluation Program GE 3 GE Type 3 INES International Nuclear Event Scale GE 4 GE Type 4 ISFSI independent spent fuel GE 5 GE Type 5 storage installation GE 6 GE Type 6 ISR in situ recovery WEST 2LP Westinghouse Two-Loop KAIS Kaiser Engineers WEST 3LP Westinghouse Three-Loop KI potassium iodide WEST 4LP Westinghouse Four-Loop kW kilowatt(s) NSTS National Source Tracking System kWh kilowatt-hour(s) OECD Organisation for Economic LLP B&W lowered loop Co-operation and Development LLW low-level radioactive waste OIG Office of the Inspector General LM Legacy Management OL operating license LMFB liquid metal fast breeder (reactor) OL Issued date of latest full-power LOCA loss-of-coolant accident operating license LR Issued license renewal issued PG&E Pacific Gas & Electric Company LSN Licensing Support Network PHWR pressurized heavy-water reactor LTP license termination plan PRA probabilistic risk assessment LWGR light-water-cooled graphitemoderated reactor PRIS Power Reactor Information Mo-99 molybdenum-99 System MOU memorandum of understanding PSDAR post-shutdown decommissioning MOX mixed oxide activities report MW megawatt(s) PSEG Public Service Electric and Gas Company MWe megawatt(s) electric PWR pressurized-water reactor MWh megawatt-hour(s) rad radiation absorbed dose MWt megawatt(s) thermal RDD radiological dispersal device NARM naturally occurring or accelerator-produced radioactive material RIC Regulatory Information NEA Nuclear Energy Agency Conference NEIMA Nuclear Energy Innovation and RLP B&W raised loop Modernization Act ROP Reactor Oversight Process NEPA National Environmental Policy Act RSS Really Simple Syndication NINA Nuclear Innovation North America RTR research and test reactor NMMSS Nuclear Materials Management and S&L Sargent & Lundy Safeguards System S&W Stone & Webster NNSA National Nuclear Security SCF sodium-cooled fast (reactor)
Administration SHINE SHINE Medical Technologies, LLC NOV notice of violation SI Systme Internationale NPUF nonpower production and utilization (d'unités) (International facility System of Units)
NRC Nuclear Regulatory SL severity level Commission (U.S.)
SL site-specific license NSP Northern States Power Company SMR small modular reactor SR subsequent license renewal SSI Southern Services Incorporated STP South Texas Project Sv sievert APPENDICES l 81
Abbreviations (continued)
TMI-2 Three Mile Island, Unit 2 U.S. EPR U.S. [version of] Evolutionary TRIGA Training Reactor and Isotopes Pressurized-Water Reactor Production, General Atomics VBWR Vallecitos Boiling-Water TVA Tennessee Valley Authority Reactor UE&C United Engineers & Constructors WEST Westinghouse Electric UF6 uranium hexafluoride WNA World Nuclear Association U-235 uranium-235 Y-90 yttrium-90 UNSCEAR United Nations Scientific Committee on the Effects of Atomic Radiation UO2 uranium dioxide US-APWR U.S. [version of] Advanced Pressurized-Water Reactor State and Territory Abbreviations Alabama AL Maine ME Puerto Rico PR Alaska AK Maryland MD Rhode Island RI American Samoa AS Massachusetts MA South Carolina SC Arizona AZ Michigan MI South Dakota SD Arkansas AR Minnesota MN Tennessee TN California CA Mississippi MS Texas TX Colorado CO Missouri MO Utah UT Connecticut CT Montana MT Vermont VT Delaware DE Nebraska NE Virgin Islands VI District of Columbia DC Nevada NV Virginia VA Florida FL New Hampshire NH Washington WA Georgia GA New Jersey NJ West Virginia WV Guam GU New Mexico NM Wisconsin WI Hawaii HI New York NY Wyoming WY Idaho ID North Carolina NC Illinois IL North Dakota ND Indiana IN Northern Mariana Islands MP Iowa IA Ohio OH Kansas KS Oklahoma OK Kentucky KY Oregon OR Louisiana LA Pennsylvania PA 82 l APPENDICES
Quick-Reference Metric Conversion Tables SPACE AND TIME Quantity From Inch-Pound Units To Metric Units Multiply by Length mi (statute) km 1.609347 yd m *0.9144 ft (int) m *0.3048 in. cm *2.54 Area mi2 km2 2.589998 acre m2 4,046.873 yd2 m2 0.8361274 ft2 m2 *0.09290304 in2 cm2 *6.4516 Volume acre foot m3 1,233.489 yd3 m3 0.7645549 ft3 m3 0.02831685 ft3 L 28.31685 gal L 3.785412 fl oz mL 29.57353 in3 cm3 16.38706 Velocity mi/h km/h 1.609347 ft/s m/s *0.3048 Acceleration ft/s2 m/s2 *0.3048 NUCLEAR REACTION AND IONIZING RADIATION Quantity From Inch-Pound Units To Metric Units Multiply by Activity (of a radionuclide) curie (Ci) MBq *37,000.0 dpm becquerel (Bq) 0.016667 Absorbed dose rad gray (Gy) *0.01 rad cGy (centigray) *1.0 Dose equivalent rem sievert (Sv) *0.01 rem mSv *10.0 mrem mSv *0.01 mrem µSv (microsievert) *10.0 Exposure roentgen (R) C (coulomb)/kg 0.000258 (x-rays and gamma rays)
HEAT Quantity From Inch-Pound Units To Metric Units Multiply by Thermodynamic temperature °F K *K = (°F + 459.67)/1.8 Celsius temperature °F °C *°C = (°F - 32)/1.8 Linear expansion coefficient 1/°F 1/K or 1/°C *1.8 Thermal conductivity (Btu
- in.)/(ft2
- h * °F) W/(m * °C) 0.1442279 Coefficient of heat transfer Btu/(ft2
- h * °F) W/(m2 * °C) 5.678263 Heat capacity Btu/°F kJ/°C 1.899108 Specific heat capacity Btu/(lb * °F) kJ/(kg * °C) *4.1868 Entropy Btu/°F kJ/°C 1.899108 Specific entropy Btu/(lb * °F) kJ/(kg * °C) *4.1868 Specific internal energy Btu/lb kJ/kg *2.326 APPENDICES l 83
QUICK-REFERENCE METRIC CONVERSION TABLES MECHANICS Quantity From Inch-Pound Units To Metric Units Multiply by Mass (weight) ton (short) t (metric ton) *0.90718474 lb (avdp) kg *0.45359237 Moment of mass lb
- ft kg
- m 0.138255 Density ton (short)/yd3 t/m3 1.186553 lb/ft3 g/m3 16.01846 Concentration (mass) lb/gal g/L 119.8264 Momentum lb
- ft/s kg
- m/s 0.138255 Angular momentum lb
- ft2/s kg
- m2/s 0.04214011 Moment of inertia lb
- ft2 kg
- m2 0.04214011 Force kip (kilopound) kN (kilonewton) 4.448222 lbf N (newton) 4.448222 Moment of force, torque lbf
- ft N*m 1.355818 lbf
- in. N*m 0.1229848 Pressure atm (std) kPa (kilopascal) *101.325 bar kPa *100.0 lbf/in2 (formerly psi) kPa 6.894757 inHg (32 °F) kPa 3.38638 ftH2O (39.2 °F) kPa 2.98898 inH2O (60 °F) kPa 0.24884 mmHg (0 °C) kPa 0.133322 Stress kip/in2 (formerly ksi) MPa 6.894757 lbf/in2 (formerly psi) MPa 0.006894757 lbf/in2 (formerly psi) kPa 6.894757 lbf/ft2 kPa 0.04788026 Energy, work kWh MJ *3.6 calth J (joule) *4.184 Btu kJ 1.055056 ft
- lbf J 1.355818 therm (U.S.) MJ 105.4804 Power Btu/s kW 1.055056 hp (electric) kW *0.746 Btu/h W 0.2930711
- Exact conversion factors Notes: The information in this table is intended to familiarize readers with commonly used International System of Units (SI) units and provide a quick reference to aid understanding of documents containing SI units. The conversion factors listed here have not been approved as NRC guidelines for the development of licensing actions, regulations, or policy. To convert from metric units to inch-pound units, divide the metric unit by the conversion factor.
Sources: Federal Standard 376B, Preferred Metric Units for General Use by the Federal Government, and International Commission on Radiation Units and Measurements, Report 33, Radiation Quantities and Units, issued 1980.
84 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Arkansas Nuclear One, Unit 1 IV PWR-DRYAMB 2,568 12/06/1968 82 Entergy Operations, Inc. B&W LLP 833 05/21/1974 72 London, AR BECH 12/19/1974 87 (6 miles WNW of Russellville, AR) BECH DPR-51 06/20/2001 76 05000313 N/A 87 https://www.nrc.gov/info-finder/reactors/ano1.html 05/20/2034 102 Arkansas Nuclear One, Unit 2 IV PWR-DRYAMB 3,026 12/06/1972 89 Entergy Operations, Inc. CE 985 09/01/1978 94 London, AR BECH 03/26/1980 70 (6 miles WNW of Russellville, AR) BECH NPF-6 06/30/2005 82 05000368 N/A 82 https://www.nrc.gov/info-finder/reactors/ano2.html 07/17/2038 88 Beaver Valley Power Station, Unit 1 I PWR-DRYAMB 2,900 06/26/1970 90 Energy Harbor Nuclear Generation LLC/ WEST 3LP 907 07/02/1976 91 Energy Harbor Nuclear Corp. S&W 10/01/1976 99 Shippingport, PA S&W DPR-66 11/05/2009 92 (17 miles W of McCandless, PA) N/A 91 05000334 01/29/2036 101 https://www.nrc.gov/info-finder/reactors/bv1.html Beaver Valley Power Station, Unit 2 I PWR-DRYAMB 2,900 05/03/1974 90 Energy Harbor Nuclear Generation LLC/ WEST 3LP 901 08/14/1987 97 Energy Harbor Nuclear Corp. S&W 11/17/1987 90 Shippingport, PA S&W NPF-73 11/05/2009 90 (17 miles W of McCandless, PA) N/A 100 05000412 05/27/2047 93 https://www.nrc.gov/info-finder/reactors/bv2.html Braidwood Station, Unit 1 III PWR-DRYAMB 3,645 12/31/1975 93 Exelon Generation Co., LLC WEST 4LP 1,183 07/02/1987 90 Braceville, IL S&L 07/29/1988 98 (20 miles SSW of Joliet, IL) CWE NPF-72 01/27/2016 93 05000456 N/A 94 https://www.nrc.gov/info-finder/reactors/brai1.html 10/17/2046 102 Braidwood Station, Unit 2 III PWR-DRYAMB 3,645 12/31/1975 91 Exelon Generation Co., LLC WEST 4LP 1,154 05/20/1988 95 Braceville, IL S&L 10/17/1988 88 (20 miles SSW of Joliet, IL) CWE NPF-77 01/27/2016 92 05000457 N/A 100 https://www.nrc.gov/info-finder/reactors/brai2.html 12/18/2047 96 APPENDICES l 85
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Browns Ferry Nuclear Plant, Unit 1 II BWR-MARK 1 3,952 05/10/1967 94 Tennessee Valley Authority GE 4 1,256 12/20/1973 83 Limestone County, AL TVA 08/01/1974 97 (10 miles S of Athens, AL) TVA DPR-33 05/04/2006 82 05000259 N/A 99 https://www.nrc.gov/info-finder/reactors/bf1.html 12/20/2033 83 Browns Ferry Nuclear Plant, Unit 2 II BWR-MARK 1 3,952 05/10/1967 85 Tennessee Valley Authority GE 4 1,259 06/28/1974 94 Limestone County, AL TVA 03/01/1975 83 (10 miles S of Athens, AL) TVA DPR-52 05/04/2006 97 05000260 N/A 80 https://www.nrc.gov/info-finder/reactors/bf2.html 06/28/2034 91 Browns Ferry Nuclear Plant, Unit 3 II BWR-MARK 1 3,952 07/31/1968 92 Tennessee Valley Authority GE 4 1,260 07/02/1976 80 Limestone County, AL TVA 03/01/1977 93 (10 miles S of Athens, AL) TVA DPR-68 05/04/2006 76 05000296 N/A 94 https://www.nrc.gov/info-finder/reactors/bf3.html 07/02/2036 86 Brunswick Steam Electric Plant, Unit 1 II BWR-MARK 1 2,923 02/07/1970 93 Duke Energy Progress, LLC GE 4 938 09/08/1976 83 Southport, NC UE&C 03/18/1977 93 (20 miles S of Wilmington, NC) BRRT DPR-71 06/26/2006 85 05000325 N/A 92 https://www.nrc.gov/info-finder/reactors/bru1.html 09/08/2036 84 Brunswick Steam Electric Plant, Unit 2 II BWR-MARK 1 2,923 02/07/1970 81 Duke Energy Progress, LLC GE 4 932 12/27/1974 92 Southport, NC UE&C 11/03/1975 82 (20 miles S of Wilmington, NC) BRRT DPR-62 06/26/2006 93 05000324 N/A 85 https://www.nrc.gov/info-finder/reactors/bru2.html 12/27/2034 99 Byron Station, Unit 1 III PWR-DRYAMB 3,645 12/31/1975 88 Exelon Generation Co., LLC WEST 4LP 1,164 02/14/1985 97 Byron, IL S&L 09/16/1985 89 (17 miles SW of Rockford, IL) CWE NPF-37 11/19/2015 94 05000454 N/A 100 https://www.nrc.gov/info-finder/reactors/byro1.html 10/31/2044 96 Byron Station, Unit 2 III PWR-DRYAMB 3,645 12/31/1975 94 Exelon Generation Co., LLC WEST 4LP 1,136 01/30/1987 96 Byron, IL S&L 08/02/1987 89 (17 miles SW of Rockford, IL) CWE NPF-66 11/19/2015 100 05000455 N/A 95 https://www.nrc.gov/info-finder/reactors/byro2.html 11/06/2046 97 86 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Callaway Plant, Unit 1 IV PWR-DRYAMB 3,565 04/16/1976 96 Union Electric Co. WEST 4LP 1190 10/18/1984 87 Fulton, MO BECH 12/19/1984 77 (25 miles ENE of Jefferson City, MO) DANI NPF-30 03/06/2015 100 05000483 N/A 86 https://www.nrc.gov/info-finder/reactors/call.html 10/18/2044 74 Calvert Cliffs Nuclear Power Plant, Unit 1 I PWR-DRYAMB 2,737 07/07/1969 97 Calvert Cliffs Nuclear Power Plant, LLC CE 866 07/31/1974 89 Exelon Generation Co., LLC BECH 05/08/1975 97 Lusby, MD BECH DPR-53 03/23/2000 92 (40 miles S of Annapolis, MD) N/A 100 05000317 07/31/2034 97 https://www.nrc.gov/info-finder/reactors/calv1.html Calvert Cliffs Nuclear Power Plant, Unit 2 I PWR-DRYAMB 2,737 07/07/1969 86 Calvert Cliffs Nuclear Power Plant, LLC CE 842 08/13/1976 95 Exelon Generation Co., LLC BECH 04/01/1977 91 Lusby, MD BECH DPR-69 03/23/2000 100 (40 miles S of Annapolis, MD) N/A 92 05000318 08/13/2036 104 https://www.nrc.gov/info-finder/reactors/calv2.html Catawba Nuclear Station, Unit 1 II PWR-ICECND 3,469 08/07/1975 88 Duke Energy Carolinas, LLC WEST 4LP 1,160 01/17/1985 97 York, SC DUKE 06/29/1985 90 (18 miles S of Charlotte, NC) DUKE NPF-35 12/05/2003 93 05000413 N/A 100 https://www.nrc.gov/info-finder/reactors/cat1.html 12/05/2043 91 Catawba Nuclear Station, Unit 2 II PWR-ICECND 3,411 08/07/1975 86 Duke Energy Carolinas, LLC WEST 4LP 1,150 05/15/1986 88 York, SC DUKE 08/19/1986 96 (18 miles S of Charlotte, NC) DUKE NPF-52 12/05/2003 91 05000414 N/A 92 https://www.nrc.gov/info-finder/reactors/cat2.html 12/05/2043 100 Clinton Power Station, Unit 1 III BWR-MARK 3 3,473 02/24/1976 87 Exelon Generation Co., LLC GE 6 1,065 04/17/1987 89 Clinton, IL S&L 11/24/1987 84 (23 miles SSE of Bloomington, IL) BALD NPF-62 N/A 88 05000461 N/A 87 https://www.nrc.gov/info-finder/reactors/clin.html 09/29/2026 101 APPENDICES l 87
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Columbia Generating Station IV BWR-MARK 2 3,544 03/19/1973 78 Energy Northwest GE 5 1,163 04/13/1984 92 Hanford Reservation in Benton County, WA B&R 12/13/1984 77 (15 miles NNW of Richland , WA) BECH NPF-21 05/22/2012 96 05000397 N/A 88 https://www.nrc.gov/info-finder/reactors/wash2.html 12/20/2043 92 Comanche Peak Nuclear Power Plant, Unit 1 IV PWR-DRYAMB 3,612 12/19/1974 100 Comanche Peak Power Co., LLC. WEST 4LP 1,205 04/17/1990 92 Vistra Operating Co., LLC G&H 08/13/1990 91 Glen Rose, TX BRRT NPF-87 N/A 100 (40 miles SW of Fort Worth, TX) N/A 89 05000445 02/08/2030 92 https://www.nrc.gov/info-finder/reactors/cp1.html Comanche Peak Nuclear Power Plant, Unit 2 IV PWR-DRYAMB 3,612 12/19/1974 88 Comanche Peak Power Co., LLC. WEST 4LP 1,195 04/06/1993 100 Vistra Operating Co., LLC BECH 08/03/1993 68 Glen Rose, TX BRRT NPF-89 N/A 93 (40 miles SW of Fort Worth, TX) N/A 94 05000446 02/02/2033 92 https://www.nrc.gov/info-finder/reactors/cp2.html Cooper Nuclear Station IV BWR-MARK 1 2,419 06/04/1968 97 Nebraska Public Power District GE 4 770 01/18/1974 84 Brownville, NE B&R 07/01/1974 99 (23 miles S of Nebraska City, NE) B&R DPR-46 11/29/2010 81 05000298 N/A 100 https://www.nrc.gov/info-finder/reactors/cns.html 01/18/2034 92 Davis-Besse Nuclear Power Station, Unit 1 III PWR-DRYAMB 2,817 03/24/1971 97 Energy Harbor Nuclear Generation LLC B&W RLP 894 04/22/1977 79 Energy Harbor Nuclear Corp. BECH 07/31/1978 97 Oak Harbor, OH B&W NPF-3 12/08/2015 93 (21 miles ESE of Toledo, OH) N/A 98 05000346 04/22/2037 92 https://www.nrc.gov/info-finder/reactors/davi.html Diablo Canyon Nuclear Power Plant, Unit 1 IV PWR-DRYAMB 3,411 4/23/1968 87 Pacific Gas & Electric Co. WEST 4LP 1,122 11/02/1984 98 Avila Beach, CA PG&E 05/07/1985 81 (12 miles WSW of San Luis Obispo, CA) PG&E DPR-80 Withdrawn 98 05000275 N/A 89 https://www.nrc.gov/info-finder/reactors/diab1.html 11/02/2024 90 88 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Diablo Canyon Nuclear Power Plant, Unit 2 IV PWR-DRYAMB 3,411 12/09/1970 95 Pacific Gas & Electric Co. WEST 4LP 1,118 08/26/1985 88 Avila Beach, CA PG&E 03/13/1986 95 (12 miles WSW of San Luis Obispo, CA) PG&E DPR-82 Withdrawn 87 05000323 N/A 75 https://www.nrc.gov/info-finder/reactors/diab2.html 08/26/2025 75 Donald C. Cook Nuclear Plant, Unit 1 III PWR-ICECND 3,304 03/25/1969 78 Indiana Michigan Power Co. WEST 4LP 1,009 10/25/1974 82 Bridgman, MI AEP 08/28/1975 72 (13 miles S of Benton Harbor, MI) AEP DPR-58 08/30/2005 100 05000315 N/A 79 https://www.nrc.gov/info-finder/reactors/cook1.html 10/25/2034 94 Donald C. Cook Nuclear Plant, Unit 2 III PWR-ICECND 3,468 03/25/1969 79 Indiana Michigan Power Co. WEST 4LP 1,168 12/23/1977 71 Bridgman, MI AEP 07/01/1978 104 (13 miles S of Benton Harbor, MI) AEP DPR-74 08/30/2005 79 05000316 N/A 84 https://www.nrc.gov/info-finder/reactors/cook2.html 12/23/2037 97 Dresden Nuclear Power Station, Unit 2 III BWR-MARK 1 2,957 01/10/1966 83 Exelon Generation Co., LLC GE 3 902 02/20/1991A 91 Morris (Grundy County), IL S&L 06/09/1970 84 (25 miles SW of Joliet, IL) UE&C DPR-19 10/28/2004 99 05000237 N/A 89 https://www.nrc.gov/info-finder/reactors/dres2.html 12/22/2029 101 Dresden Nuclear Power Station, Unit 3 III BWR-MARK 1 2,957 10/14/1966 89 Exelon Generation Co., LLC GE 3 895 01/12/1971 84 Morris (Grundy County), IL S&L 11/16/1971 91 (25 miles SW of Joliet, IL) UE&C DPR-25 10/28/2004 94 05000249 N/A 99 https://www.nrc.gov/info-finder/reactors/dres3.html 01/12/2031 96 Edwin I. Hatch Nuclear Plant, Unit 1 II BWR-MARK 1 2,804 09/30/1969 101 Southern Nuclear Operating Co., Inc. GE 4 876 10/13/1974 93 Baxley, GA BECH 12/31/1975 97 (20 miles S of Vidalia, GA) GPC DPR-57 01/15/2002 91 05000321 N/A 98 https://www.nrc.gov/info-finder/reactors/hat1.html 08/06/2034 83 A: The Atomic Energy Commission (AEC) issued a provisional operating license (OL) on 12/22/1969, allowing commercial operation.
The NRC issued a full-term OL on 02/20/1991.
APPENDICES l 89
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Edwin I. Hatch Nuclear Plant, Unit 2 II BWR-MARK 1 2,804 12/27/1972 91 Southern Nuclear Operating Co., Inc. GE 4 883 06/13/1978 101 Baxley, GA BECH 09/05/1979 95 (20 miles S of Vidalia, GA) GPC NPF-5 01/15/2002 95 05000366 N/A 82 https://www.nrc.gov/info-finder/reactors/hat2.html 06/13/2038 97 Fermi, Unit 2 III BWR-MARK 1 3,486 09/26/1972 69 DTE Electric Company GE 4 1,141 03/20/1985 86 Newport, MI S&L 01/23/1988 82 (25 miles NE of Toledo, OH) DANI NPF-43 12/15/2016 75 05000341 N/A 99 https://www.nrc.gov/info-finder/reactors/ferm2.html 03/20/2045 61 Grand Gulf Nuclear Station, Unit 1 IV BWR-MARK 3 4,408 09/04/1974 93 Entergy Operations, Inc. GE 6 1,401 11/01/1984 47 Port Gibson, MS BECH 07/01/1985 58 (20 miles S of Vicksburg, MS) BECH NPF-29 12/01/2016 57 05000416 N/A 88 https://www.nrc.gov/info-finder/reactors/gg1.html 11/01/2044 53 H.B. Robinson Steam Electric Plant, Unit 2 II PWR-DRYAMB 2,339 04/13/1967 85 Duke Energy Progress, LLC WEST 3LP 759 07/31/1970 95 Hartsville, SC EBSO 03/07/1971 88 (26 miles NW of Florence, SC) EBSO DPR-23 04/19/2004 79 05000261 N/A 94 https://www.nrc.gov/info-finder/reactors/rob2.html 07/31/2030 92 Hope Creek Generating Station, Unit 1 I BWR-MARK 1 3,902 11/04/1974 83 PSEG Nuclear, LLC GE 4 1,172 07/25/1986 85 Hancocks Bridge, NJ BECH 12/20/1986 94 (18 miles SE of Wilmington, DE) BECH NPF-57 07/20/2011 90 05000354 N/A 84 https://www.nrc.gov/info-finder/reactors/hope.html 04/11/2046 103 James A. FitzPatrick Nuclear Power Plant I BWR-MARK 1 2,536 05/20/1970 96 Exelon Generation Co., LLC GE 4 848 10/17/1974 76 Scriba, NY S&W 07/28/1975 80 (6 miles NE of Oswego, NY) S&W DPR-59 09/08/2008 89 05000333 N/A 100 https://www.nrc.gov/info-finder/reactors/fitz.html 10/17/2034 89 Joseph M. Farley Nuclear Plant, Unit 1 II PWR-DRYAMB 2,775 08/16/1972 86 Southern Nuclear Operating Co., Inc. WEST 3LP 874 06/25/1977 86 Columbia, AL SSI 12/01/1977 100 (18 miles E of Dothan, AL) DANI NPF-2 05/12/2005 84 05000348 N/A 91 https://www.nrc.gov/info-finder/reactors/far1.html 06/25/2037 102 90 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Joseph M. Farley Nuclear Plant, Unit 2 II PWR-DRYAMB 2,775 08/16/1972 98 Southern Nuclear Operating Co., Inc. WEST 3LP 877 03/31/1981 90 Columbia, AL SSI 07/30/1981 91 (18 miles E of Dothan, AL) BECH NPF-8 05/12/2005 99 05000364 N/A 92 https://www.nrc.gov/info-finder/reactors/far2.html 03/31/2041 91 LaSalle County Station, Unit 1 III BWR-MARK 2 3,546 09/10/1973 99 Exelon Generation Co., LLC GE 5 1,131 04/17/1982 89 Marseilles, IL S&L 01/01/1984 96 (11 miles SE of Ottawa, IL) CWE NPF-11 10/19/2016 92 05000373 N/A 99 https://www.nrc.gov/info-finder/reactors/lasa1.html 04/17/2042 96 LaSalle County Station, Unit 2 III BWR-MARK 2 3,546 09/10/1973 83 Exelon Generation Co., LLC GE 5 1,134 12/16/1983 95 Marseilles, IL S&L 10/19/1984 88 (11 miles SE of Ottawa, IL) CWE NPF-18 10/19/2016 98 05000374 N/A 92 https://www.nrc.gov/info-finder/reactors/lasa2.html 12/16/2043 102 Limerick Generating Station, Unit 1 I BWR-MARK 2 3,515 06/19/1974 100 Exelon Generation Co., LLC GE 4 1,120 08/08/1985 93 Limerick, PA BECH 02/01/1986 100 (21 miles NW of Philadelphia, PA) BECH NPF-39 10/20/2014 92 05000352 N/A 99 https://www.nrc.gov/info-finder/reactors/lim1.html 10/26/2044 93 Limerick Generating Station, Unit 2 I BWR-MARK 2 3,515 06/19/1974 89 Exelon Generation Co., LLC GE 4 1,122 08/25/1989 101 Limerick, PA BECH 01/08/1990 86 (21 miles NW of Philadelphia, PA) BECH NPF-85 10/20/2014 99 05000353 N/A 91 https://www.nrc.gov/info-finder/reactors/lim2.html 06/22/2049 104 McGuire Nuclear Station, Unit 1 II PWR-ICECND 3,411 02/23/1973 95 Duke Energy Carolinas, LLC WEST 4LP 1,158 05/27/1981 89 Huntersville, NC DUKE 12/01/1981 90 (17 miles N of Charlotte, NC) DUKE NPF-9 12/05/2003 100 05000369 N/A 90 https://www.nrc.gov/info-finder/reactors/mcg1.html 06/12/2041 93 APPENDICES l 91
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date McGuire Nuclear Station, Unit 2 II PWR-ICECND 3,411 02/23/1973 87 Duke Energy Carolinas, LLC WEST 4LP 1,158 05/27/1983 97 Huntersville, NC DUKE 03/01/1984 86 (17 miles N of Charlotte, NC) DUKE NPF-17 12/05/2003 92 05000370 N/A 100 https://www.nrc.gov/info-finder/reactors/mcg2.html 03/03/2043 95 Millstone Power Station, Unit 2 I PWR-DRYAMB 2,700 12/11/1970 85 Dominion Energy Nuclear Connecticut, Inc. CE 853 09/26/1975 93 Waterford, CT BECH 12/26/1975 85 (3.2 miles WSW of New London, CT) BECH DPR-65 11/28/2005 82 05000336 N/A 97 https://www.nrc.gov/info-finder/reactors/mill2.html 07/31/2035 89 Millstone Power Station, Unit 3 I PWR-DRYSUB 3,650 08/09/1974 97 Dominion Energy Nuclear Connecticut, Inc. WEST 4LP 1,220 01/31/1986 83 Waterford, CT S&W 04/23/1986 89 (3.2 miles WSW of New London, CT) S&W NPF-49 11/28/2005 100 05000423 N/A 89 https://www.nrc.gov/info-finder/reactors/mill3.html 11/25/2045 84 Monticello Nuclear Generating Plant, Unit 1 III BWR-MARK 1 2,004 06/19/1967 78 Northern States Power Company-Minnesota GE 3 617 01/09/1981B 93 Monticello, MN BECH 06/30/1971 86 (30 miles NW of Minneapolis, MN) BECH DPR-22 11/08/2006 99 05000263 N/A 88 https://www.nrc.gov/info-finder/reactors/mont.html 09/08/2030 103 Nine Mile Point Nuclear Station, Unit 1 I BWR-MARK 1 1,850 04/12/1965 88 Nine Mile Point Nuclear Station, LLC GE 2 621 12/26/1974C 96 Scriba, NY NIAG 12/01/1969 87 (6 miles NE of Oswego, NY) S&W DPR-63 10/31/2006 99 05000220 N/A 85 https://www.nrc.gov/info-finder/reactors/nmp1.html 08/22/2029 100 Nine Mile Point Nuclear Station, Unit 2 I BWR-MARK 2 3,988 06/24/1974 100 Nine Mile Point Nuclear Station, LLC GE 5 1,292 07/02/1987 92 Scriba, NY S&W 03/11/1988 101 (6 miles NE of Oswego, NY) S&W NPF-69 10/31/2006 90 05000410 N/A 99 https://www.nrc.gov/info-finder/reactors/nmp2.html 10/31/2046 90 B: The AEC issued a provisional OL on 09/08/1970, allowing commercial operation. The NRC issued a full-term OL on 01/09/1981.
