ML18037A641

NUREG-1350, Vol. 29, Rev. 01, Information Digest 2017-2018.

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NUREG-1350 V29 R01
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Information Digest2017-2018 NRC Reference Material As of November 1999, you may electronically access NUREG-series publications and other NRC records at the NRC's Public Electronic Reading Room at http://www.nrc.gov/reading

-rm.html. Publicly released records include, to name a few, NUREG

-series publications; Federal Register notices; applicant, licensee, and vendor documents and correspondence; NRC correspondence and internal memoranda; bulletins and information notices; inspection and investigative reports; licensee event reports; and Commission papers and their attachments.

NRC publications in the NUREG series, NRC regulations, and Title 10, "Energy ," in the Code of Federal Regulations may also be purchased from one of these two sources.

1. The Superintendent of Documents U.S. Government Publishing Office Washington, DC 20402-0001 Internet: http://bookstore.gpo.gov Telephone:

1-866-512-1800 Fax: (202) 512-2104 2. The National Technical Information Service 5301 Shawnee Road Alexandria, VA 22161-0002 http://www.ntis.gov 1-800-553-6847 or, locally, (703) 605-6000 A single copy of each NRC draft report for comment is available free, to the extent of supply, upon written request as follows:

U.S. Nuclear Regulatory Commission Office of Administration

Publications Branch

Washington, DC 20555-0001 E-mail: distribution.resource@nrc.gov Facsimile:

(301) 415-2289 Some publications in the NUREG series that are posted at the NRC's Web site address http://www.nrc.gov/reading

-rm/doc-collections/nuregs are updated periodically and may differ from the last printed version. Although references to material found on a Web site bear the date the material was accessed, the material available on the date cited may subsequently be removed from the site.

Non-NRC Reference Material Documents available from public and special technical libraries include all open literature items, such as books, journal articles, transactions, Federal Register notices, Federal and State legislation, and congressional reports. Such documents as theses, dissertations, foreign reports and translations, and non

-NRC conference proceedings may be purchased from their sponsoring organization.

Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at

- The NRC Technical Library Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 These standards are available in the library for reference use by the public.

Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from- American National Standards Institute 11 West 42 nd Street New York, NY 10036

-8002 http://www.ansi.org (212) 642-4900 AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATION S Legally binding regulatory requirements are stated only in laws; NRC regulations; licenses, including technical specifications; or orders, not in NUREG

-series publications. The views expressed in contractor

-prepared publications in this series are not necessarily those of the NRC.

The NUREG series comprises (1) technical and administrative reports and books prepared by the staff (NUREG-XXXX) or agency contractors (NUREG/CR-XXXX), (2) proceedings of conferences (NUREG/CP-XXXX), (3) reports resulting from international agreements (NUREG/IA-XXXX), (4) brochures (NUREG/BR

-XXXX), and (5) compilations of legal decisions and orders of the Commission and Atomic and Safety Licensing Boards and of Directors' decisions under Section 2.206 of NRC's regulations (NUREG-0750). DISCLAIMER:

This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product, or process disclosed in this publication, or represents that its use by such third party would not infringe privately owned rights.

SR-CR 08/2016 Information Digest2017-2018NUREG-1350, Volume 29, Rev. 1 Manuscript Completed: October 2017

Date Published: December 2017 U.S. Nuclear Regulatory CommissionOf~ce of Public Affairs Washington, DC 20555-0001www.nrc.gov ii Section Photo Captions:

Section 1: NRC: An Independent Regulatory Agency

1. The Prairie Island nuclear power plant in Minnesota.

2. The NRC Headquarters complex in Rockville, MD.

3. An NRC inspector conducts routine inspections of plant equipment to ensure the plant is meeting NRC regulations. Section 2: Nuclear Energy in the U.S. and Worldwide1. A satellite photograph captures the sunrise over the Earth.

2. The NRC participates in the annual General Conference for the International Atomic Energy Agency in Vienna, Austria.

3. The United Nations General Assembly meets in New York to discuss, among other topics, world nuclear matters.

Section 3: Nuclear Reactors

1. The St. Lucie nuclear power plant in Florida.

2. An NRC inspector conducts routine inspections of plant equipment to ensure the plant is meeting NRC regulations.

3. Transmission lines distribute electricity generated by nuclear power plants to the power grid.

Section 4: Nuclear Materials

1. Physicians use yttrium-90 microspheres to treat liver cancers.

2. A moisture density gauge indicates whether a foundation is suitable for constructing a building or roadway.

3. A worker displays a small ceramic fuel pellet.Section 5: Radioactive Waste1. Dry casks are transported to a storage site.

2. A transport package is placed inside a conveyance vehicle.

3. A worker inspects a dry cask storage facility. Section 6: Security and Emergency Preparedness

1. Biometric access control locks within a nuclear facility provide another layer of protection.

2. Barbed wire provides an added layer of security while protecting a nuclear

facility from intruders.

3. Security of~cers protect nuclear facilities from intruders.

Section 7: Appendices

1. The Susquehanna Steam Electric Station, Units 1 and 2, in Pennsylvania.

2. Permanent removal of a major component as part of the decommissioning process of the Trojan site near Ranier, OR.

3. NRC regulations are contained in Title 10, "Energy" of the Code of Federal

Regulations , Chapter 1, Parts 1 to 199.

Section 8: Glossary

1. A worker displays a small ceramic fuel pellet.

2. A piece of natural uranium ore.3. Diagram of a moisture density gauge.Section 9: Web Link Index

1. A computer and keyboard.2. An icon of the World Wide Web and url address link.

3. A graphical representation of the global reach of the Internet.

iii iiiAbstract The U.S. Nuclear Regulatory Commission (NRC) has published the Information Digest annually since 1989.

The Information Digest provides information about the agency and the industries it regulates. It describes the agency's 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 2017-2018 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 data) that were updated as of May 2017 with revisions in October, including data associated with maps and graphics. The next Information Digest that will contain updated data will be published in August 2019. In this edition, we have not included industry trends information from 2001 to 2016 because the program was discontinued. The Digest will remain an annual publication, with certain data being updated every 2 years. Readers will be directed to the most current

information, which is available online.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 ~nal unless otherwise noted.

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 Of~ce of Public Affairs at U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or at

OPA.Resource@nrc.gov.

iv NRC resident inspectors perform routine inspection activities to ensure nuclear power plants operate according to NRC regulations.

vContentsAbstract iii NRC At A Glance xi 2016-2017 Accomplishments and Highlights xv 1. NRC: An Independent Regulatory Agency 1 Mission 2 Major Activities 4 Organizations and Functions 8Fiscal Year 2017 Budget 12 2. Nuclear Energy in the U.S. and Worldwide 15Worldwide Electricity Generated by Commercial Nuclear Power 16International Activities 17 3. Nuclear Reactors 23U.S. Electricity Generated by Commercial Nuclear Power 24U.S. Commercial Nuclear Power Reactors 24Oversight of U.S. Commercial Nuclear Power Reactors 32 Reactor License Renewal 34Research and Test Reactors 37New Commercial Nonpower Production and Utilization Facility Licensing 39New Commercial Nuclear Power Reactor Licensing 41Nuclear Regulatory Research 45 4. Nuclear Materials 49 Materials Licenses 50 Medical and Academic 51 Industrial 52Transportation 54 Material Security 55 Nuclear Fuel Cycle 56 Fuel Cycle Facilities 60 vi5. Radioactive Waste 63Low-Level Radioactive Waste Disposal 64High-Level Radioactive Waste Management 66Transportation 72 Decommissioning 73 6. Security and Emergency Preparedness 77 Overview 78 Facility Security 78 Cyber Security 79 Materials Security 80Emergency Preparedness 80 Incident Response 83 Emergency Classi~cations 84International Emergency Classi~cations 85 7. Appendices 87Abbreviations 88Quick-Reference Metric Conversion Tables 90 APPENDIX A: Commercial Nuclear Power Reactors 92 APPENDIX B: New Nuclear Power Plant Licensing Applications 109APPENDIX C: Commercial Nuclear Power Reactors Undergoing Decommissioning and Permanently Shut Down Formerly Licensed To Operate 110 APPENDIX D:

Canceled Commercial Nuclear Power Reactors 114 APPENDIX E:

Commercial Nuclear Power Reactors by Parent Company 120 APPENDIX F: Commercial Nuclear Power Reactor Operating Licenses-Issued by Year 122 APPENDIX G: Commercial Nuclear Power Reactor Operating Licenses-Expiration by Year, 2013-2055 122 APPENDIX H: Operating Nuclear Research and Test Reactors

Regulated by the NRC 123 APPENDIX I: Nuclear Research and Test Reactors under Decommissioning

Regulated by the NRC 125 APPENDIX J:

Radiation Doses and Regulatory Limits 125 vii APPENDIX K: Materials Licenses by State 126 APPENDIX L:

Major U.S. Fuel Cycle Facility Sites 127 APPENDIX M: Dry Spent Fuel Storage Designs:

NRC-Approved for Use by General Licensees 128 APPENDIX N:

Dry Cask Spent Fuel Storage Licensees 129 APPENDIX O:

U.S. Low-Level Radioactive Waste Disposal Compact Membership 133 APPENDIX P:

NRC-Regulated Complex Materials Sites Undergoing Decommissioning, 2016 134 APPENDIX Q:

Nuclear Power Units by Nation 135 APPENDIX R:

Nuclear Power Units by Reactor Type, Worldwide 136 APPENDIX S: Native American Reservations and Trust Lands

within a 50-Mile Radius of a Nuclear Power Plant 137APPENDIX T:

States with Integrated University Grants Program Recipients in FY 2016 138 APPENDIX U:

Signi~cant Enforcement Actions Issued, 2016 139APPENDIX V:

Laws Governing the U.S. Nuclear Regulatory Commission 141APPENDIX W:

International Activities: Conventions and Treaties Pertaining

to Nuclear Safety, Security, and International Safeguards 142 APPENDIX X:

International Activities: List of the NRC's Participation with

Multilateral Organizations 143APPENDIX Y:

International Activities: List of Import and Export Licenses

issued for 2016 1458. Glossary 149Glossary (Abbreviations, Definitions, and Illustrations) 1509. Web Link Index 183 viiiFiguresNRC: An Independent Regulatory AgencyFigure 1. How We Regulate 3Figure 2. A Typical Rulemaking Process 6Figure 3. NRC Organizational Chart 9Figure 4. NRC Regions 11Figure 5. NRC Total Authority, FYs 2007-2017 12Figure 6.

NRC FY 2017 Distribution of Enacted Budget Authority; Recovery of NRC Budget 13 Nuclear Energy in the U.S. and WorldwideFigure 7. Nuclear Share of Electricity Generated by Country 16 Nuclear ReactorsFigure 8. U.S. Gross Electric Generation by Energy Source, 2016 25Figure 9. U.S. Electric Share and Generation by Energy Source, 2011-2016 25Figure 10. Gross Electricity Generated in Each State by Nuclear Power 26Figure 11. U.S. Operating Commercial Nuclear Power Reactors 28Figure 12. Day in the Life of an NRC Resident Inspector 29Figure 13. NRC Post-Fukushima Safety Enhancements 31Figure 14. Reactor Oversight Action Matrix Performance Indicators 33Figure 15. Reactor Oversight Framework 33Figure 16. License Renewals Granted for Operating Nuclear Power Reactors 35Figure 17.

U.S. Commercial Nuclear Power Reactors-

Years of Operation by the End of 2017 35Figure 18. License Renewal Process 36Figure 19. Size Comparison of Commercial and Research Reactors 37Figure 20. U.S. Nuclear Research and Test Reactors 38Figure 21. The Different NRC Classi~cations for Types of Reactors 40Figure 22. New Reactor Licensing Process 42Figure 23. Locations of New Nuclear Power Reactor Applications 42Figure 24. NRC Research Funding, FY 2017 47 ix Nuclear MaterialsFigure 25. Agreement States 50Figure 26. Life-Cycle Approach to Source Security 55Figure 27. The Nuclear Fuel Cycle 56Figure 28. The In Situ Uranium Recovery Process 58Figure 29. Locations of NRC-Licensed Uranium Recovery Facility Sites 59Figure 30. Locations of NRC-Licensed Fuel Cycle Facilities 61Figure 31. Simpli~ed Fuel Fabrication Process 61 Radioactive Waste Figure 32. Low-Level Radioactive Waste Disposal 65Figure 33. Spent Fuel Generation and Storage After Use 68Figure 34. Dry Storage of Spent Nuclear Fuel 70 Figure 35. Licensed and Operating Independent Spent Fuel Storage

Installations by State 71Figure 36. Ensuring Safe Spent Fuel Shipping Containers 72Figure 37. Reactor Decommissioning Overview Timeline 73Figure 38. Power Reactor Decommissioning Status 74Figure 39. Locations of NRC-Regulated Sites Undergoing Decommissioning 75 Security and Emergency PreparednessFigure 40. Security Components 79Figure 41. Emergency Planning Zones 81Figure 42. The International Nuclear and Radiological Event Scale 85 xNRC regulations are contained in Title 10, "Energy," of the Code of Federal Regulations, Chapter 1, Parts 1 to 199.

xiMission The U.S. Nuclear Regulatory Commission (NRC) is an independent agency created by Congress. Its mission is to license and regulate the civilian use of radioactive materials in the United States to protect public health and safety, promote the common defense and security, and protect the environment.The NRC regulates commercial nuclear power plants; research, test, and training reactors; nuclear fuel cycle facilities; and radioactive materials used in medicine, academia, and industry. The agency also regulates the transport, storage, and disposal of radioactive materials and waste; most Federal agencies' use and possession of radioactive materials; and the export and import of radioactive materials.

Commission Chairman Kristine L. Svinicki Term ends June 30, 2022Commissioner Jeff Baran Term ends June 30, 2018 Commissioner Stephen G. Burns Term ends June 30, 2019Vacant Vacant Locations Headquarters:

U.S. Nuclear Regulatory Commission Rockville, MD, 301-415-7000, 1-800-368-5642 Regional Of~ces:

Region I-King of Prussia, PA, 610-337-5000, 1-800-432-1156

Region II-Atlanta, GA, 404-997-4000, 1-800-577-8510 Region III-Lisle, IL, 630-829-9500, 1-800-522-3025 Region IV-Arlington, TX, 817-860-8100, 1-800-952-9677 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, Chattanooga, TN, 423-855-6500 Professional Development Center, Rockville, MD, 301-287-0556 Resident Sites:

At least two NRC resident inspectors, who report to the appropriate regional of~ce, are located at each nuclear power plant site.

NRC Fiscal Year 2017 Budget

• Total authority: $940 million ($917 million enacted budget with $23 million carryover authority)

• Total authorized staff: 3,396 full-time equivalents

• Estimated fees to be recovered: $804.6 million

• The Of~ce of the Inspector General received its own appropriation of $12.1 million

• Total Research Budget: $30 million Reactor Program: $22 million New/Advanced Reactor Licensing: $6 million Materials and Waste: $2 million NRC AT A GLANCE xiiWhat Does the NRC Do?

• Regulation and guidance-rulemaking

• Policymaking

• Licensing, decommissioning, and certi~cation

• Research

• Oversight and enforcement

• Emergency preparedness and response

• Incident response NRC Governing Legislation The NRC was established by the Energy Reorganization Act of 1974. The most signi~cant laws that govern the regulatory process of the agency are in Appendix V to this Digest. The NRC's 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 NumbersU.S. Electricity Generated by Commercial Nuclear PowerNRC-licensed nuclear reactors generate about 20 percent of U.S. gross electricity, or about

805 billion kilowatt-hours.

Nuclear Reactors

• 99 commercial nuclear power plants operating in 30 States at 59 sites

- 65 pressurized-water reactors and 34 boiling-water reactors

• Four reactor fuel vendors

• 23 parent operating companies

• About 80 different designs

• About 6,550 total inspection hours at each operating reactor site in 2016

• Licensees expected to shut down or not seek license renewal include:

- Palisades Nuclear Plant (Entergy) will close by end of October 2022.

- Pilgrim Nuclear Power Station (Entergy) will close by end of May 2019.

- Three Mile Island Unit 1 (Exelon) plans to shut down in September 2019.

- Indian Point Nuclear Generating Station, Units 2 and 3 (Entergy), will close in 2020 and 2021, respectively.

- Oyster Creek (Exelon) plans to shut down in December 2019.

- Diablo Canyon (Paci~c Gas & Electric) intends to close by August 2025.

Reactor License Renewal Commercial power reactor operating licenses are valid for 40 years and may be renewed for additional 20-year terms.

• 13 reactors operate under their original license.

• 89 reactors were issued renewal licenses, including 3 reactors permanently shut down.

• Five sites have license renewal applications in review.

• Three sites have submitted letters of intent to request initial license renewal.

• Two sites have submitted letters of intent to request subsequent license renewal.

Early Site Permits for New Reactors

• Five early site permits (ESPs) issued and one application docketed:

- System Energy Resources, Inc., for the Grand Gulf site in Mississippi

- Exelon Generation Company, LLC, for the Clinton site in Illinois

- Dominion Nuclear North Anna, LLC, for the North Anna site in Virginia

- Southern Nuclear Operating Company, for the Vogtle site in Georgia

- PSEG Power, LLC, and PSEG Nuclear, LLC, for a site in New Jersey

- The NRC is reviewing one ESP application from the Tennessee Valley Authority (TVA) for two or more small modular reactor (SMR) modules at the Clinch River Nuclear Site in Roane County, Tennessee.

xiiiCombined License-Construction and Operating 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 suspended or canceled 10 COL application reviews at the request of the applicants (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).

• As of July 1, 2017, the NRC has issued COLs for 12 reactors at Fermi, MI; North Anna, VA; South Texas Project, TX; V.C. Summer, SC; and Vogtle, GA. On July 31, 2017 South Carolina Electric & Gas (SCE&G) announced plans to cease construction on V.C. Summer nuclear power plant, Units 2 and 3; and as of October 2017, Duke Energy has announced plans to cancel Levy County, FL Units 1 and 2, and William States Lee, SC Units 3 and 4.

• The NRC has completed the safety and environmental reviews for two reactors at Turkey Point, FL Mandatory and contested hearings are planned for Fall 2017.

• Five reactor design certi~cations (DCs) have been issued:

- General Electric Nuclear Energy's ABWR (Advanced Boiling-Water Reactor)

- Westinghouse Electric Company's System 80+

- Westinghouse Electric Company's AP600

- Westinghouse Electric Company's AP1000

- General Electric-Hitachi Nuclear Energy's ESBWR (Economic Simpli~ed Boiling-Water Reactor)

• Three DC applications are under review for the APR1400, US-APWR designs, and NuScale designs.

• One DC application for US-EPR (Evolutionary Pressurized-Water Reactor) is suspended at the request of the applicant.

• One DC renewal application is under review for the ABWR design.

Nuclear Research and Test Reactors

• 31 licensed research and test reactors operate in 21 States.

Nuclear Materials Materials Licensing

• The NRC and the Agreement States have approximately 19,600 licensees for medical, academic, industrial, and general users of nuclear materials.

- The NRC regulates approximately 2,600 licenses.

- 37 Agreement States regulate approximately 17,000 licenses.

• Wyoming has submitted a draft application and Vermont has submitted a letter of intent to become Agreement States.

• The NRC issues approximately 2,000 new licenses, renewals, or amendments for existing materials licenses annually. The NRC conducts approximately 900 health, safety, and security inspections of materials licensees each year.

Nuclear Fuel Cycle

• 11 uranium recovery sites are licensed by the NRC:

- 10 in situ recovery sites

- One conventional mill in standby status with the potential to restart in the future

• Three applications have been submitted for renewal; two are active, one is delayed.

• Six applications for facility expansion have been received. Three of those applications are under review.

• 13 fuel cycle facilities are licensed by the NRC:

- One uranium hexauoride conversion facility

- Five uranium fuel fabrication facilities

- Four gas centrifuge uranium enrichment facilities (one operating, one used for testing and currently transitioning to decommissioning, and two construction pending)

- One mixed-oxide fuel fabrication facility (under construction and review)

- One laser separation enrichment facility (construction decision pending)

- One uranium hexauoride deconversion facility (construction decision pending)

• The NRC issues about 60 fuel cycle facility licensing actions per year, including amendments; renewals; new licenses; and safety, environmental, and safeguards reviews.

xivNational Source Tracking System The National Source Tracking System, also known as NSTS, tracks more than 76,000 sources held by about 1,400 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.

Domestic Safeguards The NRC and the U.S. Department of Energy use the Nuclear Materials Management and Safeguards System (NMMSS) to track transfers and inventories of special nuclear material. Licensees that import and export source material, and licensees that possess foreign-obligated source material, must report transfers and inventories to NMMSS. More than 300 licensees report to the NMMSS database. These licensees verify their inventories on an annual basis through a process of reconciliation that checks their reported transactions against their previous year's inventory.

Radioactive Waste Low-Level Radioactive Waste

• 10 regional compacts

• Four licensed disposal facilities High-Level Radioactive Waste Management Spent Nuclear Fuel Storage

• 78 licenses for independent spent fuel storage installations in 34 States:

- 15 site-speci~c licenses

- 63 general licenses

Transportation-Principal Licensing and Inspection Activities

• 1,000 safety inspections of fuel, reactor, and materials licensees are conducted annually.

• 50-70 new, renewal, or amended container-design applications for the transport of nuclear materials are reviewed annually.

• 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 Nation's yearly hazardous material shipments.

Decommissioning Approximately 150 materials licenses are terminated each year. The NRC's decommissioning program focuses on the termination of licenses that are not routine and that require complex

activities.

• 20 nuclear power reactors in various stages of decommissioning (DECON or SAFSTOR)

• Four research and test reactors permanently shut down and in various stages of decommissioning

• 13 complex materials sites in various stages of decommissioning

• Two fuel cycle facilities (partial decommissioning)

• 11 NRC-licensed uranium recovery facilities in various stages of decommissioning 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 (FEMA).

• Plants conduct additional emergency drills between full-scale exercises to maintain their preparedness and pro~ciency in responding to emergencies.

• Every 3 years, each nuclear plant undergoes a force-on-force security inspection. These inspections include mock combat drills. The NRC spends about 16,000 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.

xvNuclear Reactors Power Reactors

• con~rmed implementation of post-Fukushima safety enhancements related to the mitigating strategies and spent fuel pool instrumentation orders; resolved and closed remaining Tier 2 and 3 recommendations

• completed more than 1,200 licensing actions and other licensing tasks, while also reviewing a number of nuclear power plant license renewal applications

• issued combined licenses for Levy County Units 1 and 2 (Florida), Williams States Lee

Units 1 and 2 (South Carolina), and North Anna Unit 3 (Virginia)

• issued the ~nal environment impact statement and ~nal safety evaluation report for the Turkey Point Units 6 and 7 (Florida) combined license application

• continued oversight of construction at two new reactor construction sites-one reactor site announced cease of construction activity on July 31, 2017

• completed all required inspection and assessment activities of the Reactor Oversight Process, including initiating six inspections in response to safety-signi~cant events

• participated in Eagle Horizon 2016 and 2017, a national-level exercise that tested the NRC's ability to relocate senior managers during a Continuity of Operations event

• completed the fourth full cycle of force-on-force security inspections at U.S. nuclear power plants, testing licensees' abilities to protect against a design-basis threat

• completed comprehensive review of security plans for three decommissioning reactor sites, the ~rst such reviews since 2001

• strengthened nuclear safety cooperation through more than 100 active international agreements, including new international partnerships under the recently created Radiation Protection Analysis Program

• published extensive research results on a variety of topics related to operating facility safety, including analysis of cladding behavior during postulated accident conditions, fracture toughness of cast stainless steel under irradiated and thermal conditions, and improvements to ~re probabilistic risk assessment accuracy Nonpower Reactors

• continued reviewing a construction permit application for Northwest Medical Isotopes, LLC, for a medical isotope production facility in Missouri

• eliminated the backlog of license renewal requests for research and test reactorsMaterials and Waste

• completed approximately 1,800 radioactive materials licensing actions

• issued NUREG-1927, Revision 1, "Standard Review Plan for Renewal of Speci~c Licenses and Certi~cates of Compliance for Dry Storage of Spent Nuclear Fuel," Final Report

• completed the acceptance review for the consolidated interim storage facility applications from Waste Control Specialists, LLC and Holtec International, Inc

• completed nine Integrated Materials Performance Evaluation Program reviews of Agreement States, ~nding all adequate to protect public health and safety

• issued a source and byproduct materials license to AUC LLC for its Reno Creek In Situ Recovery Project in Campbell County, WY

• issued a major license amendment to Uranerz Energy Corporation for its Nichols Ranch In Situ Recovery Project in Powder River Basin, WY

• worked with other Federal agencies (U.S. Department of Energy, U.S. Department of State, and U.S. Environmental Protection Agency) to complete the sixth review cycle of the Joint

Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

• completed the Regulatory Basis for the proposed Rulemaking for Cyber Security at Fuel Cycle Facilities

• issued a report to Congress that evaluates the effectiveness of the requirements of Title 10

of the Code of Federal Regulations Part 37, "Physical Protection of Category 1 and

Category 2 Quantities of Radioactive Material"2016-2017 ACCOMPLISHMENTS AND HIGHLIGHTS xvi* issued the Tribal Policy Statement, establishing general policy principles to promote effective government-to-government interactions with American Indian and Alaska Native Tribes, and to encourage and facilitate Tribal involvement in areas where the Commission has jurisdiction

• deployed a portal for searching and analyzing 3.6 million documents related to the U.S. Department of Energy's (DOE) application for authorization to construct a high-level nuclear waste geologic repository at Yucca Mountain, NV Agencywide

• continued to reprioritize the agency's work, increase ef~ciency and effectiveness, and improve the ability to adapt to a changing work environment

• pursued substantial rulemaking activities on topics including decommissioning of nuclear reactors; mitigation of beyond-design-basis events; performance-based emergency core cooling system acceptance criteria; enhanced weapons, ~rearms background checks, and security event noti~cations; cyber security for fuel facilities; enhanced security for special nuclear material; low-level radioactive waste disposal; medical use of byproduct material; and the modi~ed small quantities protocol

• deployed a centralized,web-based tracking and reporting system in March 2017 to provide real-time updates on all NRC rulemaking activities at https://www.nrc.gov/about-nrc/regulatory/

rulemaking/rules-petitions.html

• issued the ~scal year (FY) 2016 proposed fee rule, held a public meeting to support stakeholder outreach, and incorporated the comments received in the ~nal fee ruleInternational Activities

• participated in various U.S. Government nuclear safety and security initiatives in collaboration with U.S. executive branch agencies through activities such as Nuclear Suppliers Group meetings and Joint Standing Committees on Nuclear Energy Cooperation

• participated as part of U.S. Government delegations to international meetings addressing implementation of treaties and conventions, including the Seventh Review Meeting for the Convention on Nuclear Safety

• participated in the International Atomic Energy Agency's (IAEA) Annual Meeting of the Standing Advisory Group on Technical Assistance and Cooperation and high-level International Conference on Nuclear Security

• provided updates on the status of the Convention on Nuclear Safety Open-Ended Working Group proposal at the 2017 G7 Nuclear Safety and Security Group meeting

• represented the NRC at the European Commission's high-level seminar on International Nuclear Cooperation: Expectations and Responsibilities

• supported several IAEA regulatory peer review missions, such as the Integrated Regulatory Review Service and the International Physical Protection Advisory Service

• participated with the U.S. executive branch agencies in the United States-Republic of Korea High Level Bilateral Commission meeting to discuss civilian nuclear programs

• arranged assistance projects for more than 140 countries

• supported completion of veri~ed national registries of radioactive sources, through the NRC's Radioactive Sources Regulatory Partnership, for about 20 regulatory counterparts

• continued regulatory program development assistance, through the NRC's International Regulatory Development Partnership, for about 30 countries considering civilian nuclear power programs

• continued participation on the U.S. delegation to the Nuclear Suppliers Group

• represented the NRC on the U.S. delegation to the Treaty on the Non-Proliferation of Nuclear Weapons Preparatory Committee meeting

• continued representing the NRC on the U.S. delegation negotiating agreements for civil nuclear cooperation (Section 123 Agreements) xviiAdministration

• processed 753 Freedom of Information Act (FOIA) requests and 166 appeals in FY 2016, with 21 FOIA requests and one FOIA appeal in the backlog by the end of FY 2016

• Issued 89 escalated enforcement actions, 16 actions involving civil penalties, and 61 escalated notices of violation without a proposed civil penalty

• continued to conduct agency outreach to audiences interested in NRC activities, including through the use of social media

• awarded and maintained a portfolio of more than 700 contracts and interagency agreements with obligations in excess of $317 million in FY 2016

• supported U.S. General Services Administration (GSA) signing a succeeding lease on the NRC's behalf in December 2016 for the continued occupancy of the Technical Training Center in Chattanooga, TN, allowing the NRC to remain at the location through 2036

• supported GSA signing a succeeding lease on the NRC's behalf in April 2016, effective in December 2018, for the continued occupancy of Two White Flint North through December 2033

• In FY 2016, the NRC received 85 proposals for the Integrated University Program and awarded 51 grants: 12 faculty development, 17 scholarship, 15 fellowship, and 7 trade school/community college scholarships; awarded $15 million in grants to 39 academic institutions

• awarded $1.98 million in grants to 9 Minority Serving Institutions in FY 2016Public Meetings and Involvement

• hosted the annual Regulatory Information Conference and the Fuel Cycle Information Exchange, where thousands of participants from around the world discussed the latest technical issues

• conducted approximately 1,000 public meetings in the Washington, DC, area and around the country addressing a full range of NRC issues

• conducted 9 full committee meetings of the Advisory Committee on Reactor Safeguards and approximately 70 subcommittee meetings in calendar year 2016

• held six public meetings of the Advisory Committee on the Medical Uses of Isotopes in calendar year 2016 News and Information

• continued to use the Web site and free listserv subscription services at https//www.nrc.gov/

public-involve/listserver.html to post NRC news releases

• continued using social media as a communication tool to allow the public to stay connected and share NRC information through the NRC Blog, Twitter, Flickr, YouTube, and Facebook For more information on the agency's accomplishments, go to https://www.nrc.gov/reading-rm/

doc-collections/congress-docs/

.

xviiiContact Us U.S. Nuclear Regulatory Commission 1-800-368-5642, 301-415-7000, TTD: 301-415-5575 Public Affairs 301-415-8200, Fax: 301-415-3716 e-mail: opa.resource@nrc.gov Public Document Room

1-800-397-4209, Fax: 301-415-3548 TDD: 1-800-635-4512 Employment Human Resources: 301-415-7400

General Counsel Intern Program, Honor Law Graduate Programs, or 2-Year Judicial Clerkship Program: 301-415-1515 Contracting Opportunities Small Business: 1-800-903-7227 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 11555 Rockville Pike, Rockville, MD 20852 Stay Connected https://www.~ickr.

com/photos/nrcgov Flickr https://public-blog.nrc-gateway.gov/

NRC Bloghttps://www.youtube.

com/user/NRCgovYouTube https://www.nrc.gov/public-involve/listserver.html#gov GovDeliveryhttps://twitter.com/

/nrcgovTwitterhttps://www.nrc.gov/public-involve/listserver.html#rss RSShttps://www.facebook.com/

nrcgov/Facebook xixReport a Concern Emergency Report an emergency involving a nuclear facility or radioactive materials, including:

• 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 NRC's 24-Hour Headquarters Operations Center:

301-816-5100 We accept collect calls. We record 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:

NRC's 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 Standard 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 at https://scp.nrc.gov/allegations.html.

The NRC's Office of the Inspector General The Of~ce 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 con~dentially 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 identi~cation feature associated with the hotline or any other telephone line in the Inspector General's of~ce. 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:

1-800-233-3497, TDD: 1-800-270-2787 7 a.m.-4 p.m. (Eastern Standard Time)

After hours, please leave a message.

1 2MissionThe U.S. Nuclear Regulatory Commission (NRC) is an independent agency created by Congress. Its mission is to license and regulate the civilian use of radioactive materials in the United States to protect public health and safety, promote the common defense and security, and protect the environment. The NRC regulates commercial nuclear power plants; research, test, and training reactors; nuclear fuel cycle facilities; and radioactive materials used in medicine, academia, and industry. The agency also regulates the transport, storage, and disposal of radioactive materials and waste; most Federal agencies' use and possession of radioactive materials; and the export and import of radioactive materials. The NRC regulates industries within the United States and works with agencies around the world to enhance global nuclear safety and security. To ful~ll its responsibilities, the NRC performs ~ve principal regulatory functions, as seen in Figure 1: How We Regulate.

Vision and Values A trusted, independent, transparent, and effective nuclear regulatorTo 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. This vision is an outgrowth of the NRC operating in a manner consistent with its longstanding Principles of Good Regulation-independence, openness, ef~ciency, clarity, and reliability-and its organizational values.These principles guide 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 external

stakeholders. By adhering to these principles and values, the NRC maintains its regulatory competence, conveys that competence to the stakeholders, and promotes trust in the agency. The agency puts these principles into practice with effective, realistic, and timely actions.

NRC Organizational Values Integrity in our working relationships, practices, and decisions Service to the public and others who are affected by our work Openness in communications and decision making Commitment to public health and safety, security, and the environment Cooperation in the planning, management, and performance of agency work Excellence in our individual and collective actions Respect for individuals' diversity, roles, beliefs, viewpoints, and work/life balance 3Figure 1. How We Regulate

1. Developing regulations and guidance for applicants and licensees.

2. Licensing or certifying applicants to use nuclear materials, operate nuclear facilities, and decommission facilities.

3. Inspecting and assessing licensee operations and facilities to ensure licensees

comply with NRC requirements, responding to incidents, investigating allegations

of wrongdoing, and taking appropriate followup or enforcement actions when necessary.

4. Evaluating operational experience of licensed facilities and activities.

5. Conducting research, holding hearings, and obtaining independent reviews to support regulatory decisions.NRC staff members meet with stakeholders to discuss the agency's regulatory issues.

4Strategic 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 oversee-but not promote-the commercial nuclear industry so the United States could bene~t from the use of radioactive materials while also protecting people and the environment. The agency began operations on January 18, 1975. The NRC's regulations can be found in Title 10, "Energy,"

of the Code of Federal Regulations (10 CFR). The principal statutory authorities that govern the NRC's work can be found on the NRC's Web site (see the Web Link Index for more information).

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 NRC's regulatory program play a key role.

Ultimately, however, the licensees bear the primary responsibility for safely handling and using radioactive materials.

Major ActivitiesThe NRC ful~lls its responsibilities by doing the following:

• licensing the design, 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

• licensing the siting, design, construction, operation, and closure of low-level radioactive waste (LLW) disposal sites in States under NRC jurisdiction

• certifying the design, construction, and operation of commercial transportation casks

• licensing the design, construction, and operation of spent fuel storage casks and interim storage facilities for spent fuel and high-level radioactive waste

• licensing nuclear reactor operators See the complete list of NRC's authorizing

legislation in Appendix V.

5* licensing uranium enrichment facilities

• conducting research to develop regulations and to anticipate potential reactor and other nuclear facility safety issues

• collecting, analyzing, and disseminating information about the safe 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 and security issues

• investigating nuclear incidents and allegations concerning any matter regulated by the NRC

• 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 and security and on environmental concerns

• implementing international legal commitments made by the U.S. Government in treaties and conventions

• developing effective working relationships with State and Tribal governments

• maintaining an effective 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

• 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; providing ways to report safety concerns; and providing documents under the Freedom of Information Act and through the NRC's Web site (see Figure 2: A Typical Rulemaking Process)

• engaging and informing the public through social media platforms and by providing interactive, high-value data sets (data in a form that allows members of the public to search, ~lter, or repackage information)

6Figure 2. A Typical Rulemaking ProcessThe 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.

Proposed Rules NRC regulations (rules) provide licensees with requirements that, if met, will result

in adequate protection of workers, the public, and the environment. The impetus

for a proposed rule could be a direction from the Commission to the NRC staff or a petition for rulemaking submitted by a member of the public. Each proposed rule that involves signi~cant matters of policy is sent to the NRC Commission for

approval.

7 If approved, the proposed rule is published in the Federal Register and usually contains the following items:

1. the background information about the proposed rule

2. an address for submitting comments

3. the date by which comments should be received in order to ensure consideration by the staff

4. an explanation indicating why the rule change is thought to be needed, 5. the proposed text to be changed Usually, the public is given 75 to 90 days to provide written comments. Not all rules are issued for public comment. Generally, those excepted from public comment concern agency organization, procedure, or practice; are

interpretive rules (e.g., guidance interpreting current regulations); or are rules for which delaying their publication to receive comments would be contrary to public interest and impracticable.

Final Rules Once the public comment period has closed, the staff analyzes the

comments, makes any needed changes, and prepares a draft ~nal rule for

Commission approval. Once approved, the ~nal 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 ~nal rulemaking process. This process is only used for

regulatory changes that the NRC believes are noncontroversial.

Advance Notice of Proposed Rulemakings For especially important or complex rules, the NRC may publish an

advance notice of proposed rulemaking and conduct one or more public

meetings. 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.

8Organizations and FunctionsThe NRC's Commission has ~ve members nominated by the President of the United States and con~rmed by the U.S. Senate for 5-year terms. The members' terms are staggered so one Commissioner's term expires on June 30 of each year. The President designates one member to serve as Chairman. The Chairman is the principal executive of~cer 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 of~ces (see Figure 3: NRC Organizational Chart).Commissioner Term Expiration*

The NRC is headquartered in Rockville, MD, and has four regional of~ces. They are located in King of Prussia, PA; Atlanta, GA; Lisle, IL; and Arlington, TX. The major program of~ces within the NRC include:

The Of~ce of Nuclear Reactor Regulation handles all licensing and inspection activities for existing nuclear power reactors and research and test reactors.

The Of~ce of New Reactors oversees the design, siting, licensing, and construction of new commercial nuclear power reactors.

The Of~ce of Nuclear Regulatory Research provides independent expertise and information for making timely regulatory judgments, anticipating potentially signi~cant 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.* Commissioners listed by seniority. There are two positions vacant.

Stephen G. Burns June 30, 2019VacantVacant Kristine L. Svinicki Chairman June 30, 2022 Jeff Baran June 30, 2018 9Figure 3. NRC Organizational Chart Note: For the most recent information, go to NRC Organizational Chart at https://www.nrc.gov/about-nrc/organization.html 10 The Of~ce 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 of~ce also works with other Federal agencies, States, and Tribal and local governments on regulatory matters.

The Of~ce of Nuclear Security and Incident Response initiates and oversees 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 of~ce also maintains the NRC's emergency preparedness and incident response programs.

The NRC regional of~ces conduct inspections and investigations, take enforcement actions (in coordination with the Of~ce of Enforcement), and maintain emergency response programs for nuclear reactors, fuel facilities, and materials licensees. In addition, the regional of~ces carry out licensing for certain materials licensees (see Figure 4: NRC Regions).

The advisory committees, including the Advisory Committee on Reactor Safeguards (ACRS) and the Advisory Committee on the Medical Uses of Isotopes (ACMUI), are independent of the NRC staff. The ACRSs report directly to the Commission, which appoints their 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 Commission's 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.

The NRC headquarters complex is located in Rockville, MD.

11Figure 4. NRC Regions Nuclear Power Plants

• Each regional of~ce oversees the plants in its region-except 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.

12Fiscal Year 2017 Budget For ~scal year (FY) 2017 (October 1, 2016, through September 30, 2017), the NRC's budget is $917.1 million. The NRC's FY 2017 full-time equivalents (FTE) are 3,396; this includes the Of~ce of the Inspector General (see Figure 5: NRC Total Authority, FYs 2007-2017). The Of~ce of the Inspector General received its own appropriation of $12.1 million. This amount is included in the total NRC budget. The breakdown of the budget is shown in Figure 6: NRC FY 2017 Distribution of Total Authority; Recovery of NRC Enacted Budget. By law, the NRC must recover, through fees billed to licensees, approximately 90 percent of its budget authority, less the amounts appropriated from general funds for Waste-Incidental-to-Reprocessing activities, Generic Homeland Security activities, Defense Nuclear Facilities Safety Board activities, and Advanced

Reactors Regulatory Readiness activities. The NRC collects fees each year by September 30 and transfers them to the U.S. Treasury. Estimated fees to be recovered in FY 2017 are $804.6 million.Figure 5. NRC Total Authority, FYs 2007-2017 13Figure 6.

NRC FY 2017 Distribution of Enacted Budget Authority; Recovery of NRC Budget

• Recovered fees do not include the use of prior year carryover where fees were previously collected. Notes: The NRC incorporates corporate and administrative costs proportionately within programs.

Numbers are rounded. Enacted Budget for FY 2017.

15 16Worldwide Electricity Generated by Commercial Nuclear Power Nuclear reactor technology was ~rst developed in the 1940s initially for producing weapons, but President Dwight D. Eisenhower's Atoms for Peace program shifted the focus to power generation, scienti~c 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 May 2017, there were 449 operating reactors in 30 countries with a total installed capacity of 392,116 megawatts electric (MWe). In addition, two nuclear power plants were in long-term shutdown and 60 were under construction. Based on preliminary data from 2016, France had the highest portion (72 percent) of total domestic energy generated by nuclear power (Figure 7: Nuclear Share of Electricity Generated by Country).

See Appendix Q for the number of nuclear power reactor units

by nation and Appendix R for nuclear power reactor units by reactor type, worldwide.Figure 7. Nuclear Share of Electricity Generated by CountryNote: Each country's short-form name is used.

Source: IAEA, Power Reactor Information System database, as of May 2017 17See Appendices W, X, and Y for lists of international activities.In addition to generating electricity, nuclear materials and technology are used worldwide for many other peaceful purposes, such as:

• 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 related to the safe and secure civilian use of nuclear materials and technologies.

International Activities The NRC's international activities support the NRC's domestic mission, as well as broader U.S. domestic and international interests. They are wide ranging and address these issues:

• convention and treaty implementation

• nuclear nonproliferation

• export and import licensing for nuclear materials and equipment

• international safeguards support and assistance

• international safety and security cooperation and assistance

• international safety and security information exchanges

• cooperative safety research

• physical protection

• emergency noti~cation and assistance

• liabilityThe 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 learn the best regulatory safety and security practices. In addition, joint research projects give the NRC access to research facilities not available in the United States.

The NRC also works with other U.S. agencies to implement conventions and treaties by participating in interagency groups devoted to establishing and enforcing rules, regulations, and policies.

18Conventions and TreatiesAll 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 (CNS). 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. The Convention is an important part of the evolving global nuclear safety regime.In addition, the NRC actively participates in and provides support for the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention establishes an international peer review process and provides incentives for nations to take appropriate steps to bring their nuclear activities into compliance with general safety standards and practices. Both the CNS and the Joint Convention are important parts of the evolving global nuclear safety regime.Other examples include the NRC's international cooperation and assistance activities, as well as import and export licensing of nuclear materials and equipment. These activities ful~ll obligations undertaken according to Articles II, III, and IV of the Treaty on the Non-Proliferation of Nuclear Weapons, which, for instance, gives all parties to the Treaty the right to participate in the fullest possible exchange of equipment, materials, and scienti~c and technological information for the peaceful uses of nuclear energy.

Export and Import LicensingThe NRC conducts reviews to license exports and imports of nuclear materials and equipment to determine that such exports and imports will be in the best interest of the United States and will be consistent with agreements for the peaceful use of nuclear materials (Section 123 Agreements). The NRC's export and import regulations are found in

10 CFR 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.

See Appendix W for a list of Conventions and

Treaties and Appendix Y for a list of export and import licenses.

19Bilateral Cooperation and AssistanceThe NRC has information-sharing agreements with other countries, as well as Taiwan and the European Atomic Energy Community (see Appendix X for the list of bilateral information exchange and cooperation agreements with the NRC).

CooperationThere are 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. With countries that have new programs, the NRC focuses on helping develop and improve their regulatory activities.

Some of the bene~ts of consulting with other countries include:

• awareness of reactor construction activities that could apply to new reactors being built in the United States

• prompt noti~cation to foreign partners of U.S. safety issues

• sharing of safety and security information AssistanceThe NRC offers bilateral training, workshops, and peer reviews of regulatory documents to assist more than 60 countries as they develop or enhance their national nuclear regulatory infrastructures and programs. The NRC also supports and participates in regional working group meetings to exchange technical information among specialists. If asked, the NRC will respond directly to countries looking for help to improve their controls of radioactive material.

See Appendix X for a list of the NRC's participation with

multilateral organizations and a list of countries with bilateral information exchange

and cooperation agreements with the NRC.The NRC participates in the annual General Conference for the International Atomic Energy Agency in Vienna, Austria.

Photo courtesy of IAEA 20Foreign Assignee Program The NRC provides on-the-job training to foreign nationals at NRC Headquarters and the regional of~ces. The NRC's Foreign Assignee Program allows the NRC staff to exchange information with regulators from around the world. This helps both organizations better understand each other's 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 of~cials in other countries. Since its inception in 1975, the NRC has hosted more than 300 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. On a regular basis, some two dozen regulatory staff members from other countries attend NRC training courses.

Multilateral Cooperation and AssistanceThe NRC plays an active role in the different programs and committee work of global organizations. The agency works with multiple regulatory counterparts through IAEA, OECD/NEA, and other multilateral organizations on issues related to:

• safety research and development of standards

• radiation protection

• risk assessment

• emergency preparedness

• waste management

• transportation

• safeguards, physical protection, and security

• technical assistance

• training, communications, and public outreachInternational Cooperative ResearchThe NRC participates in international cooperative research programs to share U.S. operating experience and to learn from the experiences of other countries.

The NRC also participates in international efforts to improve the security of radioactive materials and the management of radioactive waste.The NRC participates in cooperative research programs with many countries and organizations. This helps leverage access to foreign test facilities otherwise

unavailable to the United States.

21The United Nations General Assembly meets in New York to discuss, among other topics, world nuclear matters.

23 24U.S. Electricity Generated by Commercial Nuclear Power In 2016, NRC-licensed nuclear reactors generated 19.7 percent of U.S. gross electricity, or about 805 billion kilowatt-hours (see Figure 8: U.S. Gross Electric Generation by Energy Source, 2016, and Figure 9: U.S. Electric Share and Generation by Energy Source, 2011-2016).Since the 1970s, the Nation's 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 amount of heat, or power level, is used with other data in many analyses that demonstrate the safety of the nuclear power plant. This power level is included in the plant's license and technical speci~cations. The NRC must review and approve any licensee's requested change to a license or technical speci~cation. Increasing a commercial nuclear power plant's 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. The NRC expects a few more power uprate applications through 2018.

See Glossary for information on electric power grid.

According to the U.S. Energy Information Administration (EIA), in 2016, each of the following States generated more than 40 percent of its electricity from nuclear power: Connecticut, Illinois, Maryland, New Hampshire, New Jersey, and South Carolina. The 2016 data cited reect the percentages of the total gross generation from nuclear sources in each of these States (see Figure 10: Gross Electricity Generated in Each State by Nuclear Power). As of June 2016, 29 of the 50 States generate electricity from nuclear power plants.

U.S. Commercial Nuclear Power Reactors Power plants convert heat into electricity using steam. At nuclear power plants, the heat to make the steam is created when atoms split apart in a process called ~ssion.

When the process is repeated over and over, it is called a chain reaction. The heat from ~ssion creates steam to turn a turbine. As the turbine spins, the generator turns and its magnetic ~eld 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. Some of the systems 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 A-Z 25Figure 9.

U.S. Electric Share and Generation by Energy Source, 2011-2016Source: DOE/EIA, May 2017, https://www.eia.govFigure 8. U.S. Gross Electric Generation by Energy Source, 2016Note: Figures are rounded. Source: DOE/EIA, May 2017, https://www.eia.gov

26Figure 10. Gross Electricity Generated in Each State by Nuclear PowerTotal Nuclear Power Generated (in thousand megawatt-hours)

None 20 States 1-20%11 States 2 1-29%9 States 30-39%4 States 40+%6 StatesPercent of Total Nuclear Power GeneratedSource: DOE/EIA, "Monthly Nuclear Utility Generation by State and Reactor," December 2016, EIA-923 and EIA-860 Reports, https://www.eia.gov Illinois 98,240 Pennsylvania 82,924 S. Carolina 55,826N. Carolina 42,786Texas 42,079 New York 41,571 Alabama 39,902 Georgia 34,481 Arizona 32,377 Michigan 31,552 New Jersey 29,885 Virginia 29,732 Tennessee 29,578 Florida 29,320 California 18,908 Louisiana 17,152 Ohio 16,817 Connecticut 16,575 Maryland 14,760 Minnesota 13,861 Arkansas 13,421 New Hampshire 10,761 Wisconsin 10,151 Washington 9,626 Missouri 9,430 Nebraska 9,351 Kansas 8,246 Mississippi 5,897 Massachusetts 5,414 Iowa 4,702 27the reactor. To keep reactors performing ef~ciently, operators remove about one-third or half of the fuel every year or two and replace it with fresh fuel. Used fuel is stored and cooled in deep pools on site. The process of removing used fuel and adding fresh fuel is known as refueling.There are two types of commercial reactors in the United States.

Pressurized-water reactors are known as PWRs. They keep water under pressure so it heats 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, or BWRs, the water heated in the reactor actually boils and turns into steam to turn the generator. In both types of plants, the steam is turned back into water and can be used again in the process.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. Although commercial U.S. reactors have many similarities, each one is considered unique (see Figure 11: U.S. Operating Commercial Nuclear Power Reactors).

See Glossary for typical PWR and BWR design illustrations.

Resident Inspectors Since the late 1970s, the NRC has maintained its own sets of eyes and ears at the Nation's nuclear power plants. These onsite NRC staff are referred to as resident

inspectors. Each plant has at least two such inspectors, and their work is at the core of the agency's reactor inspection program. On a daily basis, these highly trained and quali~ed professionals scrutinize activities at the plants and verify adherence to Federal safety requirements. Oversight includes inspectors visiting the control room and reviewing operator logbook entries, visually assessing areas of the plant, observing tests of (or repairs to) important systems or components, interacting with plant employees to see if they have any safety concerns, and checking corrective action documents to ensure that problems have been identi~ed and appropriate ~xes implemented.Resident inspectors promptly notify plant operators of any safety-signi~cant issues the inspectors ~nd so they are corrected, if necessary, and communicated to NRC management. If problems are signi~cant enough, the NRC will consider whether enforcement action is warranted. More information about the NRC's Reactor Oversight Process and the resident inspector program is available on the agency's Web site (see Figure 12: Day in the Life of an NRC Resident Inspector).