92 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date North Anna Power Station, Unit 1 II PWR-DRYSUB 2,940 02/19/1971 91 Virginia Electric & Power Co. WEST 3LP 948 04/01/1978 89 Mineral (Louisa County), VA S&W 06/06/1978 99 (40 miles NW of Richmond, VA) S&W NPF-4 03/20/2003 90 05000338 N/A 93 https://www.nrc.gov/info-finder/reactors/na1.html 04/01/2038 102 North Anna Power Station, Unit 2 II PWR-DRYSUB 2,940 02/19/1971 99 Virginia Electric & Power Co. WEST 3LP 944 08/21/1980 87 Mineral (Louisa County), VA S&W 12/14/1980 89 (40 miles NW of Richmond, VA) S&W NPF-7 03/20/2003 99 05000339 N/A 88 https://www.nrc.gov/info-finder/reactors/na2.html 08/21/2040 88 Oconee Nuclear Station, Unit 1 II PWR-DRYAMB 2,610 11/06/1967 96 Duke Energy Carolinas, LLC B&W LLP 847 02/06/1973 83 Seneca, SC DBDB 07/15/1973 95 (30 miles W of Greenville, SC) DUKE DPR-38 05/23/2000 90 05000269 N/A 100 https://www.nrc.gov/info-finder/reactors/oco1.html 02/06/2033 92 Oconee Nuclear Station, Unit 2 II PWR-DRYAMB 2,610 11/06/1967 89 Duke Energy Carolinas, LLC B&W LLP 848 10/06/1973 98 Seneca, SC DBDB 09/09/1974 88 (30 miles W of Greenville, SC) DUKE DPR-47 05/23/2000 100 05000270 N/A 90 https://www.nrc.gov/info-finder/reactors/oco2.html 10/06/2033 103 Oconee Nuclear Station, Unit 3 II PWR-DRYAMB 2,610 11/06/1967 97 Duke Energy Carolinas, LLC B&W LLP 859 07/19/1974 91 Seneca, SC DBDB 12/16/1974 97 (30 miles W of Greenville, SC) DUKE DPR-55 05/23/2000 92 05000287 N/A 100 https://www.nrc.gov/info-finder/reactors/oco3.html 07/19/2034 93 Palisades Nuclear Plant III PWR-DRYAMB 2,565.4 03/14/1967 89 Entergy Nuclear Operations, Inc. CE 769 02/21/1991D 99 Covert, MI BECH 12/31/1971 86 (5 miles S of South Haven, MI) BECH DPR-20 01/17/2007 77 05000255 N/A 97 https://www.nrc.gov/info-finder/reactors/pali.html 03/24/2031 89 C: The AEC issued a provisional OL on 08/22/1969, allowing commercial operation. The NRC issued a full-term OL on 12/26/1974.
D:The AEC issued a provisional OL on 03/24/1971, allowing commercial operation. The NRC issued a full-term OL on 02/21/1991.
APPENDICES l 93
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Palo Verde Nuclear Generating Station, Unit 1 IV PWR-DRYAMB 3,990 05/25/1976 94 Arizona Public Service Company CE 80-2L 1,311 06/01/1985 83 Wintersburg, AZ BECH 01/28/1986 85 (50 miles W of Phoenix, AZ) BECH NPF-41 04/21/2011 97 05000528 N/A 90 https://www.nrc.gov/info-finder/reactors/palo1.html 06/01/2045 85 Palo Verde Nuclear Generating Station, Unit 2 IV PWR-DRYAMB 3,990 05/25/1976 85 Arizona Public Service Company CE 80-2L 1,314 04/24/1986 95 Wintersburg, AZ BECH 09/19/1986 86 (50 miles W of Phoenix, AZ) BECH NPF-51 04/21/2011 82 05000529 N/A 98 https://www.nrc.gov/info-finder/reactors/palo2.html 04/24/2046 91 Palo Verde Nuclear Generating Station, Unit 3 IV PWR-DRYAMB 3,990 05/25/1976 85 Arizona Public Service Company CE 80-2L 1,312 11/25/1987 85 Wintersburg, AZ BECH 01/08/1988 92 (50 miles W of Phoenix, AZ) BECH NPF-74 04/21/2011 90 05000530 N/A 87 https://www.nrc.gov/info-finder/reactors/palo3.html 11/25/2047 98 Peach Bottom Atomic Power Station, Unit 2 I BWR-MARK 1 4,016 01/31/1968 99 Exelon Generation Co., LLC GE 4 1,265 10/25/1973 96 Delta, PA BECH 07/05/1974 92 (17.9 miles S of Lancaster, PA) BECH DPR-44 05/07/2003 94 05000277 03/05/2020 100 https://www.nrc.gov/info-finder/reactors/pb2.html 08/08/2053 92 Peach Bottom Atomic Power Station, Unit 3 I BWR-MARK 1 4,016 01/31/1968 75 Exelon Generation Co., LLC GE 4 1,285 07/02/1974 95 Delta, PA BECH 12/23/1974 86 (17.9 miles S of Lancaster, PA) BECH DPR-56 05/07/2003 94 05000278 03/05/2020 93 https://www.nrc.gov/info-finder/reactors/pb3.html 07/02/2054 103 Perry Nuclear Power Plant, Unit 1 III BWR-MARK 3 3,758 05/03/1977 83 Energy Harbor Nuclear Generation LLC/ GE 6 1,240 11/13/1986 91 Energy Harbor Nuclear Corp. GIL 11/18/1987 85 Perry, OH KAIS NPF-58 N/A 99 (35 miles NE of Cleveland, OH) N/A 83 05000440 03/18/2026 101 https://www.nrc.gov/info-finder/reactors/perr1.html 94 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Point Beach Nuclear Plant, Unit 1 III PWR-DRYAMB 1,800 07/19/1967 92 NextEra Energy Point Beach, LLC WEST 2LP 598 10/05/1970 86 Two Rivers, WI BECH 12/21/1970 86 (13 miles NNW of Manitowoc, WI) BECH DPR-24 12/22/2005 99 05000266 N/A 91 https://www.nrc.gov/info-finder/reactors/poin1.html 10/05/2030 92 Point Beach Nuclear Plant, Unit 2 III PWR-DRYAMB 1,800 07/25/1968 86 NextEra Energy Point Beach, LLC WEST 2LP 603 03/08/1973E 94 Two Rivers, WI BECH 10/01/1972 85 (13 miles NNW of Manitowoc, WI) BECH DPR-27 12/22/2005 94 05000301 N/A 99 https://www.nrc.gov/info-finder/reactors/poin2.html 03/08/2033 93 Prairie Island Nuclear Generating Plant, Unit 1 III PWR-DRYAMB 1,677 06/25/1968 77 Northern States Power Co.Minnesota WEST 2LP 521 04/05/1974F 81 Welch, MN FLUR 12/16/1973 88 (28 miles SE of Minneapolis, MN) NSP DPR-42 06/27/2011 89 05000282 N/A 99 https://www.nrc.gov/info-finder/reactors/prai1.html 08/09/2033 95 Prairie Island Nuclear Generating Plant, Unit 2 III PWR-DRYAMB 1,677 06/25/1968 65 Northern States Power Co.Minnesota WEST 2LP 519 10/29/1974 78 Welch, MN FLUR 12/21/1974 80 (28 miles SE of Minneapolis, MN) NSP DPR-60 06/27/2011 100 05000306 N/A 91 https://www.nrc.gov/info-finder/reactors/prai2.html 10/29/2034 104 Quad Cities Nuclear Power Station, Unit 1 III BWR-MARK 1 2,957 02/15/1967 83 Exelon Generation Co., LLC GE 3 908 12/14/1972 92 Cordova, IL S&L 02/18/1973 85 (20 miles NE of Moline, IL) UE&C DPR-29 10/28/2004 99 05000254 N/A 91 https://www.nrc.gov/info-finder/reactors/quad1.html 12/14/2032 101 Quad Cities Nuclear Power Station, Unit 2 III BWR-MARK 1 2,957 02/15/1967 95 Exelon Generation Co., LLC GE 3 911 12/14/1972 85 Cordova, IL S&L 03/10/1973 89 (20 miles NE of Moline, IL) UE&C DPR-30 10/28/2004 92 05000265 N/A 99 https://www.nrc.gov/info-finder/reactors/quad2.html 12/14/2032 95 E: The AEC issued a provisional OL on 11/18/1971. The NRC issued a full-term OL on 03/08/1973.
F: The AEC issued a provisional OL on 08/09/1973. The NRC issued a full-term OL on 04/05/1974.
APPENDICES l 95
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date R.E. Ginna Nuclear Power Plant I PWR-DRYAMB 1,775 04/25/1966 89 R.E. Ginna Nuclear Power Plant, LLC WEST 2LP 581 09/19/1969 94 Ontario, NY GIL 07/01/1970 87 (20 miles NE of Rochester, NY) BECH DPR-18 05/19/2004 93 05000244 N/A 99 https://www.nrc.gov/info-finder/reactors/ginn.html 09/18/2029 85 River Bend Station, Unit 1 IV BWR-MARK 3 3,091 03/25/1977 76 Entergy Operations, Inc. GE 6 968 11/20/1985 78 St. Francisville, LA S&W 06/16/1986 77 (24 miles NNW of Baton Rouge, LA) S&W NPF-47 12/20/2018 82 05000458 N/A 76 https://www.nrc.gov/info-finder/reactors/rbs1.html 08/29/2045 94 St. Lucie Plant, Unit 1 II PWR-DRYAMB 3,020 07/01/1970 83 Florida Power & Light Co. CE 981 03/01/1976 73 Jensen Beach, FL EBSO 12/21/1976 90 (10 miles SE of Ft. Pierce, FL) EBSO DPR-67 10/02/2003 91 05000335 N/A 70 https://www.nrc.gov/info-finder/reactors/stl1.html 03/01/2036 101 St. Lucie Plant, Unit 2 II PWR-DRYAMB 3,020 05/02/1977 77 Florida Power & Light Co. CE 987 04/06/1983 92 Jensen Beach, FL EBSO 08/08/1983 84 (10 miles SE of Ft. Pierce, FL) EBSO NPF-16 10/02/2003 87 05000389 N/A 100 https://www.nrc.gov/info-finder/reactors/stl2.html 04/06/2043 93 Salem Nuclear Generating Station, Unit 1 I PWR-DRYAMB 3,459 09/25/1968 95 PSEG Nuclear, LLC WEST 4LP 1,153 12/01/1976 68 Hancocks Bridge, NJ PSEG 06/30/1977 90 (18 miles SE of Wilmington, DE) UE&C DPR-70 06/30/2011 100 05000272 N/A 79 https://www.nrc.gov/info-finder/reactors/salm1.html 08/13/2036 71 Salem Nuclear Generating Station, Unit 2 I PWR-DRYAMB 3,459 09/25/1968 85 PSEG Nuclear, LLC WEST 4LP 1,142 05/20/1981 85 Hancocks Bridge, NJ PSEG 10/13/1981 85 (18 miles SE of Wilmington, DE) UE&C DPR-75 06/30/2011 87 05000311 N/A 99 https://www.nrc.gov/info-finder/reactors/salm2.html 04/18/2040 90 96 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Seabrook Station, Unit 1 I PWR-DRYAMB 3,648 07/07/1976 87 NextEra Energy Seabrook, LLC WEST 4LP 1,250 03/15/1990 99 Seabrook, NH UE&C 08/19/1990 92 (13 miles S of Portsmouth, NH) UE&C NPF-86 03/12/2019 92 05000443 N/A 100 https://www.nrc.gov/info-finder/reactors/seab1.html 03/15/2050 90 Sequoyah Nuclear Plant, Unit 1 II PWR-ICECND 3,455 05/27/1970 87 Tennessee Valley Authority WEST 4LP 1,152 09/17/1980 71 Soddy-Daisy, TN TVA 07/01/1981 88 (16 miles NE of Chattanooga, TN) TVA DPR-77 09/24/2015 89 05000327 N/A 82 https://www.nrc.gov/info-finder/reactors/seq1.html 09/17/2040 97 Sequoyah Nuclear Plant, Unit 2 II PWR-ICECND 3,455 05/27/1970 73 Tennessee Valley Authority WEST 4LP 1,126 09/15/1981 90 Soddy-Daisy, TN TVA 06/01/1982 83 (16 miles NE of Chattanooga, TN) TVA DPR-79 09/28/2015 88 05000328 N/A 99 https://www.nrc.gov/info-finder/reactors/seq2.html 09/15/2041 94 Shearon Harris Nuclear Power Plant, Unit 1 II PWR-DRYAMB 2,948 01/27/1978 87 Duke Energy Progress, Inc. WEST 3LP 964 10/24/1986 90 New Hill, NC EBSO 05/02/1987 99 (20 miles SW of Raleigh, NC) DANI NPF-63 12/17/2008 89 05000400 N/A 89 https://www.nrc.gov/info-finder/reactors/har1.html 10/24/2046 98 South Texas Project, Unit 1 IV PWR-DRYAMB 3,853 12/22/1975 78 STP Nuclear Operating Co. WEST 4LP 1,280 03/22/1988 95 Bay City, TX BECH 08/25/1988 85 (90 miles SW of Houston, TX) EBSO NPF-76 09/28/2017 89 05000498 N/A 100 https://www.nrc.gov/info-finder/reactors/stp1.html 08/20/2047 93 South Texas Project, Unit 2 IV PWR-DRYAMB 3,853 12/22/1975 85 STP Nuclear Operating Co. WEST 4LP 1,280 03/28/1989 88 Bay City, TX BECH 06/19/1989 97 (90 miles SW of Houston, TX) EBSO NPF-80 09/28/2017 90 05000499 N/A 91 https://www.nrc.gov/info-finder/reactors/stp2.html 12/15/2048 103 APPENDICES l 97
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Surry Power Station, Unit 1 II PWR-DRYSUB 2,587 06/25/1968 76 Virginia Electric and Power Co. WEST 3LP 838 05/25/1972 96 Surry, VA S&W 12/22/1972 101 (17 miles NW of Newport News, VA) S&W DPR-32 03/20/2003 87 05000280 05/04/2021 88 https://www.nrc.gov/info-finder/reactors/sur1.html 05/25/2052 103 Surry Power Station, Unit 2 II PWR-DRYSUB 2,587 06/25/1968 82 Virginia Electric and Power Co. WEST 3LP 838 01/29/1973 101 Surry, VA S&W 05/01/1973 93 (17 miles NW of Newport News, VA) S&W DPR-37 03/20/2003 88 05000281 05/04/2021 100 https://www.nrc.gov/info-finder/reactors/sur2.html 01/29/2053 92 Susquehanna Steam Electric Station, Unit 1 I BWR-MARK 2 3,952 11/03/1973 76 Susquehanna Nuclear, LLC GE 4 1,247 07/17/1982 77 Salem Township (Luzerne County), PA BECH 06/08/1983 97 (70 miles NE of Harrisburg, PA) BECH NPF-14 11/24/2009 86 05000387 N/A 99 https://www.nrc.gov/info-finder/reactors/susq1.html 07/17/2042 85 Susquehanna Steam Electric Station, Unit 2 I BWR-MARK 2 3,952 11/03/1973 82 Susquehanna Nuclear, LLC GE 4 1,247 03/23/1984 93 Salem Township (Luzerne County), PA BECH 02/12/1985 86 (70 miles NE of Harrisburg, PA) BECH NPF-22 11/24/2009 99 05000388 N/A 89 https://www.nrc.gov/info-finder/reactors/susq2.html 03/23/2044 97 Turkey Point Nuclear Generating, Unit 3 II PWR-DRYAMB 2,644 04/27/1967 78 Florida Power & Light Co. WEST 3LP 837 07/19/1972 93 Homestead, FL BECH 12/14/1972 80 (20 miles S of Miami, FL) BECH DPR-31 06/06/2002 89 05000250 12/04/2019 99 https://www.nrc.gov/info-finder/reactors/tp3.html 07/19/2052 89 Turkey Point Nuclear Generating, Unit 4 II PWR-DRYAMB 2,644 04/27/1967 106 Florida Power & Light Co. WEST 3LP 861 04/10/1973 99 Homestead, FL BECH 09/07/1973 98 (20 miles S of Miami, FL) BECH DPR-41 06/06/2002 100 05000251 12/04/2019 91 https://www.nrc.gov/info-finder/reactors/tp4.html 04/10/2053 80 Virgil C. Summer Nuclear Station, Unit 1 II PWR-DRYAMB 2,900 03/21/1973 79 Dominion Energy South Carolina, Inc. WEST 3LP 971 11/12/1982 96 Jenkinsville, SC GIL 01/01/1984 77 (26 miles NW of Columbia, SC) DANI NPF-12 04/23/2004 85 05000395 N/A 95 https://www.nrc.gov/info-finder/reactors/sum.html 08/06/2042 91 98 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors (continued)
CP Issued 2015-Plant Name, Unit Number Con Type Licensed OL Issued 2020*
Licensee NSSS MWt Comm. Op Capacity Location NRC Architect Engineer MWe LR Issued Factor Docket Number Region Constructor License SR Issued (Percent)
NRC Web page Address Number Exp. Date Vogtle Electric Generating Plant, Unit 1 II PWR-DRYAMB 3,625.6 06/28/1974 91 Southern Nuclear Operating Co., Inc. WEST 4LP 1,150 03/16/1987 101 Waynesboro, GA SBEC 06/01/1987 93 (26 miles SE of Augusta, GA) GPC NPF-68 06/03/2009 93 05000424 N/A 100 https://www.nrc.gov/info-finder/reactors/vog1.html 01/16/2047 95 Vogtle Electric Generating Plant, Unit 2 II PWR-DRYAMB 3,625.6 06/28/1974 100 Southern Nuclear Operating Co., Inc. WEST 4LP 1,152 03/31/1989 94 Waynesboro, GA SBEC 05/20/1989 96 (26 miles SE of Augusta, GA) GPC NPF-81 06/03/2009 100 05000425 N/A 92 https://www.nrc.gov/info-finder/reactors/vog2.html 02/09/2049 92 Waterford Steam Electric Station, Unit 3 IV PWR-DRYAMB 3,716 11/14/1974 80 Entergy Operations, Inc. COMB CE 1,165 03/16/1985 96 Killona, LA EBSO 09/24/1985 80 (25 miles W of New Orleans, LA) EBSO NPF-38 12/27/2018 100 05000382 N/A 74 https://www.nrc.gov/info-finder/reactors/wat3.html 12/18/2044 88 Watts Bar Nuclear Plant, Unit 1 II PWR-ICECND 3,459 01/23/1973 76 Tennessee Valley Authority WEST 4LP 1,123 02/07/1996 85 Spring City, TN TVA 05/27/1996 77 (60 miles SW of Knoxville, TN) TVA NPF-90 N/A 87 05000390 N/A 86 https://www.nrc.gov/info-finder/reactors/wb1.html 11/09/2035 92 Watts Bar Nuclear Plant, Unit 2 II PWR-ICECND 3,411 01/24/1973 Tennessee Valley Authority WEST 4LP 1,122 10/22/2015 26 Spring City, TN TVA 10/19/2016 45 (60 miles SW of Knoxville, TN) TVA NPF-96 N/A 95 05000391 N/A 88 https://www.nrc.gov/info-finder/reactors/wb2.html 10/22/2055 86 Wolf Creek Generating Station, Unit 1 IV PWR-DRYAMB 3,565 05/17/1977 78 Wolf Creek Nuclear Operating Corp. WEST 4LP 06/04/1985G 74 Burlington (Coffey County), KS BECH 09/03/1985 96 (28 miles SE of Emporia, KS) DANI NPF-42 11/20/2008 86 05000482 N/A 87 https://www.nrc.gov/info-finder/reactors/wc.html 03/11/2045 98 G: The original OL (NPF-32) was issued on 03/11/1985. The license was superseded by OL (NPF-42), issued on 06/04/1985.
APPENDICES l 99
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors Under Active Construction or Deferred Policy
CP Issued Plant Name, Unit Number Con Type Licensed OL Issued Licensee NSSS MWt Comm. Op.
Location Architect Engineer MWe LR Issued Docket Number NRC Constructor License
NRC Web page Address Region Number Exp. Date Bellefonte Nuclear Power Station, Unit 1** II PWR-DRYAMB 3,763 12/24/1974 Tennessee Valley Authority B&W 205 (6 miles NE of Scottsboro, AL) TVA 05000438 TVA https://www.nrc.gov/reactors/new-reactors/bellefonte-constr-permits.html Bellefonte Nuclear Power Station, Unit 2** II PWR-DRYAMB 3,763 12/24/1974 Tennessee Valley Authority B&W 205 (6 miles NE of Scottsboro, AL) TVA 05000439 TVA https://www.nrc.gov/reactors/new-reactors/bellefonte-constr-permits.html Enrico Fermi Nuclear Plant, Unit 3 III ESBWR 4,500 DTE Electric Company GEH NPF-95 05/01/2015 Newport, MI (25 miles NE of Toledo, OH)
05200033
https://www.nrc.gov/reactors/new-reactors/col-holder/ferm3.html North Anna Power Station, Unit 3 II BWR 4,500 Dominion Virginia Power ESBWR NPF-103 06/02/2017 Mineral (Louisa County), VA GEH
(40 miles NW of Richmond, VA)
05200017
https://www.nrc.gov/reactors/new-reactors/col-holder/na3.html
Turkey Point Nuclear Generating, Unit 6 II PWR 3,400 Florida Power and Light AP1000 NPF-104 04/12/2018 Homestead, FL WEST 2LP
(20 miles S of Miami, FL)
05200040
https://www.nrc.gov/reactors/new-reactors/col-holder/tp6.html Turkey Point Nuclear Generating, Unit 7 II PWR 3,400 Florida Power and Light AP1000 NPF-105 04/12/2018 Homestead, FL WEST 2LP
(20 miles S of Miami, FL)
05200041
https://www.nrc.gov/reactors/new-reactors/col-holder/tp7.html Vogtle Electric Generating Plant, Unit 3 II PWR 3,400 Southern Nuclear Operating Co., Inc. AP1000 NPF-91 02/10/2012 Waynesboro (Burke County), GA WEST 2LP
(26 miles SE of Augusta, GA)
05200025
https://www.nrc.gov/reactors/new-reactors/col-holder/vog3.html 100 l APPENDICES
APPENDIX A Commercial Nuclear Power Reactors Operating Reactors Under Active Construction or Deferred Policy (continued)
CP Issued Plant Name, Unit Number Con Type Licensed OL Issued Licensee NSSS MWt Comm. Op.
Location Architect Engineer MWe LR Issued Docket Number NRC Constructor License
NRC Web page Address Region Number Exp. Date Vogtle Electric Generating Plant, Unit 4 II PWR 3,400 Southern Nuclear Operating Co., Inc. AP1000 NPF-92 02/10/2012 Waynesboro (Burke County), GA WEST 2LP
(26 miles SE of Augusta, GA)
05200026
https://www.nrc.gov/reactors/new-reactors/col-holder/vog4.html William States Lee III Nuclear Station, Unit 3A II PWR 3,400 Duke Energy Carolinas AP1000 NPF-101 12/19/2016 Cherokee County, SC WEST 2LP (2 miles SE of Gafney, SC)
05200018 https://www.nrc.gov/reactors/new-reactors/col-holder/lee1.html William States Lee III Nuclear Station, Unit 4A II PWR 3,400 Duke Energy Carolinas AP1000 NPF-102 12/19/2016 Cherokee County, SC WEST 2LP (2 miles SE of Gafney, SC)
05200019 https://www.nrc.gov/reactors/new-reactors/col-holder/lee2.html A: In September 2017, Duke Energy announced cancellation of William States Lee nuclear power plant, Units 3 and 4.
- Average capacity factor is listed in year order starting with 2014.
- Bellefonte Units 1 and 2 are under the Commission Policy Statement on Deferred Plants (52 FR 38077; October 14, 1987).
Note: Plant names and data are as identified on the license as of August 2021; the next printed update will be in September 2022.
Source: NRC, with some data compiled from the U.S. Department of Energy's (DOE's) Energy Information Administration (EIA).
APPENDICES l 101
APPENDIX B New Nuclear Power Plant Licensing Applications Docket Submittal Existing Date Applicant Number Type Date Design Site State Plant? Accepted Status Combined License (Construction and Operating)
Nuclear Innovation 05200012 & COL 09/20/07 ABWR South Texas TX Yes 11/29/07 COL North America, LLC 05200013 9/20/2007 Project, Units 3 terminated (NINA) and 4 07/12/2018 Tennessee Valley 05200014 & COL 10/30/07 AP1000 Bellefonte, AL No 01/18/08 Withdrawn-Authority (TVA) 05200015 Units 3 and 4 12/02/2016 Dominion Virginia 05200017 COL 11/27/07 ESBWR North Anna, VA Yes 01/28/08 COL Issued Power Unit 3 06/02/2017 Duke Energy 05200018 & COL 12/13/07 AP1000 Lee Nuclear SC No 02/25/08 COL Issued Carolinas 05200019 Station, 12/19/2016 Units 3 and 4 Progress 05200022 & COL 02/19/08 AP1000 Shearon Harris, NC Yes 04/17/08 Suspended-Energy 05200023 Units 2 and 3 05/02/2013 Southern Nuclear 05200025 & COL 03/28/08 AP1000 Vogtle, GA Yes 05/30/08 COL Issued Operating Co., Inc. 05200026 Units 3 and 4 02/10/2012 AmerenUE 05200037 COL 07/24/08 U.S. EPR Callaway, Unit 2 MO Yes 12/12/08 Withdrawn-10/29/2015 DTE Electric 05200033 COL 09/18/08 ESBWR Fermi, Unit 3 MI Yes 11/25/08 COL Issued Company 05/01/2015 Luminant 05200034 & COL 09/19/08 US-APWR Comanche Peak, TX Yes 12/02/08 Suspended-Generation Co. 05200035 Units 3 and 4 03/31/2014 Entergy 05200036 COL 09/25/08 ESBWR River Bend, LA Yes 12/04/08 Withdrawn-Unit 3 06/14/2016 PPL Bell Bend 05200039 COL 10/10/08 U.S. EPR Bell Bend PA Yes 12/19/08 Withdrawn-(1 Unit) 09/22/2016 Florida Power 05200040 & COL 06/30/09 AP1000 Turkey Point, FL Yes 09/04/09 COL Issued and Light 05200041 Units 6 and 7 04/12/2018 Duke Energy Florida 05200029 & COL 07/30/08 AP1000 Levy County, FL No 10/06/08 COL 05200030 Units 1 and 2 Terminated 04/26/2018 Oklo Power LLC 05200049 COL 03/11/20 Aurora Idaho National ID No 06/05/20 Scheduled Laboratory 102 l APPENDICES
APPENDIX B New Nuclear Power Plant Licensing Applications (continued)
Docket Submittal Existing Date Applicant Number Type Date Design Site State Plant? Accepted Status Design Certification AREVA NP 05200020 DC 12/11/07 U.S. EPR N/A N/A N/A 02/25/08 Suspended-03/27/2015 Mitsubishi Heavy 05200021 DC 12/31/07 US-APWR N/A N/A N/A 02/29/08 Suspended-Industries 03/03/2020 Korea Electric 05200046 DC 12/23/14 APR 1400 N/A N/A N/A 03/04/15 Certified Power Company and 09/19/2019 Korea Hydro and Nuclear Power Toshiba 05200044 DC 10/27/10 ABWR N/A N/A N/A 12/14/10 Withdrawn-Corporation 12/30/2016 GE-Hitachi 05200045 DC 12/7/10 ABWR N/A N/A N/A 02/14/11 Scheduled Nuclear Energy NuScale Power LLC 05200048 DC 01/6/17 NuScale N/A N/A N/A 03/23/17 Scheduled Early Site Permit PSEG Power, LLC, 05200043 ESP 05/25/10 Not yet PSEG Site NJ Yes 08/04/10 Issued and PSEG Nuclear, announced 05/06/2016 LLC (PSEG)
Tennessee Valley 05200047 ESP 05/12/16 Not yet Clinch River Site TN No 12/30/16 Issued Authority announced 12/19/2019 Notes: Withdrawal was requested for Calvert Cliffs, Grand Gulf, Nine Mile Point, Victoria County, Bellefonte, and Callaway combined license and early site permit (ESP). In September 2017, Duke Energy announced cancellation of William States Lee nuclear power plant Units 3 and 4.