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 S for Native American Reservations and Trust lands

near nuclear power plants, and Appendix J for radiation doses and regulatory limits.

A-Z 28Figure 11. U.S. Operating Commercial Nuclear Power Reactors Licensed to Oper a te (99)R E G I ON I CO N NEC T I C U T Mill s tone 2 an d 3 Calvert C liff s 1 a n d 2 MA S SACH U S E TT S N E W H A MPSH I R E Seabrook N E W J E R SE Y Ho p e C ree k Oyster Cree k Sa l em 1 a n d 2 F itz P a tric k Ind i an P o i nt 2 and 3 N i ne M i le P oint 1 P E N N SY L V AN I A Be a ver V al l ey 1 an d 2 L i meri c k 1 an d 2 P eac h B ottom 2 a nd 3 Susq u e h a n na 1 a n d 2 Three M i le I s land 1 RE G I O N I I AL A BA M A B r o w ns F er r y 1 , 2 , and 3 F arley 1 and 2 FLORID A St. Luc i e 1 and 2 T urkey P oi n t 3 and 4 GEORGI A Ed w in I. H a tch 1 and 2 V o g tle 1 and 2 NO R TH C AR O LI N A B r u n s w ick 1 and 2 McGu i re 1 and 2 Harris 1 S O UTH CAROLIN A C a t a w b a 1 and 2 Oconee 1 , 2 , and 3 R obinso n 2 S u mme r TE N NESSE E Seq u oy ah 1 and 2 W a tts Bar 1 and 2 V I RG I NI A North An n a 1 an d 2 S u r r y 1 and 2 RE G I O N II I Braid w ood 1 a n d 2 Byron 1 a n d 2 C l into n Dre s den 2 a n d 3 LaSalle 1 and 2 Quad Cities 1 a n d 2 Duane A rnol d M ICHIGA N Cook 1 and 2 F ermi 2 P a l isade s M I N NE S O T A Monticell o Prairie Isla n d 1 a n d 2 D a vis-B e s s e P er r y WIS C ON S I N P o i nt Beach 1 an d 2 R E G I ON I V A R KA N SAS Arkansas Nuclear 1 and 2 A R I Z O N A P a l o V erde 1 , 2 , a n d 3 C A L I FO R N I A Di a bl o Ca n yo n 1 an d 2 W o l f C reek 1 L O UI SI A N A R iver Be n d 1 W a terford 3 M IS S I S SI PP I Gran d G u l f M IS S O U R I C al l a wa y N E B R AS K A C oope r C oma nc he P eak 1 a n d 2 So u th T exas Pro j ect 1 a nd 2 W A S H I NG T O N C ol u mb i a MA R YL A N D Pilgri m N E W YO R K Gi n n a a n d 2 ILLINOI S IO W A OHI O K A N S A S T EX A S U.S. Operating Commercial Nuclear Power ReactorsNote: NRC-abbreviated reactor names listed. Data are as of May 2017. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/

29Figure 12. Day in the Life of an NRC Resident Inspector 3 1Learn more about resident inspectors. Watch the videos on the NRC YouTube Channel at https//www.youtube.com/user/NRCgov.

2 4 5 6 7 30Post-Fukushima Dai-ichi Nuclear AccidentOn March 11, 2011, a 9.0-magnitude earthquake struck off the coast of Japan and created a 45-foot tsunami. The reactors at the Fukushima Dai-ichi facility survived the earthquake but were damaged by the tsunami that arrived almost an hour later. Without power from the grid and with the tsunami knocking out backup power, three of the plant's reactors suffered catastrophic failures.The NRC sent experts to Japan in the days and weeks after the accident, and other agency staff reviewed the lessons from the accident. The review concluded that U.S. plants can operate safely while NRC actions, based on those lessons, enhance safety at U.S. commercial nuclear power plants. At the front lines of this effort were the agency's resident inspectors and regional staff. They have inspected and monitored U.S. reactors as the plants work on these enhancements. This work will continue to ensure plants have the required resources, plans, and training (see Figure 13: NRC Post-Fukushima Safety Enhancements and the Web Link Index). Principal Licensing, Inspection, and Enforcement ActivitiesThe NRC's commercial reactor licensing and inspection activities include:

• reviewing separate license change requests from power reactor licensees

• performing inspection-related activities at each operating reactor site

• ensuring the quali~cations of NRC-licensed reactor operators, who must requalify every 2 years and ask the NRC to renew their license every 6 years

• reviewing applications for proposed new reactors

• inspecting construction activities

• reviewing operating experience items each year and distributing lessons learned that could help licensed facilities operate more effectively

• issuing notices of violation, civil penalties, or orders to operating reactors for signi~cant violations of NRC regulations regarding public health and safety

• investigating allegations of inadequacy or impropriety associated with NRC-regulated activities

• incorporating independent advice from the ACRS, which holds both full

committee meetings and subcommittee meetings during each year to examine potential safety issues for existing or proposed reactors See Appendix C for a list of reactors undergoing decommissioning and

permanently shut down and Appendix U for a list of signi~cant enforcement actions.

31Note: FLEX refers to the industry's term for mitigation strategy equipment.Figure 13. NRC Post-Fukushima Safety Enhancements An NRC inspector conducts routine inspections of plant equipment to ensure the plant is meeting NRC regulations.

32Oversight 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 the plants operate safely and securely within these requirements by licensing the plants to operate, licensing control room personnel, establishing technical speci~cations for operating each plant, and inspecting plants daily.

Reactor Oversight ProcessThe NRC's Reactor Oversight Process (ROP) veri~es 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 ~ndings and performance records for each reactor and uses this information to assess the reactor's safety performance and security measures. Every 3 months, through the ROP, the NRC places each reactor in one of ~ve categories.

The top category is "fully meeting all safety cornerstone objectives,"

while the bottom is "unacceptable performance" (see Figure 14: 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 NRC's inspections increase. The agency's supplemental inspections and other actions (if needed) ensure licensees promptly address signi~cant performance issues. The latest reactor-speci~c inspection ~ndings and historical performance information can be found on the NRC's Web site (see the Web Link Index). The ROP is informed by 30 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 NRC's Web site and in

NUREG-1649, Revision 6, "Reactor Oversight Process," issued

July 2016 (see Figure 15: Reactor Oversight Framework).

33Figure 14. Reactor Oversight Action Matrix Performance IndicatorsFigure 15. Reactor Oversight Framework 34Reactor License RenewalThe 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 NRC's 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 16: License Renewals Granted for Operating Nuclear Power Reactors). For current reactors grouped by how long they have operated, see Figure 17:

U.S. Commercial Nuclear Power Reactors-Years of Operation by the End of 2017. Nuclear power plant owners typically seek license renewal based on a plant's economic situation and on whether it can continue to meet NRC requirements in the future.The NRC reviews a license renewal application on two tracks: safety and environmental impacts. The safety review evaluates the licensee's 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) 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 plant's site. The public has two opportunities to contribute to the environmental review-at 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 ~nal 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 reactor's licensed operating life before ultimate disposal (previously referred to as "waste con~dence"). The environmental impacts of continued storage of spent nuclear fuel are incorporated into each environmental review for 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 in the initial license renewal). The Commission determined the agency's existing regulations are adequate for subsequent license renewals, but the new guidance would help licensees develop aging management programs appropriate for the 60-year to 80-year period. The ~nal guidance documents were published in the summer of 2017. The NRC has received letters of intent for Peach Bottom to apply for subsequent license renewal in 2018 and Surry to apply in 2019.

See Appendices F and G for power reactor operating licenses issued and expired by year.

35Figure 16.

License Renewals Granted for Operating Nuclear Power Reactors Licensed to Operate (99)

Original License (1 3) License Renewal Granted (8 6)Figure 17.

U.S. Commercial Nuclear Power Reactors-Years of Operation by the End of 2017Note: Ages have been rounded up to the end of the year. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/Note: The NRC has issued a total of 89 license renewals; three of these units have permanently shut down. Fort Calhoun nuclear power plant permanently shut down on 10/24/2016. Data are as of October 2017. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/

36Figure 18. License Renewal ProcessPublic 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 and holds public meetings. The agency fully and publicly documents the results of its technical and environmental reviews. In addition, ACRS public meetings often discuss technical or safety issues related to reactor designs or a particular plant or site. Individuals or groups can raise legal arguments against a license renewal application in an Atomic Safety and Licensing Board (ASLB) 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.)

37Research and Test Reactors Nuclear research and test reactors (RTRs), also called "nonpower" reactors, 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 ~elds. These reactors do not produce electricity. Most U.S.research and test reactors are at universities or colleges. The largest U.S. RTR (which produces 20 megawatts thermal (MWt) is one-75th the size of the smallest U.S. commercial power nuclear reactor (which produces1,500MWt). The NRC regulates currently operating research and test reactors (see Figure 19: Size Comparison of Commercial and Research Reactors and Figure 20: U.S. Nuclear Research and Test Reactors). The U.S. Department of Energy (DOE) uses research reactors, but they are not regulated by the NRC.NRC inspectors visit each RTR facility at least once a year to conduct varying levels of oversight. RTRs licensed to produce 2 MWt or more receive a full NRC inspection every year. Those licensed to produce less than 2 MWt receive a full inspection every 2 years. Figure 19. Size Comparison of Commercial and Research ReactorsNote: Nuclear research and test reactors also known as "nonpower" reactors do not produce comercial electricity.

38 Principal Licensing and Inspection Activities The NRC's RTR licensing and inspection activities include:

• licensing the operating sites, including license renewals and license amendments

• overseeing decommissioning

• licensing operators

• overseeing operator relicensing programs

• overseeing security programs

• conducting inspections each year, based on inspection frequency and procedures for operating RTRs See Appendices H and I for a list of research and test reactors regulated by the NRC that are operating or are in the process of decommissioning.Figure 20. U.S. Nuclear Research and Test ReactorsRTRs Licensed/Currently Operating (31)

Note: For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/

39New Commercial Nonpower Production and Utilization Facility Licensing Doctors worldwide rely on a steady supply of molybdenum-99 (Mo-99), to generate in hospitals the production of technetium-99m, which is used in radiopharmaceuticals 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 Mo-99 production facilities submitted in accordance with the provisions of Title 10 of the Code of Federal Regulations. Since 2013, the NRC staff has received two construction permit applications for nonpower production and utilization facilities from SHINE Medical Technologies, Inc. (SHINE) and Northwest Medical Isotopes, LLC. The proposed facilities would irradiate low-enriched uranium targets in utilization facilities, such as SHINE's proposed accelerator-driven subcritical operating assemblies, then separate Mo-99 from other ~ssion products in hot cells contained within a production facility. The NRC approved the construction permit for SHINE in early 2016.The NRC staff conducts safety and environmental reviews on these construction permit applications, which will also be the subject of both a mandatory hearing and an independent review by the ACRS. If the NRC issues these construction permits, each facility must also submit an application for, and be granted, an

operating license.The NRC anticipates receiving additional construction permit applications, operating license applications, materials license applications, and license amendment requests in the coming years from other potential Mo-99 producers.Ahead of the issuance of any permit or license, the NRC continues to develop 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 (99mTc) is produced by the decay of molybdenum-99 (99Mo) and is used in diagnostic nuclear medical imaging procedures.

40Figure 21. The Different NRC Classi~cations for Types of ReactorsOperating ReactorsSmall Modular ReactorsAdvanced ReactorsResearch and Test Reactors Design: The U.S. ~eet 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.

Design: Small modular reactors (SMRs) are similar to 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 meet increased energy needs.

Design: Advanced reactors are a new generation of nonlight-water reactors.

They use coolants ranging from molten salt to liquid metal and even gases.

Design: Research and test reactors-also called "nonpower" reactors-are primarily used for research, training, and development. They are classied by their moderator, the material used to slow down the neutrons, in the nuclear reaction. Typical moderators include water (H 2O), heavy water (D 2O), polyethylene, and graphite.

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 classied by the type of fuel used, such as MTR (plate-type fuel) or TRIGA fuel. TRIGA fuel is unique fuel in that a moderator (hydrogen) is chemically bonded to the fuel.

Capacity: These facilities range in size from 0.10 watt (less than a night light) to 20 MWt (equivalent to 20 standard medical X-ray machines).

Capacity: The generation base load of these plants is 1,500 MWt (495 MWe) or higher.

Capacity: These reactor are about one-third the size of typical reactors with generation base load of 1,000 MWt (300 MWe) or less.

Capacity: These plants range in power from very small reactors to a power level comparable to existing operating reactors.

Safety: These reactors have "active" safety systems powered by alternating current (ac) and require an operator to shut down.

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.

Safety: These reactor have passive designs that rely on physical phenomena such as gravity and natural cooling, as well as longer lasting batteries rather than ac-powered systems, for a specied time (e.g., 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). They may not require an operator to shut down.

Fuel: These reactor require uranium enrichment.

Fuel: These reactors require uranium enrichment.

Fuel: These reactor require enriched uranium or used nuclear fuel.

41New Commercial Nuclear Power Reactor Licensing New reactors are often considered to be any reactors proposed in addition to the current eet of operating reactors (see Figure 21: The Different NRC Classi~cations for Types of Reactors). The NRC's current review of new power reactor license applications improves on the process used through the 1990s (see Figure 22: New Reactor Licensing Process). In 2012, the NRC issued the ~rst 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 certi~cations, 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 Commission's policies on new reactor safety through rules, guidance, staff reviews, and inspection.See Glossary for typical PWR and BWR design Illustrations.

The NRC's ongoing design certi~cation, 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 ~nal Continued Storage Rule and supporting generic environmental impact statement in September 2014. Section 5 discusses the Continued Storage Rule in more detail.

Combined License Applications-Construction and Operating By issuing a COL, the NRC authorizes the licensee to construct and (with speci~ed conditions) operate a nuclear power plant at a speci~c site, in accordance with established laws and regulations. A COL's operating license portion is valid for 40 years from the date the Commission ~nds acceptance criteria in the combined license are met. A COL can be renewed for additional 20-year terms (see Figure23:

Locations of New Nuclear Power Reactor Applications). For the current review schedule for active licensing applications, consult the NRC's Web site (see the Web Link Index).

A-Z See Appendix B for a list of new nuclear power plant licensing applications in the United States.

42Figure 22. New Reactor Licensing Process Public CommentsCombined License Application Review Process Notice of Hearing Hearings Commission Decision on Application Safety Review Public Involvement Environmental Review Combined License Application Final Environmental Impact Statement Final Safety Evaluation

Report Location of Projected New Nuclear Power ReactorsFermi PSEG (ESP)Turkey Point North Anna Clinch River (ESP)

Shearon Harris*VogtleComanche Peak*South Texas = A proposed new reactor at or near an existing nuclear plant = A proposed reactor at a site that has not previously produced nuclear power

= Approved reactor

= 2 units

= 1 unit 2 2 2 2 2 2 CA NV OR WA ID UT WY MT CO NM AZ TX OK KS NE SD ND MN WI IA IL MO AR LA MS AL TN KY VA MD DC DE NJ RI WV OH MI PA NY ME V T CT NH MA IN GA FL AK HI SC NCFigure 23. Locations of New Nuclear Power Reactor Applications

• Review suspended Note: On July 31, 2017, a decision was announced by South Carolina Electric & Gas (SCE&G) ceased construction on V.C. Summer nuclear power plant, Units 2 and 3; and as of October 2017, Duke Energy has announced plans to cancel Levy County, FL and William States Lee, SC reactors. Applications were withdrawn for Calvert Cliffs, Grand Gulf, Nine Mile Point, Victoria County, and Callaway (COL and ESP). NRC-abbreviated reactor names listed. Data are as of July 2017. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/

43Public 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 in the process. After the application is submitted, the NRC asks the public to comment on which factors should be considered in the agency's environmental review conducted under the National Environmental Policy Act. The NRC later posts a draft environmental evaluation on the agency's Web site and asks for public input. There is no formal opportunity for public comment on the staff's 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 ASLB 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 press releases, in the Federal Register, and on the NRC's Web site. 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 NRC's ESP review, and the public can challenge an application in a hearing.

The NRC issues certi~cations for reactor designs that meet basic requirements

for ensuring safe operation. Utilities can cite a certi~ed design when applying for a nuclear power plant COL. The certi~cation is valid for 15 years from the date issued and can be renewed for an additional 15 years. The new reactor designs under review incorporate new elements such as passive safety systems and simpli~ed system designs. The ~ve certi~ed designs are-

• General Electric Nuclear Energy's Advanced Boiling-Water Reactor (ABWR)

• Westinghouse Electric Company's System 80+

• Westinghouse Electric Company's AP600

• Westinghouse Electric Company's AP1000

• General Electric-Hitachi Nuclear Energy's (GEH's) Economic Simpli~ed Boiling-Water Reactor (ESBWR)The NRC is reviewing three applications for design certi~cations for the APR1400, U.S. Advanced Pressurized-Water Reactor, and NuScale designs.

44The NRC is reviewing a GEH application to renew the ABWR design certi~cation.

GEH submitted its application in 2010.

Advanced Reactor Designs Several companies are considering advanced reactor designs and technologies and are conducting preapplication activities with the NRC. These technologies include light-water reactors that are a fraction of the size of today's designs. Other potential reactor designs are cooled by liquid metals or high-temperature gas. The NRC's advanced reactor efforts will ensure the agency has the resources and expertise to address these new technologies. While developing the regulatory framework for advanced reactor licensing, the NRC is also examining policy issues in areas such as security and emergency preparedness. Advanced reactors' primary difference from today's designs is that the advanced concepts use 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 today's enriched-uranium dioxide pellets within zirconium cladding. Advanced reactor designers have expressed interest in following the SMR approach of bundling several small reactors in a single plant.Small Modular Reactors Small Modular Reactors (SMRs) use water to cool the reactor core in the same way as today's large light

-water reactors. SMR designs also use the same enriched uranium fuel as today's reactors. However, SMR designs are considerably smaller and bundle several reactors together in a single containment. Each SMR module generates 300 MWe (1,000 MWt) or less, compared to today's large designs that can generate 1,000 MWe (3,300 MWt) or more per reactor. The NRC's discussions to date with SMR designers involve modules generating less than 200 MWe (660MWt).New Reactor Construction Inspections NRC inspectors based in the agency's Region II of~ce in Atlanta, GA, monitor reactor construction activity. These expert staff members ensure licensees carry out construction according to NRC license speci~cations and related regulations.The NRC staff examines the licensee's operational programs in areas such as security, radiation protection, and operator training and quali~cation. Inspections at a construction site verify that a licensee has completed required inspections, tests, and analyses and has met associated acceptance criteria. The NRC's onsite resident construction inspectors oversee day-to-day licensee and contractor activities. In addition, specialists at NRC Region II's Center for Construction Inspection periodically visit the sites to ensure the facilities are being constructed using the approved design.

45The NRC's Construction Reactor Oversight Process assesses all of these activities. Before the agency will allow a new reactor to start up, NRC inspectors must con~rm

that the licensee has met all of 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 NRC's regulatory requirements. The NRC's Web site has more information on new reactor licensing activities (see the Web Link Index).

Nuclear Regulatory ResearchThe NRC's research supports the agency's 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 NRC's research includes:

• independently con~rming 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 focuses on the challenges of an evolving industry, as well as on retaining technical skills when experienced staff members retire. The NRC's research covers the light-water reactor technology developed in the 1960s and 1970s, today's advanced light-water reactor designs, and fuel cycle facilities. The agency has longer term research plans for more exotic reactor concepts, such as those cooled by high-temperature gases or liquid metals. The NRC's research programs examine a broad range of subjects, such as:

• material performance (such as environmentally assisted degradation and cracking of metallic alloys, aging management of reactor components and materials, boric-acid corrosion, radiation effects on concrete, alkali-silica reaction in concretes, the use of high-density polyethylene material for buried piping, 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 ~re conditions in nuclear facilities, to examine how reactor fuel performs, and to assess nuclear power plant risk

• new and evolving technologies (such as computerized instrumentation and control, and safety-critical software)

• experience gained from operating reactors 46* digital instrumentation and controls (such as 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 and ooding hazards

• equipment performance under extreme conditions (e.g., heat, radiation, or humidity)

• 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 roomsThe Of~ce of Nuclear Regulatory Research also plans, develops, and manages research on ~re safety and risk, including modeling, and evaluates potential security vulnerabilities and possible solutions (see the Web Link Index for more information on speci~c NRC research projects and activities).The NRC's research program involves about 6 percent of the agency's personnel and uses about 14 percent of its contracting funds. The NRC's $30 million research budget for FY 2017 includes contracts with national laboratories, universities, Universities and other academic institutions use nuclear materials in laboratory

experiments while conducting research.

47research 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 24: NRC Research Funding, FY 2017, illustrates the primary areas of research. The majority of the NRC's research program supports maintaining operating reactor safety and security. The remaining research budget 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 nonpro~t organizations on research for the agency's speci~c interests.The NRC's international cooperation in research areas leverages agency resources, facilitates work on advancing existing technologies, and determines any safety implications of new technologies. The NRC's leadership role in international organizations such as the IAEA and the OECD/NEA helps guide the agency's

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, ~re risk, and human-factors research. Cooperation under these agreements is more ef~cient than conducting research independently. Figure 24. NRC Research Funding, FY 2017 Note: Dollars are rounded to the nearest million.

Note: Totals may not equal sum of components because of rounding.

Source: U.S. Nuclear Regulatory Commission New/Advanced Reactor Licensing-$6 MReactor Program-$22 MMaterials and Waste-$2 M See Appendix T for States with Integrated University Grants Program recipients.

49 50Figure 25. Agreement StatesThe NRC regulates each phase of the nuclear fuel cycle-the steps needed to turn uranium ore into fuel for nuclear power plants-as 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 health, 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 25: Agreement States). These States develop regulations and appoint of~cials to ensure nuclear materials are used safely and securely. Agreement States must adopt rules consistent with the NRC's. Only the NRC regulates nuclear reactors, fuel fabrication facilities, consumer product distribution, and certain amounts of what is called "special nuclear material"-that is, radioactive material that can ~ssion 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 accelerator-a machine that propels charged particles. The NRC does not regulate accelerators but does license the use of radioactive materials produced in accelerators.

See Appendix K for a list of the number of materials licenses by State.Note: For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/

datasets/

51Medical 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 the NRC does not regulate x-ray machines or other devices that produce radiation without using radioactive materials.

Medical The NRC and Agreement States license hospitals and physicians 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 agency sponsors the Advisory Committee on the Medical Uses of

Isotopes. This expert committee includes scientists, physicians, and other health care professionals who have experience with medical radionuclides. Nuclear MedicineDoctors 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.

Photo courtesy: SirtexPhoto courtesy: NordionSamples from two manufacturers of yttrium-90 (Y-90), SIR-Spheres (left) TheraSphere (right). Vial containing millions of Y-90 microspheres used to treat liver cancers.

52Radiation 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:

1. 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.

2. 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 (up to 2.54 centimeters) from the target area.

3. 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 issues licenses to academic institutions for education and research.

For example, quali~ed instructors may use radioactive materials in classroom

demonstrations. Scientists in many disciplines use radioactive materials for laboratory research.

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 ~nd structural defects in metal and welds. Gas chromatography uses low-energy radiation sources to identify the chemical elements in an unknown substance. This process can determine the components of complex mixtures, such as petroleum products, smog, and cigarette smoke. (It can also be 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 inside a well. This process is used

extensively for oil, gas, coal, and mineral exploration.

53 A-ZNuclear 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, uid levels in oil and chemical tanks, and the moisture and density of soils and material at construction sites. Gauges may be ~xed or portable.

See Glossary for illustrations of ~xed and portable gauges.

The measurement indicates the thickness, density, moisture content, or some other property that is displayed on a gauge readout or on a computer monitor. The top of the 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 ~xed gauge has a radioactive source shielded in a container. When the user opens the container's 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 uid 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 densities, ow rates, levels, thicknesses, 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 reect back to the bottom of 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 reected radiation.The moisture density gauge, shown at right, is a portable gauge 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.

A moisture density gauge indicates whether

a foundation is suitable for supporting a building or roadway.

54 A-ZCommercial 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 ooring, 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 tube, or an electron beam.

See Glossary for information and illustrations of commercial irradiators.

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. 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. 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 Nation's 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 DOT's safety regulations.

Truck carries NAC LWT transport package.

55 A-ZMaterial SecurityTo monitor the manufacture, distribution, and ownership of the most high-risk sources, the NRC set up the National Source Tracking System (NSTS) in

January 2009. Licensees use this secure Web-based system to enter information on the receipt or transfer of tracked radioactive sources (see Figure 26: Life-Cycle Approach to Source Security). The NRC and the Agreement States use the system to monitor where high-risk sources are made, shipped, and used.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.

See Glossary for de~nitions of the categories of radioactive sources.

The NRC and the Agreement States have increased controls on the most sensitive radioactive materials. Stronger physical-security requirements and stricter limits on who can access the materials give the NRC and the Agreement States added con~dence in their security. The NRC has also joined with other Federal agencies, such as the U.S. Department of Homeland Security (DHS) and DOE's 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 26. Life-Cycle Approach to Source Security B a c k g r o u n d C h e c k s A c c e s s C o n t r o l s / P h y s i c a l B a r r i e r s L a w E n f o r c e m e n t C o o r d i n a t i o n M o n i t o r i n g o f S h i p m e n t s I n c i d e n t R e s p o n s e B a c k g r o u n d C h e c k s A c c e s s C o n t r o l s / P h y s i c a l B a r r i e r s L a w E n f o r c e m e n t C o o r d i n a t i o n M o n i t o r i n g o f S h i p m e n t s I n c i d e n t R e s p o n s e Life Cycle Approach to Source Security DisposalSecurity Controls DistributionTransfersManufactureof SourcesNational Source Tracking System B a c k g r o u n d C h e c k s A c c e s s C o n t r o l s / P h y s i c a l B a r r i e r s L a w E n f o r c e m e n t C o o r d i n a t i o n M o n i t o r i n g o f S h i p m e n t s I n c i d e n t R e s p o n s e Life Cycle Approach to Source Security DisposalSecurity Controls DistributionTransfersManufactureof SourcesNational Source Tracking System 56Figure 27. The Nuclear Fuel Cycle* 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. Nuclear Fuel Cycle The typical nuclear fuel cycle uses uranium in different chemical and physical forms. Figure 27: The Nuclear Fuel Cycle illustrates the stages, which include uranium recovery, conversion, enrichment, and fabrication, to produce fuel for nuclear power plants. Uranium is recovered or extracted from ore, converted, and enriched. Then the enriched uranium is manufactured into pellets. These pellets are placed into fuel assemblies to power nuclear reactors.

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 (ISR) facilities, and heap leach facilities. Once this processing is done, the uranium is in a powder form known as yellowcake, which is packed into 55-gallon (208-liters) 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.

57 A-ZConventional 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.

In Situ RecoveryISR is another way to extract uranium-in this case, directly from underground ore. In situ facilities recover uranium from ores that cannot be processed economically using other methods. In this process, a solution of native 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 28: The In Situ Uranium Recovery Process).

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. 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. The NRC does not currently license any heap leach facilities.

See Glossary for de~nition and illustration of heap leach recovery process.

Licensing Uranium Recovery Facilities The NRC continues to receive applications to build new uranium recovery facilities and to expand or restart existing facilities. The current status of applications can be found on the NRC's Web site (see the Web Link Index on page 187). Existing facilities and new potential sites are located in Wyoming, New Mexico, Nebraska, South Dakota, and Oregon and in the Agreement States of Texas, Colorado, and Utah (see Figure 29: Locations of NRC-Licensed Uranium Recovery Facility Sites).

58Figure 28. The In Situ Uranium Recovery ProcessInjection wells pump a solution of native ground water, usually mixed with sodium bicarbonate and oxygen, 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 welleld. Conning layers keep ground water from moving from one aquifer to another.

59 A-Z The NRC takes into account the views of stakeholders, including Native American Tribal governments, to address their concerns with licensing new uranium recovery facilities. 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 ~nancial requirements to ensure funds are available for

decommissioning

• making sure licensees follow requirements for underground disposal of mill tailings and provide liners for tailings impoundments

• monitoring to prevent ground water contamination

• monitoring and overseeing decommissioned facilities

See Glossary for more information on mill tailings.

Figure 29. Locations of NRC-Licensed Uranium Recovery Facility SitesNote: For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/

datasets/

60 See Appendix L for major U.S. fuel cycle facility sites.

A-ZFuel Cycle Facilities The NRC licenses all commercial fuel cycle facilities involved in conversion, enrichment, and fuel fabrication (see Figure 30: Locations of NRC-Licensed Fuel Cycle Facilities, and Figure 31: Simpli~ed Fuel Fabrication Process).

See Glossary for more information on enrichment processes.

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 hexauoride (UF 6). Next, an enrichment facility heats the solid UF 6 enough to turn it into a gas, which is "enriched," or processed to increase the concentration of the isotope uranium-235.The enriched uranium gas is mechanically and chemically processed back into a solid uranium dioxide (UO

2) powder. The powder is blended, milled, pressed, and fused into ceramic fuel pellets about the size of a ~ngertip. 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.After careful inspection, 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 this operation to ensure it is conducted safely.

Domestic Safeguards Program The NRC's 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 veri~es 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. The NRC has issued licenses

authorizing facilities to possess special nuclear material in quantities ranging from a single pound to multiple tons. 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 con~rm their inventory annually in the NMMSS database.

61 Uranium Hexa~uoride Conversion Facility (1)

Uranium Fuel Fabrication Facility (5)

Mixed-Oxide Fuel Fabrication Facility (1)

Gas Centrifuge Uranium Enrichment Facility (4)*

Laser Separation Enrichment Facility (1)

Uranium Hexa~uoride Deconversion Facility (1)Figure 30. Locations of NRC-Licensed Fuel Cycle Facilities* Lead Cascade facility used for testing, is currently transitioning to decommissioning, Note: There are no fuel cycle facilities in Alaska or Hawaii.

For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/Figure 31. Simpli~ed Fuel Fabrication Process Fabrication of commercial light-water reactor fuel consists of the following three basic steps:

(1) the chemical conversion of UF 6 to UO 2 powder (2) a ceramic process that converts UO 2 powder to small ceramic pellets (3) a mechanical process that loads the fuel pellets into rods and constructs ~nished fuel assemblies

63Photo courtesy: NAC International 64Low-Level Radioactive Waste DisposalLow-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, ~lters, reactor water treatment residues, equipment and tools, medical waste, and laboratory animal carcasses and tissue. Some LLW is quite low in radioactivity-even 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 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 32: Low-Level Radioactive Waste Disposal).The NRC classi~es LLW based on its potential hazards. The NRC has speci~ed disposal and waste requirements for three classes of waste-Class A, B, and C-with 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. Determining the classi~cation of waste is a complex process. A fourth class of LLW, called "greater-than-Class-C waste," is not generally acceptable for near-surface disposal. 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 varies from year to year. Waste volumes currently include several million cubic feet each year from reactor facilities undergoing decommissioning and from cleanup of contaminated sites.The LLW Policy Amendments Act gave the States responsibility for LLW disposal.

The Act authorized States to:

• form regional compacts, with each compact to provide for LLW disposal site access

• manage LLW import to, and export from, a

compact* exclude waste generated outside a compact See Appendix O for regional compacts and closed LLW sites.

65Figure 32. Low-Level Radioactive Waste DisposalThis LLW disposal site accepts waste from States participating in a regional disposal agreement.The States have licensed four active LLW disposal facilities:

• EnergySolutions' Barnwell facility, located in Barnwell, SC-Previously, Barnwell accepted LLW from all U.S. generators of LLW. Barnwell now accepts waste only from the Atlantic Compact States of 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, UT-Clive accepts waste from all regions of the United States. The State of Utah licensed Clive for Class A waste only.

• US Ecology's Richland facility, located in Richland, WA, on the Hanford Nuclear Reservation-Richland 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, TX-Andrews accepts waste from the Texas Compact, which consists of Texas and Vermont. It also accepts waste from out-of-the-compact generators on a case-by-case basis.

The State of Texas licensed Andrews to receive Class A, B, and C waste.

66High-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. Several storage facilities do not have operating power reactors but are safely storing spent fuel. 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 lives.

Facilities originally planned to store spent fuel temporarily in deep pools of continuously circulating water, which cools the spent fuel assemblies. After a few years, the facilities 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 in the United States. Although the Government later lifted the restriction, reprocessing has not resumed in the United States.

See Glossary for fuel reprocessing (recycling).

As a result, facilities expanded their storage capacity by using high-density storage racks in their spent fuel pools. To provide supplemental storage, some fuel assemblies are stored in dry casks on site (see Figure 33: Spent Fuel Generation and Storage after Use). These facilities are called independent spent fuel storage installations (ISFSIs) and are licensed by the NRC. These large casks are typically made of leak-tight, welded, and bolted steel and concrete surrounded by another layer of steel or concrete. 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 34: Dry Storage of Spent Nuclear Fuel). The NRC regulates facilities that store spent fuel in two different ways. The NRC may grant site-speci~c licenses after a safety review of the technical requirements and

operating conditions for an ISFSI. The NRC has issued a general license authorizing nuclear power reactor licensees to store spent fuel on site in dry storage casks that the NRC has certi~ed. Following a similar safety review, the NRC may issue a Certi~cate of Compliance and add the cask to a list of approved systems through

a rulemaking. The agency issues licenses and certi~cates for terms not to exceed 40 years, but they can be renewed for up to an additional 40 years (see Figure 35:

Licensed and Operating Independent Spent Fuel Storage Installations by State).

See Appendices M and N for information about dry spent fuel storage and licensees.

A-Z 67Public Involvement The public can participate in decisions about spent fuel storage, as it can in many licensing and rulemaking decisions. The Atomic Energy Act of 1954, as amended, and the NRC's own regulations call for public hearings about site-speci~c licensing actions and allow the public to comment on certi~cate of compliance rulemakings. Members of the public may also ~le petitions for rulemaking. Additional information on ISFSIs is available on the NRC's 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 de~ned 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 reactor's operating license has expired; the medium term, or 160 years after license expiration; and inde~nite, which assumes a repository never becomes available. The NRC's ~ndings-that any environmental impacts can be managed-appear in the 2014 report NUREG-2157, "Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel." The NRC adopted those ~ndings 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.

The NRC holds public meetings around the country, where NRC staff members provide information about the agency's role and mission and about the

performance of area nuclear power plants.

68Figure 33. Spent Fuel Generation and Storage After Use 1A nuclear reactor is powered by enriched uranium-235 fuel. Fission (splitting of atoms) 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 bullet-

sized pellets loaded into long

metal rods that are bundled together into fuel assemblies.

Pressurized-water reactors (PWRs) contain between

120 and 200 fuel assemblies.

Boiling-water reactors (BWRs) contain between

370 and 800 fuel assemblies.

2After 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-~fth the original amount of uranium-235.

Uranium Fuel Pellet Fuel Rod 69 3Commercial 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 owing water to cool the spent fuel. Extra water for the pool is provided by other pumps 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 (as shown in Figure 34) or transported off site for

interim storage or disposal.

Uranium Fuel Pellet Fuel Rod 70Figure 34. Dry Storage of Spent Nuclear Fuel 2 The canisters can also be stored in aboveground concrete bunkers, each of which is about the size of a one-car garage.

1 Once the spent fuel has suf~ciently cooled, it is

loaded into special canisters that are designed to hold nuclear fuel assemblies. Water and air are removed. The canister is ~lled 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.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.

71Figure 35.

Licensed and Operating Independent Spent Fuel Storage Installations by StatePENNSYLVANIA Limerick Susquehanna Peach Bottom Beaver Valley Three Mile Island SOUTH CAROLINA Oconee Robinson Catawba Summer TENNESSEE Sequoyah Watts Bar TEXAS Comanche PeakUTAH Private Fuel Storage VERMONT Vermont Yankee VIRGINIA Surry North AnnaWASHINGTON Columbia WISCONSIN Point Beach

Kewaunee LaCrosse ILLINOIS Braidwood Byron GE Hitachi Morris (Wet)

Dresden La Salle Quad Cities

ZionIOWA Duane Arnold LOUISIANA River Bend Waterford MAINE Maine YankeeMARYLAND Calvert Cliffs MASSACHUSETTS Yankee Rowe

Pilgrim MICHIGAN Big Rock Point Palisades

Cook FermiMINNESOTA Monticello Prairie Island MISSISSIPPI Grand Gulf MISSOURI Callaway NEBRASKA Cooper Ft. Calhoun NEW HAMPSHIRE Seabrook NEW JERSEY Hope Creek

Salem Oyster Creek NEW YORK Indian Point FitzPatrick

Ginna Nine Mile PointNORTH CAROLINA Brunswick

McGuire OHIO Davis-Besse Perry OREGON Trojan ALABAMA Browns Ferry Farley ARIZONA Palo Verde ARKANSAS Arkansas Nuclear CALIFORNIA Diablo Canyon Rancho Seco San Onofre Humboldt Bay COLORADO Fort St. Vrain CONNECTICUT Haddam Neck

Millstone FLORIDA St. Lucie Turkey Point GEORGIA Hatch Vogtle IDAHO DOE: TMI-2 (Fuel Debris)

DOE: Idaho Spent Fuel Facility ISFSI Site-Speci~c License (15)

ISFSI General License (63) 34 States have at least one ISFSIAlaska and Hawaii are not pictured and have no sites. Data are current as of July 2017. NRC-abbreviated site names listed. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/

72Transportation The NRC is also involved in the transportation of spent nuclear fuel. The NRC establishes safety and security requirements in collaboration with DOT, certi~es transportation cask designs, and conducts inspections to ensure that requirements are being met. Spent fuel transportation casks are designed to meet the following safety criteria under both normal and accident conditions:

• prevent the loss or dispersion of radioactive contents

• shield everything outside the cask from the radioactivity of the contents

• dissipate the heat from the contents

• prevent nuclear criticality (a self-sustaining nuclear chain reaction) from occurring inside the caskTransportation casks must be designed to survive a sequence of tests, including a 30-foot (9-meter) drop onto an unyielding surface, a puncture test, a fully engul~ng ~re at 1,475 degrees Fahrenheit (802 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 ~re and then falling into a river, simulates conditions more severe than 99 percent of vehicle accidents (see Figure 36: Ensuring Safe Spent

Fuel Shipping Containers).To ensure the safe transportation of spent 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 certi~es new, renewed, or amended transportation package design applicationsFigure 36.

Ensuring Safe Spent Fuel Shipping Containers The impact (free drop and puncture), ~re, and water immersion tests are considered in sequence to determine their cumulative effects on a given package.

73* conducts inspections of cask vendors and manufacturers to ensure the quality of dry cask design and fabrication

• reviews and evaluates license applications for the export or import of nuclear materialsAdditional information on materials transportation is available on the NRC's Web site (see the Web Link Index).

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 all

licensees to maintain ~nancial 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 37: Reactor Decommissioning Overview Timeline).Figure 37. Reactor Decommissioning Overview Timeline See Appendices C, I, and P for licensees undergoing

decommissioning.

74Figure 38.

Power Reactor Decommissioning Status FLORIDA Crystal River 3 ILLINOIS Dresden 1 Zion 1 and 2MARYLAND N.S. Savannah MASSACHUSETTS Yankee Rowe MAINE Maine Yankee MICHIGAN Fermi 1 Big Rock Point NEBRASKA Fort Calhoun NEW YORK Indian Point 1

Shoreham OREGON Trojan PENNSYLVANIA Saxton Peach Bottom 1 Three Mile Island 2SOUTH DAKOTA Path~nder VERMONT Vermont Yankee WISCONSIN LaCrosse Kewaunee CALIFORNIA GE EVESR GE VBWR Humboldt Bay 3 Rancho Seco San Onofre 1 San Onofre 2 and 3 COLORADO Fort St. Vrain (DOE License)

CONNECTICUT Millstone 1 Haddam NeckSAFSTOR DECONISFSI (Independent Spent Fuel Storage Installation) onlyLicense Terminated Decommissioning CompletedAlaska and Hawaii are not pictured and have no sites. Notes: GE Bonus, Hallam, and Piqua decommissioned reactor sites are part of the DOE nuclear legacy. For more information, visit DOE's Of~ce of Legacy Management LM Sites Web page at https://www.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. Licensees have announced their intention to permanently cease operations for the following: Palisades (2018), Pilgrim (2018), Three Mile Island (2019), Indian Point (2020 and 2021), Oyster Creek (2018), and Diablo Canyon (2025). NRC-abbreviated reactor names are listed. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/

75For commercial power reactors that have ceased operations, the decommissioning process may take up to 60 years. This may include extended periods of inactivity (called SAFSTOR), during which residual radioactivity is allowed to decay, making eventual cleanup easier and more ef~cient. A facility is said to be in DECON when active demolition and decontamination is underway. Active decommissioning of a

nuclear power plant takes about 10 years on average.The NRC terminates approximately 150 materials licenses each year. Most of these license terminations are routine, and the sites require little or no cleanup to meet the NRC's criteria for unrestricted access. The decommissioning program focuses on the termination of licenses for sites involving more complex decommissioning activities (see Figure 38: Power Reactor Decommissioning Status, and Figure 39:

Locations of NRC-Regulated Sites Undergoing Decommissioning).

The Status of the Decommissioning Program-2016 Annual Report (SECY 16-0129) contains additional information on the decommissioning programs of the NRC and Agreement States. More information is on the NRC's Web site (see the Web Link Index).Figure 39.

Locations of NRC-Regulated Sites Undergoing DecommissioningPower Reactor Sites Complex Materials Fuel Cycle FacilitiesResearch and Test Reactors Uranium Recovery SitesNote: For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/

77 78 A-ZOverview Nuclear security is a high priority 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 private sector facilities in the United States. However, given today's threat environment, the agency recognizes the need for continued vigilance and high levels of security.In recent years, the NRC has made many enhancements to the security of nuclear power plants. Because nuclear power plants are inherently robust structures, these additional security upgrades (see Figure 40: Security Components) largely focus on:

• well-trained and armed security of~cers

• 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 ~ngerprinting of workersThe NRC also coordinates and shares threat information with DHS, the

U.S. Department of Defense, the Federal Bureau of Investigation, intelligence agencies, and local law enforcement.

Facility SecurityUnder 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). This includes threats to a plant's or facility's physical security, personnel security, and cyber security. The NRC does not make details of the DBT public because of security concerns. However, the agency continuously evaluates this set of threats against real-world intelligence to ensure the DBT remains current. To test the adequacy of a facility's defenses against the DBT, the NRC conducts rigorous force-on-force inspections at each facility every 3 years.

See Glossary for de~nitions of the categories of special nuclear material.

During these inspections, a highly trained mock adversary force "attacks" a nuclear facility. Beginning in 2004, the NRC made these exercises more realistic, more challenging, and more frequent.

79Figure 40.

Security Components Protecting nuclear facilities requires all of the security

features to come

together and

work as one.Publicly available portions of security-related inspection reports are on the NRC's 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.

Nuclear power plants that have begun decommissioning may therefore apply for exemptions from NRC security requirements.

Cyber SecurityNuclear facilities use digital and analog systems to monitor, control, and run 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 cyber security. The reactor control systems of nuclear plants are isolated from the Internet, but for added security, all nuclear power plants licensed by the NRC must have a cyber security program.In 2013, the NRC began regular cyber security inspections of nuclear power plants under new regulations designed to guard against the cyber threat. The experience that the NRC gained in developing the cyber security requirements for nuclear power plants provided a basis for developing similar cyber security requirements for nonreactor licensees and other nuclear facilities.

80The NRC's cyber security team includes technology and threat experts who constantly evaluate and identify emerging cyber-related issues that could possibly endanger plant systems. The team also makes recommendations to other NRC of~ces and programs on cyber security issues. In October 2014, the NRC joined other independent regulatory agencies to create the Cyber Security Forum for Independent and Executive Branch Regulators. According to its mission statement, the forum aims to "increase the overall effectiveness and consistency of regulatory authorities' cyber security efforts pertaining to U.S. critical infrastructure, much of which is operated by industry and overseen by a number of federal regulatory authorities."

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 a dirty bomb. The NRC has established rules to provide the requirements for the physical protection of certain types and quantities of radioactive material. Additionally, the NRC works with the Agreement States, other Federal agencies, 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 PreparednessOperators 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 includes emergency preparedness in its inspections and monitors performance indicators associated with emergency preparedness. Nuclear power plant operators must conduct full-scale exercises with the NRC, the Federal Emergency Management Agency (FEMA), and State and local of~cials

at least once every 2 years. Some of these exercises include security and terrorism-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.

81Emergency Planning ZonesThe NRC de~nes two emergency planning zones (EPZs) around each nuclear power plant. The exact size and con~guration 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 exible, and the NRC may expand these zones during an emergency if circumstances warrant. For a typical EPZ around a nuclear plant, see Figure 41: Emergency Planning Zones. The two types of EPZs are the plume-exposure pathway and 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 about the public's exposure to and inhalation of airborne radioactive contamination. Research has shown the most signi~cant 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 about the ingestion of food and liquid contaminated by radioactivity.Figure 41.

Emergency Planning ZonesNote: A 2-mile ring around the plant is identi~ed for evacuation, along with a 5-mile zone downwind of the projected release path.

82Protective 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 of~cials in communities within the EPZ have detailed plans to protect the public during a radiation release. These of~cials make their protective action decisions, including decisions to order evacuations, based on these and other assessments.

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 preferable 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 of~ce buildings. Depending on the type of structure, sheltering can signi~cantly reduce someone's dose when compared

to staying outside. In certain situations, KI may be used as a supplement to sheltering. 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.The risk of an offsite radiological release is signi~cantly lower and the types of possible accidents signi~cantly 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 these FEMA and NRC emergency planning requirements.

Once the exemptions are granted, State and local agencies may apply their comprehensive emergency plans-known as all-hazard plans-to respond to incidents at the plant. Additional information on emergency preparedness is available on the NRC's Web site (see Web Link Index).

83Incident Response Quick communication among the NRC, other Federal and State agencies, and the nuclear industry is critical when responding to any incident. The NRC staff supports several Federal incident response centers where of~cials can coordinate assessments of event-related information. The NRC Headquarters Operations Center, located in the agency's 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.

DHS may lead and manage the overall Federal response to an event, according to Homeland Security Presidential Directive 5, "Management of Domestic Incidents." In this case, the NRC would provide technical expertise and help share information among the various organizations and licensees. 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 four 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.During an exercise in the agency's Headquarters Operation Center, the NRC reactor

safety team looks at simulated projected core temperature levels.

84The NRC staff provides expert consultation, support, and assistance to State and local public safety of~cials 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 of~cials. If needed, the NRC will dispatch a team of technical experts from the responsible regional of~ce to the site. This team would assist the NRC's resident inspectors who work at the plant.

The Headquarters Operations Center would continue to provide around-the-clock communications, logistical support, and technical analysis throughout the response.Emergency ClassificationsEmergencies at nuclear facilities are classi~ed according to the risk posed to the public. These classi~cations help guide ~rst responders on the actions necessary to protect the population near the site. Nuclear power plants use these four emergency classi~cations:

Noti~cation of Unusual Event:

Events that indicate a potential degradation in the level of safety of the plant are in progress or have occurred. No release of radioactive material requiring offsite response or monitoring is expected unless further degradation occurs.

Alert: Events that involve an actual or potential substantial degradation in the level of plant safety 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).Site Area Emergency: Events that may result in actual or likely major failures of plant functions needed to protect the public are in progress or have occurred. Any releases of radioactive material are not expected to exceed the limits set forth by the EPA except near the site boundary.

General Emergency: Events that involve actual or imminent substantial core damage or melting of reactor fuel with the potential for loss of containment integrity are in progress or have occurred. Radioactive releases can be expected to exceed the limits set forth by the EPA for more than the immediate site area.

Nuclear materials and fuel cycle facility licensees use these emergency classi~cations:

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.Site Area Emergency: Events that could lead to a signi~cant 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.

85IAEA uses the International Nuclear and Radiological Event Scale (INES) as a tool for promptly and consistently communicating to the public the safety signi~cance of reported nuclear and radiological incidents and accidents worldwide (see Figure 42:

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 noti~cations using the INES. But the NRC has a commitment to transmit to IAEA an INES-based rating for an applicable event occurring in the United States rated at Level 2 or above, or events attracting international public interest.Figure 42. The International Nuclear and Radiological Event ScaleBelow Scale/Level 0 INES events are classi~ed 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 signi~cance are called deviations and are classi~ed as Below Scale or at Level 0.

7 6 5 4 3 2 1Major AccidentAccident IncidentSerious AccidentAccident with Wider ConsequencesAccident with Local Consequences Serious Incident IncidentAnomalySource: www.ns.iaea.org/emergency/ines.asp

87This edition of the Digest provides a snapshot of data; for the most current information and data collection, please visit the NRC Web site Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/.

88Abbreviations ABWR advanced boiling-water reactor AC Allis Chalmers ac alternating current ACRS Advisory Committee on Reactor Safeguards ADR Alternative Dispute Resolution AEC Atomic Energy Commission (U.S.)

AEP American Electric Power Company AGN solid homogeneous core (Aerojet-General Nucleonics)

AP1000 Advanced Passive 1000 Megawatt (Westinghouse pressurized-water reactor)ASLB Atomic Safety and Licensing Board B&R Burns & Roe B&W Babcock & Wilcox BALD Baldwin Associates BECH BechtelBRRT Brown & Root BWR boiling-water reactor CE Combustion Engineering CFR Code of Federal Regulations Co company COL combined license Comm. Op. date of commercial operationCon Type containment typeDRYAMB dry, ambient pressureDRYSUB dry, subatmospheric ICECND wet, ice condenser MARK I wet, Mark I MARK II wet, Mark II MARK III wet, Mark III CP Issued date of construction permit issuance CT computerized tomography CVP civil penalties CWE Commonwealth Edison Company DANI Daniel International DBDB Duke & Bechtel DBT design-basis threat DC design certi~cation DHS Department of Homeland Security (U.S.)DOE Department of Energy (U.S.)