Data are current as of June 2021 the next printed update will be in September 2022. NRC-abbreviated reactor names listed.
APPENDICES l 103
APPENDIX C Commercial Nuclear Power Reactors Undergoing Decommissioning and Permanently Shut Down Formerly Licensed To Operate Unit Reactor NSSS OL Issued Decommissioning Location Type Vendor Shut Down Alternative Selected Docket Number MWt OL Terminated Current License Status MWe Closure Date Est.
Big Rock Point BWR GE 05/01/1964 DECON Charlevoix, MI 240 08/29/1997 DECON Completed 05000155 01/08/2007 Crystal River 3 PWR B&W LLP 12/03/1976 SAFSTOR Crystal River, FL 2,609 02/20/2013 SAFSTOR in Progress 05000302
2074 Dresden 1 BWR GE 09/28/1959 SAFSTOR Morris, IL 700 10/31/1978 SAFSTOR 05000010
2036 Duane Arnold BWR-MARK 1 GE 4 06/22/1970 SAFSTOR Palo, IA 1,912 08/10/2020 SAFSTOR in Progress 05000331
2040 Fermi 1 SCF CE 05/10/1963 SAFSTOR Newport, MI 200 09/22/1972 SAFSTOR 05000016
2032 Fort Calhoun 1 PWR-DRYAMB CE 08/09/1973 SAFSTOR Ft. Calhoun, NE 1,500 10/24/2016 SAFSTOR in Progress 05000285
2076 Fort St. Vrain HTG GA 12/21/1973 DECON Platteville, CO 842 08/18/1989 DECON Completed 05000267 08/08/1997
GE EVESR Experimental GE 11/12/1963 SAFSTOR Sunol, CA Superheat Reactor 02/01/1967 SAFSTOR 05000183 12.5 04/15/1970
2025 GE VBWR (Vallecitos) BWR GE 08/31/1957 SAFSTOR Sunol, CA 50 12/09/1963 SAFSTOR 05000018
2025 Haddam Neck PWR WEST 12/27/1974 DECON Meriden, CT 1,825 12/05/1996 DECON Completed 05000213 11/26/2007 104 l APPENDICES
APPENDIX C Commercial Nuclear Power Reactors Undergoing Decommissioning and Permanently Shut Down Formerly Licensed To Operate (continued)
Unit Reactor NSSS OL Issued Decommissioning Location Type Vendor Shut Down Alternative Selected Docket Number MWt OL Terminated Current License Status MWe Closure Date Est.
Humboldt Bay 3 BWR GE 08/28/1962 DECON Eureka, CA 200 07/02/1976 DECON in Progress 05000133
2019 Indian Point 1 PWR B&W 03/26/1962 DECON Buchanan, NY 615 10/31/1974 DECON in Progress 05000003
2036 Indian Point 2 PWR WEST 09/28/1973 DECON Buchanan, NY 3,216 04/30/2020 DECON in Progress 05000247
Indian Point 3 PWR WEST 12/12/1975 DECON Buchanan, NY 3,216 04/30/2021 DECON in Progress 05000286 Kewaunee PWR WEST 2LP 12/21/1973 SAFSTOR Carlton, WI 1,772 05/07/2013 SAFSTOR 05000305
2073 LaCrosse BWR AC 07/03/1967 DECON Genoa, WI 165 04/30/1987 DECON in Progress 05000409
2020 Maine Yankee PWR CE 06/29/1973 DECON Wiscasset, ME 2,700 12/06/1996 DECON Completed 05000309 09/30/2005 Millstone 1 BWR GE 10/31/1970 SAFSTOR Waterford, CT 2,011 07/21/1998 SAFSTOR 05000245 12/31/2056 Oyster Creek BWR GE 04/09/1969 SAFSTOR Forked River, NJ 1,930 09/17/2018 SAFSTOR 05000219
2078 Pathfinder BWR AC 03/12/1964 DECON Sioux Falls, SD 190 09/16/1967 DECON Completed 05000130 07/27/2007 APPENDICES l 105
APPENDIX C Commercial Nuclear Power Reactors Undergoing Decommissioning and Permanently Shut Down Formerly Licensed To Operate (continued)
Unit Reactor NSSS OL Issued Decommissioning Location Type Vendor Shut Down Alternative Selected Docket Number MWt OL Terminated Current License Status MWe Closure Date Est.
Peach Bottom 1 HTG GA 01/24/1966 SAFSTOR Delta, PA 115 10/31/1974 SAFSTOR 05000171 12/31/2034 Pilgrim BWR-MARK 1 GE 3 06/08/1972 SAFSTOR Plymouth, MA 2,028 05/31/2019 SAFSTOR 05000293
2064 Rancho Seco PWR B&W 08/16/1974 DECON Herald, CA 2,772 06/07/1989 DECON Completed 05000312 09/25/2009 San Onofre 1* PWR WEST 03/27/1967 DECON San Clemente, CA 1,347 11/30/1992 SAFSTOR 05000206
2030 San Onofre 2 PWR CE CE 02/16/1982 DECON San Clemente, CA 3,438 06/12/2013 DECON in Progress 05000361
2030 San Onofre 3 PWR CE CE 11/15/1982 DECON San Clemente, CA 3,438 06/12/2013 DECON in Progress 05000362
2030 Savannah, N.S. PWR B&W 08/1965 DECON Baltimore, MD 74 11/1970 DECON in Progress 05000238
2031 Saxton PWR WEST 11/15/1961 DECON Saxton, PA 23.5 05/01/1972 DECON Completed 05000146 11/07/2005 Shoreham BWR GE 04/21/1989 DECON Wading River, NY 2,436 06/28/1989 DECON Completed 05000322 04/11/1995 Three Mile Island 1 PWR WEST 04/19/1974 SAFSTOR Middletown, PA 2,568 09/20/2019 05000289
2079 106 l APPENDICES
APPENDIX C Commercial Nuclear Power Reactors Undergoing Decommissioning and Permanently Shut Down Formerly Licensed To Operate (continued)
Unit Reactor NSSS OL Issued Decommissioning Location Type Vendor Shut Down Alternative Selected Docket Number MWt OL Terminated Current License Status MWe Closure Date Est.
Three Mile Island 2** PWR B&W 02/08/1978 DECON Middletown, PA 2,770 03/28/1979 DECON in Progress 05000320 12/31/2036 Trojan PWR WEST 11/21/1975 DECON Rainier, OR 3,411 11/09/1992 DECON Completed 05000344 05/23/2005 Yankee Rowe PWR WEST 12/24/1963 DECON Rowe, MA 600 10/01/1991 DECON Completed 05000029 08/10/2007 Vermont Yankee BWR-Mark 1 GE 4 03/21/1972 DECON Vernon, VT 1,912 12/29/2014 DECON in Progress 05000271
2030 Zion 1 PWR WEST 10/19/1973 DECON Zion, IL 3,250 02/21/1997 DECON in Progress 05000295
2021 Zion 2 PWR WEST 11/14/1973 DECON Zion, IL 3,250 09/19/1996 DECON in Progress 05000304
2021
- Site has been dismantled and decontaminated with the exception of the reactor vessel, which is in long-term storage.
- Three Mile Island Unit 2 has been placed in a post-defueling monitored storage mode until Unit 1 permanently ceases operation, at which time both units are planned to be decommissioned.
Notes: GE Bonus, Hallam, and Piqua decommissioned reactor sites are part of the DOE nuclear legacy. For more information, visit DOE's Legacy Management Web site at https://energy.gov/lm/sites/lm-sites. CVTR, Elk River, and Shippingport decommissioned reactor sites were either decommissioned before the formation of the NRC or were not licensed by the NRC. N.S. = Nuclear Ship See the Glossary for definitions of decommissioning alternatives (DECON, SAFSTOR).
Source: DOE, Integrated Database for 1990, U.S. Spent Fuel and Radioactive Waste, Inventories, Projections, and Characteristics (DOE/RW-0006, Rev. 6), and NRC, Nuclear Power Plants in the World, Edition 6.
Data are current as of August 2021. The next printed update will be in September 2022.
APPENDICES l 107
APPENDIX D Canceled Commercial Nuclear Power Reactors 10 CFR Part 50Domestic Licensing of Production and Utilization Facilities Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Allens Creek 1 BWR 1982 Houston Lighting & Power Company 1,150 Under CP Review 4 miles NW of Wallis, TX 05000466 Allens Creek 2 BWR 1976 Houston Lighting & Power Company 1,150 Under CP Review 4 miles NW of Wallis, TX 05000467 Atlantic 1 & 2 PWR 1978 Public Service Electric & Gas Company 1,150 Under CP Review Floating plants off the coast of NJ 05000477 & 478 Bailly 1 BWR 1981 Northern Indiana Public Service Company 645 With CP 12 miles NNE of Gary, IN 05000367 Barton 1 & 2 BWR 1977 Alabama Power & Light 1,159 Under CP Review 15 miles SE of Clanton, AL 05000524 & 525 Barton 3 & 4 BWR 1975 Alabama Power & Light 1,159 Under CP Review 15 miles SE of Clanton, AL 05000526 & 527 Black Fox 1 & 2 BWR 1982 Public Service Company of Oklahoma 1,150 Under CP Review 3.5 miles S of Inola, OK 05000556 & 557 Blue Hills 1 & 2 PWR 1978 Gulf States Utilities Company 918 Under CP Review SW tip of Toledo Bend Reservoir, TX 05000510 & 511 Cherokee 1 PWR 1983 Duke Power Company 1,280 With CP 6 miles SSW of Blacksburg, SC 05000491 Cherokee 2 & 3 PWR 1982 Duke Power Company 1,280 With CP 6 miles SSW of Blacksburg, SC 05000492 & 493 108 l APPENDICES
APPENDIX D Canceled Commercial Nuclear Power Reactors 10 CFR Part 50Domestic Licensing of Production and Utilization Facilities (continued)
Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Clinch River LMFB 1983 Project Management Corp., DOE, TVA 350 Under CP Review 23 miles W of Knoxville, in Oak Ridge, TN 05000537 Clinton 2 BWR 1983 Illinois Power Company 933 With CP 6 miles E of Clinton, IL 05000462 Davis-Besse 2 & 3 PWR 1981 Toledo Edison Company 906 Under CP Review 21 miles ESE of Toledo, OH 05000500 & 501 Douglas Point 1 & 2 BWR 1977 Potomac Electric Power Company 1,146 Under CP Review Charles County, MD 05000448 & 449 Erie 1 & 2 PWR 1980 Ohio Edison Company 1,260 Under CP Review Berlin, OH 05000580 & 581 Forked River 1 PWR 1980 Jersey Central Power & Light Company 1,070 With CP 2 miles S of Forked River, NJ 05000363 Fort Calhoun 2 PWR 1977 Omaha Public Power District 1,136 Under CP Review 19 miles N of Omaha, NE 05000548 Fulton 1 & 2 HTG 1975 Philadelphia Electric Company 1,160 Under CP Review 17 miles S of Lancaster, PA 05000463 & 464 Grand Gulf 2 BWR 1990 Entergy Nuclear Operations, Inc. 1,250 With CP 20 miles SW of Vicksburg, MS 05000417 Greene County PWR 1980 Power Authority of the State of NY 1,191 Under CP Review 20 miles N of Kingston, NY 05000549 Greenwood 2 & 3 PWR 1980 Detroit Edison Company 1,200 Under CP Review Greenwood Township, MI 05000452 & 453 APPENDICES l 109
APPENDIX D Canceled Commercial Nuclear Power Reactors 10 CFR Part 50Domestic Licensing of Production and Utilization Facilities (continued)
Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Hartsville A1 & A2 BWR 1984 Tennessee Valley Authority 1,233 With CP 5 miles SE of Hartsville, TN 05000518 & 519 Hartsville B1 & B2 BWR 1982 Tennessee Valley Authority 1,233 With CP 5 miles SE of Hartsville, TN 05000520 & 521 Haven 1 (formerly Koshkonong) PWR 1980 Wisconsin Electric Power Company 900 Under CP Review 4.2 miles SSW of Fort Atkinson, WI 05000502 Haven 2 (formerly Koshkonong) PWR 1978 Wisconsin Electric Power Company 900 Under CP Review 4.2 miles SSW of Fort Atkinson, WI 05000503 Hope Creek 2 BWR 1981 Public Service Electric & Gas Company 1,067 With CP 18 miles SE of Wilmington, DE 05000355 Jamesport 1 & 2 PWR 1980 Long Island Lighting Company 1,150 With CP 65 miles E of New York City, NY 05000516 & 517 Marble Hill 1 & 2 PWR 1985 Public Service of Indiana 1,130 With CP 6 miles NE of New Washington, IN 05000546 & 547 Midland 1 PWR 1986 Consumers Power Company 492 With CP S of City of Midland, MI 05000329 Midland 2 PWR 1986 Consumers Power Company 818 With CP S of City of Midland, MI 05000330 Montague 1 & 2 BWR 1980 Northeast Nuclear Energy Company 1,150 Under CP Review 1.2 miles SSE of Turners Falls, MA 05000496 & 497 New England 1 & 2 PWR 1979 New England Power Company 1,194 Under CP Review 8.5 miles E of Westerly, RI 05000568 & 569 110 l APPENDICES
APPENDIX D Canceled Commercial Nuclear Power Reactors 10 CFR Part 50Domestic Licensing of Production and Utilization Facilities (continued)
Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number New Haven 1 & 2 PWR 1980 New York State Electric & Gas Corporation 1,250 Under CP Review 3 miles NW of New Haven, NY 05000596 & 597 North Anna 3 PWR 1982 Virginia Electric & Power Company 907 With CP 40 miles NW of Richmond, VA 05000404 North Anna 4 PWR 1980 Virginia Electric & Power Company 907 With CP 40 miles NW of Richmond, VA 05000405 North Coast 1 PWR 1978 Puerto Rico Water Resources Authority 583 Under CP Review 4.7 miles ESE of Salinas, PR 05000376 Palo Verde 4 & 5 PWR 1979 Arizona Public Service Company 1,270 Under CP Review 36 miles W of Phoenix, AZ 05000592 & 593 Pebble Springs 1 & 2 PWR 1982 Portland General Electric Company 1,260 Under CP Review 55 miles WSW of Richland, WA, near Arlington, OR 05000514 & 515 Perkins 1, 2, & 3 PWR 1982 Duke Power Company 1,280 Under CP Review 10 miles N of Salisbury, NC 05000488, 489 & 490 Perry 2 BWR 1994 Cleveland Electric Illuminating Co. 1,205 Under CP Review 35 miles NE of Cleveland, OH 05000441 Phipps Bend 1 & 2 BWR 1982 Tennessee Valley Authority 1,220 With CP 15 miles SW of Kingsport, TN 05000553 & 554 Pilgrim 2 PWR 1981 Boston Edison Company 1,180 Under CP Review 4 miles SE of Plymouth, MA 05000471 Pilgrim 3 PWR 1974 Boston Edison Company 1,180 Under CP Review 4 miles SE of Plymouth, MA 05000472 APPENDICES l 111
APPENDIX D Canceled Commercial Nuclear Power Reactors 10 CFR Part 50Domestic Licensing of Production and Utilization Facilities (continued)
Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Quanicassee 1 & 2 PWR 1974 Consumers Power Company 1,150 Under CP Review 6 miles E of Essexville, MI 05000475 & 476 River Bend 2 BWR 1984 Gulf States Utilities Company 934 With CP 24 miles NNW of Baton Rouge, LA 05000459 Seabrook 2 PWR 1988 Public Service Co. of New Hampshire 1,198 With CP 13 miles S of Portsmouth, NH 05000444 Shearon Harris 2 PWR 1983 Carolina Power & Light Company 900 With CP 20 miles SW of Raleigh, NC 05000401 Shearon Harris 3 & 4 PWR 1981 Carolina Power & Light Company 900 With CP 20 miles SW of Raleigh, NC 05000402 & 403 Skagit/Hanford 1 & 2 PWR 1983 Puget Sound Power & Light Company 1,277 Under CP Review 23 miles SE of Bellingham, WA 05000522 & 523 Sterling PWR 1980 Rochester Gas & Electric Corporation 1,150 With CP 50 miles E of Rochester, NY 05000485 Summit 1 & 2 HTG 1975 Delmarva Power & Light Company 1,200 Under CP Review 15 miles SSW of Wilmington, DE 05000450 & 451 Sundesert 1 & 2 PWR 1978 San Diego Gas & Electric Company 974 Under CP Review 16 miles SW of Blythe, CA 05000582 & 583 Surry 3 & 4 PWR 1977 Virginia Electric & Power Company 882 With CP 17 miles NW of Newport News, VA 05000434 & 435 Tyrone 1 PWR 1981 Northern States Power Company 1,150 Under CP Review 8 miles NE of Durond, WI 05000484 112 l APPENDICES
APPENDIX D Canceled Commercial Nuclear Power Reactors 10 CFR Part 50Domestic Licensing of Production and Utilization Facilities (continued)
Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Tyrone 2 PWR 1974 Northern States Power Company 1,150 With CP 8 miles NE of Durond, WI 05000487 Vogtle 3 & 4 PWR 1974 Georgia Power Company 1,113 With CP 26 miles SE of Augusta, GA 050000426 & 427 Washington Nuclear 1 (WPPSS) PWR 1995 Energy Northwest 1,266 With CP 12 miles NE of Richland, WA 05000460 Washington Nuclear 3 (WPPSS) PWR 1995 Energy Northwest 1,242 With CP 12 miles NE of Richland, WA 05000508 Washington Nuclear 4 (WPPSS) PWR 1982 Energy Northwest 1,218 With CP 12 miles NE of Richland, WA 05000513 Washington Nuclear 5 (WPPSS) PWR 1982 Energy Northwest 1,242 With CP 12 miles NE of Richland, WA 05000509 Yellow Creek 1 & 2 BWR 1984 Tennessee Valley Authority 1,285 With CP 15 miles E of Corinth, MS 05000566 & 567 Zimmer 1 BWR 1984 Cincinnati Gas & Electric Company 810 With CP 25 miles SE of Cincinnati, OH 05000358 APPENDICES l 113
APPENDIX D Canceled Commercial Nuclear Power Reactors 10 CFR Part 52Licensing, Certification, and Approvals for Nuclear Power Plants Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Bellefonte 3 & 4 AP1000 December 2, 2016 Tennessee Valley Authority 3,763 With COL Review Scottsboro, Jackson County, AL 05200014 & 05200015 Bell Bend U.S. EPR September 22, 2016 Bell Bend, LLC 1,600 With COL Review Luzerne County, PA 5200039 Callaway 2 U.S. EPR October 29, 2015 Union Electric Company (Ameren UE) 1,600 With COL Review Fulton, Callaway County, MO 05200037 Calvert Cliffs 3 U.S. EPR July 17, 2015 UniStar Nuclear Operating Services, LLC 1,594 With COL Review Near Lusby in Calvert County, MD 05200016 Grand Gulf 3 ESBWR September 15, 2015 Entergy Operations, Inc. 1,594 With COL Review Near Port Gibson in Claiborne County, MS 05200024 Levy 1 and 2 AP1000 April 26, 2018 Duke Energy Florida 1,100 With COL 2 miles NE of Inglis, FL 05200029 & 05200030 Nine Mile Point 3 ESBWR March 31, 2014 UniStar Nuclear Operating Services, LLC 1,594 With COL Review 25 miles SE of Cincinnati, OH 05000038 River Bend 3 ESBWR June 14, 2016 Entergy Operations, Inc. 1,594 With COL Review St. Francisville, LA 05200036 South Texas Project 3 and 4 ABWR July 12, 2018 Nuclear Innovation North America, LLC 3,926 With COL Bay City, TX 05200012 & 05200013 V.C. Summer, Units 2 and 3 AP100 March 6, 2019 South Carolina Electric & Gas Co. 1,100 With COL Jenkinsville, SC 05200027 & 05200028 Victoria County Station 1 and 2 ESBWR July 20, 2010 Exelon Nuclear Texas Holdings, LLC 4,500 With COL Review Near Victoria City in Victoria County, TX 05200031 & 05200032 Notes: Cancellation is defined as public announcement of cancellation or written notification to the NRC. Only NRC-docketed applications are included. Status is the status of the application at the time of cancellation. NRC actions are still pending. In September 2017, Duke Energy announced plans to cancel William States Lee III, Units 3 and 4.
Data are current as of August 2021; the next printed update will be in September 2022. NRC-abbreviated reactor names listed.
Source: DOE/EIA, Commercial Nuclear Power 1991, DOE/EIA-0438, Appendix E, and the NRC.
114 l APPENDICES
APPENDIX E Commercial Nuclear Power Reactors by Parent Company Utility NRC-Abbreviated Reactor Unit Name AmerenUE Callaway*
www.ameren.com Arizona Public Service Company Palo Verde 1, 2, and 3*
www.aps.com Dominion Generation Millstone 2 and 3 www.dom.com North Anna 1 and 2 Surry 1 and 2 Summer 1 DTE Electric Company Fermi 2 www.dteenergy.com Duke Energy Brunswick 1 and 2 www.duke-energy.com Catawba 1 and 2 Harris 1 McGuire 1 and 2 Oconee 1, 2, and 3 Robinson 2 Energy Harbor Corp. Beaver Valley 1 and 2 www.energyharbor.com Davis-Besse 1 Perry 1 Energy Northwest Columbia www.energy-northwest.com Entergy Corporation, Inc. Arkansas Nuclear One 1 and 2 www.entergy-nuclear.com Grand Gulf 1 (formerly Entergy Nuclear Operations, Inc.) Indian Point 2 and 3 Palisades River Bend 1 Waterford 3 Exelon Corporation, LLC Braidwood 1 and 2 www.exeloncorp.com Byron 1 and 2 Calvert Cliffs 1 and 2 Clinton 1 Dresden 2 and 3 FitzPatrick Ginna LaSalle 1 and 2 Limerick 1 and 2 Nine Mile Point 1 and 2 Peach Bottom 2 and 3 Quad Cities 1 and 2 APPENDICES l 115
APPENDIX E Commercial Nuclear Power Reactors by Parent Company (continued)
Utility NRC-Abbreviated Reactor Unit Name Indiana Michigan Power Company Cook 1 and 2 www.indianamichiganpower.com Nebraska Public Power District Cooper www.nppd.com NextEra Energy Inc. with principal subsidiaries Point Beach 1 and 2 Florida Power and Light Co. and Seabrook 1 NextEra Energy Resources, LLC St. Lucie 1 and 2 www.fplgroup.com or nexteraenergy.com Turkey Point 3 and 4 Northern States Power Company Monticello 1 Minnesota doing business as Xcel Energy Prairie Island 1 and 2 www.xcelenergy.com Pacific Gas and Electric Company Diablo Canyon 1 and 2*
www.pge.com PSEG Nuclear, LLC Hope Creek 1 www.pseg.com Salem 1 and 2 Southern Nuclear Operating Company Farley 1 and 2 www.southerncompany.com Hatch 1 and 2 Vogtle 1 and 2 STP Nuclear Operating Company South Texas Project 1 and 2*
www.stpnoc.com Talen Energy Corp. Susquehanna 1 and 2 www.talenenergy.com Tennessee Valley Authority Browns Ferry 1, 2, and 3 www.tva.gov Sequoyah 1 and 2 Watts Bar 1 and 2 Vistra Energy Comanche Peak 1 and 2*
www.vistraenergy.com Wolf Creek Nuclear Operating Corporation Wolf Creek 1*
www.wolfcreeknuclear.com
- These plants have a joint program called the Strategic Teaming and Resource Sharing group. They share resources for refueling out-ages and develop some shared licensing applications.
Note: Data are current as of August 2021; the next printed update will be in September 2022.
116 l APPENDICES
APPENDIX F Commercial Nuclear Power Reactor Operating Licenses Issued by Year 1969 Dresden 2* Cooper McGuire 1 Hope Creek 1 Ginna* D.C. Cook 1 Salem 2 Millstone 3 Nine Mile Point 1* (1974) FitzPatrick Sequoyah 2 Palo Verde 2 Hatch 1 1982 LaSalle 1 Perry 1 1970 Point Beach 1* Oconee 3 Summer 1 1987 Beaver Valley 2 Robinson 2 Peach Bottom 3 Susquehanna 1 Braidwood 1 1971 Dresden 3 Prairie Island 1 1983 McGuire 2 Byron 2 Monticello 1* (1970) Prairie Island 2 St. Lucie 2 Clinton 1 1972 Palisades* (1971) 1975 Millstone 2 1984 Callaway Harris 1(1986)
Quad Cities 1 1976 Beaver Valley 1 Columbia Nine Mile Point 2 Quad Cities 2 Browns Ferry 3 Diablo Canyon 1 Palo Verde 3 Surry 1 Brunswick 1 Grand Gulf 1 Vogtle 1 Turkey Point 3 Calvert Cliffs 2 LaSalle 2 (1983) 1988 Braidwood 2 1973 Browns Ferry 1 Salem 1 Susquehanna 2 South Texas Project 1 Oconee 1 St. Lucie 1 1985 Byron 1 Oconee 2 1977 Davis-Besse 1 Catawba 1 1989 Limerick 2 Peach Bottom 2 D.C. Cook 2 Diablo Canyon 2 South Texas Project 2 Point Beach 2* Farley 1 Fermi 2 Vogtle 2 Surry 2 1978 Arkansas Nuclear 2 Limerick 1 1990 Comanche Peak 1 Turkey Point 4 Hatch 2 Palo Verde 1 Seabrook 1 1974 Arkansas Nuclear 1 North Anna 1 River Bend 1 1993 Comanche Peak 2 Browns Ferry 2 1980 North Anna 2 Waterford 3 1996 Watts Bar 1 Brunswick 2 Sequoyah 1 Wolf Creek 1 2015 Watts Bar 2 Calvert Cliffs 1 1981 Farley 2 1986 Catawba 2
- The Atomic Energy Commission issued a provisional operating license allowing commercial operations.
Notes: This list is limited to reactors licensed to operate. Year is based on the date the initial full-power operating license was issued.
NRC-abbreviated reactor names are listed. Data are current as of August 2021; the next printed update will be in September 2022.