DOT Department of Transportation (U.S.)DUKE Duke Power Company EBSO Ebasco EIA Energy Information Administration (DOE)

EP emergency preparednessEPA Environmental Protection Agency (U.S.)EPR Evolutionary Power Reactor EPZ emergency planning zone ESBWR Economic Simpli~ed Boiling-Water Reactor ESP early site permit EVESR ESADA (Empire States Atomic Development Associates)

Vallecitos Experimental Superheat Reactor Exp. Date expiration date of operating

license FBR fast breeder reactor FEMA Federal Emergency Management

Agency FERC Federal Energy Regulatory

Commission FLUR Fluor Pioneer FOIA Freedom of Information Act FTE full-time equivalent FW Foster Wheeler FY ~scal year G&H Gibbs & Hill GA General Atomics GCR gas-cooled reactor GE General Electric GEH General Electric-Hitachi Nuclear Energy GEIS generic environmental impact statement GETR General Electric Test Reactor GIL Gilbert Associates GL general license GPC Georgia Power Company GWh gigawatt-hour(s) HLW high-level waste HTG high-temperature gas (reactor)

HWR heavy-water reactor IAEA International Atomic Energy Agency INES International Nuclear Event Scale ISFSI independent spent fuel storage installation ISR in situ recovery IUP Intergrated University Program KAIS Kaiser Engineers kW kilowatt(s)

LLP B&W lowered loopLLW low-level radioactive waste LMFB liquid metal fast breeder (reactor)

LR Issued license renewal issuedLWGR light-water-cooled graphite-moderated reactor MOX mixed oxide MW megawatt(s)MWe megawatt(s) electric MWh megawatt-hour(s)

MWt megawatt(s) thermal NIAG Niagara Mohawk Power Corporation NEA Nuclear Energy Agency NMMSS Nuclear Materials Management and Safeguards System NOV notice of violation NRC Nuclear Regulatory Commission (U.S.)

89 Alabama AL Alaska AK Arizona AZ Arkansas ARCalifornia CA Colorado CO Connecticut CTDelaware DE District of Columbia DC Florida FL Georgia GA Guam GU Hawaii HI Idaho ID Illinois IL Indiana IN Iowa IA Kansas KS Kentucky KY Louisiana LA Maine ME Maryland MD Massachusetts MA Michigan MI Minnesota MN Mississippi MS Missouri MO Montana MT Nebraska NE Nevada NVNew Hampshire NH New Jersey NJ New Mexico NMNew York NYNorth Carolina NC North Dakota ND Ohio OH Oklahoma OK Oregon OR Pennsylvania PA Puerto Rico PR Rhode Island RISouth Carolina SC South Dakota SDTennessee TNTexas TX Utah UTVermont VTVirgin Islands VIVirginia VAWashington WA West Virginia WV Wisconsin WI Wyoming WY NSP Northern States Power Company NSSS nuclear steam system supplier and design type GE 2 GE Type 2 GE 3 GE Type 3 GE 4 GE Type 4 GE 5 GE Type 5 GE 6 GE Type 6 WEST 2LP Westinghouse Two-Loop WEST 3LP Westinghouse Three-Loop WEST 4LP Westinghouse Four-Loop NSTS National Source Tracking System OECD Organisation for Economic Co-operation and Development OIG Of~ce of the Inspector General OL operating license OL Issued date of latest full power operating license PG&E Paci~c Gas & Electric Company PHWR pressurized heavy water reactor PRA probabilistic risk assessment PSEG Public Service Electric and Gas Company PWR pressurized-water reactor RLP B&W raised loop ROP Reactor Oversight ProcessRTR research and test reactor S&L Sargent & Lundy S&W Stone & Webster SCF sodium-cooled fast (reactor)

SDP signi~cance determination process SI Systme Internationale (d'unités) (International System of Units)

SL severity level SMR small modular reactor SOARCA State-of-the-Art Reactor

Consequence Analysis SSI Southern Services Incorporated

STP South Texas Project TMI-2 Three Mile Island, Unit 2 Sv sievert TRIGA Training Reactor and Isotopes Production, General AtomicsTVA Tennessee Valley Authority UNSCEAR United Nations Scienti~c Committee on the Effects of

Atomic Radiation UE&C United Engineers & Constructors US-APWR U.S. [version of] Advanced Pressurized-Water Reactor VBWR Vallecitos Boiling-Water Reactor WDCO Westinghouse Development Corporation

WEST Westinghouse Electric WNA World Nuclear AssociationState and Territory Abbreviations 90SPACE 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 *2.54Area mi 2 km 2 2.589998 acre m 2 4,046.873 yd 2 m 2 0.8361274 ft 2 m 2 *0.09290304 in 2 cm 2 *6.4516Volume acre foot m 3 1,233.489 yd 3 m 3 0.7645549 ft 3 m 3 0.02831685 ft 3 L 28.31685 gal L 3.785412 oz mL 29.57353 in 3 cm 3 16.38706Velocity mi/h km/h 1.609347 ft/s m/s *0.3048 Acceleration ft/s 2 m/s 2 *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)

• 10.0Exposure roentgen (R)

C (coulomb)/kg 0.000258 (x-rays and gamma rays)QUICK-REFERENCE METRIC CONVERSION TABLESHEAT Quantity From Inch-Pound Units To Metric Units Multiply by Thermodynamic

°F K *K = (°F + 459.67)/1.8 temperatureCelsius temperature

°F °C *°C = (°F - 32)/1.8 Linear expansion 1/°F 1/K or 1/°C

• 1.8 coef~cient

Thermal conductivity (Btu

• in)/(ft 2

• h * °F)

W/(m * °C) 0.1442279Coef~cient of heat Btu/(ft 2

• h * °F)

W/(m 2 * °C) 5.678263 transfer Heat capacity Btu/°F kJ/°C 1.899108 Speci~c heat capacity Btu/(lb * °F) kJ/(kg * °C)

• 4.1868 91QUICK-REFERENCE METRIC CONVERSION TABLESEntropy Btu/°F kJ/°C 1.899108Speci~c entropy Btu/(lb * °F) kJ/(kg * °C)

• 4.1868Speci~c internal Btu/lb kJ/kg *2.326 energy 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)/yd 3 t/m 3 1.186553 lb/ft 3 g/m 3 16.01846 Concentration (mass) lb/gal g/L 119.8264 Momentum lb

• ft/s kg

• m/s 0.138255 Angular momentum lb

• ft 2/s kg

• m 2/s 0.04214011 Moment of inertia lb

• ft 2 kg

• m 2 0.04214011Force kip (kilopound) kN (kilonewton) 4.448222 lbf N (newton) 4.448222Moment of force, torque lbf

• ft N

• m 1.355818 lbf

• in N

• m 0.1229848Pressure atm (std) kPa (kilopascal)

• 101.325 bar kPa *100.0 lbf/in 2 (formerly psi) kPa 6.894757 inHg (32 °F) kPa 3.38638 ftH 2 O (39.2 °F) kPa 2.98898 inH 2 O (60 °F) kPa 0.24884 mmHg (0 °C) kPa 0.133322Stress kip/in 2 (formerly ksi)

MPa 6.894757 lbf/in 2 (formerly psi)

MPa 0.006894757 lbf/in 2 (formerly psi) kPa 6.894757 lbf/ft 2 kPa 0.04788026Energy, work kWh MJ *3.6 cal th 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 factorsNotes: The information contained 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, ICRU Report 33, "Radiation Quantities and Units," issued 1980.HEAT (continued) 92 Arkansas Nuclear One, Unit 1 IV PWR-DRYAMB 2,568 12/06/1968 87Entergy Operations, Inc. B&W LLP DPR-51 05/21/1974 102 London, AR BECH 12/19/1974 56 (6 miles WNW of Russellville, AR)

BECH 06/20/2001 98 05000313 05/20/2034 82https://www.nrc.gov/info-~nder/reactors/ano1.html 72 Arkansas Nuclear One, Unit 2 IV PWR-DRYAMB 3,026 12/06/1972 90Entergy Operations, Inc. CE NPF-6 09/01/1978 93 London, AR BECH 03/26/1980 91 (6 miles NW of Russellville, AR)

BECH 06/30/2005 85 05000368 07/17/2038 94https://www.nrc.gov/info-~nder/reactors/ano2.html 89Beaver Valley Power Station, Unit 1 I PWR-DRYAMB 2,900 06/26/1970 101FirstEnergy Nuclear Operating Co. WEST 3LP DPR-66 07/02/1976 92Shippingport, PA S&W 10/01/1976 86(17 miles W of McCandless, PA)

S&W 11/05/2009 86 05000334 01/29/2036 90https://www.nrc.gov/info-~nder/reactors/bv1.html 91 Beaver Valley Power Station, Unit 2 I PWR-DRYAMB 2,900 05/03/1974 102FirstEnergy Nuclear Operating Co. WEST 3LP NPF-73 08/14/1987 91Shippingport, PA S&W 11/17/1987 97(17 miles W of McCandless, PA)

S&W 11/05/2009 98 05000412 05/27/2047 90https://www.nrc.gov/info-~nder/reactors/bv2.html 97 Braidwood Station, Unit 1 III PWR-DRYAMB 3,645 12/31/1975 101 Exelon Generation Co., LLC WEST 4LP NPF-72 07/02/1987 91 Braceville, IL S&L 07/29/1988 95 (20 miles SSW of Joliet, IL) CWE N/A 103 05000456 10/17/2026 93https://www.nrc.gov/info-~nder/reactors/brai1.html 90 Braidwood Station, Unit 2 III PWR-DRYAMB 3,645 12/31/1975 93 Exelon Generation Co., LLC WEST 4LP NPF-77 05/20/1988 93 Braceville, IL S&L 10/17/1988 98 (20 miles SSW of Joliet, IL) CWE N/A 96 05000457 12/18/2027 91https://www.nrc.gov/info-~nder/reactors/brai2.html 95Browns Ferry Nuclear Plant, Unit 1 II BWR-MARK 1 3,458 05/10/1967 91Tennessee Valley Authority GE 4 DPR-33 12/20/1973 88 Athens (Limestone County), AL TVA 08/01/1974 94 (32 miles W of Huntsville, AL) TVA 05/04/2006 90 05000259 12/20/2033 94https://www.nrc.gov/info-~nder/reactors/bf1.html 83 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 93Browns Ferry Nuclear Plant, Unit 2 II BWR-MARK 1 3,458 05/10/1967 80Tennessee Valley Authority GE 4 DPR-52 06/28/1974 99 Athens (Limestone County), AL TVA 03/01/1975 79 (32 miles W of Huntsville, AL) TVA 05/04/2006 98 05000260 06/28/2034 85https://www.nrc.gov/info-~nder/reactors/bf2.html 94Browns Ferry Nuclear Plant, Unit 3 II BWR-MARK 1 3,458 07/31/1968 87Tennessee Valley Authority GE 4 DPR-68 07/02/1976 83 Athens (Limestone County), AL TVA 03/01/1977 89 (32 miles W of Huntsville, AL) TVA 05/04/2006 88 05000296 07/02/2036 92https://www.nrc.gov/info-~nder/reactors/bf3.html 80 Brunswick Steam Electric Plant, Unit 1 II BWR-MARK 1 2,923 02/07/1970 100Duke Energy Progress, LLC GE 4 DPR-71 09/08/1976 77 Southport, NC UE&C 03/18/1977 92 (30 miles S of Wilmington, NC) BRRT 06/26/2006 89 05000325 09/08/2036 93https://www.nrc.gov/info-~nder/reactors/bru1.html 83 Brunswick Steam Electric Plant, Unit 2 II BWR-MARK 1 2,923 02/07/1970 79Duke Energy Progress, LLC GE 4 DPR-62 12/27/1974 98 Southport, NC UE&C 11/03/1975 73 (30 miles S of Wilmington, NC) BRRT 06/26/2006 98 05000324 12/27/2034 81https://www.nrc.gov/info-~nder/reactors/bru2.html 92Byron Station, Unit 1 III PWR-DRYAMB 3,645 12/31/1975 88 Exelon Generation Co., LLC WEST 4LP NPF-37 02/14/1985 88Byron, IL S&L 09/16/1985 96(17 miles SW of Rockford, IL) CWE N/A 97 05000454 10/31/2024 88https://www.nrc.gov/info-~nder/reactors/byro1.html 97Byron Station, Unit 2 III PWR-DRYAMB 3,645 12/31/1975 93 Exelon Generation Co., LLC WEST 4LP NPF-66 01/30/1987 94Byron, IL S&L 08/02/1987 86(17 miles SW of Rockford, IL) CWE N/A 94 05000455 11/06/2026 94https://www.nrc.gov/info-~nder/reactors/byro2.html 86 Callaway Plant, Unit 1 IV PWR-DRYAMB 3,565 04/16/1976 90 Union Electric Co.

WEST 4LP NPF-30 10/18/1984 103 Fulton, MO BECH 12/19/1984 77(25 miles ENE of Jefferson City, MO) DANI 03/06/2015 89 05000483 10/18/2044 96https://www.nrc.gov/info-~nder/reactors/call.html 87 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 94Calvert Cliffs Nuclear Power Plant, Unit 1 I PWR-DRYAMB 2,737 07/07/1969 101Calvert Cliffs Nuclear Power Plant, LLC CE DPR-53 07/31/1974 81 Exelon Generation Co., LLC BECH 05/08/1975 97Lusby, MD BECH 03/23/2000 91 (40 miles S of Annapolis, MD) 07/31/2034 97 05000317 89https://www.nrc.gov/info-~nder/reactors/calv1.html Calvert Cliffs Nuclear Power Plant, Unit 2 I PWR-DRYAMB 2,737 07/07/1969 92Calvert Cliffs Nuclear Power Plant, LLC CE DPR-69 08/13/1976 101 Exelon Generation Co., LLC BECH 04/01/1977 81Lusby, MD BECH 03/23/2000 100 (40 miles S of Annapolis, MD) 08/13/2036 86 05000318 95https://www.nrc.gov/info-~nder/reactors/calv2.html Catawba Nuclear Station, Unit 1 II PWR-ICECND 3,411 08/07/1975 89Duke Energy Carolinas, LLC WEST 4LP NPF-35 01/17/1985 89York, SC DUKE 06/29/1985 96 (18 miles S of Charlotte, NC) DUKE 12/05/2003 86 05000413 12/05/2043 88https://www.nrc.gov/info-~nder/reactors/cat1.html 97 Catawba Nuclear Station, Unit 2 II PWR-ICECND 3,411 08/07/1975 101Duke Energy Carolinas, LLC WEST 4LP NPF-52 05/15/1986 92York, SC DUKE 08/19/1986 86 (18 miles S of Charlotte, NC) DUKE 12/05/2003 100 05000414 12/05/2043 86https://www.nrc.gov/info-~nder/reactors/cat2.html 88 Clinton Power Station, Unit 1 III BWR-MARK 3 3,473 02/24/1976 93 Exelon Generation Co., LLC GE 6 NPF-62 04/17/1987 100 Clinton, IL S&L 11/24/1987 82 (23 miles SSE of Bloomington, IL)

BALD N/A 97 05000461 09/29/2026 87https://www.nrc.gov/info-~nder/reactors/clin.html 89 Columbia Generating Station IV BWR-MARK 2 3,486 03/19/1973 50Energy Northwest GE 5 NPF-21 04/13/1984 97Benton County, WA B&R 12/13/1984 80(12 miles NW of Richland, WA) BECH 05/22/2012 98 05000397 12/20/2043 78https://www.nrc.gov/info-~nder/reactors/wash2.html 92 Comanche Peak Nuclear Power Plant, Unit 1 IV PWR-DRYAMB 3,612 12/19/1974 91 Vistra Operating Co., LLC WEST 4LP NPF-87 04/17/1990 98 Glen Rose, TX G&H 08/13/1990 94(40 miles SW of Fort Worth, TX)

BRRT N/A 85 05000445 02/08/2030 100https://www.nrc.gov/info-~nder/reactors/cp1.html 92 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 95 Comanche Peak Nuclear Power Plant, Unit 2 IV PWR-DRYAMB 3,612 12/19/1974 92 Vistra Operating Co., LLC WEST 4LP NPF-89 04/06/1993 91 Glen Rose, TX BECH 08/03/1993 99(40 miles SW of Fort Worth, TX)

BRRT N/A 93 05000446 02/02/2033 88https://www.nrc.gov/info-~nder/reactors/cp2.html 100 Cooper Nuclear Station IV BWR-MARK 1 2,419 06/04/1968 86 Nebraska Public Power District GE 4 NPF-46 01/18/1974 87Brownville, NE B&R 07/01/1974 97(23 miles S of Nebraska City, NE)

B&R 11/29/2010 88 05000298 01/18/2034 97https://www.nrc.gov/info-~nder/reactors/cns.html 84 Davis-Besse Nuclear Power Station, Unit 1 III PWR-DRYAMB 2,817 03/24/1971 81FirstEnergy Nuclear Operating Co.

B&W RLP NFP-3 04/22/1977 91Oak Harbor, OH BECH 07/31/1978 95(21 miles ESE of Toledo, OH) B&W 12/08/2015 74 05000346 04/22/2037 97https://www.nrc.gov/info-~nder/reactors/davi.html 79 Diablo Canyon Nuclear Power Plant, Unit 1 IV PWR-DRYAMB 3,411 4/23/1968 100 Paci~c Gas & Electric Co. WEST 4LP DPR-80 11/02/1984 84Avila Beach, CA PG&E 05/07/1985 95 (12 miles SW of San Luis Obispo, CA) PG&E N/A 87 05000275 11/02/2024 87https://www.nrc.gov/info-~nder/reactors/diab1.html 98 Diablo Canyon Nuclear Power Plant, Unit 2 IV PWR-DRYAMB 3,411 12/09/1970 89 Paci~c Gas & Electric Co. WEST 4LP DPR-82 08/26/1985 97Avila Beach, CA PG&E 03/13/1986 82 (12 miles SW of San Luis Obispo, CA) PG&E N/A 86 05000323 08/26/2025 95https://www.nrc.gov/info-~nder/reactors/diab2.html 88 Donald C. Cook Nuclear Plant, Unit 1 III PWR-ICECND 3,304 03/25/1969 87 Indiana Michigan Power Co. WEST 4LP DPR-58 10/25/1974 104 Bridgman, MI AEP 08/28/1975 78(13 miles S of Benton Harbor, MI)

AEP 08/30/2005 94 05000315 10/25/2034 78https://www.nrc.gov/info-~nder/reactors/cook1.html 82 Donald C. Cook Nuclear Plant, Unit 2 III PWR-ICECND 3,468 03/25/1969 104 Indiana Michigan Power Co. WEST 4LP DPR-74 12/23/1977 91 Bridgman, MI AEP 07/01/1978 85(13 miles S of Benton Harbor, MI)

AEP 08/30/2005 101 05000316 12/23/2037 79https://www.nrc.gov/info-~nder/reactors/cook2.html 71 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 96 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent)Dresden Nuclear Power Station, Unit 2 III BWR-MARK 1 2,957 01/10/1966 95 Exelon Generation Co., LLC GE 3 DPR-19 02/20/1991 A 104 Morris, IL S&L 06/09/1970 85 (25 miles SW of Joliet, IL) UE&C 10/28/2004 98 05000237 12/22/2029 83https://www.nrc.gov/info-~nder/reactors/dres2.html 91Dresden Nuclear Power Station, Unit 3 III BWR-MARK 1 2,957 10/14/1966 99 Exelon Generation Co., LLC GE 3 DPR-25 01/12/1971 91 Morris, IL S&L 11/16/1971 89 (25 miles SW of Joliet, IL) UE&C 10/28/2004 95 05000249 01/12/2031 89https://www.nrc.gov/info-~nder/reactors/dres3.html 84Duane Arnold Energy Center III BWR-MARK 1 1,912 06/22/1970 99NextEra Energy Duane Arnold, LLC GE 4 DPR-49 02/22/1974 83 Palo, IA BECH 02/01/1975 89 (8 miles NW of Cedar Rapids, IA)

BECH 12/16/2010 79 05000331 02/21/2034 88https://www.nrc.gov/info-~nder/reactors/duan.html 79 Edwin I. Hatch Nuclear Plant, Unit 1 II BWR-MARK 1 2,804 09/30/1969 98Southern Nuclear Operating Co.

GE 4 DPR-57 10/13/1974 89Baxley, GA BECH 12/31/1975 94 (20 miles S of Vidalia, GA) GPC 01/15/2002 89 05000321 08/06/2034 101https://www.nrc.gov/info-~nder/reactors/hat1.html 93 Edwin I. Hatch Nuclear Plant, Unit 2 II BWR-MARK 1 2,804 12/27/1972 78Southern Nuclear Operating Co., Inc. GE 4 NPF-5 06/13/1978 98Baxley, GA BECH 09/05/1979 89 (20 miles S of Vidalia, GA) GPC 01/15/2002 99 05000366 06/13/2038 91https://www.nrc.gov/info-~nder/reactors/hat2.html 101 Fermi, Unit 2 III BWR-MARK 1 3,486 09/26/1972 94 DTE Electric Company GE 4 NPF-43 07/15/1985 54 Newport, MI S&L 01/23/1988 62(25 miles NE of Toledo, OH) DANI N/A 82 05000341 03/20/2025 69https://www.nrc.gov/info-~nder/reactors/ferm2.html 86 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.

97 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent)Grand Gulf Nuclear Station, Unit 1 IV BWR-MARK 3 4,408 09/04/1974 94Entergy Operations, Inc. GE 6 NPF-29 11/01/1984 70 Port Gibson, MS BECH 07/01/1985 86(20 miles S of Vicksburg, MS) BECH N/A 82 05000416 11/01/2024 93https://www.nrc.gov/info-~nder/reactors/gg1.html 47 H.B. Robinson Steam Electric Plant, Unit 2 II PWR-DRYAMB 2,339 04/13/1967 100Duke Energy Progress, Inc. WEST 3LP DPR-23 07/31/1970 85 Hartsville, SC EBSO 03/07/1971 85(26 miles NW of Florence, SC) EBSO 04/19/2004 86 05000261 07/31/2030 85https://www.nrc.gov/info-~nder/reactors/rob2.html 95Hope Creek Generating Station, Unit 1 I BWR-MARK 1 3,840 11/04/1974 103PSEG Nuclear, LLC GE 4 NPF-57 07/25/1986 93 Hancocks Bridge, NJ BECH 12/20/1986 80 (18 miles SE of Wilmington, DE)

BECH 07/20/2011 102 05000354 04/11/2046 83https://www.nrc.gov/info-~nder/reactors/hope.html 85 Indian Point Nuclear Generating, Unit 2 I PWR-DRYAMB 3,216 10/14/1966 98Entergy Nuclear Indian Point 2, LLC WEST 4LP DPR-26 09/28/1973 90 Buchanan, NY UE&C 08/01/1974 77(24 miles N of New York, NY) WDCO N/A 93 05000247 09/28/2013 77https://www.nrc.gov/info-~nder/reactors/ip2.html 53 Indian Point Nuclear Generating, Unit 3 I PWR-DRYAMB 3,216 08/13/1969 90Entergy Nuclear Indian Point 3, LLC WEST 4LP DPR-64 12/12/1975 100 Buchanan, NY UE&C 08/30/1976 94(24 miles N of New York, NY) WDCO N/A 98 05000286 12/12/2015 86https://www.nrc.gov/info-~nder/reactors/ip3.html 102 James A. FitzPatrick Nuclear Power Plant I BWR-MARK 1 2,536 05/20/1970 97Entergy Nuclear FitzPatrick, LLC GE 4 DPR-59 10/17/1974 84 Scriba, NY S&W 07/28/1975 89 (6 miles NE of Oswego, NY) S&W 09/08/2008 79 05000333 10/17/2034 96https://www.nrc.gov/info-~nder/reactors/~tz.html 76 Joseph M. Farley Nuclear Plant, Unit 1 II PWR-DRYAMB 2,775 08/16/1972 101Southern Nuclear Operating Co.

WEST 3LP NPF-2 06/25/1977 91 Columbia, AL SSI 12/01/1977 90 (18 miles E of Dothan, AL) DANI 05/12/2005 102 05000348 06/25/2037 86https://www.nrc.gov/info-~nder/reactors/far1.html 86 98 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent)Joseph M. Farley Nuclear Plant, Unit 2 II PWR-DRYAMB 2,775 08/16/1972 89Southern Nuclear Operating Co.

WEST 3LP NPF-8 03/31/1981 104 Columbia, AL SSI 07/30/1981 91 (18 miles E of Dothan, AL) BECH 05/12/2005 89 05000364 03/31/2041 98https://www.nrc.gov/info-~nder/reactors/far2.html 90 LaSalle County Station, Unit 1 III BWR-MARK 2 3,546 09/10/1973 101 Exelon Generation Co., LLC GE 5 NPF-11 04/17/1982 97 Marseilles, IL S&L 01/01/1984 95 (11 miles SE of Ottawa, IL) CWE 10/19/2016 93 05000373 04/17/2042 99https://www.nrc.gov/info-~nder/reactors/lasa1.html 89 LaSalle County Station, Unit 2 III BWR-MARK 2 3,546 09/10/1973 96 Exelon Generation Co., LLC GE 5 NPF-18 12/16/1983 103 Marseilles, IL S&L 10/19/1984 88 (11 miles SE of Ottawa, IL) CWE 10/19/2016 95 05000374 12/16/2043 83https://www.nrc.gov/info-~nder/reactors/lasa2.html 95 Limerick Generating Station, Unit 1 I BWR-MARK 2 3,515 06/19/1974 96 Exelon Generation Co., LLC GE 4 NPF-39 08/08/1985 85Limerick, PA BECH 02/01/1986 101(21 miles NW of Philadelphia, PA)

BECH N/A 91 05000352 10/26/2024 100https://www.nrc.gov/info-~nder/reactors/lim1.html 93 Limerick Generating Station, Unit 2 I BWR-MARK 2 3,515 06/19/1974 90 Exelon Generation Co., LLC GE 4 NPF-85 08/25/1989 95Limerick, PA BECH 01/08/1990 94(21 miles NW of Philadelphia, PA)

BECH N/A 99 05000353 06/22/2029 89https://www.nrc.gov/info-~nder/reactors/lim2.html 101McGuire Nuclear Station, Unit 1 II PWR-ICECND 3,411 02/23/1973 94Duke Energy Carolinas, LLC WEST 4LP NPF-9 07/08/1981 105 Huntersville, NC DUKE 12/01/1981 82 (17 miles N of Charlotte, NC) DUKE 12/05/2003 82 05000369 06/12/2041 95https://www.nrc.gov/info-~nder/reactors/mcg1.html 89McGuire Nuclear Station, Unit 2 II PWR-ICECND 3,411 02/23/1973 91Duke Energy Carolinas, LLC WEST 4LP NPF-17 05/27/1983 82 Huntersville, NC DUKE 03/01/1984 95 (17 miles N of Charlotte, NC) DUKE 12/05/2003 94 05000370 03/03/2043 87https://www.nrc.gov/info-~nder/reactors/mcg2.html 97 99 Millstone Power Station, Unit 2 I PWR-DRYAMB 2,700 12/11/1970 87 Dominion Nuclear Connecticut, Inc. CE DPR-65 09/26/1975 83Waterford, CT BECH 12/26/1975 95 (3.2 miles SW of New London, CT)

BECH 11/28/2005 85 05000336 07/31/2035 85https://www.nrc.gov/info-~nder/reactors/mill2.html 93 Millstone Power Station, Unit 3 I PWR-DRYSUB 3,650 08/09/1974 87 Dominion Nuclear Connecticut, Inc. WEST 4LP NPF-49 01/31/1986 100Waterford, CT S&W 04/23/1986 87 (3.2 miles SW of New London, CT)

S&W 11/28/2005 87 05000423 11/25/2045 97https://www.nrc.gov/info-~nder/reactors/mill3.html 83 Monticello Nuclear Generating Plant, Unit 1 III BWR-MARK 1 2,004 06/19/1967 69Northern States Power Company-Minnesota GE 3 DPR-22 01/09/1981 B 101 Monticello, MN BECH 06/30/1971 50 (30 miles NW of Minneapolis, MN)

BECH 11/08/2006 78 05000263 09/08/2030 78https://www.nrc.gov/info-~nder/reactors/mont.html 93 Nine Mile Point Nuclear Station, Unit 1 I BWR-MARK 1 1,850 04/12/1965 84 Nine Mile Point Nuclear Station, LLC GE 2 DPR-63 12/26/1974 C 87 Scriba, NY NIAG 12/01/1969 88 (6 miles NE of Oswego, NY) S&W 10/31/2006 98 05000220 08/22/2029 88https://www.nrc.gov/info-~nder/reactors/nmp1.html 96 Nine Mile Point Nuclear Station, Unit 2 I BWR-MARK 2 3,988 06/24/1974 95 Nine Mile Point Nuclear Station, LLC GE 5 NPF-69 07/02/1987 83 Scriba, NY S&W 03/11/1988 99 (6 miles NE of Oswego, NY) S&W 10/31/2006 87 05000410 10/31/2046 100https://www.nrc.gov/info-~nder/reactors/nmp2.html 92 North Anna Power Station, Unit 1 II PWR-DRYSUB 2,940 02/19/1971 78Virginia Electric & Power Co. WEST 3LP NPF-4 04/01/1978 89Mineral (Louisa County), VA S&W 06/06/1978 89(40 miles NW of Richmond, VA)

S&W 03/20/2003 100 05000338 04/01/2038 91https://www.nrc.gov/info-~nder/reactors/na1.html 89 North Anna Power Station, Unit 2 II PWR-DRYSUB 2,940 02/19/1971 76Virginia Electric & Power Co. WEST 3LP NPF-7 08/21/1980 99Mineral (Louisa County), VA S&W 12/14/1980 85(40 miles NW of Richmond, VA)

S&W 03/20/2003 92 05000339 08/21/2040 99https://www.nrc.gov/info-~nder/reactors/na2.html 87 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.

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.

APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 100 Oconee Nuclear Station, Unit 1 II PWR-DRYAMB 2,568 11/06/1967 79Duke Energy Carolinas, LLC B&W LLP DPR-38 02/06/1973 90 Seneca, SC DBDB 07/15/1973 91(30 miles W of Greenville, SC) DUKE 05/23/2000 91 05000269 02/06/2033 96https://www.nrc.gov/info-~nder/reactors/oco1.html 83 Oconee Nuclear Station, Unit 2 II PWR-DRYAMB 2,568 11/06/1967 93Duke Energy Carolinas, LLC B&W LLP DPR-47 10/06/1973 102 Seneca, SC DBDB 09/09/1974 82(30 miles W of Greenville, SC) DUKE 05/23/2000 101 05000270 10/06/2033 89https://www.nrc.gov/info-~nder/reactors/oco2.html 98 Oconee Nuclear Station, Unit 3 II PWR-DRYAMB 2,568 11/06/1967 103Duke Energy Carolinas, LLC B&W LLP DPR-55 07/19/1974 86 Seneca, SC DBDB 12/16/1974 97(30 miles W of Greenville, SC) DUKE 05/23/2000 92 05000287 07/19/2034 97https://www.nrc.gov/info-~nder/reactors/oco3.html 91Oyster Creek Nuclear Generating Station I BWR-MARK 1 1,930 12/15/1964 98 Exelon Generation Co., LLC GE 2 DPR-16 07/02/1991 D 88Forked River, NJ B&R 12/23/1969 106(9 miles S of Toms River, NJ) B&R 04/08/2009 90 05000219 04/09/2029 109https://www.nrc.gov/info-~nder/reactors/oc.html 95 Palisades Nuclear Plant III PWR-DRYAMB 2,565.4 03/14/1967 96Entergy Nuclear Operations, Inc.

CE DPR-20 02/21/1991 E 74 Covert, MI BECH 12/31/1971 85 (5 miles S of South Haven, MI) BECH 01/17/2007 86 05000255 03/24/2031 89https://www.nrc.gov/info-~nder/reactors/pali.html 99Palo Verde Nuclear Generating Station, Unit 1 IV PWR-DRYAMB 3,990 05/25/1976 83 Arizona Public Service Company CE 80-2L NPF-41 06/01/1985 100Wintersburg, AZ BECH 01/28/1986 85 (50 miles W of Phoenix, AZ) BECH 04/21/2011 90 05000528 06/01/2045 94https://www.nrc.gov/info-~nder/reactors/palo1.html 83Palo Verde Nuclear Generating Station, Unit 2 IV PWR-DRYAMB 3,990 05/25/1976 91 Arizona Public Service Company CE80-2L NPF-51 04/24/1986 90Wintersburg, AZ BECH 09/19/1986 91 (50 miles W of Phoenix, AZ) BECH 04/21/2011 90 05000529 04/24/2046 85https://www.nrc.gov/info-~nder/reactors/palo2.html 95 D: The AEC issued a provisional OL on 04/09/1969, allowing commercial operation. The NRC issued a full-term OL on 07/02/1991.

E: The AEC issued a provisional OL on 03/24/1971, allowing commercial operation. The NRC issued a full-term OL on 02/21/1991.

APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 101Palo Verde Nuclear Generating Station, Unit 3 IV PWR-DRYAMB 3,990 05/25/1976 97 Arizona Public Service Company CE80-2L NPF-74 11/25/1987 88Wintersburg, AZ BECH 01/08/1988 79 (50 miles W of Phoenix, AZ) BECH 04/21/2011 101 05000530 11/25/2047 85https://www.nrc.gov/info-~nder/reactors/palo3.html 85 Peach Bottom Atomic Power Station, Unit 2 I BWR-MARK 1 3,514 01/31/1968 101 Exelon Generation Co., LLC GE 4 DPR-44 10/25/1973 88Delta, PA BECH 07/05/1974 100(17.9 miles S of Lancaster, PA) BECH 05/07/2003 88 05000277 08/08/2033 99https://www.nrc.gov/info-~nder/reactors/pb2.html 96 Peach Bottom Atomic Power Station, Unit 3 I BWR-MARK 1 3,514 01/31/1968 90 Exelon Generation Co., LLC GE 4 DPR-56 07/02/1974 103Delta, PA BECH 12/23/1974 85(17.9 miles S of Lancaster, PA) BECH 05/07/2003 103 05000278 07/02/2034 75https://www.nrc.gov/info-~nder/reactors/pb3.html 95 Perry Nuclear Power Plant, Unit 1 III BWR-MARK 3 3,758 05/03/1977 79FirstEnergy Nuclear Operating Co.

GE 6 NPF-58 11/13/1986 92Perry, OH GIL 11/18/1987 73 (35 miles NE of Cleveland, OH)

KAIS N/A 96 05000440 03/18/2026 83https://www.nrc.gov/info-~nder/reactors/perr1.html 91 Pilgrim Nuclear Power Station I BWR-MARK 1 2,028 08/26/1968 85Entergy Nuclear Operations, Inc.

GE 3 DPR-35 06/08/1972 98 Plymouth, MA BECH 12/01/1972 74 (38 miles SE of Boston, MA) BECH 05/29/2012 97 05000293 06/08/2032 85https://www.nrc.gov/info-~nder/reactors/pilg.html 92 Point Beach Nuclear Plant, Unit 1 III PWR-DRYAMB 1,800 07/19/1967 79NextEra Energy Point Beach, LLC WEST 2LP DPR-24 10/05/1970 100Two Rivers, WI BECH 12/21/1970 84 (13 miles NW of Manitowoc, WI)

BECH 12/22/2005 90 05000266 10/05/2030 92https://www.nrc.gov/info-~nder/reactors/poin1.html 86 Point Beach Nuclear Plant, Unit 2 III PWR-DRYAMB 1,800 07/25/1968 67NextEra Energy Point Beach, LLC WEST 2LP DPR-27 03/08/1973 F 89Two Rivers, WI BECH 10/01/1972 93 (13 miles NW of Manitowoc, WI)

BECH 12/22/2005 90 05000301 03/08/2033 94https://www.nrc.gov/info-~nder/reactors/poin2.html 86F: AEC issued a provisional OL on 11/18/1971. The NRC issued a full-term OL on 03/08/1973.

APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 102 Prairie Island Nuclear Generating Plant, Unit 1 III PWR-DRYAMB 1,677 06/25/1968 91Northern States Power Co.-Minnesota WEST 2LP DPR-42 04/05/1974 G 81Welch, MN FLUR 12/16/1973 90 (28 miles SE of Minneapolis, MN)

NSP 06/27/2011 84 05000282 08/09/2033 77https://www.nrc.gov/info-~nder/reactors/prai1.html 81 Prairie Island Nuclear Generating Plant, Unit 2 III PWR-DRYAMB 1,677 06/25/1968 99Northern States Power Co.-Minnesota WEST 2LP DPR-35 10/29/1974 74Welch, MN FLUR 12/21/1974 59 (28 miles SE of Minneapolis, MN)

NSP 06/27/2011 101 05000306 10/29/2034 65https://www.nrc.gov/info-~nder/reactors/prai2.html 78 Quad Cities Nuclear Power Station, Unit 1 III BWR-MARK 1 2,957 02/15/1967 92 Exelon Generation Co., LLC GE 3 DPR-29 12/14/1972 102Cordova, IL S&L 02/18/1973 85 (20 miles NE of Moline, IL) UE&C 10/28/2004 103 05000254 12/14/2032 83https://www.nrc.gov/info-~nder/reactors/quad1.html 92 Quad Cities Nuclear Power Station, Unit 2 III BWR-MARK 1 2,957 02/15/1967 104 Exelon Generation Co., LLC GE 3 DPR-30 12/14/1972 92Cordova, IL S&L 03/10/1973 91 (20 miles NE of Moline, IL) UE&C 10/28/2004 90 05000265 12/14/2032 95https://www.nrc.gov/info-~nder/reactors/quad2.html 85 R.E. Ginna Nuclear Power Plant I PWR-DRYAMB 1,775 04/25/1966 84 R.E. Ginna Nuclear Power Plant, LLC WEST 2LP DPR-18 09/19/1969 90 Ontario, NY GIL 07/01/1970 93(20 miles NE of Rochester, NY) BECH 05/19/2004 91 05000244 09/18/2029 89https://www.nrc.gov/info-~nder/reactors/ginn.html 94 River Bend Station, Unit 1 IV BWR-MARK 3 3,091 03/25/1977 90Entergy Nuclear Operations, Inc.

GE 6 NPF-47 11/20/1985 91 St. Francisville, LA S&W 06/16/1986 84 (24 miles NW of Baton Rouge, LA)

S&W N/A 96 05000458 08/29/2025 76https://www.nrc.gov/info-~nder/reactors/rbs1.html 78 St. Lucie Plant, Unit 1 II PWR-DRYAMB 3,020 07/01/1970 85 Florida Power & Light Co. CE DPR-67 03/01/1976 72 Jensen Beach, FL EBSO 12/21/1976 74(10 miles SE of Ft. Pierce, FL) EBSO 10/02/2003 101 05000335 03/01/2036 83https://www.nrc.gov/info-~nder/reactors/stl1.html 68G: AEC issued a provisional OL on 08/09/1973. The NRC issued a full-term OL on 04/05/1974.

APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 103 St. Lucie Plant, Unit 2 II PWR-DRYAMB 3,020 05/02/1977 66 Florida Power & Light Co. CE NPF-16 06/10/1983 68 Jensen Beach, FL EBSO 08/08/1983 91(10 miles SE of Ft. Pierce, FL) EBSO 10/02/2003 82 05000389 04/06/2043 77https://www.nrc.gov/info-~nder/reactors/stl2.html 85 Salem Nuclear Generating Station, Unit 1 I PWR-DRYAMB 3,459 09/25/1968 86PSE&G Nuclear, LLC WEST 4LP DPR-70 12/01/1976 97 Hancocks Bridge, NJ PSEG 06/30/1977 88 (18 miles SE of Wilmington, DE)

UE&C 06/30/2011 86 05000272 08/13/2036 95https://www.nrc.gov/info-~nder/reactors/salm1.html 99 Salem Nuclear Generating Station, Unit 2 I PWR-DRYAMB 3,459 09/25/1968 89PSE&G Nuclear, LLC WEST 4LP DPR-75 05/20/1981 88 Hancocks Bridge, NJ PSEG 10/13/1981 100 (18 miles SE of Wilmington, DE)

UE&C 06/30/2011 73 05000311 04/18/2040 85https://www.nrc.gov/info-~nder/reactors/salm2.html 71Seabrook Station, Unit 1 I PWR-DRYAMB 3,648 07/07/1976 77NextEra Energy Seabrook, LLC WEST 4LP NPF-86 03/15/1990 75Seabrook, NH UE&C 08/19/1990 100 (13 miles S of Portsmouth, NH)

UE&C N/A 93 05000443 03/15/2030 87https://www.nrc.gov/info-~nder/reactors/seab1.html 90 Sequoyah Nuclear Plant, Unit 1 II PWR-ICECND 3,455 05/27/1970 98Tennessee Valley Authority WEST 4LP DPR-77 09/17/1980 89Soddy-Daisy, TN TVA 07/01/1981 83 (16 miles NE of Chattanooga, TN)

TVA N/A 100 05000327 09/17/2020 87https://www.nrc.gov/info-~nder/reactors/seq1.html 90 Sequoyah Nuclear Plant, Unit 2 II PWR-ICECND 3,455 05/27/1970 89Tennessee Valley Authority WEST 4LP DPR-79 09/15/1981 77Soddy-Daisy, TN TVA 06/01/1982 90 (16 miles NE of Chattanooga, TN)

TVA N/A 90 05000328 09/15/2021 73https://www.nrc.gov/info-~nder/reactors/seq2.html 95Shearon Harris Nuclear Power Plant, Unit 1 II PWR-DRYAMB 2,900 01/27/1978 103Duke Energy Progress, Inc. WEST 3LP NPF-63 10/24/1986 90 New Hill, NC EBSO 05/02/1987 83 (20 miles SW of Raleigh, NC) DANI 12/17/2008 99 05000400 10/24/2046 87https://www.nrc.gov/info-~nder/reactors/har1.html 88 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 104South Texas Project, Unit 1 IV PWR-DRYAMB 3,853 12/22/1975 94 STP Nuclear Operating Co. WEST 4LP NPF-76 03/22/1988 93Bay City, TX BECH 08/25/1988 91 (90 miles SW of Houston, TX) EBSO 09/28/2017 81 05000498 08/20/2047 78https://www.nrc.gov/info-~nder/reactors/stp1.html 73South Texas Project, Unit 2 IV PWR-DRYAMB 3,853 12/22/1975 88 STP Nuclear Operating Co. WEST 4LP NPF-80 03/28/1989 72Bay City, TX BECH 06/19/1989 59 (90 miles SW of Houston, TX) EBSO 09/28/2017 103 05000499 12/15/2048 85https://www.nrc.gov/info-~nder/reactors/stp2.html 92 Surry Power Station, Unit 1 II PWR-DRYSUB 2,587 06/25/1968 101Virginia Electric and Power Co.

WEST 3LP DPR-32 05/25/1972 92Surry, VA S&W 12/22/1972 91(17 miles NW of Newport News, VA) S&W 03/20/2003 99 05000280 05/25/2032 76https://www.nrc.gov/info-~nder/reactors/sur1.html 96 Surry Power Station, Unit 2 II PWR-DRYSUB 2,587 06/25/1968 76Virginia Electric and Power Co.

WEST 3LP DPR-37 01/29/1973 91Surry, VA S&W 05/01/1973 101(17 miles NW of Newport News, VA) S&W 03/20/2003 95 05000281 01/29/2033 82https://www.nrc.gov/info-~nder/reactors/sur2.html 101 Susquehanna Steam Electric Station, Unit 1 I BWR-MARK 2 3,952 11/03/1973 86Susquehanna Nuclear, LLC GE 4 NPF-14 07/17/1982 70Berwick, PA BECH 06/08/1983 87(70 miles NE of Harrisburg, PA) BECH 11/24/2009 83 05000387 07/17/2042 76https://www.nrc.gov/info-~nder/reactors/susq1.html 77 Susquehanna Steam Electric Station, Unit 2 I BWR-MARK 2 3,952 11/03/1973 72 PPL Susquehanna, LLC GE 4 NPF-22 03/23/1984 83Berwick, PA BECH 02/12/1985 80(70 miles NE of Harrisburg, PA) BECH 11/24/2009 88 05000388 03/23/2044 82https://www.nrc.gov/info-~nder/reactors/susq2.html 93Three Mile Island Nuclear Station, Unit 1 I PWR-DRYAMB 2,568 05/18/1968 92 Exelon Generation Co., LLC B&W LLP DPR-50 04/19/1974 100Middletown, PA GIL 09/02/1974 78(10 miles SE of Harrisburg, PA) UE&C 10/22/2009 104 05000289 04/19/2034 77https://www.nrc.gov/info-~nder/reactors/tmi1.html 82 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 105Turkey Point Nuclear Generating, Unit 3 II PWR-DRYAMB 2,644 04/27/1967 96 Florida Power & Light Co. WEST 3LP DPR-31 07/19/1972 40 Homestead, FL BECH 12/14/1972 81 (20 miles S of Miami, FL) BECH 06/06/2002 84 05000250 07/19/2032 78https://www.nrc.gov/info-~nder/reactors/tp3.html 93Turkey Point Nuclear Generating, Unit 4 II PWR-DRYAMB 2,644 04/27/1967 84 Florida Power & Light Co. WEST 3LP DPR-41 04/10/1973 85 Homestead, FL BECH 09/07/1973 70 (20 miles S of Miami, FL) BECH 06/06/2002 88 05000251 04/10/2033 106https://www.nrc.gov/info-~nder/reactors/tp4.html 99Virgil C. Summer Nuclear Station, Unit 1 II PWR-DRYAMB 2,900 03/21/1973 88South Carolina Electric & Gas Co.

WEST 3LP NPF-12 11/12/1982 86 Jenkinsville, SC GIL 01/01/1984 93 (26 miles NW of Columbia, SC)

DANI 04/23/2004 81 05000395 08/06/2042 79https://www.nrc.gov/info-~nder/reactors/sum.html 96Vogtle Electric Generating Plant, Unit 1 II PWR-DRYAMB 3,625.6 06/28/1974 92Southern Nuclear Operating Co., Inc. WEST 4LP NPF-68 03/16/1987 91Waynesboro, GA SBEC 06/01/1987 101 (26 miles SE of Augusta, GA) GPC 06/03/2009 87 05000424 01/16/2047 91https://www.nrc.gov/info-~nder/reactors/vog1.html 101Vogtle Electric Generating Plant, Unit 2 II PWR-DRYAMB 3,625.6 06/28/1974 94Southern Nuclear Operating Co., Inc. WEST 4LP NPF-81 03/31/1989 102Waynesboro, GA SBEC 05/20/1989 87 (26 miles SE of Augusta, GA) GPC 06/03/2009 92 05000425 02/09/2049 100https://www.nrc.gov/info-~nder/reactors/vog2.html 94Waterford Steam Electric Station, Unit 3 IV PWR-DRYAMB 3,716 11/14/1974 82Entergy Operations, Inc. COMB CE NPF-38 03/16/1985 77 Killona, LA EBSO 09/24/1985 89 (25 miles W of New Orleans, LA)

EBSO N/A 90 05000382 12/18/2024 80https://www.nrc.gov/info-~nder/reactors/wat3.html 96Watts Bar Nuclear Plant, Unit 1 II PWR-ICECND 3,459 01/23/1973 84Tennessee Valley Authority WEST 4LP NPF-90 02/07/1996 87Spring City, TN TVA 05/27/1996 90 (60 miles SW of Knoxville, TN) TVA N/A 89 05000390 11/09/2035 76https://www.nrc.gov/info-~nder/reactors/wb1.html 85 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 106Watts Bar Nuclear Plant, Unit 2 II PWR-ICECND 3,411 01/24/1973

---Tennessee Valley Authority WEST 4LP NPF-96 10/22/2015

---Spring City, TN TVA 10/19/2016

---(60 miles SW of Knoxville, TN) TVA N/A ---05000391 10/22/2055 0https://www.nrc.gov/info-~nder/reactors/wb2.html 26Wolf Creek Generating Station, Unit 1 IV PWR-DRYAMB 3,565 05/17/1977 72Wolf Creek Nuclear Operating Corp. WEST 4LP NPF-42 06/04/1985 H 80Burlington (Coffey County), KS BECH 09/03/1985 65 (28 miles SE of Emporia, KS) DANI 11/20/2008 83 05000482 03/11/2045 78https://www.nrc.gov/info-~nder/reactors/wc.html 74 H: The original OL (NPF-32) was issued on 03/11/1985. The license was superseded by OL (NPF-42), issued on 06/04/1985.

Bellefonte Nuclear Power Station, Unit 1**

II PWR-DRYAMB 3,763 12/24/1974 N/ATennessee Valley Authority B&W 205 (6 miles NE of Scottsboro, AL) TVA 05000438 TVAhttp://www.nrc.gov/reactors/new-reactors/col/bellefonte.html Bellefonte Nuclear Power Station, Unit 2**

II PWR-DRYAMB 3,763 12/24/1974 N/ATennessee Valley Authority B&W 205 (6 miles NE of Scottsboro, AL) TVA 05000439 TVAhttp://www.nrc.gov/reactors/new-reactors/col/bellefonte.html Enrico Fermi Nuclear Plant, Unit 3 III ESBWR 4,500 N/A 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

Levy County Nuclear Plant, Unit 1 A III PWR 3,400 N/ADuke Energy Florida, LLC AP1000 NPF-99 10/26/2016Levy County, FL WEST 2LP (2 miles NE of Inglis, FL) 05200029 https://www.nrc.gov/reactors/new-reactors/col-holder/levy1.html APPENDIX ACommercial Nuclear Power Reactors Operating Reactors (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent)Operating Reactors Under Active Construction or Deferred Policy Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent) 107 APPENDIX ACommercial Nuclear Power Reactors Operating Reactors under Active Construction or Deferred Policy (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type Licensed OL Issued 2016*Location NSSS MWt Comm. Op. CapacityDocket Number NRC Architect Engineer License LR Issued FactorNRC Web Page Address Region Constructor Number Exp. Date (Percent)Levy County Nuclear Plant, Unit 2 A III PWR 3,400 N/ADuke Energy FL, LLC AP1000 NPF-100 10/26/2016Levy County, FL WEST 2LP (2 miles NE of Inglis, FL) 05200030 https://www.nrc.gov/reactors/new-reactors/col-holder/levy2.html North Anna Power Station, Unit 3 II BWR 4,500 N/ADominion 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 South Texas Project, Unit 3 IV BWR 3,926 N/A STP Nuclear Operating Co. ABWR NPF-97 02/12/2016 Bay City, TX (90 miles SW of Houston, TX) 05200012 https://www.nrc.gov/reactors/new-reactors/col-holder/stp3.html South Texas Project, Unit 4 IV BWR 3,926 N/A STP Nuclear Operating Co. ABWR NPF-98 02/12/2016 Bay City, TX (90 miles SW of Houston, TX) 05200013 https://www.nrc.gov/reactors/new-reactors/col-holder/stp4.html Virgil C. Summer Nuclear Station, Unit 2 B II PWR 3,400 N/ASouth Carolina Electric & Gas Co.