APPENDIX G Commercial Nuclear Power Reactor Operating Licenses Expiration by Year, 2024-2055 2024 Diablo Canyon 1 Calvert Cliffs 1 2041 Farley 2 2046 Braidwood 1 2025 Diablo Canyon 2 D.C. Cook 1 McGuire 1 Byron 2 2026 Clinton 1 Cooper Sequoyah 2 Harris 1 Perry 1 FitzPatrick 2042 LaSalle 1 Hope Creek 1 2029 Dresden 2 Hatch 1 Summer 1 Nine Mile Point 2 Ginna Oconee 3 Susquehanna 1 Palo Verde 2 Nine Mile Point 1 Prairie Island 2 2043 Catawba 1 2047 Beaver Valley 2 2030 Comanche Peak 1 2035 Millstone 2 Catawba 2 Braidwood 2 Monticello 1 Watts Bar 1 Columbia Palo Verde 3 Point Beach 1 2036 Beaver Valley 1 LaSalle 2 South Texas Project 1 Robinson 2 Browns Ferry 3 McGuire 2 Vogtle 1 2031 Dresden 3 Brunswick 1 St. Lucie 2 2048 South Texas Project 2 Palisades Calvert Cliffs 2 2044 Byron 1 2049 Limerick 2 2032 Quad Cities 1 St. Lucie 1 Callaway Vogtle 2 Quad Cities 2 Salem 1 Grand Gulf 1 2050 Seabrook 2033 Browns Ferry 1 2037 D.C. Cook 2 Limerick 1 Turkey Point 3 Comanche Peak 2 Davis-Besse 1 Susquehanna 2 Surry 1 Oconee 1 Farley 1 Waterford 3 Oconee 2 2038 Arkansas Nuclear 2 2052 Peach Bottom 2 2045 Fermi 2 Prairie Island 1 Hatch 2 Millstone 3 2053 Surry 2 Point Beach 2 North Anna 1 Turkey Point 4 2040 North Anna 2 Palo Verde 1 2034 Arkansas Nuclear 1 River Bend 1 2054 Peach Bottom 3 Browns Ferry 2 Salem 2 2055 Watts Bar 2 Sequoyah 1 Wolf Creek 1 Brunswick 2 Notes: NRC-abbreviated reactor names are listed. Data are current as of August 2021; the next printed update will be in September 2022.
APPENDICES l 117
APPENDIX H Operating Nuclear Research and Test Reactors Regulated by the NRC Licensee Reactor Type Power Level Licensee Number Location OL Issued (kW) Docket Number Aerotest TRIGA (Indus) 250 R-98 San Ramon, CA 07/02/1965 05000228 Armed Forces Radiobiology TRIGA 1,100 R-84 Research Institute 06/26/1962 05000170 Bethesda, MD Dow Chemical Company TRIGA MARK I 300 R-108 Midland, MI 07/03/1967 05000264 GE-Hitachi Tank 100 R-33 Sunol, CA 10/31/1957 05000073 Idaho State University AGN-201 #103 0.005 R-110 Pocatello, ID 10/11/1967 05000284 Kansas State University TRIGA MARK II 1,250 R-88 Manhattan, KS 10/16/1962 05000188 Massachusetts Institute HWR Reflected 6,000 R-37 of Technology 06/09/1958 05000020 Cambridge, MA Missouri University of Science Pool, MTR type fuel 200 R-79 and Technology 11/21/1961 05000123 Rolla, MO National Institute of Nuclear Test 20,000 TR-5 Standards and Technology 05/21/1970 05000184 Gaithersburg, MD North Carolina State University Pulstar 1,000 R-120 Raleigh, NC 08/25/1972 05000297 Ohio State University Pool 500 R-75 Columbus, OH 02/24/1961 05000150 Oregon State University TRIGA MARK II 1,100 R-106 Corvallis, OR 03/07/1967 05000243 Pennsylvania State University TRIGA 1,100 R-2 State College, PA 07/08/1955 05000005 Purdue University Lockheed 12 R-87 West Lafayette, IN 08/16/1962 05000182 Reed College TRIGA MARK I 250 R-112 Portland, OR 07/02/1968 05000288 Rensselaer Polytechnic Institute Critical Assembly 0.1 CX-22 Troy, NY 07/03/1964 05000225 Rhode Island Atomic GE Pool 2,000 R-95 Energy Commission 07/23/1964 05000193 Narragansett, RI Texas A&M University AGN-201M #106 0.005 R-23 College Station, TX 08/26/1957 05000059 118 l APPENDICES
APPENDIX H Operating Nuclear Research and Test Reactors Regulated by the NRC (continued)
Licensee Reactor Type Power Level Licensee Number Location OL Issued (kW) Docket Number Texas A&M University TRIGA 1,000 R-83 College Station, TX 12/07/1961 05000128 U.S. Geological Survey TRIGA MARK I 1,000 R-113 Denver, CO 02/24/1969 05000274 University of California/Davis TRIGA MARK II 2,300 R-130 Sacramento, CA 08/13/1998 05000607 University of California/Irvine TRIGA MARK I 250 R-116 Irvine, CA 11/24/1969 05000326 University of Florida Argonaut 100 R-56 Gainesville, FL 05/21/1959 05000083 University of Maryland TRIGA 250 R-70 College Park, MD 10/14/1960 05000166 University of Massachusetts/Lowell GE Pool 1,000 R-125 Lowell, MA 12/24/1974 05000223 University of Missouri/Columbia Tank 10,000 R-103 Columbia, MO 10/11/1966 05000186 University of New Mexico AGN-201M #112 0.005 R-102 Albuquerque, NM 09/17/1966 05000252 University of Texas TRIGA MARK II 1,100 R-129 Austin, TX 01/17/1992 05000602 University of Utah TRIGA MARK I 100 R-126 Salt Lake City, UT 09/30/1975 05000407 University of Wisconsin TRIGA 1,000 R-74 Madison, WI 11/23/1960 05000156 Washington State University TRIGA 1,000 R-76 Pullman, WA 03/06/1961 05000027 Note: Data are current as of August 2021; the next printed update will be in September 2022.
APPENDICES l 119
APPENDIX I Nuclear Research and Test Reactors under Decommissioning Regulated by the NRC Licensee Reactor Type OL Issued Location Power Level (kW) Shutdown General Atomics TRIGA MARK F 07/01/60 San Diego, CA 1,500 09/07/94 General Atomics TRIGA MARK I 05/03/58 San Diego, CA 250 12/17/96 General Electric Company GETR (Tank) 01/07/59 Sunol, CA 50,000 06/26/85 Note: Data are current as of August 2021; the next printed update will be in September 2022.
APPENDIX J Radiation Doses and Regulatory Limits Radiation Doses and Regulatory Limits (in Millirem) 5,000 5,000 Annual Nuclear Worker Dose Limit (NRC) 1,000 Whole Body CT 1,000 800 Doses in Millirem 620 Average U.S. Annual Dose 600 450 Denver Avg. Annual Natural Background Dose 400 310 U.S. Avg. Natural Background Dose 200 100 40 30 10 4 2.5 0
Annual Public From Cosmic Chest Safe Transatlantic Dose Limit Your Rays X-Ray Drinking Flight (NRC) Body Water Limit (EPA)
Dose Limit from NRC-Licensed Activity Radiation Doses 120 l APPENDICES
APPENDIX K Commercial Nuclear Power Plant Licensing History 1955-2020 Year Original Licensing Regulations Alternative Licensing (10 CFR Part 50)1 Regulations (10 CFR Part 52)3 CP Issued2 Full-Power COL Operating Permanent Operable OL Issued Issued4 COLs5 Shutdowns6 Units 1955 1 0 -- -- 0 0 1956 3 0 -- -- 0 0 1957 1 1 -- -- 0 1 1958 0 0 -- -- 0 1 1959 3 1 -- -- 0 2 1960 7 1 -- -- 0 3 1961 0 0 -- -- 0 3 1962 1 6 -- -- 0 9 1963 1 2 -- -- 1 11 1964 3 3 -- -- 1 13 1965 1 0 -- -- 0 13 1966 5 2 -- -- 17 14 1967 14 3 -- -- 2 15 1968 23 0 -- -- 1 13 1969 7 4 -- -- 0 17 1970 10 3 -- -- 1 20 1971 4 2 -- -- 0 22 1972 8 6 -- -- 2 27 1973 14 15 -- -- 0 42 1974 23 15 -- -- 2 55 1975 9 2 -- -- 0 57 1976 9 7 -- -- 1 63 1977 15 4 -- -- 0 67 1978 13 4 -- -- 1 70 1979 2 0 -- -- 1 69 1980 0 2 -- -- 0 71 1981 0 4 -- -- 0 75 1982 0 4 -- -- 1 78 1983 0 3 -- -- 0 81 1984 0 6 -- -- 0 87 1985 0 9 -- -- 0 96 1986 0 5 -- -- 0 101 1987 0 8 -- -- 1 107 1988 0 2 -- -- 0 109 1989 0 4 -- -- 3 111 1990 0 2 -- -- 0 112 1991 0 0 -- -- 1 111 1992 0 0 -- -- 2 109 1993 0 1 -- -- 0 110 1994 0 0 -- -- 0 109 1995 0 0 -- -- 0 109 1996 0 1 -- -- 3 109 APPENDICES l 121
APPENDIX K Commercial Nuclear Power Plant Licensing History 1955-2020 (continued)
Year Original Licensing Regulations Alternative Licensing (10 CFR Part 50)1 Regulations (10 CFR Part 52)3 CP Issued2 Full-Power COL Operating Permanent Operable OL Issued Issued4 COLs5 Shutdowns6 Units 1997 0 0 0 0 2 107 1998 0 0 0 0 1 104 1999-0 0 0 0 0 104 2011 2012 0 0 4 units 0 0 104 2013 0 0 0 0 4 100 2014 0 0 0 0 1 99 2015 0 1 1 unit 0 0 100 2016 0 0 6 units 0 1 99 2017 0 0 1 unit 0 0 99 2018 0 0 2 units 0 1 98 2019 0 0 0 0 2 96 2020 0 0 0 0 2 94 2021 0 0 0 0 1 93 Total 177 133 14 units 0 39 --
U.S. Atomic Energy Commission was the regulatory authority.
- - Not applicable 1
Data in columns 1-3 are based on 10 CFR Part 50. Numbers reflect permits or licenses issued in a given year, not extant permits or licenses.
2 Issuance by regulatory authority of a permit, or equivalent permission, to begin construction. Under alternative licensing regulations in 10 CFR Part 52, a construction permit (CP) is not issued separately from the operating license.
3 Data in columns 4-6 are based on 10 CFR Part 52. Numbers reflect permits or licenses issued in a given year, not extant permits or licenses.
4.
Number of combined licenses (COLs) issued in a given year, including six that were subsequently terminated. See Appendix A on status of plant construction and Appendix B for more information on withdrawn and suspended applications.
5 Issuance by the NRC of a finding under 10 CFR 52.103(g), in a given year.
6 Number of operating plants transitioned to shutdown in a given year. Does not represent the total number of reactor units included.
7 These are DOE nuclear legacy sites: Hallam (1964), Piqua (1966), Elk River (1968), and Shippingport (1982). For more information, visit DOE's Legacy Management Web site at https://energy.gov/lm/sites/lm-sites and see the Glossary for definitions of decommissioning alternatives (DECON, SAFSTOR).
Source: U.S. Energy Information Administration/Annual Energy Review 2011 located at https://www.eia.gov/aer and compilation of NRC information following 2011.
Data are current as of September 2022; the next printed update will be in August 2022.
122 l APPENDICES
APPENDIX L Materials Licenses by State Number of Licenses Number of Licenses Agreement Agreement State NRC States State NRC States Alabama 11 337 New Hampshire 2 71 New Jersey 21 523 Alaska 58 0 New Mexico 9 204 Arizona 5 351 New York 14 1,250 Arkansas 4 178 North Carolina 18 532 California 46 1,677 North Dakota 3 76 Colorado 16 311 Ohio 40 534 Connecticut 118 0 Oklahoma 12 224 Delaware 40 0 Oregon 3 304 District of Columbia 33 0 Pennsylvania 42 539 Florida 16 1,538 Rhode Island 1 42 Georgia 14 389 South Carolina 3 317 Hawaii 52 0 South Dakota 33 0 Idaho 67 0 Tennessee 21 502 Illinois 19 562 Texas 43 1,404 Indiana 199 0 Iowa 1 137 Utah 7 190 Kansas 13 255 Vermont 1 33 Kentucky 6 339 Virginia 50 374 Louisiana 12 440 Washington 12 330 West Virginia 133 0 Maine 2 91 Wisconsin 6 284 Maryland 64 528 Wyoming 73 14 Massachusetts 17 401 Puerto Rico 102 0 Michigan 379 0 Virgin Islands 9 0 Minnesota 14 149 Guam 5 0 Mississippi 12 257 American Samoa 2 0 Missouri 223 0 Northern Marianas 1 0 Montana 75 0 Total number of materials Nebraska 4 130 licenses in Agreement State 16,040 Nevada 1 223 jurisdiction Total number of materials licenses in NRC jurisdiction 2,186 Agreement State Total number of materials licenses in the United States 18,226 Letter of Intent Notes: The NRC and Agreement State data are current as of September 2022. These totals represent an estimate because the number of specific radioactive materials licenses per State may change daily. The next printed update will be in August 2022. The NRC licenses Federal agencies in Agreement States.
APPENDICES l 123
APPENDIX M Major U.S. Fuel Cycle Facility Sites Licensee Location Status Docket #
Uranium Hexafluoride Conversion Facility Honeywell International, Inc. Metropolis, IL ready-idle* 04003392 Uranium Fuel Fabrication Facilities Global Nuclear Fuel-Americas, LLC Wilmington, NC active 07001113 Westinghouse Electric Company, LLC Columbia, SC active 07001151 Columbia Fuel Fabrication Facility Nuclear Fuel Services, Inc. Erwin, TN active 07000143 BWXT Nuclear Operations Group, Inc. Lynchburg, VA active 07000027 Framatome, Inc. Richland, WA active 07001257 Gas Centrifuge Uranium Enrichment Facilities Centrus Energy Corp Piketon, OH license issued, 07007004 American Centrifuge Plant under construction Centrus Energy Corp Piketon, OH license active 07007003 Lead Cascade (facility decommissioned)
URENCO-USA (Louisiana Energy Services) Eunice, NM active 07003103 Uranium Enrichment Laser Separation Facility GE-Hitachi Global Laser Enrichment, LLC Wilmington, NC license terminated 07007016 Depleted Uranium Deconversion Facility International Isotopes, Inc. Hobbs, NM license issued, 04009086 (Lea County) construction not started
- The facility is being maintained with minimal operations to support a future return to production.
Notes: On February 8, 2018, the NRC issued a termination of the construction authorization (CAMOX-001) for the Mixed-Oxide Fuel Fabrication Facility (see ADAMS Accession No. ML18318A135). Centrus Energy Corp - American Centrifuge Plantis under construc-tion for High Assay Low Enriched Uranium Demonstration Program. On January 5, 2021, the NRC issued a letter terminating the license for the GLE Laser Separation Enrichment Facility (see ADAMS Accession No. ML20293A175.
Data are current as of August 2021; the next printed update will be in September 2022.
124 l APPENDICES
APPENDIX N Dry Spent Fuel Storage Designs:
NRC-Approved for Use by General Licensees Vendor Docket # Storage Design Model General Nuclear Systems, Inc. 07201000 CASTOR V/21 (expired)
NAC International, Inc. 07201002 NAC S/T (expired) 07201003 NAC-C28 S/T (expired) 07201015 NAC-UMS 07201025 NAC-MPC 07201031 MAGNASTOR 07201013 NAC-STC Holtec International 07201008 HI-STAR 100 07201014 HI-STORM 100 07201032 HI-STORM FW 07201040 HI-STORM UMAX Westinghouse Electric Co. 07201007 VSC-24 07201026 Fuel SolutionsTM (WSNF-220, -221, -223)
W-150 Storage Cask
W-100 Transfer Cask
W-21, W-74 Canisters TN Americas, LLC 07201005 TN-24 (expired)
(formerly Transnuclear, Inc.) 07201027 TN-68 07201021 TN-32 07201004 Standardized NUHOMS-24P, -24PHB, 24PTH, -32PT,
-32PTH1, -37PTH, -52B, -61BT DSC,-61BTH, -69BTH 07201029 Standardized Advanced NUHOMS-24PT1, -24PT4 07201030 NUHOMS HD-32PTH 07201042 NUHOMS EOS Notes: Data are current as of August 2021; the next printed update will be in September 2022. (See the latest list on the NRC Web site at https://www.nrc.gov/waste/spent-fuel-storage/designs.html.)
APPENDICES l 125
APPENDIX O Dry Cask Spent Fuel Storage Licensees Name License Storage Docket Licensee Type Vendor Model Number Arkansas Nuclear GL Westinghouse Electric Co. VSC-24 07200013 Entergy Nuclear Holtec International HI-STORM 100 Operations, Inc.
Beaver Valley GL TN Americas, LLC NUHOMS-37PTH 07201043 FirstEnergy Nuclear
Operating Company Big Rock Point GL Westinghouse Electric Co. Fuel SolutionsTM 07200043 Entergy Nuclear W74 Operations, Inc.
Braidwood GL Holtec International HI-STORM 100 07200073 Exelon Generation Co., LLC Browns Ferry GL Holtec International HI-STORM 100S 07200052 Tennessee Valley Authority HI-STORM FW Brunswick GL TN Americas, LLC NUHOMS-HD-61BTH 07200006 Carolina Power Co.
Byron GL Holtec International HI-STORM 100 07200068 Exelon Generation Co., LLC Callaway GL Holtec International HI-STORM UMAX 07201045 Union Electric Co.
Ameren Missouri Calvert Cliffs SL TN Americas, LLC NUHOMS-24P 07200008 Calvert Cliffs Nuclear NUHOMS-32P Power Plant, Inc.
Catawba GL NAC International, Inc. NAC-UMS 07200045 Duke Energy Carolinas, LLC MAGNASTOR Clinton GL Holtec International HI-STORM FW 07201046 Exelon Generation Co., LLC Columbia Generating GL Holtec International HI-STORM 100S 07200035 Station
Energy Northwest
Comanche Peak GL Holtec International HI-STORM 100 07200074 Luminant Generation Company, LLC Cooper Nuclear Station GL TN Americas, LLC NUHOMS-61BT 07200066 Nebraska Public Power District Crystal River GL TN Americas, LLC NUHOMS--32PT 07201035 Duke Energy Company Davis-Besse GL TN Americas, LLC NUHOMS-24P 07200014 FirstEnergy Nuclear NUHOMS--32PTH Operating Company
DC Cook GL Holtec International HI-STORM 100 07200072 Indiana/Michigan Power Diablo Canyon SL Holtec International HI-STORM 100 07200026 Pacific Gas & Electric Co.
Dresden GL Holtec International HI-STAR 100 07200037 Exelon Generation HI-STORM 100 Company, LLC Duane Arnold GL TN Americas, LLC NUHOMS-61BT 07200032 NextEra Energy Inc.
Duane Arnold, LLC
126 l APPENDICES
APPENDIX O Dry Cask Spent Fuel Storage Licensees (continued)
Name License Storage Docket Licensee Type Vendor Model Number Fermi GL Holtec International HI-STORM 100 07200071 DTE Electric Company Fort Calhoun GL TN Americas, LLC NUHOMS-32PT 07200054 Omaha Public Power District Fort St. Vrain* SL FW Energy Modular Vault 07200009 U.S. Department of Energy Applications, Inc. Dry Store Grand Gulf GL Holtec International HI-STORM 100S 07200050 Entergy Nuclear Operations, Inc.
H.B. Robinson SL TN Americas, LLC NUHOMS-7P 07200003 Carolina Power & GL TN Americas, LLC NUHOMS-24P 07200060 Light Company NUHOMS-24PTH Haddam Neck GL NAC International, Inc. NAC-MPC 07200039 CT Yankee AtomicPower Hatch GL Holtec International HI-STORM100 07200036 Southern Nuclear Operating Co. Inc. HI-STAR100 Hope Creek GL Holtec International HI-STORM 100 07200048 PSEG Nuclear, LLC Humboldt Bay SL Holtec International HI-STAR 100HB 07200027 Pacific Gas & Electric Co.
Idaho National Laboratory SL TN Americas, LLC NUHOMS-12T 07200020 TMI-2 U.S. Department of Energy Idaho Spent Fuel Facility SL Foster Wheeler Concrete Vault 07200025 U.S. Department of Energy
Indian Point GL Holtec International HI-STORM 100 07200051 Entergy Nuclear Operations, Inc.
James A. FitzPatrick GL Holtec International HI-STORM 100 07200012 Entergy Nuclear Operations, Inc. HI-STORM 100S 07200013 Joseph M. Farley GL Holtec International HI-STORM 100S 07200042 Southern Nuclear Operating Co.
Kewaunee GL TN Americas, LLC NUHOMS-32PT 07200064 Dominion Energy NAC International, Inc. MAGNASTOR Kewaunee, Inc. La Salle GL Holtec International HI-STORM 100S 07200070 Exelon Generation Co., LLC LaCrosse GL NAC International, Inc. NAC-MPC 07200046 Dairyland Power Limerick GL TN Americas, LLC NUHOMS-61BT 07200065 Exelon Generation Co., LLC NUHOMS-61BTH Maine Yankee GL NAC International, Inc. NAC-UMS 07200030 Maine Yankee Atomic Power Company
McGuire GL TN Americas, LLC TN-32 07200038 Duke Energy, LLC NAC International, Inc. NAC-UMS
MAGNASTOR Millstone GL TN Americas, LLC NUHOMS-32PT 07200047 Dominion Generation
Monticello GL TN Americas, LLC NUHOMS-61BT 07200058 Northern States Power NUHOMS-61BTH Co., Minnesota APPENDICES l 127
APPENDIX O Dry Cask Spent Fuel Storage Licensees (continued)
Name License Storage Docket Licensee Type Vendor Model Number Nine Mile Point GL TN Americas, LLC NUHOMS-61BT 07201036 Constellation Energy North Anna GL TN Americas, LLC NUHOMS32PTH1 07200056 Virginia Electric & Power Co. SL TN Americas, LLC TN-32 07200016 (Dominion Energy Virginia)
Oconee SL TN Americas, LLC NUHOMS-24P 07200004 Duke Energy Company GL TN Americas, LLC NUHOMS-24P 07200040 Oyster Creek GL TN Americas, LLC NUHOMS-61BT 07200015 Oyster Creek Environmental NUHOMS-61BTH Protection, LLC
Palisades GL Westinghouse Electric Co VSC-24 07200007 Entergy Nuclear TN Americas, LLC NUHOMS-32PT Operations, Inc. NUHOMS-24PT Holtec International HI-STORM FW Palo Verde GL NAC International, Inc. NAC-UMS 07200044 Arizona Public Service Co.
Peach Bottom GL TN Americas, LLC TN-68 07200029 Exelon Generation Co., LLC
Perry GL Holtec International HI-STORM 100 07200069 FirstEnergy Pilgrim GL Holtec International HI-STORM 100 07201044 Holtec Pilgrim, LLC Point Beach GL Westinghouse Electric Co. VSC-24 07200005 NextEra Energy TN Americas, LLC NUHOMS-32PT Prairie Island SL TN Americas, LLC TN-40 HT 07200010 Northern States Power TN-40 Co., Minnesota Private Fuel Storage SL Holtec International HI-STORM 100 07200022 Facility Quad Cities GL Holtec International HI-STORM 100S 07200053 Exelon Generation Co., LLC Rancho Seco SL TN Americas, LLC NUHOMS-24PT 07200011 Sacramento Municipal Utility District R.E. Ginna GL TN Americas, LLC NUHOMS-32PT 07200067 Constellation Energy
River Bend GL Holtec International HI-STORM 100S 07200049 Entergy Nuclear Operations, Inc.
Salem GL Holtec International HI-STORM 100 07200048 PSEG Nuclear (Duplicate, see Hope Creek)
San Onofre GL TN Americas, LLC NUHOMS-24PT4 07200041 Southern California Edison Co. NUHOMS-24PT1
Holtec International HI-STORM UMAX Seabrook GL TN Americas, LLC NUHOMS-HD-32PTH 07200063 FPL Energy
Sequoyah GL Holtec International HI-STORM 100 07200034 Tennessee Valley Authority HI-STORM FW HI-STORM 100S 128 l APPENDICES
APPENDIX O Dry Cask Spent Fuel Storage Licensees (continued)
Name License Storage Docket Licensee Type Vendor Model Number South Texas Project GL Holtec International HI-STORM FW 07201041 STP Nuclear Operating Co.
St. Lucie GL TN Americas, LLC NUHOMS-HD-32PTH 07200061 Florida Power & Light Co.
Surry SL TN Americas, LLC NUHOMSHD 07200002 Virginia Electric & Power Co. GL TN Americas, LLC NUHOMSHD-32PTH 07200055 (Dominion Energy Virginia) Gesellschaft für Castor
Nuklear-Service
NAC International, Inc. NAC-128
Westinghouse Electric Co MC-10 Susquehanna GL TN Americas, LLC NUHOMS-52B 07200028 Pennsylvania Power & Light Co. NUHOMS-61BT
NUHOMS-61BTH Trojan SL Holtec International HI-STORM 100 07200017 Portland General
Electric Corp.
Turkey Point ISFSI GL TN Americas, LLC NUHOMS-HD-32PTH 07200062 Florida Power & Light Co.
Vermont Yankee GL Holtec International HI-STORM 100 07200059 NorthStar Vermont Yankee, LLC Virgil C. Summer GL Holtec International HI-STORM FW 07201038 South Carolina Electric & Gas Vogtle GL Holtec International HI-STORM 100S 07201039 Southern Nuclear Operating Co. Inc.
Waterford Steam GL Holtec International HI-STORM 100 07200075 Electric Station Entergy Nuclear Operations, Inc.
Watts Bar GL Holtec International HI-STORM FW 07201048 Tennessee Valley Authority WCS Consolidated Interim SL TN Americas, LLC NUHOMS-MP187 07201050 Storage Facility, CISF NUHOMS 24PT1 Interim Storage Partners, LLC NUHOMS 61BT
NUHOMS 61BTH NAC International, Inc. NAC-MPC
NAC-UMS
MAGNASTOR Yankee Rowe GL NAC International, Inc. NAC-MPC 07200031 Yankee Atomic Electric Zion GL NAC International, Inc. MAGNASTOR 07201037 Zion Solutions, LLC
Notes: NRC-abbreviated unit names. Data are current as of Sept. 2021; the next printed update will be in September 2022.
License Types: SL = site-specific license, GL = general license APPENDICES l 129
APPENDIX P U.S. Low-Level Radioactive Waste Disposal Compact Membership Appalachian Compact Midwest Compact Southeast Compact Delaware Indiana Alabama Maryland Iowa Florida Pennsylvania Minnesota Georgia West Virginia Missouri Mississippi Ohio Tennessee Atlantic Compact Wisconsin Virginia Connecticut New Jersey Northwest Compact Southwestern Compact South Carolina* Alaska Arizona Hawaii California Central Compact Idaho North Dakota Arkansas Montana South Dakota Kansas Oregon Louisiana Utah* Texas Compact Oklahoma Washington* Texas*
Wyoming Vermont Central Midwest Compact Illinois Rocky Mountain Compact Unaffiliated Kentucky Colorado District of Columbia Nevada Maine New Mexico Massachusetts (Northwest accepts Michigan Rocky Mountain waste Nebraska as agreed between compacts.) New Hampshire New York North Carolina Puerto Rico Rhode Island Closed Low-Level Radioactive Waste Disposal Facility Sites Licensed by the NRC or Agreement States Beatty, NV, closed 1993 Sheffield, IL, closed 1978 Maxey Flats, KY, closed 1977 West Valley, NY, closed 1975
- Site of an active low-level waste disposal facility.
Note: Data are current as of August 2021; the next printed update will be in September 2022.
130 l APPENDICES
APPENDIX Q NRC-Regulated Complex Materials Sites NRC-Regulated ComplexUndergoing Materials Sites Undergoing Decommissioning Decommissioning RI NRC-regulated complex materials sites (11)
Company Location Alameda Naval Air Station Alameda, CA BWX Technology, Inc., Shallow Land Disposal Area Vandergrift, PA Cimarron Environmental Response Trust Cimarron City, OK Department of the Army, Jefferson Proving Ground Madison, IN Department of the Army, Picatinny Arsenal (ARDEC) Picatinny, NJ FMRI, Inc. (Fansteel) Muskogee, OK Hunters Point Naval Shipyard San Francisco, CA McClellan Air Force Base Sacramento, CA Sigma Aldrich Maryland Heights, MO UNC Naval Products New Haven, CT West Valley Demonstration Project West Valley, NY Note: Data are current as of August 2021; the next printed update will be in September 2022.