AP1000 NPF-93 03/30/2012South Carolina Public Service Auth. WEST 2LP Jenkinsville (Fair~eld County), SC (26 miles NW of Columbia, SC) 0520027 https://www.nrc.gov/reactors/new-reactors/col-holder/sum2.htmlVirgil C. Summer Nuclear Station, Unit 3 B II PWR 3,400 N/ASouth Carolina Electric & Gas Co.

AP1000 NPF-94 03/30/2012South Carolina Public Service Auth. WEST 2LP Jenkinsville (Fair~eld County), SC (26 miles NW of Columbia, SC) 05200028 https://www.nrc.gov/reactors/new-reactors/col-holder/sum3.html A: In September 2017, Duke Energy Florida announced cancellation of Levy County nuclear power plant, Units 1 and 2 project. B: On July 31, 2017, South Carolina Electric & Gas (SCE&G) to ceased construction on V.C. Summer nuclear power plant, Units 2 and 3.

108Vogtle Electric Generating Plant, Unit 3 II PWR 3,400 N/ASouthern Nuclear Operating Co., Inc. AP1000 NPF-91 02/10/2012Waynesboro (Burke County), GA WEST 2LP (26 miles SE of Augusta, GA) 05200025 https://www.nrc.gov/reactors/new-reactors/col-holder/vog3.htmlVogtle Electric Generating Plant, Unit 4 II PWR 3,400 N/ASouthern Nuclear Operating Co., Inc. AP1000 NPF-92 02/10/2012Waynesboro, (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 3 C II PWR 3,400 N/ADuke Energy Carolinas AP1000 NPF-101 12/19/2016Cherokee 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 4 C II PWR 3,400 N/ADuke Energy Carolinas AP1000 NPF-102 12/19/2016Cherokee County, SC WEST 2LP(2 miles SE of Gafney, SC) 05200019 https://www.nrc.gov/reactors/new-reactors/col-holder/lee2.html APPENDIX ACommercial Nuclear Power Reactors Operating Reactors under Active Construction or Deferred Policy (continued)

Plant Name, Unit Number CP Issued 2011-Licensee Con Type COL Issued 2016*Location NSSS Comm. Op. CapacityDocket Number NRC Architect Engineer Licensed LR Issued FactorNRC Web Page Address Region Constructor MWt Exp. Date (Percent)C: In September 2017, Duke Energy announced cancellation of the William States Lee nuclear power plant, Units 3 and 4 project.

• Average capacity factor is listed in year order starting with 2009. ** 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 identi~ed on the license as of July 2017; the next printed update will be in August 2018.

Source: NRC, with some data compiled from U.S. Department of Energy's (DOE's) Energy Information Administration (EIA).

109 Applicant Docket Number TypeSubmittal

Date Design Site StateExisting Plant?Date Accepted Status Combined Operating LicenseNuclear Innovation North America, LLC 05200012 &

05200013 COL 9/20/07 ABWRSouth Texas Project, Units 3 and 4 TXYes 11/29/07 COL Issued 02/09/2016Tennessee Valley Authority (TVA)05200014 &

05200015 COL 10/30/07 AP1000Bellefonte, Units 3 and 4 AL No 1/18/08Withdrawn-

12/02/2016Dominion Virginia Power 05200017 COL 11/27/07 ESBWRNorth Anna, Unit 3 VAYes 01/28/08 COL Issued 06/02/2017 Duke Energy Carolinas05200018 &

05200019 COL 12/13/07 AP1000Lee Nuclear Station, Units 3 and 4 SC No 2/25/08 COL Issued 12/19/2016 Progressive Energy05200022 &

05200023 COL 2/19/08 AP1000Shearon Harris, Units 2 and 3 NCYes 4/17/08 Suspended-

05/02/2013Southern Nuclear Operating Co.05200025 &

05200026 COL 3/31/08 AP1000Vogtle, Units 3 and 4 GAYes 5/30/08 COL Issued

02/10/2012South Carolina Electric and Gas05200027 &

05200028 COL 3/31/08 AP1000V.C. Summer, Units 2 and 3 SCYes 7/31/08 COL Issued

03/30/2012 AmerenUE 05200037 COL 7/24/08U.S. EPRCallaway, Unit 2 MOYes 12/12/08Withdrawn-

10/19/2015Duke Energy Florida05200029 &

05200030 COL 7/30/08 AP1000Levy County, Units 1 and 2 FL No 10/6/08 COL Issued

10/26/2016DTE Electric Company 05200033 COL 9/18/08 ESBWRFermi, Unit 3 MIYes 11/25/08 COL Issued 05/01/2015Luminant Generation Co.05200034 &

05200035 COL 9/19/08 US-APWRComanche Peak, Units 3 and 4 TXYes 12/2/08 Suspended-

03/31/2014Entergy 05200036 COL 9/25/08 ESBWRRiver Bend, Unit 3 LAYes 12/4/08Withdrawn-

06/14/2016 PPL Bell Bend 05200039 COL 10/10/08U.S. EPRBell Bend (1 Unit)PAYes 12/19/08Withdrawn-

09/22/2016Florida Power and Light05200040 &

05200041 COL 6/30/09 AP1000Turkey Point, Units 6 and 7 FLYes 9/4/09 Scheduled Design Certi~cationAREVA NP 05200020 DC 12/11/07U.S. EPR N/A N/A N/A 2/25/08Suspended-

03/27/2015Mitsubishi Heavy

Industries 05200021 DC 12/31/07 US-APWR N/A N/A N/A 2/29/08Applicant Delayed

-Not ScheduledKorea Electric Power Company and Korea Hydro and Nuclear Power 05200046 DC 12/23/14 APR 1400 N/A N/A N/A 3/4/15Scheduled Toshiba Corporation 05200044 DC 10/27/10 ABWR N/A N/A N/A 12/14/10Withdrawn-

12/30/2016GE-Hitachi Nuclear Energy 05200045DC 12/7/10 ABWR N/A N/A N/A 2/14/11 ScheduledNuScale Power LLC 05200048DC 01/06/17 NuScale N/A N/A N/A 3/23/17 Scheduled Early Site Permit PSEG Site 05200043 ESP 5/25/10Not yet announced PSEG Site NJYes 8/4/10Issued 05/06/2016TVA Clinch River SMR Site 05200043 ESP 5/25/10Not yet announced Clinch River Site TN No 1/12/17 Scheduled APPENDIX B New Nuclear Power Plant Licensing Applications Notes: Withdrawal was requested for Calvert Cliffs, Grand Gulf, Nine Mile Point, Victoria County, and Callaway (COL and ESP). On July 31, 2017, a decision was announced by South Carolina Electric & Gas (SCE&G) to cease construction on V.C. Summer nuclear power plant, Units 2 and 3.

In September 2017, Duke Energy has announced cancellation of the William States Lee nuclear power plant, Units 3 and 4 project, and Levy County Units 1 and 2. Data are current as of October 2017; the next printed update will be in August 2018. NRC-abbreviated reactor names listed.

110 APPENDIX CCommercial 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 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 2074Dresden 1 BWR GE 09/28/1959 SAFSTOR Morris, IL 700 10/31/1978 SAFSTOR 05000010 2036 GE EVESR Experimental GE 11/12/1963 SAFSTOR Sunol, CA Superheat Reactor 02/1/1967 Possession Only 05000183 12.5 04/15/1970 License Expires 01/1/2019 01/2016GE VBWR (Vallecitos)

BWR GE 08/31/1957 SAFSTOR Sunol, CA 50 12/09/1963 SAFSTOR 05000018 2019 Fermi 1 SCF CE 05/10/1963 SAFSTOR Newport, MI 200 09/22/1972 DECON 05000016 2032 Fort Calhoun 1 PWR-DRYAMB CE 08/09/1973 SAFSTOR Ft. Calhoun, NE 1,500 10/24/2016 SAFSTOR in Progress 05000285 2065 Fort St. Vrain HTG GA 12/21/1973 DECON Platteville, CO 842 08/18/1989 DECON Completed 05000267 08/08/1997 Haddam Neck PWR WEST 12/27/1974 DECON Meriden, CT 1,825 12/05/1996 DECON Completed 05000213 11/26/2007

111 APPENDIX CCommercial 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 Closure Date Est.

Humboldt Bay 3 BWR GE 08/28/1962 DECON Eureka, CA 200 07/02/1976 DECON in Progress 05000133 2017 Indian Point 1 PWR B&W 03/26/1962 SAFSTOR Buchanan, NY 615 10/31/1974 SAFSTOR 05000003 2026 Kewaunee PWR WEST 2LP 12/21/1973 SAFSTOR Carlton, WI 1,772 05/07/2013 SAFSTOR 05000305 2073La Crosse BWR AC 07/03/1967 DECON Genoa, WI 165 04/30/1987 DECON in Progress 05000409 TBD 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

Path~nder BWR AC 03/12/1964 DECON Sioux Falls, SD 190 09/16/1967 DECON Completed 05000130 07/27/2007 Peach Bottom 1 HTG GA 01/24/1966 SAFSTOR Delta, PA 115 10/31/1974 SAFSTOR 05000171 12/31/2034 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 12/30/2030

112 APPENDIX CCommercial 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 Closure Date Est.San Onofre 2*

PWR CE CE 02/16/1982 DECON San Clemente, CA 3,438 06/12/2013 DECON in Progress 05000361 2030San 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 SAFSTOR Baltimore, MD 74 11/1970 SAFSTOR 05000238 12/01/2031 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 2 PWR B&W 02/08/1978

• • Middletown, PA 2,770 03/28/1979 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 SAFSTOR Vernon, VT 1,912 12/29/2014 SAFSTOR in Progress 05000271 2073 Zion 1 PWR WEST 10/19/1973 DECON Zion, IL 3,250 02/21/1997 DECON in Progress 05000295 113 APPENDIX CCommercial 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 Closure Date Est.

Zion 2 PWR WEST 11/14/1973 DECON Zion, IL 3,250 09/19/1996 DECON in Progress 05000304 2020

• 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 postdefueling 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 http://energy.gov/lm/sites/lm-sites. CVTR, Elk River, and Shippingport decommissioned reactor sites were either decommissioned prior to the formation of the NRC or were not licensed by the NRC.

See the Glossary for de~nitions 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 July 2017. The next printed update will be in August 2018.

114 APPENDIX DCanceled Commercial Nuclear Power ReactorsPart 50-Domestic Licensing of Production and Utilization Facilities Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket NumberAllens Creek 1 BWR 1982 Houston Lighting & Power Company 1,150 Under CP Review 4 miles NW of Wallis, TX 05000466Allens 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 & 511Cherokee 1 PWR 1983 Duke Power Company 1,280 With CP 6 miles SSW of Blacksburg, SC 05000491Cherokee 2 & 3 PWR 1982 Duke Power Company 1,280 With CP 6 miles SSW of Blacksburg, SC 05000492 & 493 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 & 501 115 APPENDIX DCanceled Commercial Nuclear Power Reactors (continued)Part 50-Domestic Licensing of Production and Utilization Facilities Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number 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 05000417Greene County PWR 1980 Power Authority of the State of NY 1,191 Under CP Review 20 miles N of Kingston, NY 05000549Greenwood 2 & 3 PWR 1980 Detroit Edison Company 1,200 Under CP Review Greenwood Township, MI 05000452 & 453 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 05000503Hope Creek 2 BWR 1981 Public Service Electric & Gas Company 1,067 With CP 18 miles SE of Wilmington, DE 05000355 116 APPENDIX DCanceled Commercial Nuclear Power Reactors (continued)Part 50-Domestic Licensing of Production and Utilization Facilities Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number 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 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 05000376Palo 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 & 490 117 APPENDIX DCanceled Commercial Nuclear Power Reactors (continued)Part 50-Domestic Licensing of Production and Utilization Facilities Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number 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 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 05000459Seabrook 2 PWR 1988 Public Service Co. of New Hampshire 1,198 With CP 13 miles S of Portsmouth, NH 05000444Shearon Harris 2 PWR 1983 Carolina Power & Light Company 900 With CP 20 miles SW of Raleigh, NC 05000401Shearon Harris 3 & 4 PWR 1981 Carolina Power & Light Company 900 With CP 20 miles SW of Raleigh, NC 05000402 & 403Skagit/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 & 583 118 APPENDIX DCanceled Commercial Nuclear Power Reactors (continued)Part 50-Domestic Licensing of Production and Utilization Facilities Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Surry 3 & 4 PWR 1977 Virginia Electric & Power Company 882 With CP 17 miles NW of Newport News, VA 05000434 & 435Tyrone 1 PWR 1981 Northern States Power Company 1,150 Under CP Review 8 miles NE of Durond, WI 05000484Tyrone 2 PWR 1974 Northern States Power Company 1,150 With CP 8 miles NE of Durond, WI 05000487Vogtle 3 & 4 PWR 1974 Georgia Power Company 1,113 With CP 26 miles SE of Augusta, GA 050000426 & 427Washington Nuclear 1 (WPPSS)

PWR 1995 Energy Northwest 1,266 With CP 12 miles NE of Richland, WA 05000460Washington Nuclear 3 (WPPSS)

PWR 1995 Energy Northwest 1,242 With CP 12 miles NE of Richland, WA 05000508Washington Nuclear 4 (WPPSS)

PWR 1982 Energy Northwest 1,218 With CP 12 miles NE of Richland, WA 05000513Washington Nuclear 5 (WPPSS)

PWR 1982 Energy Northwest 1,242 With CP 12 miles NE of Richland, WA 05000509Yellow 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 Bellefonte 3 & 4 AP1000 2016 Tennessee Valley Authority 1,100 With COL Scottsboro, Jackson County, AL 05200014 & 05200015 Bell Bend U.S. EPR 2016 Bell Bend, LLC 1,600 With COL Luzerne County, PA 5200039 119 Callaway 2 U.S. EPR 2015 Union Electric Company (Ameren UE) 1,600 With COL Fulton, Callaway County , MO 05200037Calvert Cliffs 3 U.S. EPR July 17, 2015 UniStar Nuclear Operating Services, LLC 4,500 With COL Review Near Lusby in Calvert County, MD 05200016 Grand Gulf 3 ESBWR January 9, 2009 Entergy Operations, Inc.

4,500 With COL Review Near Port Gibson in Claiborne County, MS 05200024 Nine Mile Point 3 ESBWR January 9, 2009 UniStar Nuclear Operating Services, LLC 4,500 With COL Review 25 miles SE of Cincinnati, OH 0500038 River Bend 3 ESBWR 2016 Entergy Operations, Inc.

1,594 With COL St. Francisville, LA 5200036 Victoria County Station 1 and 2 ESBWR June 11, 2010 Exelon Nuclear Texas Holdings, LLC 4,500 With COL Review Near Victoria City in Victoria County, TX 05200031 & 05200032 APPENDIX DCanceled Commercial Nuclear Power Reactors (continued)Part 52-Licensing, Certi~cation, and Approvals for Nuclear Power Plants Unit Canceled Date Utility Con Type Status Location MWe per Unit Docket Number Notes: Cancellation is de~ned as public announcement of cancellation or written noti~cation to the NRC. Only NRC-docketed applications are included. "Status" is the status of the application at the time of cancellation.Data are current as of July 2017; the next printed update will be in August 2018.

Withdrawal was requested for Calvert Cliffs, Grand Gulf, Nine Mile Point, Victoria County, and Callaway (COL and ESP). NRC-abbreviated reactor names listed.Source: DOE/EIA, "Commercial Nuclear Power 1991," DOE/EIA-0438, Appendix E, and the NRC.

120 APPENDIX ECommercial Nuclear Power Reactors by Parent Company Utility NRC-Abbreviated Reactor Unit NameAmerenUE Callaway* www.ameren.com Arizona Public Service Company Palo Verde 1, 2, & 3*

www.aps.com Dominion Generation Millstone 2 & 3 www.dom.com North Anna 1 & 2 Surry 1 & 2 DTE Electric Company Fermi 2 www.dteenergy.com Duke Energy Brunswick 1 & 2 www.duke-energy.com Catawba 1 & 2 Harris 1 McGuire 1 & 2 Oconee 1, 2, & 3 Robinson 2Energy Northwest Columbia www.energy-northwest.comEntergy Nuclear Operations, Inc.

Arkansas Nuclear One 1 & 2 www.entergy-nuclear.com FitzPatrick Grand Gulf 1 Indian Point 2 & 3 Palisades Pilgrim 1 River Bend 1 Waterford 3 Exelon Corporation, LLC Braidwood 1 & 2 www.exeloncorp.com Byron 1 & 2 Calvert Cliffs 1 & 2 Clinton Dresden 2 & 3 Ginna LaSalle 1 & 2 Limerick 1 & 2 Nine Mile Point 1 & 2 Oyster Creek Peach Bottom 2 & 3 Quad Cities 1 & 2 Three Mile Island 1First Energy Nuclear Operating Company Beaver Valley 1 & 2 www.~rstenergycorp.com Davis-Besse

Perry 1 121 APPENDIX ECommercial Nuclear Power Reactors by Parent Company (continued)

Utility NRC-Abbreviated Reactor Unit Name Indiana Michigan Power Company Cook 1 & 2 www.indianamichiganpower.com Nebraska Public Power District Cooper www.nppd.comNextEra Energy Inc. with principal subsidiaries Duane Arnold Florida Power & Light Co. and Point Beach 1 & 2 NextEra Energy Resources, LLC Seabrook 1 www.fplgroup.com St. Lucie 1 & 2 Turkey Point 3 & 4Northern States Power Company Monticello Minnesota doing business as Xcel Energy Prairie Island 1 & 2 www.xcelenergy.com

Paci~c Gas & Electric Company Diablo Canyon 1 & 2*

www.pge.comPSEG Nuclear, LLC Hope Creek 1 www.pseg.com Salem 1 & 2South Carolina Electric & Gas Company Summer www.sceg.comSouthern Nuclear Operating Company Farley 1 & 2 www.southerncompany.com Hatch 1 & 2 Vogtle 1 & 2 STP Nuclear Operating Company South Texas Project 1 & 2*

www.stpegs.comTalen Energy Corp.

Susquehanna 1 & 2 www.talenenergy.comTennessee Valley Authority Browns Ferry 1, 2, & 3 www.tva.gov Sequoyah 1 & 2 Watts Bar 1 & 2Vistra Energy Comanche Peak 1 & 2*

www.vistraenergy.com Wolf Creek Nuclear Operating Corporation Wolf Creek 1*

www.wcnoc.com

• These plants have a joint program called the Strategic Teaming and Resource Sharing group.

They share resources for refueling outages and develop some shared licensing applications.Note: Data are current as of July 2017; the next printed update will be in August 2018.

122* AEC 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 July 2017; the next printed update will be in August 2018.

1969Dresden 2*

Ginna*Nine Mile Point 1*Oyster Creek*

1970 Point Beach 1*

Robinson 2 1971Dresden 3 Monticello*

1972 Palisades*

Pilgrim Quad Cities 1

Quad Cities 2 Surry 1Turkey Point 3 1973Browns Ferry 1 Indian Point 2 Oconee 1 Oconee 2 Peach Bottom 2

Point Beach 2*

Surry 2Turkey Point 4 1974 Arkansas Nuclear 1Browns Ferry 2 Brunswick 2Calvert Cliffs 1 Cooper Cook 1 Duane Arnold FitzPatrick

Hatch 1 Oconee 3 Peach Bottom 3 Prairie Island 1 Prairie Island 2Three Mile Island 1 1975 Millstone 2 1976Beaver Valley 1Browns Ferry 3 Brunswick 1 Calvert Cliffs 2 Indian Point 3 Salem 1 St. Lucie 1 1977 Davis-Besse D.C. Cook 2 Farley 1 1978 Arkansas Nuclear 2 Hatch 2 North Anna 1 1980 North Anna 2 Sequoyah 1 1981 Farley 2McGuire 1 Salem 2 Sequoyah 2 1982 LaSalle 1 SummerSusquehanna 1 1983McGuire 2 St. Lucie 2 1984 Callaway Columbia Diablo Canyon 1 Grand Gulf 1 LaSalle 2 Susquehanna 2 1985Byron 1 Catawba 1 Diablo Canyon 2 Fermi 2 Limerick 1 Palo Verde 1 River Bend 1Waterford 3Wolf Creek 1 1986 Catawba 2Hope Creek 1 Millstone 3 Palo Verde 2 Perry 1 1987Beaver Valley 2 Braidwood 1Byron 2 Clinton Harris 1 Nine Mile Point 2Palo Verde 3 Vogtle 1 1988 Braidwood 2South Texas Project 1 1989 Limerick 2 South Texas Project 2Vogtle 2 1990 Comanche Peak 1Seabrook 1 1993 Comanche Peak 2 1996Watts Bar 1 APPENDIX FCommercial Nuclear Power Reactor Operating Licenses-Issued by Year APPENDIX GCommercial Nuclear Power Reactor Operating Licenses-Expiration by Year, 2013-2055Notes: This list includes Indian Point 2 & 3, which entered timely renewal on September 29, 2013, and December 12, 2015. Limited to reactors licensed to operate. NRC-abbreviated reactor names listed. Data are current as of October 2017; the next printed update will be in August 2018.2013 Indian Point 2 2015 Indian Point 3 2024 Diablo Canyon 1Waterford 3 2025 Diablo Canyon 2 River Bend 1 2026 Clinton Perry 2029Ginna Nine Mile Point 1 Oyster Creek 2030 Comanche Peak 1

Monticello

Point Beach 1 Robinson 2Seabrook 2031Dresden 3 Palisades 2032Pilgrim Quad Cities 1

Quad Cities 2 Surry 1Turkey Point 3 2033Browns Ferry 1

Comanche Peak 2

Fort Calhoun Oconee 1 Oconee 2 Peach Bottom 2

Point Beach 2 Prairie Island 1 Surry 2 Turkey Point 4 2034 Arkansas Nuclear 1Browns Ferry 2 Brunswick 2 Calvert Cliffs 1 Cook 1 Cooper Duane Arnold

Hatch 1 FitzPatrick Oconee 3 Peach Bottom 3

Prairie Island 2Three Mile Island 1 2035Millstone 2 Watts Bar 1 2036Beaver Valley 1 Browns Ferry 3 Brunswick 1 Calvert Cliffs 2 St. Lucie 1

Salem 1 2037Cook 2 Davis-Besse 1 Farley 1 2038 Arkansas Nuclear 2 Hatch 2 North Anna 1 2040 North Anna 2

Salem 2 Sequoyah 1 2041 Farley 2McGuire 1 Sequoyah 2 2042 LaSalle 1 Summer Susquehanna 1 2043 Catawba 1 Catawba 2 Columbia LaSalle 2 McGuire 2 St. Lucie 2 2044Byron 1 Calloway Grand Gulf 1 Limerick 1 Susquehanna 2 2045 Fermi 2 Millstone 3 Palo Verde 1Wolf Creek 1 2046 Braidwood 1 Byron 2 Harris 1Hope CreekNine Mile Point 2 Palo Verde 2 2047Beaver Valley 2 Braidwood 2 Palo Verde 3South Texas Project 1 Vogtle 12048 South Texas Project 2 2049 Limerick 2 Vogtle 2 2055Watts Bar 2 123 APPENDIX HOperating Nuclear Research and Test Reactors Regulated by the NRC Licensee Reactor Type Power Level Licensee Number Location OL Issued (kW) Docket NumberAerotest TRIGA (Indus) 250 R-98 San Ramon, CA 07/02/1965 05000228Armed Forces Radiobiology TRIGA 1,100 R-84 Research Institute 06/26/1962 05000170 Bethesda, MD Dow Chemical Company TRIGA 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 250 R-88 Manhattan, KS 10/16/1962 05000188 Massachusetts Institute HWR Reected 6,000 R-37 of Technology 06/09/1958 05000020 Cambridge, MA

Missouri University of Science Pool 200 R-79 and Technology 11/21/1961 05000123 Rolla, MO National Institute of Nuclear Test 20,000 TR-5 Standards & 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 05000150Oregon 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 05000005Purdue 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 124 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, RITexas A&M University AGN-201M #106 0.005 R-23 College Station, TX 08/26/1957 05000059Texas 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 05000274University of California/Davis TRIGA 2,300 R-130 Sacramento, CA 08/13/1998 05000607University 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 05000252University 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 05000156Washington State University TRIGA 1,000 R-76 Pullman, WA 03/06/1961 05000027 Note: Data are current as of July 2017; the next printed update will be in August 2018.