APPENDICES l 131
APPENDIX R Nuclear Power Units by Nation In Operation Under Construction or on Order
Nuclear Power Number Electrical Number Electrical
Country Production GWh* of Units Capacity of Units Capacity Shutdown Argentina 10,011 3 1,641 1 25 0 Armenia 2,552 1 415 0 0 1P Bangladesh 0 0 0 2 2,160 0 Belarus 338 1 1,110 1 1,110 0 Belgium 32,606 7 5,942 0 0 1P Brazil 14,053 2 1,884 1 1,340 0 Bulgaria 16,626 2 2,006 0 0 4P Canada 92,652 19 13,624 0 0 6P China 366,300 51 48,528 13 12,565 0 Czech Republic 28,372 6 3,934 0 0 0 Finland 22,358 4 2,794 1 1,600 0 France 379,500 56 61,370 1 1,630 14P Germany 60,918 6 8,113 0 0 30P Hungary 15,179 4 1,902 0 0 0 India 40,374 23 6,885 6 4,194 0 Iran 5,792 1 915 1 974 0 Italy 0 0 0 0 0 4P Japan 43,000 33 31,679 2 2,653 27P Kazakhstan 0 0 0 0 0 1P Korea, Republic of 152,328 24 23,150 4 5,360 2P Lithuania 0 0 0 0 0 2P Mexico 10,864 2 1,552 0 0 0 Netherlands 3,865 1 482 0 0 1P Pakistan 9,640 6 2,332 1 1,014 0 Romania 10,558 2 1,300 0 0 0 Russia 215,745 38 28,578 3 3,459 9P Slovakia Republic 15,444 4 1,837 2 880 3P Slovenia 6,041 1 688 0 0 0 132 l APPENDICES
APPENDIX R Nuclear Power Units by Nation (continued)
In Operation Under Construction or on Order
Nuclear Power Number Electrical Number Electrical
Country Production GWh* of Units Capacity of Units Capacity Shutdown South Africa 11,616 2 1,860 0 0 0 Spain 55,793 7 7,121 0 0 3P Sweden 47,262 6 6,882 0 0 7P Switzerland 22,990 4 2,960 0 0 2P Turkey 0 0 0 3 3,242 0 Ukraine 76,202 15 13,107 2 2,070 4P United Arab Emirates 1,562 1 0 3 4,035 0 United Kingdom 45,668 15 8,923 2 3,260 30P United States 789,919 93 95,523 2 2,234 40P Overview of Worldwide Nuclear Power ReactorsAs of June 28, 2021 Nuclear Electricity Supplied (GWh) 2,553,208 Net Installed Capacity (MWe) 394,226 Nuclear Power Reactors in Operation 444 Nuclear Power Reactors in Long-Term Shutdown 0 Nuclear Power Reactors in Permanent Shutdown 193 Nuclear Power Reactors under Construction 51
- Annual electrical power production for 2018. P = Permanent Shutdown Notes: Totals include reactors that are operable, under construction, or on order; the country's short-form name is used; and the figures are rounded to the nearest whole number. Source: IAEA Power Reactor Information System Database; analysis compiled by the NRC. For more information, go to https://www.iaea.org/pris/. Data are current as of June 28, 2021. The next printed update will be in September 2022.
APPENDIX S Nuclear Power Units by Reactor Type, Worldwide
In Operation
Number
Reactor Type of Units Net MWe Pressurized light-water reactors (PWR) 303 288,068 Boiling light-water reactors (BWR) 63 64,122 Heavy-water reactors, all types (HWR, PHWR) 49 24,553 Gas-cooled reactors, all types (GCR) 14 7,725 Light-water-cooled graphite-moderated reactor (LWGR) 12 8,358 Liquid-metal-cooled fast breeder reactors (FBR) 3 1,400 Total 444 394,226 Note: Megawatts electric (MWe) values are rounded to the nearest whole number.
Source: IAEA Power Reactor Information System Database, https://www.iaea.org/pris/ Compiled by the NRC from IAEA data.
Data are current as of June 28, 2021. The next printed update will be in September 2022..
APPENDICES l 133
APPENDIX T Native American Reservations and Trust Lands within a 50-Mile Native Radius ofReservations American an Operating Nuclear and Trust Power Lands Plant within U.S. Operating a 50-Mile Radius of a Operating Commercial Nuclear Power Nuclear Power Plant Reactors RI REGION I REGION III REGION II REGION IV ARIZONA LOUISIANA NEBRASKA VIRGINIA Palo Verde River Bend Cooper Surry Ak-Chin Indian Community Tunica-Biloxi Reservation Sac & Fox Trust Land Pamunkey Reservation Gila River Reservation Sac & Fox Reservation Chickahominy Indian Tribe Tohono Oodham Trust Land MARYLAND Iowa Reservation Chickahominy Indian Tribe Calvert Cliffs Iowa Trust Land Eastern Division Rappahannock Tribe Kickapoo Nansemond Indian Tribe CONNECTICUT Upper Mattaponi Tribe Upper Mattaponi Tribe Millstone NEW YORK MICHIGAN FitzPatrick WASHINGTON Mohegan Reservation Mashantucket Pequot Reservation Palisades Onondaga Reservation Columbia Narragansett Reservation Pottawatomi Reservation Oneida Reservation Yakama Reservation Shinnecock Indian Nation Matchebenashshewish Band Yakama Trust Land Pokagon Reservation Nine Mile Point FLORIDA Pokagon Trust Land* Onondaga Reservation WISCONSIN St. Lucie Oneida Reservation Point Beach DC Cook Brighton Reservation Pokagon Reservation NORTH CAROLINA Oneida Trust Land (Seminole Tribes of Florida) Oneida Reservation Fort Pierce Reservation Pokagon Trust Land McGuire MINNESOTA Catawba Reservation Turkey Point Monticello SOUTH CAROLINA Hollywood Reservation (Seminole Tribes of Florida)
Shakopee Community Catawba Shakopee Trust Land Catawba Reservation Miccosukee Reservation Mille Lacs Reservation Miccosukee Trust Land Oconee Prairie Island Eastern Cherokee Reservation Prairie Island Community*
Prairie Island Trust Land* Summer Shakopee Community Catawba Reservation Shakopee Trust Land
- Tribe is located within the 10-mile emergency preparedness zone of operating reactors.
Note: This table uses NRC-abbreviated reactor names and Native American Reservation and Trust land names. There are no reservations or Trust lands within 50 miles of a reactor in Alaska, Hawaii or U.S. Territories. For more information on other Tribal concerns, go to the NRC Web site at https://www.nrc.gov. NRC-abbreviated reactor names listed. Data as of July 2021, and the next printed update will be September 2022.
134 l APPENDICES
APPENDIX U States with NRC Grant Award Recipients in Fiscal Year 2020 State Amount Type of Grant Academic Institution Title of Proposal Awarded CA $500,000 Research and University of Southern Risk-informed Condition Assessment of Spent Nuclear Development Grant California Fuel Canisters Using Experimental Measurements and High-fidelity Computational Models CO $400,000 Fellowship Colorado State University Colorado State University Health Physics Fellowship Program FL $450,000 Faculty Development University of Florida 2020 NRC Nuclear Engineering Faculty Development Program FL $399,389 Fellowship Florida International FIU Nuclear Fellowship Program: Expanding the University Radiochemistry Ph.D. Track FL $395,277 Fellowship University of Florida 2020 NRC Graduate Fellowship Program at the University of Florida FL $199,990 Scholarship Florida Memorial Fostering Matriculation of Undergraduates in Nuclear University Research and Collaboration GA $499,927 Research and Georgia Institute of Experimental Investigation of Heat Transfer and Pressure Development Grant Technology Drop Characteristics of AHTR Channels ID $398,050 Fellowship Idaho State University Idaho State University Nuclear Education Fellowship Program ID $399,332 Fellowship University of Idaho Graduate Fellowships in Nuclear Engineering at the University of Idaho IL $400,000 Fellowship University of Illinois University of Illinois at Urbana-Champaign Nuclear Engineering Education Fellowship Program IL $500,000 Research and University of Illinois Advancing Uncertainty Analysis Processes in Development Grant Risk-Informed Regulatory Framework to Support Simulation Approaches for Aging Plants and Advanced Reactors IN $450,000 Faculty Development Purdue University Purdue University Health Physics Faculty Development Plan IN $398,092 Fellowship Purdue University Graduate Fellowship Program in Nuclear Materials at Purdue KS $400,000 Fellowship Kansas State University Kansas State University (KSU) Nuclear Engineering Fellowship Program (NEFP)
KS $418,161 Research and Kansas State University Addressing Technical Knowledge Gaps for Concrete Development Grant Creep, Creep Recovery, and Creep Fracture MA $450,000 Faculty Development University of Faculty Development Program for Radiochemistry and Massachusetts - Lowell Radiological Health Physics at the University of Massachusetts Lowell MA $450,000 Faculty Development Worcester Polytechnic WPI Nuclear Science and Engineering (NSE) Faculty Institute Development Program MA $400,000 Fellowship University of Fellowship in Nuclear Engineering and Health Physics at Massachusetts - Lowell the University of Massachusetts Lowell MD $500,000 Research and University of Maryland Improving Foundational Knowledge of Dependency in Development Grant Human Reliability Analysis MD $383,061 Research and University of Maryland Application of Advanced and Hybrid Risk Tools in External Development Grant Hazard PRA: Challenges and Opportunities MI $500,000 Research and University of Michigan High fidelity modeling and experiments to inform safety Development Grant analysis codes for heat pipe microreactors APPENDICES l 135
APPENDIX U States with NRC Grant Award Recipients in Fiscal Year 2020 (continued)
State Amount Type of Grant Academic Institution Title of Proposal Awarded MO $450,000 Faculty Development University of Missouri - University of Missouri-Columbia Radiochemistry Faculty Columbia Development Program MO $200,000 Scholarship Missouri University of Undergraduate Scholarships in Nuclear Engineering at Science and Technology Missouri S&T (2020-2022)
NC $500,000 Research and North Carolina State OECD/NRC Liquid Metal Fast Reactor (LMFR) Core Development Grant University Thermal-Hydraulic Benchmark for Verification, Validation, and Uncertainty Quantification(VVUQ) of Sub-Channel and Computational Fluid Dynamics (CFD) Codes NJ $199,396 Scholarship Thomas Edison State Thomas Edison State University Scholarship Program University for Qualified Students Matriculated in Nuclear Energy Engineering, Electronics Systems Engineering Technology, Radiation Protection, Cyber Security, and Information Technology Degree Programs NV $499,912 Research and University of Nevada - A Self-Powered Platform to Measure and Report Spent Development Grant Reno Nuclear Fuel Package Temperatures during Transport without Containment Boundary Penetrations NY $500,000 Research and Rensselaer Polytechnic Development of a Modular Paradigm to Enhance Monte Development Grant Institute Carlo Neutronics for NRC Comprehensive Reactor Analysis Bundle (CRAB)
NY $200,000 Scholarship Rensselaer Polytechnic Enabling Strong Growth of the Nuclear Engineering Institute Undergraduate Scholarship Program OH $187,105 Scholarship Case Western Reserve ThinkEnergy, ThinkNuclear: The Next Generation of University ThinkEnergy Scholars OR $400,000 Fellowship Oregon State University Oregon State University Nuclear Science and Engineering Fellowship Program OR $500,000 Research and Oregon State University Dynamic Risk Assessment for Nuclear Cybersecurity Development Grant PA $450,000 Faculty Development University of Pittsburgh Pitt Nuclear Engineering Faculty Growth and Development SC $400,000 Fellowship University of South University of South Carolina Next Generation Nuclear Carolina Engineering Fellowship Program TN $450,000 Faculty Development University of Tennessee Faculty Development Program in Nuclear Data at the University of Tennessee TX $450,000 Faculty Development Texas A&M University Texas A&M Nuclear Engineering Faculty Development Program TX $300,000 Faculty Development University of Texas at San UTSA Faculty Development in Cybersecurity of Digital I&C Antonio in Nuclear Power Plants Research and Education TX $500,000 Research and Texas A&M University Heat Transfer Experimental and Computational Data for Development Grant Molten Salt Reactors Applications TX $450,000 Research and Texas A&M University Assessment of TRACE Thermal-Hydraulic System Code Development Grant for the Prediction of the Reactor Cavity Cooling System Behavior and Performance TX $158,040 Scholarship University of Texas at NRC Scholarship at the University of Texas Austin VA $450,000 Faculty Development Virginia Commonwealth Virginia Commonwealth University Faculty University Development Program in Advanced non-LWR Nuclear Reactor Design and Thermal Hydraulics 136 l APPENDICES
APPENDIX U States with NRC Grant Award Recipients in Fiscal Year 2020 (continued)
State Amount Type of Grant Academic Institution Title of Proposal Awarded VA $499,517 Research and Virginia Polytechnic Non-dimensional Analysis of Density-Wave Instabilities Development Grant Institute and Dryout-Rewet Cycles during an ATWS WA $150,000 Trade & Community Columbia Basin College Columbia Basin College Nuclear Scholarship Program College WI $450,000 Faculty Development University of Wisconsin - University of Wisconsin-Madison Faculty Development Madison Program in Nuclear Engineering WI $499,991 Research and University of Wisconsin - Understanding Microstructure-Mechanical Behavior Development Grant Madison Relationships in Coated Cladding Accident Tolerant Fuel (ATF) Concepts for Used Fuel Storage and Transportation WI $200,000 Scholarship University of Wisconsin - University of Wisconsin-Madison Undergraduate Madison Scholarship Program in Nuclear Engineering RI ALASKA HAWAII PUERTO RICO GUAM AMERICAN SAMOA NORTHERN MARIANAS States with NRC Grant Award Recipients FY 2020 APPENDICES l 137
APPENDIX V Significant Enforcement Actions Issued, 2020 Significant (escalated) enforcement actions include notices of violation (NOVs) for severity level (SL) I, II, or III violations; NOVs associated with inspection findings that the significance determination process (SDP) categorizes as White, Yellow, or Red; civil penalties (CPs); and enforcement-related orders. The NRC Enforcement Policy also allows related violations to be categorized collectively as a single problem. Escalated enforcement actions are issued to reactor, materials, and individual licensees; nonlicensees; and fuel cycle facility licensees.
Action # Name Type Issue Date Enforcement Action EA-19-079 Bittner Engineering, Inc. Materials 02/12/2020 SLIII Problem/NOV EA-19-127 Municipality of Anchorage Materials 02/13/2020 SLIII/NOV EA-19-141 Sanders Medical Products Materials 03/03/2020 (2) SLIII/NOV EA-19-025 Duke Energy (H.B. Robinson Steam Electric Reactor 03/11/2020 Confirmatory Order result of an Plant) ADR mediation EA-19-126 Avera St. Luke's Hospital Materials 03/11/2020 SLIII Problem/NOV IA-20-005 Mr. Stanley Schultz Individual 03/11/2020 SLIII/NOV EA-19-108 Schultz Surveying & Engineering Inc. Materials 03/11/2020 SLIII Problem/NOV IA-20-025 Mr. Michael Paul Individual 03/12/2020 SLIII/NOV EA-19-071 Reed College Reactor 03/16/2020 Confirmatory Order result of an ADR mediation IA-19-035 Dr. Melinda Krahenbuhl Individual 03/16/2020 Order banning for three years; withdrawn following ADR mediation EA-19-112 Southern Nuclear Operating Co. (Vogtle Electric Reactor 03/31/2020 White/NOV Generating Plant)
EA-19-068 Lantheus Medical Imaging Materials 04/23/2020 SLIII Problem/NOV; SLIII/NOV/
CP-$7,500 IA-19-033 Mr. César Blanco Individual 04/23/2020 SLIII Problem/NOV EA-19-136 Thrasher Engineering Materials 04/27/2020 SLIII/NOV/CP-$7,500 EA-20-014 Alt and Witzig Engineering, Inc. Materials 05/13/2020 (2) SLIII/NOV/CP-$8,500 EA-20-047 Christian Wheeler Engineering Materials 06/18/2020 SLIII/NOV EA-20-046 Bayou Inspection Services, Inc. Materials 06/22/2020 SLIII/NOV EA-19-096 Hot Asphalt Paving, Inc. Materials 06/24/2020 SLIII/NOV/CP-$7,500 EA-20-010 Centro Comprensivo de Cancer de la UPR Materials 06/30/2020 SLIII Problem/NOV IA-20-023 Mr. Dennis Bergmooser Individual 07/15/2020 SLIII/NOV IA-20-040 Dr. Melinda Krahenbuhl Individual 07/27/2020 Confirmatory Order result of an ADR mediation; Order IA-19-035 withdrawn for three year ban on July 27, 2020 EA-20-057 Virginia Electric and Power Co. (Surry Power Reactor 07/30/2020 White/NOV Station)
EA-20-003 Avera McKennan Materials 08/12/2020 SLIII Problem/NOV/CP-$7,500 IA-20-008 Mr. Joseph Shea Individual 08/24/2020 Order banning for five years; Order rescinded on January 22, 2021 138 l APPENDICES
APPENDIX V Significant Enforcement Actions Issued, 2020 (continued)
Action # Name Type Issue Date Enforcement Action IA-20-009 Ms. Erin Henderson Individual 08/24/2020 SLII/NOV; NOV rescinded on January 22, 2021 EA-20-006 EA- Tennessee Valley Authority (Watts Bar Nuclear Reactor 08/24/2020 SLI Problem/NOV; SLII Prob-20-007 Plant) lem/NOV/CP-$606,942; Order Imposing CP issued October 29, 2020; Hearing requested by TVA on November 30, 2020 EA-20-065 St. Luke's Regional Medical Center Materials 09/15/2020 SLIII Problem/NOV/CP-$7,500 EA-20-095 International Isotopes, Inc. Materials 09/17/2020 SLIII/NOV EA-20-018 Entergy Operations, Inc. (Arkansas Nuclear Reactor 09/23/2020 SLIII/NOV One)
IA-20-027 Mr. Todd Hegeman Individual 09/24/2020 SLIII/NOV IA-20-028 Mr. James Johnson Individual 09/24/2020 SLIII/NOV IA-20-029 Mr. Thomas Spivey Individual 09/24/2020 SLIII/NOV IA-20-030 Mr. Denver Lee Individual 09/24/2020 SLIII/NOV EA-19-132 St. Joseph's Regional Medical Center Materials 10/07/2020 SLIII Problem/NOV/CP-$7,500 EA-20-050 Sanford Medical Center Materials 10/16/2020 SLIII Problem/NOV EA-20-073 International Isotopes, Inc. Materials 10/20/2020 SLII Problem/NOV EA-20-051 The Queen's Medical Center Materials 10/27/2020 SLIII Problem/NOV/CP-$7,500 EA-19-092 Tennessee Valley Authority (Watts Bar Nuclear Reactor 11/06/2020 SLII/NOV; (2) SL III/NOV, SL II/
Plant) NOV/CP $303,471 IA-20-017 Mr. Billy Johnson Individual 11/06/2020 SLII/NOV; SLIII/NOV IA-20-018 Mr. William Sprinkle Individual 11/06/2020 SLIII/NOV; NOV withdrawn on July 23, 2021 IA-20-020 Mr. Todd Blakenship Individual 11/06/2020 SLIII/NOV; NOV withdrawn on July 23, 2021 EA-20-054 Arizona Public Service Co. (Palo Verde Reactor 11/17/2020 Confirmatory Order result of an Nuclear Generating Station) ADR mediation EA-20-056 Armed Forces Radiobiological Research Reactor 11/19/2020 Confirmatory Order result of an Institute ADR mediation EA-20-110 TTL Associates Materials 12/03/2020 (2) SLIII/NOV EA-20-066 NAC International Non-licensee 12/21/2020 SLIII/NOV/SLIV APPENDICES l 139
APPENDIX W FUNDAMENTAL LAWS GOVERNING THE U.S. NUCLEAR REGULATORY COMMISSION
- 1. Atomic Energy Act of 1954, as amended (Pub. L.83-703)
- 2. Energy Reorganization Act of 1974, as amended (Pub. L.93-438)
- 3. Reorganization Plan No. 1 of 1980 (5 U.S.C., App. 1) 4. Uranium Mill Tailings Radiation Control Act of 1978, as amended (Pub. L.95-604)
- 5. Nuclear Non-Proliferation Act of 1978 (Pub. L.95-242)
- 6. Nuclear Waste Policy Act of 1982, as amended (Pub. L.97-425)
- 8. Low-Level Radioactive Waste Policy Amendments Act of 1985 (Pub. L.99-240)
- 9. Energy Policy Act of 1992 (Pub. L. 102-486)
- 10. Energy Policy Act of 2005 (Pub. L. 109-58)
- 11. Nuclear Energy Innovation and Modernization Act (Pub. L. 115-439)
Fundamental Laws Governing Civilian Uses of Radioactive Materials Nuclear Materials and Facilities
- 1. Atomic Energy Act of 1954, as amended
- 2. Energy Reorganization Act of 1974, as amended
- 3. Reorganization Plan No. 1 of 1980 Radioactive Waste
- 1. Nuclear Waste Policy Act of 1982, as amended
- 2. Low-Level Radioactive Waste Policy Amendments Act of 1985
- 3. Uranium Mill Tailings Radiation Control Act of 1978, as amended Nonproliferation 1. Nuclear Non-Proliferation Act of 1978 Fundamental Laws Governing the Processes of Regulatory Agencies
- 1. Administrative Procedure Act (5 U.S.C. Chapter 5, Subchapter II, and Chapter 7)
- 2. National Environmental Policy Act of 1969, as amended (42 U.S.C Chapter 55, Subchapters I and II)
- 3. National Historic Preservation Act as amended (54 U.S.C. Subtitle III, Division A) 140 l APPENDICES
APPENDIX X International Activities:
CONVENTIONS AND TREATIES PERTAINING TO NUCLEAR SAFETY, SECURITY, AND INTERNATIONAL SAFEGUARDS*
- 1. Treaty on the Non-Proliferation of Nuclear Weapons, entry into force on March 5, 1970; the United States is a party to the Treaty
- 2. Convention on Early Notification of a Nuclear Accident, entry into force October 27, 1986; the United States is a party
- 3. Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, entry into force February 26, 1987; the United States is a party
- 4. Convention on Nuclear Safety, entry into force October 24, 1996; the United States is a party
- 5. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, entry into force June 18, 2001; the United States is a party
- 6. Convention on the Physical Protection of Nuclear Material (CPPNM), entry into force February 8, 1987; the United States is a party
- 7. Amendment to the CPPNM, entry into force May 8, 2016; the United States is a party
- 8. Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, entry into force August 30, 1975; the United States is a party (also to amendments in 1978 (incineration), 1978 (disputes),
1980 (list of substances), 1989 (procedures), 1993 (banning dumping of low-level radioactive wastes into the sea), 1996 (protocol to replace the 1972 Convention with a more restrictive text regulating the use of the sea as a depository for waste materials)
- 9. Convention on Supplementary Compensation for Nuclear Damage; entry into force April 15, 2015
- 10. Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States of America (INFCIRC/288); entry into force December 9, 1980
- 11. Agreement Between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in Connection with the Treaty for the Prohibition of Nuclear Weapons in Latin America (INFCIRC/366); entry into force April 6, 1989; the United States is a party
- 12. Protocol Additional to the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States of America (INFCIRC/288/Add. 1); entry into force January 6, 2009
- This excludes arms control agreements.
Note: Data are current as of August 2021; the next printed update will be in September 2022.
APPENDICES l 141
APPENDIX Y International Activities:
LIST OF MULTILATERAL ORGANIZATIONS, COMMITTEES, AND WORKING GROUPS IN WHICH THE NRC PARTICIPATES International Commission on Radiological Protection (ICRP)
International Atomic Energy Agency (IAEA)
Commission on Safety Standards (CSS)
Emergency Preparedness and Response Standards Committee (EPReSC)
IAEA Global Nuclear Safety and Security Network Steering Committee (GNSSN)
International Nuclear and Radiological Event Scale (INES) Advisory Committee Nuclear Safety Standards Committee (NUSSC)
Nuclear Security Guidance Committee (NSGC)
Radiation Safety Standards Committee (RASSC)
Regulatory Cooperation Forum Steering Committee (RCF)
Transport Safety Standards Committee (TRANSSC)
Waste Safety Standards Committee (WASSC)
Source: http://www-ns.iaea.org/committees/
Organisation for Economic Co-operation and Development (OECD)
Nuclear Energy Agency (NEA)
Steering Committee for Nuclear Energy The Committee on the Safety of Nuclear Installations (CSNI)
The Committee on Nuclear Regulatory Activities (CNRA)
The Radioactive Waste Management Committee (RWMC)
The Committee on Decommissioning of Nuclear Installations and Legacy Management (CDLM)
The Committee on Radiation Protection and Public Health (CRPPH)
The Nuclear Law Committee (NLC)
Multinational Design Evaluation Programme (MDEP)
Nuclear Science Committee (NSC)
Source: https://www.oecd-nea.org/general/about/
United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR)
Source: https://www.unscear.org/
142 l APPENDICES
APPENDIX Y International Activities: (continued)
NRC'S BILATERAL INFORMATION EXCHANGE AND COOPERATION AGREEMENTS Agreement Country Argentina France Morocco Switzerland Armenia Georgia Netherlands TECRO (Taiwan)
Australia Germany Nigeria Thailand Belgium Ghana Peru Turkey Brazil Greece Poland Ukraine Bulgaria Hungary Republic of Korea United Arab Emirates Canada India Romania United Kingdom China Indonesia Singapore Vietnam Colombia Israel Slovakia EURATOM Croatia Italy Slovenia Czech Republic Japan South Africa Ethiopia Lithuania Spain Finland Mexico Sweden Notes: The countrys short-form name is used. The NRCs cooperation arrangements are initiated and renewed for 5-year terms.
Data are current as of August 2021; the next printed update will be in September 2022.
EURATOM is the European Atomic Energy Community.
Tecro (Taiwan) is the Taipei Economic and Cultural Representative Office in the United States.
APPENDICES l 143
APPENDIX Z International Activities:
LIST OF IMPORT AND EXPORT LICENSES ISSUED FOR 2020: APPENDIX P License Number Applicant Docket Number PXB11b.14 QSA Global, Inc. 11006092 PXB11a.04 QSA Global, Inc. 11006386 PXB12.04 QSA Global, Inc. 11006073 PXB139.05 Schlumberger Technology Corporation 11006082 PXB190a.02 International Isotopes Inc. 11006160 PXB217.01 Halliburton Energy Services, Inc. 11006287 PXB220.01 Baker Hughes Oilfield Operations, Inc. 11006304 PXB224.01 ISOFLEX Radioactive, LLC 11006318 PXB3.11 Nordion (Canada) Inc. 11006070 PXB6.30 Alpha-Omega Services, Inc. 11006027 PXB6.31 Alpha-Omega Services, Inc. 11006027 PXB6.32 Alpha-Omega Services, Inc. 11006027 PXB6.33 Alpha-Omega Services, Inc. 11006027 PXB6.34 Alpha-Omega Services, Inc. 11006027 Licenses under Appendix P to 10 CFR Part 110,Export and import of nuclear equipment and material, support the use of radioactive sealed sources for a variety of medical, industrial, research, and educational activities. Some applicants have previously obtained a combined export/import license to allow export and import of U.S-origin sources for return back to the U.S. supplier after the source has been used. These combined licenses are no longer being issued and can no longer be amended going forward, because such imports are authorized under a general license (see 10 CFR 110.27, General license for imports, and paragraph (1) under the definition of Radioactive Waste in 10 CFR 110.2). These combined import/export licenses needing amendment are converted to export-only licenses. The 2010 changes to 10 CFR Part 110 generally necessitate specific licenses for only Appendix P Category 1 and 2 exports.
144 l APPENDICES
APPENDIX Z International Activities: (continued)
LIST OF IMPORT AND EXPORT LICENSES FOR 2020: NON-APPENDIX P License Number Applicant Docket Number XB1343 Sanders Medical Products, Inc. 11006364 XCOM1291/02 Eaton Corporation 11006180 XCOM1299/02 ATI Specialty Alloys %26 Components 11006218 XCOM1310/01 Curtiss-Wright Corporation, Curtiss-Wright Nuclear Division 11006263 XCOM1328/01 Mirion Technologies (IST) Corporation 11006346 XCOM1329 Curtiss-Wright Flow Control Services LLC 11006355 XCOM1332 Curtiss-Wright Electro-Mechanical Corp 11006370 XCOM1333 Curtiss-Wright Flow Control Corporation 11006374 XCOM1335 Materion Brush, Inc. 11006389 XMAT409/02 Cambridge Isotope Laboratories Inc. 11005753 XMAT418/03 Sigma Aldrich Co. LLC 11005977 XMAT427/03 Airgas Specialty Gases 11006088 XMAT429/03 Matheson Tri Gas, Inc. 11006116 XMAT433/03 Cambridge Isotope Laboratories, Inc. 11006181 XMAT433/04 Cambridge Isotope Laboratories Inc. 11006181 XMAT441/01 Cambridge Isotope Laboratories, Inc. 11006293 XMAT441/02 Cambridge Isotope Laboratories Inc. 11006293 XMAT448/01 Cambridge Isotope Laboratories, Inc. 11006349 XMAT448/02 Cambridge Isotope Laboratories Inc. 11006349 XMAT453 Cambridge Isotope Laboratories, Inc. 11006365 XMAT455 Cambridge Isotope Laboratories, Inc. 11006378 XSNM3398/06 Global Nuclaer Fuel - Americas, LLC 11005555 XSNM3702/01 Westinghouse Electric Company, LLC 11005968 XSNM3747/04 Framatome Inc. 11006110 XSNM3763/04 Edlow International Co. as Agent for ANSTO 11006195 XSNM3799/01 Exelon Generation Company, LLC 11006329 XSNM3809 TN Americas LLC 11006358 XSNM3810 U.S. Department of Energy, National Nuclear Security Administration 11006361 XSNM3811 TAM International Inc. 11006373 XSNM3812 Edlow International Co. as Agent for NNSA 11006376 XSNM3812/01 Edlow International Co.. 11006376 XSNM3813 NBL Program Office, US Dept of Energy 11006379 XSNM3814 TN Americas LLC 11006385 XSNM3815 TAM International Inc. 11006392 XSNM3816 ALARA Logistics 11006393 XSNM3817 TAM International (US) Inc. 11006394 XSOU8707/07 MP Mine Operations LLC 11004455 XSOU8827/02 MP Mine Operations LLC 11005966 APPENDICES l 145
APPENDIX Z International Activities: (continued)
LIST OF IMPORT AND EXPORT LICENSES FOR 2020: NON-APPENDIX P (continued)
License Number Applicant Docket Number XSOU8838/01 TAM International Inc. 11006194 XSOU8840/01 Iluka Resources Inc. 11006220 XSOU8842/01 The Chemours Company FC, LLC. (Chemours) 11006256 XSOU8842/02 The Chemours Company FC, LLC. (Chemours) 11006256 XSOU8851/02 Honeywell International, Inc. 11006336 XSOU8852 Manufacturing Sciences Corp. 11006372 XSOU8853 Twin Pines Minerals; LLC 11006387 XSOU8854 Iluka Resources Inc. 11006399 XW027 Perma-Fix Northwest Richland, Inc. 11006380 Non-Appendix P Components Guide (XSNM) denotes export of special nuclear material (plutonium, other than special nuclear material, or certain ores uranium-233, or uranium enriched above 0.711 percent, by [e.g., tantalum and niobium that contain, by weight, weight, in the isotope uranium-235). 0.05 percent or more of the aforementioned materials for non-(XCOM) denotes export of minor reactor components or other nuclear end use]).
nuclear facility (e.g., nuclear fabrication) components under NRC (XB) denotes export of byproduct material; refer to jurisdiction (refer to 10 CFR Part 110, Appendix A, Items (5)-(9), 10 CFR Part 110, Appendix L, for an illustrative list of byproduct for minor reactor components and materials under NRC jurisdiction.
Appendices B-K and N-O for other nuclear facility components). (XR) denotes export of reactor equipment, refer to (XSOU) denotes export of source material (natural or depleted 10 CFR Part 110, Appendix A, Items (1)-(4).
uranium, thorium, a mixture of uranium and thorium (IW) denotes import of radioactive waste.
(XW) denotes export of radioactive waste.
146 l APPENDICES
APPENDIX AA List of Some Major Uses of Radioisotopes in the United States Radioisotope is an unstable isotope of an element that decays or disintegrates spontaneously, thereby emitting radiation.
Approximately 5,000 natural and artificial radioisotopes have been identified. Radioisotopes come from three sources: from nature, such as radon in the air or radium in the soil; from machine-produced nuclear interactions in devices, such as linear accelerators and cyclotrons; or from nuclear reactors.
The licensing and regulation of radioisotopes in the United States are shared by the NRC, the U.S. Environmental Protection Agency (EPA), and many State governments. The EPA is also responsible for, among other things, setting air emission and drinking water standards for radionuclides. The States regulate radioactive substances that occur naturally or are produced by machines, such as linear accelerators or cyclotrons. The Food and Drug Administration (FDA) regulates the manufacture and use of linear accelerators; the States regulate their operation.
Americium-241 Chromium-51 Used in many smoke detectors for homes and businesses; Used in research in red blood cell survival studies to measure levels of toxic lead in dried paint samples; to ensure uniform thickness in rolling processes like steel and Cobalt-57 paper production; and to help determine where oil wells Used as a tracer to diagnose pernicious anemia should be drilled.
Cobalt-60 Cadmium-109 Used to sterilize surgical instruments and to improve the Used to analyze metal alloys for checking stock, scrap safety and reliability of industrial fuel oil burners. Used in sorting. cancer treatment, food irradiation, gauges, and radiography.
Calcium-47 Curium-244 Important aid to biomedical researchers studying the Used in mining to analyze material excavated from pits and cellular functions and bone formation in mammals slurries from drilling operations.
Californium-252 Fluorine-18 Used to inspect airline luggage for hidden explosives; to Used for Positron Emission Imaging in medical diagnosis.
gauge the moisture content of soil in the road construction and building industries and to measure the moisture of Gallium-68 materials stored in soils. Used for Positron Emission Imaging in medical diagnosis Carbon-14 Iodine-123 Major research tool. Helps ensure potential new drugs are Widely used to diagnose thyroid disorders and other metabolized without forming harmful by-products. Used metabolic disorders including brain function.
in biological research, agriculture, pollution control, and archeology. Iodine-125 Major diagnostic tool used in clinical tests and to diagnose Cesium-137 thyroid disorders. Also used in biomedical research.
Used to measure correct patient dosages of radioactive pharmaceuticals; to measure and control the liquid flow Iodine-129 in oil pipelines; to tell researchers whether oil wells are Used to check some radioactivity counters in vitro plugged by sand; and to ensure the right fill level for diagnostic testing laboratories.
packages of food, drugs and other products. (The products in these packages do not become radioactive.)
APPENDICES l 147
Iodine-131 Radium-226 Used to treat thyroid disorders. Makes lighting rods more effective. ( The most common isotopes of radium are Ra-226 and Ra-228. Radium-226 is Iridium-192 part of the uranium decay series. Radium-228 and Ra-224 Used to test the integrity of pipeline welds, boilers and are part of the thorium decay series. All isotopes of radium aircraft parts and in brachytherapy/tumor irradiation. are radioactive. Radium decays to produce radon gas)
Iron-55 Selenium-75 Used to analyze electroplating solutions and to detect Used in protein studies in life science research.
the presence of sulphur in the air. Used in metabolism research. Sodium-24 Used to locate leaks in industrial pipe lines; and in oil well Krypton-85 studies.
Used in indicator lights in appliances such as clothes washers and dryers, stereos, and coffee makers; to gauge Strontium-85 the thickness of thin plastics and sheet metal, rubber, Used to study bone formation and metabolism.
textiles, and paper; and to measure dust and pollutant levels. Strontium-90 Used in survey meters by schools, the military and Lutecium-177 emergency management authorities. Also used in cigarette Used as part of radiopharmaceuticals for treatment of manufacturing sensors and medical treatment.
cancer.
Sulphur-35 Nickel-63 Used in genetics and molecular biology research.
Used to detect explosives, and in voltage regulators and current surge protectors in electronic devices, and in Technetium-99m electron capture detectors for gas chromatographs. The most widely used radioactive pharmaceutical for diagnostic studies in nuclear medicine. Different chemical Phosphorus-32 forms are used for brain, bone, liver, spleen and kidney Used in molecular biology and genetics research. imaging and also for blood flow studies.
Phosphorus-33 Thallium-201 Used in molecular biology and genetics research. Used in nuclear medicine for nuclear cardiology and tumor detection.
Plutonium-238 Has powered more than 20 NASA spacecraft since 1972. Thallium-204 (The most common radioisotopes of plutonium are Pu-238, Used to measure dust and pollutant levels on filter paper; Pu-239, and Pu-240.) and to gauge the thickness of plastics, sheet metal, rubber, textiles, and paper.
Polonium-210 Reduces the static charge in production of photographic Thorium-229 film and other materials. Helps fluorescent lights last longer.
Promethium-147 Thorium-232 Used in electric blanket thermo-statsand to gauge the As thoriated tungsten, used in electric arc welding rods in thickness of thin plastics, thin sheet metal, rubber, textile, construction, aircraft, petrochemical and food processing and paper. equipment industries.
Thorium-230 Provides coloring and fluorescence in colored glazes and glassware.
148 l APPENDICES
Tritium Source: NUREG/BR-0217 Rev. 1 APRIL 2000,The Regulation and Use of Radioisotopes in Todays World For more information visit the Major tool for biomedical research. Used for life science and following web pages:
drug metabolism studies to ensure the safety of potential EPA at https://www.epa.gov/radiation/radionuclides new drugs; for luminous exit signs; for luminous dials, FDA at https://www.fda.gov radiation-emitting-products gauges and wrist watches; to produce luminous paint; and National Nuclear Data Center at https://www.nndc.bnl.gov/
for geological prospecting and hydrology.
Uranium-235 Fuel for nuclear power plants and naval nuclear propulsion systems; previously used to produce fluorescent glassware, a variety of colored glazes and wall tiles.
Xenon-133 Used in nuclear medicine for lung ventilation and blood flow studies.
Yttrium-90 Used as microsphere brachytherapy for treatment of liver cancers.
RADIOACTIVE ELEMENTS Radioactive elements have no stable isotopes.
APPENDICES l 149
8 GLOSSARY
GLOSSARY (Includes Abbreviations, Definitions, and illustrations)
Advanced reactors Reactors that differ from todays reactors primarily by their use of inert gases, molten salt mixtures, or liquid metals to cool the reactor core. Advanced reactors can also consider fuel materials and designs that differ radically from todays enriched-uranium-dioxide pellets within zirconium cladding.
Agreement State A U.S. State that has signed an agreement with the U.S. Nuclear Regulatory Commission (NRC) authorizing the State to regulate certain uses of radioactive materials within the State.
Atomic energy The energy that is released through a nuclear reaction or radioactive decay pro-cess. One kind of nuclear reaction is fission, which occurs in a nuclear reactor and releases energy, usually in the form of heat and radiation. In a nuclear power plant, this heat is used to boil water to produce steam that can be used to drive large turbines. The turbines drive generators to produce electrical power.
NUCLEUS FRAGMENT NUCLEAR REACTION NUCLEUS NEW NEUTRON NEUTRON Background radiation The natural radiation that is always present in the environment. It includes cosmic radiation that comes from the sun and stars, terrestrial radiation that comes from the Earth, and internal radiation that exists in all living things and enters organisms by ingestion or inhalation. The typical average individual exposure in the United States from natural background sources is about 310 millirem (3.1 millisieverts) per year.
152 l GLOSSARY
Boiling-water reactor (BWR)
A nuclear reactor in which water is boiled using heat released from fission. The steam released by boiling then drives turbines and generators to produce electrical power. BWRs operate similarly to electrical plants using fossil fuel, except that the BWRs are heated by nuclear fission in the reactor core. Typical Boiling-Water Reactor Walls made of concrete and Containment steel Cooling System 3-5 feet thick (1-1.5 meters)
Steamline 4 Reactor Vessel Turbine Generator Separators
& Dryers Heater Feedwater Condenser 5 3 Condensate Pumps Core 1, 2 Feed Pumps Control Rods Demineralizer Recirculation Pumps Containment Emergency Water Structure Supply Systems How Nuclear Reactors Work In a typical design concept of a commercial BWR, the following process occurs:
- 1. The nuclear fuel core inside the reactor vessel creates heat from nuclear fission.
- 2. A steam-water mixture is produced when very pure water (reactor coolant) moves upward through the core, absorbing heat.
- 3. The steam-water mixture leaves the top of the core and enters the two stages of moisture separation where water droplets are removed before the steam is allowed to enter the steamline.
- 4. The steam is piped to the main turbine, causing it to turn the turbine generator, which produces electricity.
- 5. The steam is exhausted to the condenser, where it is condensed into water. The resulting water is pumped out of the condenser with a series of pumps and pumped back to the reactor vessel.
The reactors core contains fuel assemblies that are cooled by water circulated using electrically powered pumps. These pumps and other operating systems in the plant receive their power from the electrical grid. If offsite power is lost, cooling water is supplied by other pumps, which can be powered by onsite diesel generators or steam generated by the core. Other safety systems, such as the containment cooling system, also need electrical power. BWRs contain between 370-800 fuel assemblies.
GLOSSARY l 153
Brachytherapy A medical procedure during which a sealed radioactive source (or sources) is implanted directly into a person being treated for cancer (usually of the mouth, breast, lung, prostate, ovaries, or uterus). The radioactive implant may be temporary or permanent, and the radiation kills cells in the tumor as long as the device remains in place and emits radiation. Brachytherapy uses radioisotopes, such as iridium-192 or iodine-125, which are regulated by the NRC and Agreement States.
Byproduct material As defined by NRC regulations, byproduct material includes any radioactive material (except enriched uranium or plutonium) produced by a nuclear reactor or through the use of a particle accelerator, or any discrete source of radium-226 used for a commercial, medical, or research activity. It also includes the tailings or wastes produced by the extraction or concentration of uranium or thorium or the fabrication of fuel for nuclear reactors. In addition, the NRC, in consultation with the U.S. Environmental Protection Agency, U.S. Department of Energy (DOE),
U.S. Department of Homeland Security, and others, can designate as byproduct material any source of naturally occurring radioactive material, other than source material, that it determines would pose a threat to public health and safety or the common defense and security of the United States.
Canister See Dry cask storage.
Capability The maximum load that a generating unit, generating station, or other electrical apparatus can carry under specified conditions for a given period of time without exceeding approved limits of temperature and stress.
Capacity The amount of electric power that a generator, turbine, transformer, transmission, circuit, or system is able to produce, as rated by the manufacturer.
Capacity factor The ratio of the available capacity (the amount of electrical power actually produced by a generating unit) to the theoretical capacity (the amount of electrical power that could theoretically have been produced if the generating unit had operated continuously at full power) during a given time period.
Capacity utilization A percentage that a generating unit fulfilled its capacity in generating electric power over a given time period. This percentage is defined as the margin between the units available capacity (the amount of electrical power the unit actually produced) and its theoretical capacity (the amount of electrical power that could have been produced if the unit had operated continuously at full power) during a certain time period. Capacity utilization is computed by dividing the amount of power actually produced by the theoretical capacity and multiplying by 100.
Cask A heavily shielded container used for the dry storage or shipment (or both) of radioactive materials such as spent nuclear fuel or other high-level radioactive waste (HLW). Casks are often made from lead, concrete, or steel. Casks must meet regulatory requirements.
154 l GLOSSARY
Categories of radiation sources The International Atomic Energy Agencys Code of Conduct on the Safety and Security of Radioactive Sources defines the five categories for radiation sources to help ensure that sufficient controls are being used to achieve safety and security:
Category 1 sources, if not safely or securely managed, would be likely to cause permanent injury to a person who handled them or was otherwise in contact with them for more than a few minutes. It would probably be fatal to be close to this amount of unshielded material for a period of a few minutes to an hour. These sources are typically used in radiothermal generators, irradiators, and radiation teletherapy.
Category 2 sources, if not safely or securely managed, could cause permanent injury to a person who handled them or was otherwise in contact with them for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in industrial gamma radiography, high- and medium-dose-rate brachytherapy, and radiography devices.
Category 3 sources, if not safely or securely managed, could cause permanent injury to a person who handled them or was otherwise in contact with them for hours. It could possiblyalthough it is unlikely tobe fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in fixed industrial gauges such as level gauges, dredger gauges, conveyor gauges, spinning pipe gauges, and well-logging gauges.
Category 4 sources, if not safely managed or securely protected, could possibly cause temporary injury to someone who handled them or was otherwise in contact with or close to them for a period of many weeks, though this is unlikely. It is very unlikely anyone would be permanently injured by this amount of radioactive material. These sources are typically used in fixed or portable gauges, static eliminators, or low-dose brachytherapy.
Category 5 sources cannot cause permanent injury. They are used in x-ray fluorescence devices and electron capture devices.
Only Categories 1 and 2 for radiation sources are defined by NRC requirements.
Categories of special nuclear material The NRC groups special nuclear materials and the facilities that possess them into three categories based upon the materials potential for use in nuclear weapons or their strategic significance:
Category I, high strategic significance Category II, moderate strategic significance Category III, low strategic significance The NRCs physical security and safeguards requirements differ by category, with Category I facilities subject to more stringent requirements because they pose greater security and safeguards risks.
Classified information Information that has been determined pursuant to an Executive order to require protection against unauthorized disclosure and is marked to indicate its classified status when in documentary form. The NRC has two types of classified information. The first type, known as National Security Information, is information that is classified by an Executive order. Its release would damage national security. The second type, known as Restricted Data, would assist individuals or organizations in designing, manufacturing, or using nuclear weapons. Access to both types of information is restricted to authorized persons who have been properly cleared and have a need to know the information to accomplish their official duties.
Combined license (COL)
An NRC-issued license that authorizes a licensee to construct and (with certain specified conditions) operate a nuclear power facility, such as a nuclear plant at a specific site.
GLOSSARY l 155
Commercial irradiator A facility that uses high doses of radiation to sterilize or treat products, such as food and spices, medical supplies, and wood flooring. Irradiation can be used to eliminate harmful bacteria, germs, Commercial Irradiator and insects or for hardening or other purposes. The radiation does not leave radioactive residue or make the treated products radioactive. Radiation sources include radioactive materials (e.g.,
cobalt-60), an x-ray machine, or an electron beam.
Radiation Unloading Processed Photo courtesy: Nordion Shield Product Irradiation Room Conveyor System Loading Control Console Storage Pool Radiation Source Compact A group of two or more U.S. States that have formed alliances to dispose of low-level radioactive waste (LLW).
Source: U.S. Nuclear Regulatory Commission Construction recapture The maximum number of years that could be added to a nuclear power plants license expiration date to recapture the period between the date the NRC issued the plants construction permit and the date it granted an operating license. A licensee must submit an application to request this extension.
Containment structure A resilient gas-tight shell or other enclosure around a nuclear reactor to confine fission products that otherwise might be released to the atmosphere in the event of a severe reactor accident. Such enclosures are usually dome shaped and made of steel-reinforced concrete.
Contamination Undesirable radiological or chemical material (with a potentially harmful effect) that is either airborne or deposited in (or on the surface of) structures, objects, soil, water, or living organisms.
Criticality The condition involving fission of nuclear materials when the number of neutrons produced equals or exceeds the nuclear containment. During normal reactor operations, nuclear fuel sustains a fission chain reaction or criticality. A reactor achieves criticality (and is said to be critical) when each fission event releases a sufficient number of neutrons to sustain an ongoing series of reactions.
156 l GLOSSARY
Decommissioning The process of safely closing a nuclear power plant (or other facility where nuclear materials are handled) to retire it from service after its useful life has ended. This process primarily involves decontaminating the facility to reduce residual radioactivity and then releasing the property for unrestricted or (under certain conditions) restricted use. This often includes dismantling the facility or dedicating it to other purposes. See SAFSTOR.
DECON A phase of reactor decommissioning in which structures, systems, and components that contain radioactive contamination are removed from a site and safely disposed of at a commercially operated low-level waste disposal facility or decontaminated to a level that permits the site to be released for unrestricted use.
Decontamination A process used to reduce, remove, or neutralize radiological or chemical contamination to reduce the risk of exposure. Decontamination may be accomplished by cleaning or treating surfaces to reduce or remove the contamination, filtering contaminated air or water, or subjecting contamination to evaporation and precipitation. The process can also simply allow adequate time for radioactive decay to decrease the radioactivity.
Defense in depth An approach to designing and operating nuclear facilities that prevents or mitigates accidents or attacks that could result in release of radiation or hazardous materials. The key is creating multiple independent and redundant layers of controls or design features to compensate for potential human and mechanical failures so that no single control, no matter how robust, is exclusively relied upon to achieve safety or security. Defense in depth includes the use of access controls, physical barriers, redundant and diverse key safety functions, and emergency response measures.
Depleted uranium Uranium with a percentage of uranium-235 lower than the 0.7 percent (by mass) contained in natural uranium. Depleted uranium is the byproduct of the uranium enrichment process. Depleted uranium can be blended with highly enriched uranium, such as that from weapons, to make reactor fuel.
Design-basis threat (DBT)
A description of the type, composition, and capabilities of an adversary, against which a security system is designed to protect. The NRC uses the DBT as a basis for designing safeguards systems to protect against acts of radiological sabotage and to prevent the theft of special nuclear material. Certain nuclear facility licensees are required to defend against the DBT.
Design certification Certification and approval by the NRC of a standard nuclear power plant design independent of a specific site or an application to construct or operate a plant. A design certification is valid for 15 years from the date of issuance but can be renewed for an additional 10 to 15 years.
Dose (radiation)
The National Council on Radiation Protection and Measurements estimates that an average person in the United States receives a total annual dose of about 0.62 rem (620 millirem or 6.2 millisieverts) from all radiation sources, a level that has not been shown to cause humans any harm. Of this total, natural background sources of radiationincluding radon and thoron gas, natural radiation from soil and rocks, radiation from space, and radiation sources that are found naturally within the human bodyaccount for about 50 percent. Medical procedures such as computed tomography (CT) scans and nuclear medicine account for about another 48 percent.
Other small contributors of exposure to the U.S. population include consumer products and activities, industrial and research uses, and occupational tasks. The maximum permissible yearly dose for a person working with or around nuclear material is 5 rem (50 millisieverts).
GLOSSARY l 157
Dry cask storage A method for storing spent nuclear fuel in special containers known as dry casks. After fuel has been cooled in a spent fuel pool, dry cask storage allows spent fuel assemblies to be sealed in casks and surrounded by inert gas. They are welded or bolted closed, and each cask includes steel, concrete, lead, or other material to provide leak-tight containment and radiation shielding.
The casks may store fuel horizontally or vertically.
Early site permit (ESP)
A permit granted by the NRC to approve one or more proposed sites for a nuclear power facility, independent of a specific nuclear plant design or an application for a construction permit or combined license. An ESP is valid for 10 to 20 years but can be renewed for an additional 10 to 20 years.
Efficiency, plant The percentage of the total energy content of a power plants thermal energy that is converted into electricity. The remaining energy is lost to the environment as heat.
Electric power grid A system of synchronized power providers and consumers, connected by transmission and distribution lines and operated by one or more control centers. In the continental United States, the electric power grid consists of three systems the Eastern Interconnect, the Western Interconnect, and the Texas Interconnect. In Alaska and Hawaii, several systems encompass areas smaller than the State.
Electric utility A corporation, agency, authority, person, or other legal entity that owns or operates facilities within the United States, its territories, or Puerto Rico for the generation, transmission, distribution, or sale of electric power (primarily for use by the public). Facilities that qualify as cogenerators or small power producers under the Public Utility Regulatory Policies Act of 1978 are not considered electric utilities.
Emergency classifications Sets of plant conditions that indicate various levels of risk to the public and that might require response by an offsite emergency response organization to protect citizens near the site. The four emergency classification levels used for commercial nuclear power plants, in ascending order of severity, are: Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency.
Emergency Notification System A telephone system used by the NRC to receive notifications of significant nuclear events with an actual or potential effect on the health and safety of the public and the environment. Significant events are reported to the NRC by licensees, Agreement States, other Federal agencies, the public, and other countries.
The programs, plans, training, exercises, and resources used to prepare for and rapidly identify, evaluate, and respond to emergencies, including those arising from terrorism or natural events such as hurricanes. EP strives to ensure that operators of nuclear power plants and certain fuel cycle facilities can implement measures to protect public health and safety in the event of a radiological emergency. Licensees that operate certain nuclear facilities, such as nuclear power plants, must develop and maintain EP plans that meet NRC requirements.
158 l GLOSSARY
Energy Information Administration (EIA)
The agency within DOE that provides policy-neutral statistical data, forecasts, and analyses to promote sound policymaking, efficient markets, and public understanding about energy and its interaction with the economy and the environment.
Enrichment See Uranium enrichment process.
Exposure (radiation)
Absorption of ionizing radiation or the amount of a hazardous substance that has been ingested, inhaled, or in contact with the skin. Acute exposure occurs over a short period of time. Chronic exposure is exposure received over a long period of time, such as during a lifetime. See Occupational dose.
Federal Emergency Management Agency (FEMA)
A component of the U.S. Department of Homeland Security responsible for protecting the Nation and reducing the loss of life and property from all hazards such as natural disasters and acts of terrorism. FEMA leads and supports a risk-based, comprehensive emergency management system of preparedness, protection, response, recovery, and mitigation.
Federal Energy Regulatory Commission (FERC)
An independent agency that regulates the interstate transmission of electricity, natural gas, and oil. FERC also regulates and oversees hydropower projects and the construction of liquefied natural gas terminals and interstate natural gas pipelines. FERC protects the economic, environmental, and safety interests of the American public, while working to ensure abundant, reliable energy in a fair, competitive market.
Fiscal year (FY)
The 12-month period from October 1 through September 30 used by the Federal Government for budget formulation and execution. The FY is designated by the calendar year in which it ends; for example, FY 2019 runs from October 1, 2018, through September 30, 2019.
Fissile material A nuclide that is capable of undergoing fission after capturing neutrons. Although sometimes used as a synonym for fissionable material, this term has acquired its more restrictive interpretation with the limitation that the nuclide must be fissionable by thermal neutrons.
With that interpretation, the three primary fissile materials are uranium-233, uranium-235, and plutonium-239. This definition excludes natural uranium and depleted uranium that have not been irradiated or have only been irradiated in thermal reactors.
Fission The splitting of an atom, which releases a considerable amount of energy (usually in the form of heat). Fission may be spontaneous but is usually caused by the nucleus of an atom becoming unstable (or heavy) after capturing or absorbing a neutron. During fission, the nucleus splits into roughly equal parts, producing the nuclei of at least two lighter elements. In addition to energy, this reaction usually releases gamma radiation and two or more daughter neutrons.
Force-on-force A type of security exercise designed to evaluate and improve the effectiveness of a security system. For the NRC, force-on-force exercises are used to assess the ability of the licensee to defend a nuclear power plant and other nuclear facilities against a design-basis threat.
GLOSSARY l 159
Foreign Assignee Program A personnel exchange program for foreign regulatory counterparts. This helps the NRC and partners better understand each others regulatory programs, capabilities, and commitments and fosters relationships between the NRC and key officials in other countries. The assignees regulatory authorities generally identify the individuals participating and pay their salaries.
Freedom of Information Act (FOIA)
A Federal law that requires Federal agencies to provide, upon written request, access to records or information. Some material is exempt from FOIA, and FOIA does not apply to records that are maintained by State and local governments, Federal contractors, grantees, or private organizations or businesses.
Fuel assembly (fuel bundle, fuel element)
A structured group of fuel rods (long, slender, metal tubes containing pellets of fissionable material, which provide fuel for nuclear reactors). Depending on the design, each reactor core may have dozens of fuel assemblies (also known as fuel bundles), each of which contains dozens of fuel rods.
Fuel Rod Uranium Fuel Pellet Fuel assembly Spent fuel assemblies are typically 14 feet (4.3 meters) long and contain nearly 200 fuel rods for PWRs and 80-100 fuel rods for BWRs.
Fuel cycle The series of steps involved in supplying fuel for nuclear power reactors. The uranium fuel cycle includes the following:
uranium recovery to extract and concentrate the uranium to produce yellowcake conversion of yellowcake into uranium hexafluoride (UF6) enrichment to increase the concentration of uranium in UF6 fuel fabrication to convert enriched UF6 into fuel for nuclear reactors use of the fuel in reactors (nuclear power research or naval propulsion) interim storage of spent nuclear fuel reprocessing of spent fuel to recover the fissionable material remaining in the spent fuel (currently not done in the United States)
"nal disposition of high-level radioactive waste (HLW) transportation of the uranium in all forms, including spent fuel The NRC regulates these processes.
160 l GLOSSARY
Fuel reprocessing (recycling)
The processing of reactor fuel to separate the unused fissionable material from waste material.
Reprocessing extracts uranium and plutonium from spent nuclear fuel so they can be used again as reactor fuel. Commercial reprocessing is not practiced in the United States, although it has been in the past. However, DOE operates reprocessing facilities at Hanford, WA, and Savannah River, SC, for national defense purposes.
Fuel rod A long, slender, zirconium metal tube containing pellets of fissionable material, which provide fuel for nuclear reactors. Fuel rods are assembled into bundles called fuel assemblies, which are loaded individually into the reactor core.
Full-time equivalent A human resources measurement equal to one person working full time for 1 year.
Gas centrifuge Uranium enrichment technology that uses many rotating cylinders that are connected in long lines to increase the concentration of uranium-235. Gas is placed in the cylinder, which spins at a high speed, creating a strong centrifugal force. Heavier gas molecules move to the cylinder wall, while lighter molecules collect near the center. The stream, slightly enriched, is fed into the next cylinder. The depleted stream is recycled back into the previous cylinder.
Gas chromatography An analytical technique for separating chemical substances from a mixed sample by passing the sample, carried by a moving stream of gas, through a tube packed with a finely divided solid that may be coated with a liquid film. Gas chromatography devices are used to analyze air pollutants, blood alcohol content, essential oils, and food products.
Gauging devices Devices used to measure, monitor, and control the thickness of sheet metal, textiles, paper napkins, newspaper, plastics, photographic film, and other products as they are manufactured.
Gauges mounted in fixed locations are designed for measuring or controlling material density, flow, level, thickness, or weight. The gauges contain sealed sources that radiate through the substance being measured to a readout or controlling device. Portable gauging devices, such as moisture density gauges, are used at field locations. These gauges contain a gamma-emitting sealed source, usually cesium-137, or a sealed neutron source, usually americium-241 and beryllium.
Moisture Density Gauge Cross-Section of Fixed Fluid Gauge Material Detector Flow Shutter Control Shielding Bioshield Gauge Surface Detectors Depth Radiation Shutter Source Pipe Source GLOSSARY l 161
Generation (gross)
The total amount of electric energy produced by a power generating station, as measured at the generator terminals.
Generation (net)
The gross amount of electric energy produced by a generating station, minus the amount used to operate the station. Net generation is usually measured in watt-hours.
Generator capacity The maximum amount of electric energy that a generator can produce (from the mechanical energy of the turbine), adjusted for ambient conditions. Generator capacity is commonly expressed in megawatts.
Geological repository An excavated, underground facility that is designed, constructed, and operated for safe and secure permanent disposal of HLW. A geological repository uses an engineered barrier system and a portion of the sites natural geology, hydrology, and geochemical systems to isolate the radioactivity of the waste.
Gigawatt (GW)
A unit of power equivalent to one billion (1,000,000,000) watts.
Gigawatt-hour (GWh)
One billion (1,000,000,000) watt-hours.
Grid See Electric power grid.
Half-life (radiological)
The time required for half the atoms of a particular radioactive material to decay. A specific half-life is a characteristic property of each radioisotope. Measured half-lives range from millionths of a second to billions of years, depending on the stability of the nucleus. Radiological half-life is related to, but different from, biological half-life and effective half-life.
Health physics The science concerned with recognizing and evaluating the effects of ionizing radiation on the health and safety of people and the environment, monitoring radiation exposure, and controlling the associated health risks and The Heap Leach Uranium Recovery Process environmental hazards to permit the Acid Drip safe use of technologies that produce Heap ionizing radiation. Liner System Acid Recirculation Heap leach recovery process A method for extracting uranium Slope Drying from ore. The ore is placed in piles or heaps on top of liners. The liners Dried prevent uranium and other chemicals Collection Basin ip pe d Yellow-from moving into the ground. Sulfuric Str cake d
acid is dripped onto the heap and cte tra Ex dissolves uranium as it moves through Processing tra t-en the ore. Uranium solution drains into Plant C on c
collection basins, where it is piped to a ed processing plant. At the plant, uranium is extracted, concentrated, and dried G
to form yellowcake. S IN C ES T
PPRLOAN 162 l GLOSSARY
High-level radioactive waste (HLW)
The highly radioactive materials produced as byproducts of fuel reprocessing or of the reactions that occur inside nuclear reactors. HLW includes the following:
irradiated spent nuclear fuel discharged from commercial nuclear power reactors highly radioactive liquid and solid materials resulting from the reprocessing of spent nuclear fuel, which contains fission products in concentration, including some reprocessed HLW from defense activities and a small quantity of reprocessed commercial HLW other highly radioactive materials that the Commission may determine require permanent isolation Highly (or high-) enriched uranium Uranium enriched to at least 20 percent uranium-235 (a higher concentration than exists in natural uranium ore).
In situ recovery (ISR)
A common method currently used to extract uranium from ore bodies without physical excavation of the ore. This technique is also known as solution mining or in situ leaching.
Incident response Activities that address the short-term, direct effects of a natural or human-caused event and require an emergency response to protect life or property.
Independent spent fuel storage installation (ISFSI)
A complex designed and constructed for the interim storage of spent nuclear fuel; solid, reactor-related, greater-than-Class-C waste; and other associated radioactive materials. A spent fuel storage facility may be considered independent even if it is located on the site of another NRC-licensed facility.
International Atomic Energy Agency (IAEA)
A United Nations agency established in 1957 to serve as a world center of cooperation in the nuclear field. The agency works with nearly 171 member States and multiple partners worldwide to promote safe, secure, and peaceful nuclear technology.
International Nuclear Regulators Association (INRA)
An association established in 1997 to give national nuclear regulators with mature civilian nuclear reactor and materials programs a forum to discuss nuclear safety and security issues of mutual interest. Canada, France, Germany, Japan, the Republic of Korea, Spain, Sweden, the United Kingdom, and the United States are members.
Irradiation Exposure to ionizing radiation. Irradiation may be intentional, such as in cancer treatments or in sterilizing medical instruments. Irradiation may also be accidental, such as from exposure to an unshielded source. Irradiation does not usually result in radioactive contamination, but damage can occur, depending on the dose received.
Isotope Two or more forms (or atomic configurations) of a given element that have identical atomic numbers (the same number of protons in their nuclei) and the same or very similar chemical properties but different atomic masses (different numbers of neutrons in their nuclei) and distinct physical properties. Thus, carbon-12, carbon-13, and carbon-14 are isotopes of the element carbon, and the numbers denote the approximate atomic masses. Among their distinct physical properties, some isotopes (known as radioisotopes) are radioactive, because their nuclei are unstable and emit radiation as they decay spontaneously toward a more stable nuclear configuration. For example, carbon-12 and carbon-13 are stable, but carbon-14 is unstable and radioactive.
GLOSSARY l 163
Kilowatt (kW)
A unit of power equivalent to 1,000 watts.
Licensed material Source material, byproduct material, or special nuclear material that is received, possessed, used, transferred, or disposed of under a general or specific license issued by the NRC or Agreement States and is not otherwise exempt from regulation.
Licensee A company, organization, institution, or other entity to which the NRC or an Agreement State has granted a general or specific license to construct or operate a nuclear facility, or to receive, possess, use, transfer, or dispose of source, byproduct, or special nuclear material.
Licensing basis The collection of documents or technical criteria that provides the basis upon which the NRC issues a license to construct or operate a nuclear facility; to conduct operations involving the emission of radiation; or to receive, possess, use, transfer, or dispose of source, byproduct, or special nuclear material.
Licensing Support Network (LSN) Library A library providing access to publicly available documents related to the hearings regarding DOEs application for authorization to construct a high-level nuclear waste geologic repository at Yucca Mountain, NV. The LSN Library is affiliated with the Agencywide Documents Access and Management System (ADAMS), the agencys official recordkeeping system.
Light-water reactor A term used to describe reactors using ordinary water as a moderated coolant, including boiling-water reactors (BWRs) and pressurized-water reactors (PWRs), the most common types used in the United States.
Low-level radioactive waste (LLW)
A general term for a wide range of waste that is contaminated with radioactive material or has become radioactive through exposure to neutron radiation. A variety of industries, hospitals and medical institutions, educational and research institutions, private or government laboratories, and nuclear fuel cycle facilities generate LLW. Some examples include radioactively contaminated protective shoe covers and clothing; cleaning rags, mops, filters, and reactor water treatment residues; equipment and tools; medical tubes, swabs, and hypodermic syringes; and carcasses and tissues from laboratory animals.
Loss-of-coolant accident (LOCA)
A potential accident in which a breach in a reactors pressure boundary causes the coolant water to rush out of the reactor faster than makeup water can be added back in. Without sufficient coolant, the reactor core could heat up and potentially melt the zirconium fuel cladding, causing a major release of radioactivity.
Megawatt (MW)
A unit of power equivalent to 1,000,000 watts.
Megawatt-hour (MWh)
A unit of energy equivalent to 1,000 kilowatts of electricity used continuously for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Metric ton A unit of measurement equivalent to 1,000 kilograms or about 2,000 pounds.
164 l GLOSSARY
Mill tailings Primarily, the solid residue from a conventional uranium recovery facility in which uranium or thorium ore is crushed and processed mechanically or chemically to recover the uranium, thorium, or other valuable materials. This naturally radioactive ore residue contains the radioactive decay products from the uranium chains (mainly the uranium-238 chain). Although the milling process recovers about 93 percent of the uranium, the tailings contain several naturally occurring radioactive elements, including uranium, thorium, radium, polonium, and radon, as well as heavy metals and other constituents.
Mixed-oxide (MOX) fuel A type of nuclear reactor fuel that contains plutonium oxide mixed with either natural or depleted uranium oxide, in ceramic pellet form. This differs from conventional nuclear fuel, which is made of uranium oxide. The U.S. Department of Energy program to produce an MOX fuel under an agreement with Russia was canceled in 2018. The NRC terminated the facilitys construction authorization in February 2019.
Monitoring of radiation Periodic or continuous determination of the amount of ionizing radiation or radioactive contamination in a region. Radiation monitoring is a safety measure to protect the health and safety of the public and the environment through the use of bioassay, alpha scans, and other radiological survey methods to monitor air, surface water and ground water, soil and sediment, equipment surfaces, and personnel.
National Environmental Policy Act (NEPA)
A U.S. environmental law enacted on January 1, 1970. The NRC implements NEPA as part of its regulatory process by evaluating the relevant environmental effects for particular actions. A typical review will include an analysis of impacts to air, water, animal life, vegetation, natural resources, and resources of historical, archaeological, or architectural significance. The review will also evaluate cumulative economic, social, cultural, and other impacts affecting environmental justice.
National Response Framework The guiding principles, roles, and structures that enable all domestic incident response partners to prepare for and provide a unified national response to disasters and emergencies. It describes how the Federal Government, States, Tribes, communities, and the private sector work together to coordinate a national response. The fourth edition of the framework, which became effective in October 2019, is built on the scalable, flexible and adaptable concepts identified in the National Incident Management System to align key roles and responsibilities.
National Source Tracking System (NSTS)
A secure, Web-based data system that helps the NRC and its Agreement States track and regulate the medical, industrial, and academic uses of certain nuclear materials, from the time they are manufactured or imported to the time of their disposal or exportation. This information enhances the ability of the NRC and Agreement States to conduct inspections and investigations, communicate information to other government agencies, and verify the ownership and use of nationally tracked sources.
Naturally Occurring and Accelerator-Produced Radioactive Material (NARM)
The Energy Policy Act of 2005 gives the NRC regulatory authority over NARM, which includes those materials that have been processed, or concentrated, for use in commercial, medical, or research activities, including contamination resulting from the use of these materials.
GLOSSARY l 165
Natural uranium Uranium containing the relative concentrations of isotopes found in nature: 0.7 percent uranium-235, 99.3 percent uranium-238, and a trace amount of uranium-234 by mass. In terms of radioactivity, however, natural uranium contains about 2.2 percent uranium-235, 48.6 percent uranium-238, and 49.2 percent uranium-234. Natural uranium can be used as fuel in nuclear reactors or as feedstock for uranium enrichment facilities.
Net electric generation The gross amount of electric energy produced by a generating station, minus the amount used to operate the station. Note: Electricity required for pumping at pumped-storage plants is regarded as electricity for station operation and is deducted from gross generation. Net electric generation is measured in watt-hours, except as otherwise noted.
Nonpower reactor (research and test reactor)
A nuclear reactor that is used for research, training, or development purposes (which may include producing radioisotopes for medical and industrial uses) but has no role in producing electrical power. These reactors, which are also known as research and test reactors, contribute to almost every field of science, including physics, chemistry, biology, medicine, geology, archaeology, and ecology.
NRC Headquarters Operations Center The primary center of communication and coordination among the NRC, its licensees, State and Tribal agencies, and other Federal agencies for operating events involving nuclear reactors or materials. Located in Rockville, MD, the Headquarters Operations Center is staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day by employees trained to receive and evaluate event reports and coordinate incident response activities.
Nuclear energy See Atomic energy.
Nuclear Energy Agency (NEA)
A specialized agency within the Organisation for Economic Co-operation and Development (OECD), which was created to assist its member countries in maintaining and further developing the scientific, technological, and legal bases for safe, environmentally friendly, and economical use of nuclear energy for peaceful purposes. The NEAs current membership consists of 33 countries in Europe, North America, and the Asia-Pacific region, which account for about 85 percent of the worlds installed nuclear capacity. The OECD is an intergovernmental organization, based in Paris, France, that provides a forum for discussion and cooperation among the governments of industrialized countries committed to democracy and the market economy.
Nuclear fuel Fissionable material that has been enriched to a composition that will support a self-sustaining fission chain reaction when used to fuel a nuclear reactor, thereby releasing energy (usually in the form of heat or useful radiation) for use in other processes.
Nuclear materials See Special nuclear material, Source material, and Byproduct material.
Nuclear Materials Management and Safeguards System (NMMSS)
A centralized U.S. Government database used to track and account for source and special nuclear material. The system contains current and historical data on the possession, use, and shipment of source and special nuclear material within the United States, as well as all exports and imports of such material. The database is jointly funded by the NRC and DOE and is operated under a DOE contract.
166 l GLOSSARY
Nuclear poison (or neutron poison)
In reactor physics, a substance (other than fissionable material) that has a large capacity for absorbing neutrons in the vicinity of the reactor core. This effect may be undesirable in some reactor applications, because it may prevent or disrupt the fission chain reaction, thereby affecting normal operation. However, neutron-absorbing materials (commonly known as poisons) are intentionally inserted into some types of reactors to decrease the reactivity of their initial fresh fuel load for fuel intended to achieve higher burnup levels during the fuel cycle. Adding poisons, such as control rods or boron, is described as adding negative reactivity to the reactor.
Nuclear power plant A thermal power plant, in which the energy (heat) released by the fissioning of nuclear fuel is used to boil water to produce steam. The steam spins the propeller-like blades of a turbine that turns the shaft of a generator to produce electricity. Of the various nuclear power plant designs, pressurized-water reactors and boiling-water reactors are in commercial operation in the United States. These facilities generate about 20 percent of U.S. electrical power.
Nuclear/Radiological Incident Annex An annex to the Response and Recovery Federal Interagency Operational Plans that provides for a timely, coordinated response by Federal agencies to nuclear or radiological accidents or incidents. This annex covers radiological dispersal devices and improvised nuclear devices, as well as incidents involving commercial reactors or weapons production facilities, lost radioactive sources, transportation accidents involving radioactive material, and international incidents involving nuclear or radioactive material.
Nuclear reactor The heart of a nuclear power plant or nonpower reactor, in which nuclear fission may be initiated and controlled in a self-sustaining chain reaction to generate energy or produce useful radiation.
Although there are many types of nuclear reactors, they all incorporate certain essential features, including the use of fissionable material as fuel, a moderator (such as water) to increase the likelihood of fission (unless reactor operation relies on fast neutrons), a reflector to conserve escaping neutrons, coolant provisions for heat removal, instruments for monitoring and controlling reactor operation, and protective devices (such as control rods and shielding).
Nuclear waste A subset of radioactive waste that includes unusable byproducts produced during the various stages of the nuclear fuel cycle, including extraction, conversion, and enrichment of uranium; fuel fabrication; and use of the fuel in nuclear reactors. Specifically, these stages produce a variety of nuclear waste materials, including uranium mill tailings, depleted uranium, and spent (depleted) fuel, all of which are regulated by the NRC. (By contrast, radioactive waste is a broader term, which includes all wastes that contain radioactivity, regardless of how they are produced. It is not considered nuclear waste because it is not produced through the nuclear fuel cycle and is generally not regulated by the NRC.)
GLOSSARY l 167
Occupational dose The internal and external doses of ionizing radiation received by workers in the course of employment in such areas as fuel cycle facilities, industrial radiography, nuclear medicine, and nuclear power plants. These workers are exposed to varying amounts of radiation, depending on their jobs and the sources with which they work. The NRC requires its licensees to limit occupational exposure to 5,000 millirem (50 millisieverts) per year. Occupational dose does not include the dose received from natural background sources, doses received as a medical patient or participant in medical research programs, or second-hand doses to members of the public received through exposure to patients treated with radioactive materials.
Orphan sources (unwanted radioactive material)
Sealed sources of radioactive material contained in a small volume (but not radioactively contaminated soils and bulk metals) in any one or more of the following conditions:
an uncontrolled condition that requires removal to protect public health and safety from a radiological threat a controlled or uncontrolled condition for which a responsible party cannot be readily identified a controlled condition compromised by an inability to ensure the continued safety of the material (e.g., the licensee may have few or no options to provide for safe disposition of the material) an uncontrolled condition in which the material is in the possession of a person who did not seek, and is not licensed, to possess it an uncontrolled condition in which the material is in the possession of a State radiological protection program solely to mitigate a radiological threat resulting from one of the above conditions and for which the State does not have the necessary means to provide for the appropriate disposition of the material Outage The period during which a generating unit, transmission line, or other facility is out of service.
Outages may be forced or scheduled and full or partial.
Outage (forced)
The shutdown of a generating unit, transmission line, or other facility for emergency reasons, or a condition in which the equipment is unavailable as a result of an unanticipated breakdown.
An outage (whether full, partial, or attributable to a failed start) is considered forced if it could not reasonably be delayed beyond 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from identification of the problem, if there had been a strong commercial desire to do so. In particular, the following problems may result in forced outages:
any failure of mechanical, fuel handling, or electrical equipment or controls within the generators ownership or direct responsibility (i.e., from the point the generator is responsible for the fuel through to the electrical connection point) a failure of a mine or fuel transport system dedicated to that power station with a resulting fuel shortage that cannot be economically managed inadvertent or operator error limitations caused by fuel quality Forced outages do not include scheduled outages for inspection, maintenance, or refueling.
Outage (full forced)
A forced outage that causes a generating unit to be removed from the committed state (when the unit is electrically connected and generating or pumping) or the available state (when the unit is available for dispatch as a generator or pump but is not electrically connected and not generating or pumping). Full-forced outages do not include failed starts.
168 l GLOSSARY
Outage (scheduled)
The shutdown of a generating unit, transmission line, or other facility for inspection, maintenance, or refueling, which is scheduled well in advance (even if the schedule changes). Scheduled outages do not include forced outages and could be deferred if there were a strong commercial reason to do so.
Pellet, fuel A thimble-sized ceramic cylinder (about 3/8 inch (9.525 millimeter) in diameter and 5/8 inch (15.875 millimeter) in length),
consisting of uranium (typically uranium oxide), which has been enriched to increase the concentration of uranium-235 to fuel a nuclear reactor. Modern reactor cores in PWRs and BWRs may contain up to 10 million pellets stacked in the fuel rods that form fuel assemblies.
Performance-based regulation A regulatory approach that focuses on desired, measurable outcomes, rather than prescriptive processes, techniques, or procedures. Performance-based regulation leads to defined results without specific direction on how those results are to be obtained. At the NRC, performance-based regulatory actions focus on identifying performance measures that ensure an adequate safety margin and offer incentives for licensees to improve safety without formal regulatory intervention by the agency.
Performance indicator A quantitative measure of a particular attribute of licensee performance that shows how well a plant is performing when measured against established thresholds. Licensees submit their data quarterly; the NRC regularly conducts inspections to verify the submittals and then uses its own inspection data plus the licensees submittals to assess each plants performance.
Possession-only license A license, issued by the NRC, that authorizes the licensee to possess specific nuclear material but does not authorize its use or the operation of a nuclear facility.
Power uprate The process of increasing the maximum power level at which a commercial nuclear power plant may operate. This power level, regulated by the NRC, is included in the plants operating license and technical specifications. A licensee may only change its maximum power output after the NRC approves an uprate application. The NRC analyses must demonstrate that the plant could continue to operate safely with its proposed new configuration. When all requisite conditions are fulfilled, the NRC may grant the power uprate by amending the plants operating license and technical specifications.
GLOSSARY l 169
Pressurized-water reactor (PWR)
A common nuclear power reactor design in which very pure water is heated to a very high temperature by fission, kept under high pressure (to prevent it from boiling), and converted to steam by a steam generator (rather than by boiling, as in a BWR). The resulting steam is used to drive turbines, which activate generators to produce electrical power. A PWR essentially operates like a pressure cooker, where a lid is tightly placed over a pot of heated water, causing the pressure inside to increase as the temperature increases (because the steam cannot escape) but keeping the water from boiling at the usual 212 degrees Fahrenheit (100 degrees Celsius). About two-thirds of the operating Typical Pressurized-Water nuclear reactor powerReactor plants in the United States are PWRs.
Steamline Containment Walls made of concrete and steel 3-5 feet thick Cooling System (1-1.5 meters) 4 3 Steam Generator Reactor Control Turbine Vessel Rods Generator Condenser Heater Condensate Pumps Coolant Loop 2 Core 1
Feed Pumps Demineralizer Reactor Pressurizer Coolant Emergency Water Pumps Containment Structure Supply Systems How Nuclear Reactors Work In a typical design concept of a commercial PWR, the following process occurs:
- 1. The core inside the reactor vessel creates heat.
- 2. Pressurized water in the primary coolant loop carries the heat to the steam generators.
- 3. Inside the steam generators, heat from the primary coolant loop vaporizes the water in a secondary loop, producing steam.
- 4. The steamline directs the steam to the main turbine, causing it to turn the turbine generators, which produces electricity.
The steam is exhausted to the condenser, where it is condensed into water. The resulting water is pumped out of the condenser with a series of pumps, reheated, and pumped back to the steam generators. The reactors core contains fuel assemblies that are cooled by water circulated using electrically powered pumps. These pumps and other systems in the plant receive their power from the electrical grid. If offsite power is lost, cooling water is supplied by other pumps, which can be powered by onsite diesel generators. Other safety systems, such as the containment cooling system, also need electric power.
PWRs contain between 120-200 fuel assemblies.
Source: U.S. Nuclear Regulatory Commission 170 l GLOSSARY
Probabilistic risk assessment (PRA)
A systematic method for assessing three questions that the NRC uses to define risk. These questions consider (1) what can go wrong, (2) how likely it is to happen, and (3) what the consequences might be. These questions allow the NRC to understand likely outcomes, sensitivities, areas of importance, system interactions, and areas of uncertainty, which the staff can use to identify risk-significant scenarios. The NRC uses PRA to determine a numeric estimate of risk to provide insights into the strengths and weaknesses of the design and operation of a nuclear power plant.
Production expense Production expense is one component of the cost of generating electric power, which includes costs associated with fuel, as well as plant operation and maintenance.
Rad (radiation-absorbed dose)
One of the two units used to measure the amount of radiation absorbed by an object or person, known as the absorbed dose, which reflects the amount of energy that radioactive sources deposit in materials through which they pass. The radiation-absorbed dose (rad) is the amount of energy (from any type of ionizing radiation) deposited in any medium (e.g., water, tissue, air). An absorbed dose of 1 rad means that 1 gram of material absorbed 100 ergs of energy (a small but measurable amount) as a result of exposure to radiation. The related international system unit is the gray (Gy), where 1 Gy is equivalent to 100 rad.
Radiation, ionizing A form of radiation, which includes alpha particles, beta particles, gamma rays, x-rays, neutrons, high-speed electrons, and high-speed protons. Compared to nonionizing radiation, such as found in ultraviolet light or microwaves, ionizing radiation is considerably more energetic. When ionizing radiation passes through material such as air, water, or living tissue, it deposits enough energy to break molecular bonds and displace (or remove) electrons. This electron displacement may lead to changes in living cells. Given this ability, ionizing radiation has a number of beneficial uses, including treating cancer or sterilizing medical equipment. However, ionizing radiation is potentially harmful if not used correctly, and high doses may result in severe skin or tissue damage. It is for this reason that the NRC strictly regulates commercial and institutional uses of the various types of ionizing radiation.
Radiation, nuclear Energy given off by matter in the form of tiny, fast-moving particles (alpha particles, beta particles, and neutrons) or pulsating electromagnetic rays or waves (gamma rays) emitted from the nuclei of unstable radioactive atoms. All matter is composed of atoms, which are made up of various parts; the nucleus contains minute particles called protons and neutrons, and the atoms outer shell contains other particles called electrons. The nucleus carries a positive electrical charge, while the electrons carry a negative electrical charge. These forces work toward a strong, stable balance by getting rid of excess atomic energy (radioactivity). In that process, unstable radioactive nuclei may emit energy, and this spontaneous emission is called nuclear radiation. All types of nuclear radiation are also ionizing radiation, but the reverse is not necessarily true; for example, x-rays are a type of ionizing radiation, but they are not nuclear radiation because they do not originate from atomic nuclei. In addition, some elements are naturally radioactive, as their nuclei emit nuclear radiation as a result of radioactive decay, but others become radioactive by being irradiated in a reactor. Naturally occurring nuclear radiation is indistinguishable from induced radiation.
GLOSSARY l 171
Radiation source A radioactive material or byproduct that is specifically manufactured or obtained for the purpose of using the emitted radiation. Such sources are commonly used in teletherapy or industrial radiography; in various types of industrial gauges, irradiators, and gamma knives; and as power sources for batteries (such as those used in spacecraft). These sources usually consist of a known quantity of radioactive material, which is encased in a human-made capsule, sealed between layers of nonradioactive material, or firmly bonded to a nonradioactive substrate to prevent radiation leakage. Other radiation sources include devices such as accelerators and x-ray generators.
Radiation standards Exposure limits; permissible concentrations; rules for safe handling; and regulations on the receipt, possession, use, transportation, storage, disposal, and industrial control of radioactive material.
Radiation therapy (radiotherapy)
The therapeutic use of ionizing radiation to treat disease in patients. Although most radiotherapy procedures are intended to kill cancerous tissue or reduce the size of a tumor, therapeutic doses may also be used to reduce pain or treat benign conditions. For example, intervascular brachytherapy uses radiation to treat clogged blood vessels. Other common radiotherapy procedures include gamma stereotactic radiosurgery (gamma knife), teletherapy, and iodine treatment to correct an overactive thyroid gland. These procedures use radiation sources, regulated by the NRC and its Agreement States, that may be applied either inside or outside the body. In either case, the goal of radiotherapy is to deliver the required therapeutic or pain-relieving dose of radiation with high precision and for the required length of time, while preserving the surrounding healthy tissue.
Radiation warning symbol An officially prescribed magenta or black trefoil on a yellow background, which must be displayed where certain quantities of radioactive materials are present or where certain doses of radiation could be received.
Radioactive contamination Undesirable radioactive material (with a potentially harmful effect) that is either airborne or deposited in (or on the surface of) structures, objects, soil, water, or living organisms (people, animals, or plants) in a concentration that may harm people, equipment, or the environment.
Radioactive decay The spontaneous transformation of one radionuclide into one or more decay products (also known as daughters). This transformation is commonly characterized by the emission of an alpha particle, a beta particle, or gamma ray photon(s) from the nucleus of the radionuclide. The rate at which these transformations take place, when a sufficient quantity of the same radionuclide is present, depends on the half-life of the radionuclide. Some radionuclides (e.g., hydrogen-3, also known as tritium) decay to stable daughters that are not radioactive. However, other radionuclides (e.g., uranium-238) decay to radioactive daughters (e.g., thorium-234) and may be part of a radioactive decay chain consisting of two or more radionuclides linked in a cascading series of radioactive decay.
Radioactivity The property possessed by some elements (such as uranium) of spontaneously emitting energy in the form of radiation as a result of the decay (or disintegration) of an unstable atom. Radioactivity is also the term used to describe the rate at which radioactive material emits radiation. Radioactivity is measured in units of becquerels or disintegrations per second.
172 l GLOSSARY
Radiography The use of sealed sources of ionizing radiation for nondestructive examination of the structure of materials. When the radiation penetrates the material, it produces a shadow image by blackening a sheet of photographic film that has been placed behind the material, and the differences in blackening suggest flaws and unevenness in the material.
Radioisotope (radionuclide)
An unstable isotope of an element that decays or disintegrates spontaneously, thereby emitting radiation. About 5,000 natural and artificial radioisotopes have been identified.
Radiopharmaceutical A pharmaceutical drug that emits radiation and is used in diagnostic or therapeutic medical procedures. Radioisotopes that have short half-lives are generally preferred to minimize the radiation dose to the patient and the risk of prolonged exposure. In most cases, these short-lived radioisotopes decay to stable elements within minutes, hours, or days, allowing patients to be released from the hospital in a relatively short time.
Radium A radioactive substance found in nature. The Energy Policy Act of 2005 gives the NRC regulatory authority for the safe use of radium under certain conditions.
Reactor core The central portion of a nuclear reactor, which contains the fuel assemblies, water, and control mechanisms, as well as the supporting structure. The reactor core is where fission takes place.
Reactor Oversight Process (ROP)
The process by which the NRC monitors and evaluates the performance of commercial nuclear power plants. Designed to focus on those plant activities that are most important to safety, the ROP uses inspection findings and performance indicators to assess each plants safety performance.
GLOSSARY l 173
Refueling The process of removing older fuel and loading new fuel. These actions are all performed underwater to supply continuous cooling for the fuel and provide shielding from the radioactive spent fuel.
BWR Refueling Summary Refueling BWR As new fuel shipping canisters arrive in the reactor building, the Reactor Building Crane reactor building crane lifts them to the refueling floor, where the fuel is removed from the canister and Refueling Fuel Bridge inspected for defects. The fuel can Storage then be stored either the new fuel Refueling Bay Pool Spent Fuel storage area (which is dry) or in Refueling Storage Steam Cavity Racks the refueling pool, depending upon Dryer and the needs of the site. Fuel in the Separator new fuel storage area is moved Storage Pool into the fuel pool before refueling Reactor begins. To refuel the reactor, the Vessel containment vessel lid and the Containment reactor vessel head are removed, Vessel the refueling cavity above the reactor vessel is flooded, and the gates between the reactor cavity Torus and fuel pool are removed. The refueling bridge removes one fuel bundle at a time from the reactor and transfers it to the spent fuel storage racks until about a third of the fuel is removed. The process PWR Refueling Summary is reversed when fuel is removed from the fuel pool and placed in the reactor. In BWRs, the fuel remains in a vertical position throughout the process.
Refueling PWR Reactor Building Fuel (Containment) Building As new fuel shipping canisters arrive in the fuel building, the reactor building crane (not shown) lifts them Fuel Inspection to the fuel inspection stand, where the Stand Refueling fuel is removed from the canister and Bridge inspected for defects. Fuel in the new Fuel fuel storage area is moved into the Transfer Canal fuel pool before refueling begins. The fuel can then be stored in either the Refueling Bridge new fuel storage racks (which are dry) Fuel Transfer New or in the refueling pool, depending Tube Fuel upon the needs of the site. Fuel in the Storage Racks new fuel storage area is moved into Spent Spent the fuel pool before refueling begins. Reactor Fuel Fuel Storage Storage To refuel the reactor, the vessel head Vessel Pool Racks is removed, the fuel transfer canals Reactor Core and transfer tube areas are flooded, and removable gates are opened in order to connect the refueling canal to the fuel pool. The reactor building refueling bridge is used to remove a fuel assembly from the reactor vessel and transfer it to the up-ender basket, which is then tilted until it is horizontal, sent through the transfer tube into the fuel building, and returned upright. The refueling bridge then moves the fuel assembly into the spent fuel storage racks. This process is reversed when fuel is loaded into the reactor.
174 l GLOSSARY
Regulation The governmental function of controlling or directing economic entities through the process of rulemaking and adjudication.
Regulatory Information Conference An annual NRC conference that brings together NRC staff, regulated utilities, materials users, and other interested stakeholders to discuss nuclear safety topics and significant and timely regulatory activities through informal dialogue to ensure an open regulatory process.
Rem One of the two standard units used to measure the dose equivalent (or effective dose), which combines the amount of energy (from any type of ionizing radiation) that is deposited in human tissue with the biological effects of the given type of radiation. For beta and gamma radiation, the dose equivalent is the same as the absorbed dose. By contrast, the dose equivalent is larger than the absorbed dose for alpha and neutron radiation because these types of radiation are more damaging to the human body. Thus, the dose equivalent (in rem) is equal to the absorbed dose (in rads) multiplied by the quality factor of the type of radiation (Title 10 of the Code of Federal Regulations (10 CFR) 20.1004, Units of radiation dose). The related international system unit is the sievert (Sv), where 100 rem is equivalent to 1 Sv.
Renewable resources Natural, but limited, energy resources that can be replenished, including biomass, hydro, geothermal, solar, and wind. These resources are virtually inexhaustible but limited in the amount of energy that is available per unit of time. In the future, renewable resources could also include the use of ocean thermal, wave, and tidal action technologies. Utility renewable resource applications include bulk electricity generation, onsite electricity generation, distributed electricity generation, nongrid-connected generation, and demand-reduction (energy efficiency) technologies.
Risk The combined answer to three questions that consider (1) what can go wrong, (2) how likely it is to occur, and (3) what the consequences might be. These three questions allow the NRC to understand likely outcomes, sensitivities, areas of importance, system interactions, and areas of uncertainty, which can be used to identify risk-significant scenarios.
Risk-based decisionmaking An approach to regulatory decisionmaking that considers only the results of a probabilistic risk assessment.
Risk-informed decisionmaking An approach to regulatory decisionmaking in which insights from probabilistic risk assessment are considered with other engineering insights.
Risk-informed regulation An approach to regulation taken by the NRC that incorporates an assessment of safety significance or relative risk. This approach ensures that the regulatory burden imposed by an individual regulation or process is appropriate to its importance in protecting the health and safety of the public and the environment.
Risk significant The term referring to a facilitys system, structure, component, or accident sequence that exceeds a predetermined limit for contributing to the risk associated with the facility. The term also describes a level of risk exceeding a predetermined significance level.
GLOSSARY l 175
Safeguards The use of material control and accounting programs to verify that all special nuclear material is properly controlled and accounted for, as well as the physical protection (or physical security) measures and security forces. As used by IAEA, this term also means verifying that the peaceful use commitments made in binding nonproliferation agreements, both bilateral and multilateral, are honored.
Safeguards information A special category of sensitive unclassified information that must be protected. Safeguards information concerns the physical protection of operating power reactors, spent fuel shipments, strategic special nuclear material, or other radioactive material.
Safety related In the regulatory arena, this term applies to systems, structures, components, procedures, and controls (of a facility or process) that are relied upon to remain functional during and following design-basis events. Their functionality ensures that key regulatory criteria, such as levels of radioactivity released, are met. Examples of safety-related functions include shutting down a nuclear reactor and maintaining it in a safe-shutdown condition.
Safety significant When used to qualify an object, such as a system, structure, component, or accident sequence, a term identifying that object as having an impact on safety, whether determined through risk analysis or other means, that exceeds a predetermined significance criterion.
SAFSTOR A long-term storage condition for a permanently shutdown nuclear power plant. During SAFSTOR, radioactive contamination decreases substantially, making subsequent decontamination and demolition easier and reducing the amount of LLW requiring disposal.
Scram The sudden shutting down of a nuclear reactor, usually by rapid insertion of control rods, either automatically or manually by the reactor operator (also known as a reactor trip).
Sensitive unclassified non-safeguards information Information that is generally not publicly available and that encompasses a wide variety of categories, such as proprietary information, personal and private information, or information subject to attorney-client privilege.
Shutdown A decrease in the rate of fission (and heat or energy production) in a reactor (usually by the insertion of control rods into the core).
Small modular reactor (SMR)
Small reactors that use water to cool the reactor core in the same way as todays large light-water reactors. SMR designs also use the same enriched-uranium fuel as current U.S. reactors.
However, SMR designs are considerably smaller and can bundle together several reactors in a single containment. Each SMR module generates 300 megawatts electric (MWe) or less, compared to todays large designs that can generate 1,000 MWe or more per reactor. The NRCs discussions to date with SMR designers involve modules generating less than 200 MWe.
Source material Uranium or thorium, or any combination thereof, in any physical or chemical form, or ores that contain, by weight, 1/20 of 1 percent (0.05 percent) or more of (1) uranium, (2) thorium, or (3) any combination thereof. Source material does not include special nuclear material.
176 l GLOSSARY
Special nuclear material Plutonium, uranium-233, or uranium enriched in the isotopes uranium-233 or uranium-235.
Spent fuel pool An underwater storage and cooling facility for spent (depleted) fuel assemblies that have been removed from a reactor.
Spent (depleted or used) nuclear fuel Nuclear reactor fuel that has been used to the extent that it can no longer effectively sustain a chain reaction.
Subcriticality The condition of a nuclear reactor system in which nuclear fuel no longer sustains a fission chain reaction (i.e., the reaction fails to initiate its own repetition, as it would in a reactors normal operating condition). A reactor becomes subcritical when its fission events fail to release a sufficient number of neutrons to sustain an ongoing series of reactions, possibly as a result of increased neutron leakage or poisons.
Teletherapy Treatment in which the source of the therapeutic radiation is at a distance from the body. Because teletherapy is often used to treat malignant tumors deep within the body by bombarding them with a high-energy beam of gamma rays (from a radioisotope such as cobalt-60) projected from outside the body, it is often called external beam radiotherapy.
Title 10 of the Code of Federal Regulations (10 CFR)
Title 10 of the Code of Federal Regulations (CFR) addresses energy-related topics. Chapter I, Parts 1 to 199, contain the regulations (or rules) established by the NRC. These regulations govern the transportation and storage of nuclear materials; use of radioactive materials at nuclear power plants, research and test reactors, uranium recovery facilities, fuel cycle facilities, waste repositories, and other nuclear facilities; and use of nuclear materials for medical, industrial, and academic purposes.
Transient A change in the reactor coolant system temperature, pressure, or both, attributed to a change in the reactors power output. Transients can be caused by (1) adding or removing neutron poisons, (2) increasing or decreasing electrical load on the turbine generator, or (3) accident conditions.
Transuranic waste Material contaminated with transuranic elementsartificially made radioactive elements, such as neptunium, plutonium, americium, and othersthat have atomic numbers higher than uranium in the periodic table of elements. Transuranic waste is primarily produced from recycling spent fuel or using plutonium to fabricate nuclear weapons.
Tritium A radioactive isotope of hydrogen. Because it is chemically identical to natural hydrogen, tritium can easily be taken into the body by any ingestion path. It decays by emitting beta particles and has a half-life of about 12.5 years.
Uprate See Power uprate.
GLOSSARY l 177
Uranium A radioactive element with the atomic number 92 and, as found in natural ores, an atomic weight of about 238.
The two principal natural isotopes are uranium-235 and uranium-238. Uranium-235 is composed of 0.7 percent natural uranium and is fissile. Uranium-238 is composed of 99.3 percent natural uranium, is fissionable by fast neutrons, and is fertile. This means that it becomes fissile after absorbing one neutron. Natural uranium also includes a minute amount of uranium-234.
Uranium enrichment process The process of increasing the percentage of uranium-235 (U-235) from 0.7 percent in natural uranium to about 3 to 5 percent for use in fuel for nuclear Gas Centrifuge Process reactors. Enrichment can be done through gaseous Fraction Depleted in diffusion, gas centrifuges, or laser isotope separation. U-235 Fraction Enriched in In May 2013, the last remaining U.S. operating gaseous UF 6 Feed U-235 diffusion plant in Paducah, KY, shut down. A similar plant near Piketon, OH, was closed in March 2001. Another plant in Oak Ridge, TN, closed years ago and was not regulated by the NRC.
Casing Gas centrifuge process The gas centrifuge process uses many rotating cylinders that are connected in long lines. Gas is placed in the cylinder, which spins at a high Rotor speed, creating a strong centrifugal force.
Heavier gas molecules move to the cylinder wall, while lighter molecules collect near the center. The stream, now slightly enriched, is fed into the next cylinder. The depleted stream is recycled back into the previous cylinder. Electric Motor Uranium fuel fabrication facility A facility that converts enriched UF6 into fuel for commercial light-water power reactors, research and test reactors, and other nuclear reactors. The UF6, in solid form in containers, is heated to a gaseous form and then chemically processed to form uranium dioxide powder. This powder is then processed into ceramic pellets and loaded into metal tubes, which are subsequently bundled into fuel assemblies. Fabrication can also involve MOX fuel, which contains plutonium oxide mixed with either natural or depleted uranium oxide in ceramic pellet form.
Uranium hexafluoride production facility (or uranium conversion facility)
A facility that receives natural uranium in the form of ore concentrate (known as yellowcake) and converts it into UF6, in preparation for fabricating fuel for nuclear reactors.
U.S. Department of Energy (DOE)
The Federal agency established by Congress to advance the national, economic, and energy security of the United States, among other missions.
178 l GLOSSARY
U.S. Department of Homeland Security (DHS)
The Federal agency responsible for leading the unified national effort to secure the United States against those who seek to disrupt the American way of life. DHS is also responsible for preparing for and responding to all hazards and disasters and includes the formerly separate FEMA, the Coast Guard, and the Secret Service.
U.S. Environmental Protection Agency (EPA)
The Federal agency responsible for protecting human health and safeguarding the environment.
EPA leads the Nations environmental science, research, education, and assessment efforts to ensure that attempts to reduce environmental risk are based on the best available scientific information. EPA also ensures that environmental protection is an integral consideration in U.S.
policies.
Viability assessment A decisionmaking process used by DOE to assess the prospects for safe and secure permanent disposal of HLW in an excavated, underground facility known as a geologic repository. This decisionmaking process is based on (1) specific design work on the critical elements of the repository and waste package, (2) a total system performance assessment that will describe the probable behavior of the repository, (3) a plan and cost estimate for the work required to complete the license application, and (4) an estimate of the costs to construct and operate the repository.
Waste, radioactive Radioactive materials at the end of their useful life or in a product that is no longer useful and requires proper disposal. See High-level radioactive waste, Low-level radioactive waste, and Spent (depleted or used) nuclear fuel.
Waste classification (classes of waste)
Classification of low-level waste (LLW) according to its radiological hazard. The classes include Class A, B, and C, with Class A being the least hazardous and accounting for 96 percent of LLW in the United States. As the waste class and hazard increase, the regulations established by the NRC require progressively greater controls to protect the health and safety of the public and the environment.
Watt A unit of power (in the International System of Units) defined as the consumption or conversion of 1 joule of energy per second. In electricity, a watt is equal to current (in amperes) multiplied by voltage (in volts).
Watt-hour A unit of energy equal to 1 watt of power steadily supplied to, or taken from, an electrical circuit for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (or exactly 3.6 x103 joules).
Yellowcake The solid form of uranium oxide, which is produced from uranium ore in the uranium recovery (milling) process.
GLOSSARY l 179
9 WEB LINK INDEX
WEB LINK INDEX NRC: An Independent Regulatory Agency Mission, Goals, and Statutory Authority Strategic Plan (NUREG-1614) https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1614/
Statutory Authority https://www.nrc.gov/about-nrc/governing-laws.html Major Activities Public Involvement https://www.nrc.gov/public-involve.html Freedom of Information Act and Privacy Act https://www.nrc.gov/reading-rm/foia/foia-privacy.html Regulatory Guides https://www.nrc.gov/reading-rm/doc-collections/reg-guides/
Title 10, Code of Federal Regulations https://www.nrc.gov/reading-rm/doc-collections/cfr/
https://www.gpo.gov/fdsys/browse/collectionCfr.action?collectionCode=CFR Rulemaking Dockets https://www.regulations.gov Rulemaking and Petition for Rulemaking Actions https://www.nrc.gov/about-nrc/regulatory/rulemaking/rules-petitions.html Rulemaking Petition Process https://www.nrc.gov/about-nrc/regulatory/rulemaking/petition-rule.html Office of Investigations Annual Report FY 2020 https://www.nrc.gov/docs/ML2104/ML21048A429.pdf Significant Enforcement Actions https://www.nrc.gov/reading-rm/doc-collections/enforcement/actions/
Organizations and Functions Organization Chart https://www.nrc.gov/about-nrc/organization/nrcorg.pdf The Commission https://www.nrc.gov/about-nrc/organization/commfuncdesc.html Commission Direction-Setting and Policymaking Activities https://www.nrc.gov/about-nrc/policymaking.html NRC Regions https://www.nrc.gov/about-nrc/locations.html NRC Budget Congressional Budget Justification: Fiscal Year 2021(NUREG-1100) https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1100/
U.S. and Worldwide Nuclear Energy U.S. Electricity U.S. Energy Information Administration -Official Energy Statistics from the U.S. Government https://www.eia.gov 182 l WEB LINK INDEX
Worldwide Electricity Generated by Commercial Nuclear Power International Atomic Energy Agency (IAEA) https://www.iaea.org IAEA Power Reactor Information System (PRIS) https://www.iaea.org/pris/
Nuclear Energy Agency (NEA) https://www.oecd-nea.org World Nuclear Association (WNA) https://www.world-nuclear.org World Nuclear Power Reactors and Uranium Requirements https://www.world-nuclear.org/info/reactors.html WNA Reactor Database http://www.world-nuclear.org/nucleardatabase/default.aspx NRC Regulatory Information Conference https://www.nrc.gov/public-involve/conference-symposia/ric/index.html International Activities NRC Office of International Programs https://www.nrc.gov/about-nrc/organization/oipfuncdesc.html https://www.nrc.gov/about-nrc/international.html Treaties and Conventions https://www.nrc.gov/about-nrc/ip/treaties-conventions.html Code of Conduct on the Safety and Security of Radioactive Sources https://www-ns.iaea.org/tech-areas/radiation-safety/code-of-conduct.asp Radiation Sources Regulatory Partnership https://rsrp-online.org International Regulatory Development Partnership https://irdp-online.org Operating Nuclear Reactors U.S. Commercial Nuclear Power Reactors Commercial Reactors https://www.nrc.gov/info-finder/reactors/
Oversight of U.S. Commercial Nuclear Power Reactors Reactor Oversight Process (ROP) https://www.nrc.gov/reactors/operating/oversight.html NUREG/BR-0508, Reactor Oversight Process https://www.nrc.gov/reading-rm/doc-collections/nuregs/brochures/br0508/
NUREG-1649, Reactor Oversight Process https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1649/
ROP Performance Indicators Summary https://www.nrc.gov/reactors/operating/oversight/pi-summary.html ROP Contact Us Form https://www.nrc.gov/reactors/operating/oversight/contactus.html Post-Fukushima Safety Enhancements https://www.nrc.gov/reactors/operating/ops-experience/post-fukushima-safety-enhancements.html https://www.nrc.gov/docs/ML1835/ML18355A806 WEB LINK INDEX l 183
New Reactors New Reactor Licensing https://www.nrc.gov/reactors/new-reactors.html Reactor License Renewal Reactor License Renewal Process https://www.nrc.gov/reactors/operating/licensing/renewal/process.html 10 CFR Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions https://www.nrc.gov/reading-rm/doc-collections/cfr/part051/
10 CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants https://www.nrc.gov/reading-rm/doc-collections/cfr/part054/
Status of License Renewal Applications and Industry Activities https://www.nrc.gov/reactors/operating/licensing/renewal/applications.html Status of Subsequent License Renewal Applications https://www.nrc.gov/reactors/operating/licensing/renewal/subsequent-license-renewal.html U.S. Nuclear Research and Test Reactors Research and Test Reactors https://www.nrc.gov/reactors/nonpower.html Nuclear Regulatory Research Nuclear Reactor Safety Research https://www.nrc.gov/about-nrc/regulatory/research/reactor-rsch.html State-of-the-Art Reactor Consequence Analyses https://www.nrc.gov/about-nrc/regulatory/research/soar.html Risk Assessment in Regulation https://www.nrc.gov/about-nrc/regulatory/risk-informed.html Digital Instrumentation and Controls Research https://www.nrc.gov/about-nrc/regulatory/research/digital.html Computer Codes https://www.nrc.gov/about-nrc/regulatory/research/safetycodes.html Generic Issues Program https://www.nrc.gov/about-nrc/regulatory/gen-issues.html The Committee To Review Generic Requirements https://www.nrc.gov/about-nrc/regulatory/crgr.html Office of Nuclear Regulatory Research-Planned Research Activities https://www.nrc.gov/about-nrc/regulatory/research/activities.html Nuclear Materials Agreement States Office of Nuclear Material Safety and Safeguards State Communication Portal https://scp.nrc.gov NRC Tribal Web site Office of Nuclear Material Safety and Safeguards Tribal Web site https://tribal.nrc.gov/
U.S. Fuel Cycle Facilities Fuel Cycle Facilities https://www.nrc.gov/materials/fuel-cycle-fac.html Fuel Cycle Facilities Regulations, Guidance, Communications, and Cumulative Effects of Radiation https://www.nrc.gov/materials/fuel-cycle-fac/regs-guides-comm.html 184 l WEB LINK INDEX
Uranium Recovery Location of Uranium Milling/Recovery https://www.nrc.gov/info-finder/materials/uranium/
U.S. Materials Licenses Materials Licensees Toolkits https://www.nrc.gov/materials/miau/mat-toolkits.html 10 CFR-Part 70, Domestic Licensing of Special Nuclear Material https://www.nrc.gov/reading-rm/doc-collections/cfr/part070/
Medical Applications and Others Medical, Industrial, and Academic Uses of Nuclear Materials https://www.nrc.gov/materials/medical.html Medical Uses Medical Uses of Nuclear Materials https://www.nrc.gov/materials/miau/med-use.html Nuclear Gauges and Commercial Product Irradiators General License Uses of Nuclear Materials https://www.nrc.gov/materials/miau/general-use.html Industrial Applications Industrial Uses of Nuclear Materials https://www.nrc.gov/materials/miau/industrial.html License-Exempt Consumer Product Uses of Radioactive Material https://www.nrc.gov/materials/miau/consumer-pdts.html Radioactive Waste U.S. Low-Level Radioactive Waste Disposal Low-Level Waste https://www.nrc.gov/waste/low-level-waste.html U.S. High-Level Radioactive Waste Management:
Disposal and Storage High-Level Waste https://www.nrc.gov/waste/high-level-waste.html Spent Nuclear Fuel Storage Storage of Spent Nuclear Fuel https://www.nrc.gov/waste/spent-fuel-storage.html Consolidated Interim Storage Facility https://www.nrc.gov/waste/spent-fuel-storage/cis.html U.S. Nuclear Materials Transportation Materials Transportation https://www.nrc.gov/materials/transportation.html Governor and Tribal Official Transportation Advance Notification Designees https://scp.nrc.gov/special/designee.pdf Decommissioning Decommissioning of Nuclear Facilities https://www.nrc.gov/waste/decommissioning.html Status of the Decommissioning Program: 2020 Annual Report https://www.nrc.gov/docs/ML2025/ML20259A506.pdf WEB LINK INDEX l 185
Nuclear Security and Emergency Preparedness Nuclear Security Nuclear Security and Safeguards https://www.nrc.gov/security.html Research and Test Reactors Security https://www.nrc.gov/reactors/non-power.html#security Domestic Safeguards Domestic Safeguards https://www.nrc.gov/security/domestic.html Information Security Information Security https://www.nrc.gov/security/info-security.html Radioactive Material Security Radioactive Material Security https://www.nrc.gov/security/byproduct.html Required Reporting for Clearance Holders https://www.nrc.gov/security/required-reporting-for-clearance-holders.html Insider Threat Program for Licensees https:www.nrc.gov/security/insider-threat-program-for-licensees.html Cybersecurity Cybersecurity https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/cyber-security-bg.html Emergency Preparedness and Response Emergency Preparedness and Response https://www.nrc.gov/about-nrc/emerg-preparedness.html Emergency Action Level Development https://www.nrc.gov/about-nrc/emerg-preparedness/about-emerg-preparedness/emerg-action-level-dev.html Emergency Exercise Schedule https://www.nrc.gov/about-nrc/emerg-preparedness/about-emerg-preparedness/exercise-schedules.html Other Web Links Datasets Spreadsheets of NRC-Regulated Licensee Information https://www.nrc.gov/reading-rm/doc-collections/datasets/
Employment Opportunities Career Opportunities https://www.nrc.gov/about-nrc/employment.html Glossary NRC Full-Text Glossary https://www.nrc.gov/reading-rm/basic-ref/glossary/full-text.html Glossary of Energy Terms https://www.eia.gov/tools/glossary/
Public Involvement NRC Library https://www.nrc.gov/reading-rm.html Freedom of Information Act and Privacy Act https://www.nrc.gov/reading-rm/foia/foia-privacy.html Agencywide Documents Access and Management System (ADAMS) https://www.nrc.gov/reading-rm/adams.html 186 l WEB LINK INDEX
Public Document Room https://www.nrc.gov/reading-rm/pdr.html Licensing Support Network Library https://adamspublic.nrc.gov/navigator/
Public Meeting Schedule https://www.nrc.gov/pmns/mtg Documents for Comment https://www.nrc.gov/public-involve/doc-comment.html Small Business and Civil Rights Information for Small Businesses https://www.nrc.gov/about-nrc/contracting/small-business.html Workplace Diversity https://www.nrc.gov/about-nrc/employment/workingatnrc.html Civil Rights https://www.nrc.gov/about-nrc/civil-rights.html Equal Employment Opportunity Policy https://www.nrc.gov/about-nrc/civil-rights/crp/eeo.html Limited English Proficiency https://www.nrc.gov/about-nrc/civil-rights/limited-english.html Social Media Platforms Twitter https://twitter.com/nrcgov/
YouTube https://www.youtube.com/user/NRCgov/
Flickr https://www.flickr.com/photos/nrcgov/
Facebook https://www.facebook.com/nrcgov/
Linkedin https://www.linkedin.com/company/u-s--nuclear-regulatory-commission GovDelivery https://www.nrc.gov/public-involve/listserver.html#gov RSS https://www.nrc.gov/public-involve/listserver.html#rss WEB LINK INDEX l 187
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER (9-2004) (Assigned by NRC, Add Vol., Supp., Rev.,
NRCMD 3.7 and Addendum Numbers, if any.)
BIBLIOGRAPHIC DATA SHEET (See instructions on the reverse) NUREG 1350, Vol.
NUREG-1350, 3321 Vol.
- 2. TITLE AND SUBTITLE 3. DATE REPORT PUBLISHED U.S. Nuclear Regulatory Commission MONTH YEAR Information Digest October 2021 2021-2022 Edition 2008-2009 August 2009
- 5. AUTHOR(S) 6. TYPE OF REPORT IvonneCouret Ivonne Couret, et al.
Annual
- 7. PERIOD COVERED (Inclusive Dates) 2021-2022 2008
- 8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor, provide name and mailing address.)
Public Affairs Staff Office of Public Affairs U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type "Same as above"; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address.)
Same as 8, above
- 10. SUPPLEMENTARY NOTES There may be a supplementary document produced reflecting specific sections of the document.
- 11. ABSTRACT (200 words or less)
The U.S. Nuclear Regulatory Commission (NRC) has published the Information Digest annually since 1989. The Digest provides information about agency activities and licensees from the various industries it regulates. It describes the agencys responsibilities and activities, and provides general information on nuclear-related topics. The Information Digest includes NRC and industry data in an easy-to-read format. Infographics help explain the information with visual aids.
The 2021-2022 Information Digest includes NRC data in the appendices and non-NRC data (e.g., International Atomic Energy Agency, Energy Information Administration, and U.S. Department of Energy) that were updated as of August 10, 2021, including data in maps and graphics. The Digest is an annual publication, with updates to certain non-NRC data every 2 years.
The next Information Digest containing updated data will be published in September 2022. The Information Digest will include links to the most current information.
The NRC reviews the information from industry and international sources but does not independently verify it. The Web Link Index provides sources for more information on major topics. The NRC is the source of all photographs, graphics, and tables unless otherwise noted. All information is final unless otherwise noted. Any corrections and updates will appear in the digital version of the publication on the NRC Web site at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1350/.
The NRC welcomes comments or suggestions on the Information Digest. To submit comments, write to the Office of Public Affairs at U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or at opa.resource@nrc.gov.
- 12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.) 13. AVAILABILITY STATEMENT Information Information Digest Digest unlimited 2021-2022 2009-2010EditionEdition 14. SECURITY CLASSIFICATION NRC NRCFactsFacts (This Page)
Nuclear Nuclear Regulatory Regulatory Commission Commission unclassified 10 CFR (This Report) unclassified
- 15. NUMBER OF PAGES 190
- 16. PRICE NRC FORM 335 (9-2004) PRINTED ON RECYCLED PAPER
U.S. NRC 2021-2022 INFORMATION DIGEST NUREG-1350, Volume 33 October 2021