APPENDIX HOperating Nuclear Research and Test Reactors Regulated by the NRC (continued)

Licensee Reactor Type Power Level Licensee Number Location OL Issued (kW) Docket Number 125 APPENDIX INuclear 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 University of Buffalo Pulstar 03/24/61 Buffalo, NY 2,000 07/23/96 Note: Data are current as of July 2017; the next printed update will be in August 2018.

APPENDIX J Radiation Doses and Regulatory Limits

126 APPENDIX K Materials Licenses by State Number of Licenses State NRCAgreement States Alabama 16 388 Alaska 66 0 Arizona 11 339 Arkansas 6 208California 59 1,762 Colorado 19 319 Connecticut 138 0Delaware 43 0 District of Columbia 32 0 Florida 26 1,620Georgia 22 414 Hawaii 58 0 Idaho 73 0 Illinois 32 625 Indiana 239 0 Iowa 2 164 Kansas 13 272 Kentucky 12 364 Louisiana 10 459 Maine 4 103 Maryland 82 537 Massachusetts 31 424 Michigan 430 0 Minnesota 15 136 Mississippi 7 286 Missouri 246 0 Montana 84 0 Nebraska 5 140 Nevada 2 242New Hampshire 3 86 New Jersey 35 573 Number of Licenses State NRCAgreement States New Mexico 13 214New York 22 1,310North Carolina 24 578 North Dakota 4 89 Ohio 41 593 Oklahoma 16 231Oregon 5 271 Pennsylvania 46 631 Rhode Island 2 44South Carolina 15 364 South Dakota 36 0Tennessee 22 526Texas 47 1,493 Utah 10 190Vermont 33 0Virginia 57 398Washington 16 332West Virginia 161 0 Wisconsin 12 292 Wyoming 87 0 Puerto Rico 117 0Virgin Islands 8 0 Guam 7 0Total number of materials licenses in Agreement State jurisdiction 17,017Total number of materials licenses in NRC jurisdiction 2,622Total number of materials licenses

in the United States 19,639Notes: The NRC and Agreement State data are as of July 2017. These totals represent an estimate because the number of speci~c radioactive materials licenses per State may change daily. Data are current as of July 2017.

The next printed update will be in August 2018.The NRC licenses Federal agencies in Agreement States.Agreement State Letter of Intent Draft Application 127 APPENDIX L Major U.S. Fuel Cycle Facility Sites Licensee Location Status Docket #Uranium Hexauoride Conversion FacilityHoneywell International, Inc.Metropolis, IL active 04003392 Uranium Fuel Fabrication Facilities Global Nuclear Fuel-Americas, LLC Wilmington, NC active 07001139Westinghouse Electric Company, LLC Columbia Fuel Fabrication Facility Columbia, SC active 07001151 Nuclear Fuel Services, Inc.

Erwin, TN active 07000143BWXT Nuclear Operations Group, Inc.Lynchburg, VA active 07000027AREVA , Inc.Richland, WA active 07001257 Mixed-Oxide Fuel Fabrication FacilityCB&I AREVA MOX Services, LLC Aiken, SCconstruction 07003098 Gas Centrifuge Uranium Enrichment Facilities Centrus Energy Corp.

Lead Cascade: Test and Demonstration Facility Piketon, OHtransitioning into decommissiong 07007003Centrus Energy Corp American Centrifuge Plant Piketon, OHlicense issued, construction halted 07007004URENCO-USA (Louisiana Energy Services)

Eunice, NM active 07003103AREVA Enrichment Services, LLC Eagle Rock Enrichment Facilities Idaho Falls, IDlicense issued,*

construction not started 07007015 Laser Separation Enrichment Facility GE-Hitachi Global Laser Enrichment, LLC Wilmington, NClicense issued, construction not started 07007016 Uranium Hexauoride Deconversion FacilityInternational Isotopes, Inc.

Hobbs, NM (Lea County)license issued, construction not started 04009086* Operating and producing enriched uranium while undergoing further phases of construction.Note: Data are current as of July 2017; the next printed update will be in August 2018.

128Vendor 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-STCHoltec International 07201008 HI-STAR 100 07201014 HI-STORM 100 07201032 HI-STORM FW 07201040 HI-STORM UMAXEnergySolutions, Inc.

07201007 VSC-24 07201026 Fuel Solutions TM (WSNF-220, -221, -223)

W-150 Storage Cask W-100 Transfer Cask W-21, W-74 CanistersTransnuclear, Inc.

07201005 TN-24 (expired) 07201027 TN-68 07201021 TN-32 07201004 Standardized NUHOMS

-24P, -24PHB, -24PTH, -32PT, -32PTH1, -37PTH, -52B, -61BT, -61BTH, -69BTH 07201029 Standardized Advanced NUHOMS

-24PT1, -24PT4 07201030 NUHOMS HD-32PTH Note: Data are current as of July 2017; the next printed update will be in August 2018. (See latest list on the NRC Web site at https://www.nrc.gov/waste/spent-fuel-storage/designs.html.

)APPENDIX M Dry Spent Fuel Storage Designs:

NRC-Approved for Use by General Licensees 129 Arkansas Nuclear GL Energy Solutions, Inc.

VSC-24 07200013 Entergy Nuclear Holtec International HI-STORM 100 Operations, Inc.

Beaver Valley GL Transnuclear, Inc.

NUHOMS-37PTH 07201043 FirstEnergy Nuclear Operating Company Big Rock Point GL Energy Solutions, Inc.

Fuel Solutions TM 07200043 Entergy Nuclear W74 Operations, Inc. Braidwood GL Holtec International HI-STORM 100 07200073 Exelon Generation Co., LLCBrowns Ferry GL Holtec International HI-STORM 100S 07200052 Tennessee Valley Authority

Brunswick GL Transnuclear, Inc.

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 Transnuclear, Inc.

NUHOMS-24P 07200008 Calvert Cliffs Nuclear NUHOMS-32P Power Plant, Inc.

Catawba GL NAC International, Inc.

NAC-UMS 07200045 Duke Energy Carolinas, LLC Columbia Generating GL Holtec International HI-STORM 100 07200035 Station Energy Northwest Comanche Peak GL Holtec International HI-STORM 100 07200074 Luminant Generation Company, LLC Cook GL Holtec International HI-STORM 07200072 Indiana/Michigan Power Cooper Nuclear Station GL Transnuclear, Inc.

NUHOMS-61BT 07200066 Nebraska Public Power District

Davis-Besse GL Transnuclear, Inc.

NUHOMS-24P 07200014 FirstEnergy Nuclear Operating Company Diablo Canyon SL Holtec International HI-STORM 100 07200026 Paci~c Gas & Electric Co.

Dresden GL Holtec International HI-STAR 100 07200037 Exelon Generation HI-STORM 100 Company, LLC APPENDIX N Dry Cask Spent Fuel Storage Licensees Name License Storage Docket Licensee Type Vendor Model Number 130Duane Arnold GL Transnuclear, Inc.

NUHOMS-61BT 07200032 NextEra Energy Inc. Duane Arnold, LLC Fermi GL Holtec International HI-STORM 100 07200071 DTE Electric Company Fort Calhoun GL Transnuclear, Inc.

NUHOMS-32PT 07200054 Omaha Public Power DistrictFort St. Vrain*

SL FW Energy Modular Vault 07200009 U.S. Department of Energy Applications, Inc.

Dry Store Ginna GL Transnuclear, Inc.

NUHOMS-32PT 07200067 Constellation Energy Grand Gulf GL Holtec International HI-STORM 100S 07200050 Entergy Nuclear Operations, Inc.

H.B. Robinson SL Transnuclear, Inc.

NUHOMS-7P 07200003 Carolina Power &

GL Transnuclear, Inc.

NUHOMS-24P 07200060 Light Company Haddam Neck GL NAC International, Inc.

NAC-MPC 07200039 CT Yankee Atomic Power Hatch GL Holtec International HI-STAR 100 07200036 Southern Nuclear HI-STAR 100 Operating, Inc.

Hope Creek/Salem GL Holtec International HI-STORM 100 07200048 PSEG Nuclear, LLC

Humboldt Bay SL Holtec International HI-STORM 100HB 07200027 Paci~c Gas & Electric Co.

Idaho National Lab SL Transnuclear, Inc.

NUHOMS-12T 07200020 TMI-2 Fuel Debris, U.S. Department of Energy Idaho Spent Fuel Facility SL Foster Wheeler Concrete Vault 07200025 Environmental Corp.

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. Joseph M. Farley GL Transnuclear, Inc.

NUHOMS-32PT 07200042 Southern Nuclear Operating Co.

Kewaunee GL Transnuclear, Inc.

NUHOMS-39PT 07200064 Dominion Energy Kewaunee, Inc. La Salle GL Holtec International HI-STORM100 07200070 Exelon Generation Co., LLC APPENDIX N Dry Cask Spent Fuel Storage Licensees (continued)

Name License Storage Docket Licensee Type Vendor Model Number 131Lacrosse GL NAC International, Inc.

NAC-MPC 07200046 Dairyland Power Limerick GL Transnuclear, Inc.

NUHOMS-61BT 07200065 Exelon Generation Co., LLC

Maine Yankee GL NAC International, Inc.

NAC-UMS 07200030 Maine Yankee Atomic Power Company McGuire GL Transnuclear, Inc.

TN-32 07200038 Duke Energy, LLC Millstone GL Transnuclear, Inc.

NUHOMS-32PT 07200047 Dominion Generation

Monticello GL Transnuclear, Inc.

NUHOMS-61BT 07200058 Northern States Power NUHOMS-61BTH Co., Minnesota

Nine Mile Point GL Transnuclear, Inc.

NUHOMS-61BT 07201036 Constellation Energy

North Anna GL Transnuclear, Inc.

NUHOMSHD32PTH 07200056 Virginia Dominion Generation SL Transnuclear, Inc.

TN-32 07200016 Oconee SL Transnuclear, Inc.

NUHOMS-24P 07200004 Duke Energy Company GL Transnuclear, Inc.

NUHOMS-24P 07200040Oyster Creek GL Transnuclear, Inc.

NUHOMS-61BT 07200015 AmerGen Energy Company, LLC Palisades GL EnergySolutions, Inc.

VSC-24 07200007 Entergy Nuclear NUHOMS-32PT Operations, Inc.

Palo Verde GL NAC International, Inc.

NAC-UMS 07200044 Arizona Public Service Co. Peach Bottom GL Transnuclear, Inc.

TN-68 07200029 Exelon Generation Co., LLC Perry GL Holtec International HI-STORM 07200069 FirstEnergy Pilgrim GL Holtec International HI-STORM 100 07201044 Entergy Nuclear Operations, Inc.

Point Beach GL EnergySolutions, Inc.

VSC-24 07200005 FLP Energy NUHOMS-32PT Point Beach, LLC Prairie Island SL Transnuclear, Inc.

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 APPENDIX N Dry Cask Spent Fuel Storage Licensees (continued)

Name License Storage Docket Licensee Type Vendor Model Number 132 APPENDIX N Dry Cask Spent Fuel Storage Licensees (continued)

Name License Storage Docket Licensee Type Vendor Model Number Rancho Seco SL Transnuclear, Inc.

NUHOMS-24P 07200011 Sacramento Municipal Utility District River Bend GL Holtec International HI-STORM 100S 07200049 Entergy Nuclear Operations, Inc.

Salem GL Holtec International HI-STORM 07200048 PSEG Nuclear San Onofre GL Transnuclear, Inc.

NUHOMS-24PT 07200041 Southern California Edison Co.

Seabrook GL Transnuclear, Inc.

NUHOMS-HD-32PTH 07200061 FPL Energy

Sequoyah GL Holtec International HI-STORM 100 07200034 Tennessee Valley Authority

St. Lucie GL Transnuclear, Inc.

NUHOMS-HD-32PTH 07200061 Florida Power & Light Co.

Summer GL Holtec International HI-STORM FW 07201038 South Carolina Electric & Gas Surry SL Transnuclear, Inc.

NUHOMSHD 07200002 Virginia Dominion Generation GL NUHOMSHD-32PTH 07200055 Susquehanna GL Transnuclear, Inc.

NUHOMS-52B 07200028 Susquehanna Nuclear, LLC NUHOMS-61BT NUHOMS-61BTHTrojan SL Holtec International HI-STORM 100 07200017 Portland General Electric Corp.

Turkey Point ISFSI GL Transnuclear, Inc.

NUHOMS-HD-32PTH 07200062 Florida Power & Light Co.

Vermont Yankee GL Holtec International HI-STORM 100 07200059 Entergy Nuclear Operations, Inc.

Vogtle GL Holtec International HI-STORM 100S 07201039 Southern CompanyWaterford 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 AuthorityYankee Rowe GL NAC International, Inc.

NAC-MPC 07200031 Yankee Atomic Electric Zion GL NAC International, Inc.

Magnastor 07201037 Zion Solutions, LLC* Fort St. Vrain is undergoing decommissioning and was transferred to DOE on June 4, 1999.Notes: NRC-abbreviated unit names. Data are current as of July 2017, and the next printed update will be in August 2018.

License Types: SL = site-speci~c license, GL = general license 133 Appalachian CompactDelaware Maryland Pennsylvania West Virginia Atlantic Compact

Connecticut New Jersey South Carolina*

Central Compact

Arkansas Kansas Louisiana Oklahoma Central Midwest Compact

Illinois Kentucky Midwest Compact Indiana Iowa Minnesota Missouri Ohio Wisconsin Northwest Compact Alaska Hawaii Idaho Montana Oregon Utah* Washington*

Wyoming Rocky Mountain Compact Colorado Nevada New Mexico (Northwest accepts Rocky Mountain waste as agreed between compacts.)

Southeast Compact

Alabama Florida Georgia Mississippi Tennessee VirginiaSouthwestern Compact

Arizona California North Dakota South Dakota Texas Compact Texas* Vermont Unaf~liated District of Columbia Maine Massachusetts Michigan Nebraska New Hampshire New York North Carolina Puerto Rico Rhode IslandBeatty, NV, closed 1993 Shef~eld, IL, closed 1978 Maxey Flats, KY, closed 1977 West Valley, NY, closed 1975 APPENDIX OU.S. Low-Level Radioactive Waste Disposal Compact Membership Closed Low-Level Radioactive Waste Disposal Facility Sites Licensed by the NRC or Agreement States* Site of an active low-level waste disposal facility.Note: Data are current as of July 2017; the next printed update will be in August 2018.

134 Company Location Alameda Naval Air Station Alameda, CABWX Technology, Inc., Shallow Land Disposal Area Vandergrift, PABeltsville Agricultural Research Center Beltsville, MDCimarron Environmental Response Trust Cimarron, OKDepartment of Army, Jefferson Proving Ground Madison, INDepartment of Army, Picatinny Arsenal (ARDEC)

Picatinny, NJ FMRI, Inc. (Fansteel)

Muskogee, OKHunter's Point Naval Shipyard San Francisco, CAMcClellan Air Force Base Sacramento, CA Sigma Aldrich Maryland Heights, MOUNC Naval Products New Haven, CTWest Valley Demonstration Project West Valley, NYWestinghouse Electric Corporation-Hematite Festus, MONotes: Data are current as of July 2017. The next printed update will be in August 2018. Beltsville Agricultural Research Center, U.S. Department of Army, Picatinny Arsenal, and UNC Naval Products are managed by the NRC's Region I of~ce.

APPENDIX P NRC-Regulated Complex Materials Sites Undergoing Decommissioning, 2016

• NRC-regulated complex materials sites (13) 135 APPENDIX Q Nuclear Power Units by Nation Under Construction In Operation or on Order Gross MW Gross MW Nuclear Power Number Electrical Number Electrical Country Production GWh*

of Units Capacity of Units Capacity ShutdownArgentina 7,677 3 1,700 1 29 0 Armenia 2,195 1 408 0 0 1 P Belarus 0 0 0 2 2,218 0 Belgium 41,283 7 6,207 0 0 1 P Brazil 15,864 2 1,990 1 1,350 0 Bulgaria 15,775 2 2,000 0 0 4 P Canada 97,445 19 14,512 0 0 6 P China 210,519 37 34,744 20 23,360 0 Czech Republic 22,730 6 4,160 0 0 0 Finland 22,282 4 2,872 1 1,720 0 France 384,000 58 63,130 1 1,650 12 P Germany 80,070 8 11,357 0 0 28 P Hungary 15,179 4 2,000 0 0 0 India 35,000 22 6,780 5 3,300 0 Iran 5,924 1 1,000 0 0 0 Italy 0 0 0 0 0 4 P Japan 17,453 42 41,482 2 2,756 17 P & 1 L Kazakhstan 0 0 0 0 0 1 PKorea, Republic of 154,253 25 24,181 3 4,200 0 Lithuania 0 0 0 0 0 2 P Mexico 10,272 2 1,615 0 0 0 Netherlands 3,752 1 515 0 0 1 P Pakistan 5,094 4 1,090 3 2,540 0 Romania 10,368 2 1,411 0 0 0 Russia 179,724 35 27,909 7 5,937 6 P Slovakia 13,733 4 1,950 2 992 3 P Slovenia 5,931 1 727 0 0 0 South Africa 15,209 2 1,940 0 0 0 Spain 56,078 7 7,416 0 0 2 P & 1 L Sweden 60,647 10 10,147 0 0 3 P Switzerland 20,303 5 3,485 0 0 1 P 136 Ukraine 80,950 15 13,835 2 2,178 4 P United Arab Emirates 0 0 0 4 5,600 0 United Kingdom 65,149 15 10,362 0 0 30 P United States 805,327 99 105,403 4 5,000 34 P Overview of Worldwide Nuclear Power Reactors-As of May 10, 2017 Nuclear Electricity Supplied (GWh) 2,476,217Net Installed Capacity (MWe) 392,116 Nuclear Power Reactors in Operation 449Nuclear Power Reactors in Long-Term Shutdown 2 Nuclear Power Reactors in Permanent Shutdown 160 Nuclear Power Reactors under Construction 60

• Annual electrical power production for 2016.

P = Permanent Shutdown L = Long-Term Shutdown Notes: Totals include reactors that are operable, under construction, or on order; the country's short-form name is used; and the ~gures are rounded to the nearest whole number. Sources: IAEA Power Reactor Information System Database; analysis compiled by the NRC. For more information go to www.iaea.org/pris/. Data are current as of May 2017; the next printed update will be in August 2018.

APPENDIX Q Nuclear Power Units by Nation (continued)

Under Construction In Operation or on Order Gross MW Gross MW Nuclear Power Number Electrical Number Electrical Country Production GWh*

of Units Capacity of Units Capacity Shutdown In Operation Number Reactor Type of Units Net MWePressurized light-water reactors (PWR) 290 273,856Boiling light-water reactors (BWR) 78 75,323Heavy-water reactors, all types (HWR, PHWR) 49 24,629Light-water-cooled graphite-moderated reactor (LWGR) 15 10,219Gas-cooled reactors, all types (GCR) 14 7,720Liquid-metal-cooled fast breeder reactors (FBR) 3 1,369Total 449 379,261 Note: MWe values rounded to the nearest whole number.Source: IAEA Power Reactor Information System Database, www.iaea.org Compiled by the NRC from IAEA data. Data are current as of April 2015. The next printed update will be in August 2018.

APPENDIX RNuclear Power Units by Reactor Type, Worldwide 137 APPENDIX SNative American Reservations and Trust Lands within a 50-Mile Radius of a Nuclear Power Plant* Tribe is located within the 10-mile emergency preparedness zone of operating reactors.

Notes: 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 or Hawaii. For more information on other Tribal concerns, go to the NRC Web site at https://www.nrc.gov.

NRC-abbreviated reactor names listed. Data are current as of August 2017, and the next printed update will be August 2018.

• 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 or Hawaii. For more information on other Tribal concerns, go to the NRC Web site at www.nrc.gov.

NRC-abbreviated reactor names listed. Data as of August 2017, and the next printed update will be be August 2019.

ARIZONA Palo Verde Ak-Chin Indian Community Tohono O'odham Trust Land Gila River Reservation CONNECTICUT Millstone Mohegan Reservation Mashantucket Pequot Reservation Narragansett Reservation Shinnecock Indian NationFLORIDA St. Lucie Brighton Reservation (Seminole Tribes of Florida)

Fort Pierce Reservation Turkey Point Hollywood Reservation (Seminole Tribes of Florida)

Miccosukee Reservation Miccosukee Trust LandIOWA Duane Arnold Sac & Fox Trust Land Sac & Fox ReservationKANSAS Iowa Reservation Iowa Trust LandLOUISIANA River Bend Tunica-Biloxi ReservationMASSACHUSETTS Pilgrim Wampanoag Tribe of Gay Head (Aquinnah)

Trust LandMICHIGAN Palisades Pottawatomi Reservation Matchebenashshewish Band Pokagon Reservation Pokagon Trust Land*

DC Cook Pokagon Reservation Pokagon Trust LandMINNESOTA Monticello Shakopee Community Shakopee Trust Land Mille Lacs Reservation Prairie Island Prairie Island Community*

Prairie Island Trust Land*

Shakopee Community Shakopee Trust LandNEBRASKA Cooper Sac & Fox Trust Land Sac & Fox Reservation Iowa Reservation Iowa Trust Land KickapooNEW YORK FitzPatrick Onondaga Reservation Oneida Reservation Nine Mile Point Onondaga Reservation Oneida ReservationNORTH CAROLINA McGuire Catawba ReservationSOUTH CAROLINA Catawba Catawba Reservation Oconee Eastern Cherokee Reservation Summer Catawba Reservation VIRGINIA Surry Pamunkey ReservationWASHINGTON Columbia Yakama Reservation Yakama Trust Land WISCONSIN Point Beach Oneida Trust Land Oneida ReservationFor the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets/.

138 APPENDIX TStates with Integrated University Grants Program Recipients in FY 2016 Notes: The 2009 Omnibus Appropriations Act authorized the Integrated University Program (IUP) for 10 years for a total of $45 million per year: $15 million each to the U.S. Nuclear Regulatory Commission (NRC), the U.S. Department of Energy, and the National Nuclear Security Administration. The IUP provides grants to academic institutions to support education in nuclear science and engineering to develop a workforce capable of supporting the design, construction, operation, and regulation of nuclear facilities and the safe

handling of nuclear materials. To date, the NRC has awarded 423 IUP grants, including 127 faculty development, 101 scholarship, 119 fellowship, and 76 trade school and community college scholarship grants. More than 100 faculty and 3,200students have received support. The NRC has invested approximately

$9.6 million in its trade school and community college scholarship program to support the development of trade and craft workers in the nuclear industry.

Recipient of Integrated University Grants 139 Action #NameType Issue DateEnforcement Action EA-15-184 Megan, LLC Materials 1/25/16 NOV/CP SL III-$3,500 EA-15-170Wolf Creek Nuclear Operating Corp.

(Wolf Creek 1 )

Reactor 1/27/16Problem SL III EA-15-205Ferrovial Agroman, S.A.

Materials 2/1/16 NOV SL III EA-15-190Whitworth-Muench, Inc.

Materials 2/2/16 NOV SL III IA-15-074Brian F. Quinn Individual 2/8/16 NOV SL III IA-16-010 Erik Simpson Individual 2/16/16 NOV SL III EA-15-221Materials Testing Consultants, Inc.

Materials 2/19/16 NOV SL III EA-15-188Paci~c Soils Engineering & Testing Materials 3/10/16 NOV SL III EA-15-100Entergy Operations, Inc. (Waterford 3 )

Reactor 4/6/162 Con~rmatory Orders result of an ADR mediation EA-15-247Entergy Nuclear Generation Company (Pilgrim 1 )

Reactor 4/11/16Problem SL III EA-15-212C&D Technologies, Inc.

Reactor 4/20/16Con~rmatory Order result of an

ADR mediation EA-15-258Team Industrial Services, Inc.

Materials 4/20/16 NOV SL III EA-15-251Siouxland Urology Center, LLC Materials 4/21/16 NOV SL III EA-16-035Weaver Consultants Group Materials 5/10/16 NOV SL III EA-15-213 Novelis Corporation Materials 5/13/16 NOV/CP SL III-$7,000 IA 15-079 Stephen Mick Individual 5/13/16 NOV SL III EA-15-039Entergy Nuclear Operations, Inc. (Palisades )

Reactor 5/16/16Con~rmatory Order result of an

ADR mediation EA-16-054 FMC & Associates, LLC Materials 5/17/16Problem SL III EA-16-031Wayne County Well Surveys, Inc.

Materials 5/19/16 NOV SL III EA-16-078Curtis-Wright Corporation Materials 5/20/16 NOV SL III IA-15-053Terry LaBue Individual 5/25/16 NOV SL III IA-15-052 Kristen Smith Individual 5/31/16 NOV SL III EA-16-045 Thielsch Engineering, Inc.

Materials 6/1/16Problem SL III EA-15-165 Montana State University Materials 6/24/16 NOV SL III IA-16-018 Curtis Hofer Individual 6/24/16 NOV SL III EA-14-080 CAMPCO, Inc.

Materials 6/26/16Con~rmatory Order result of an

ADR mediation EA-16-098 7NT Enterprises Materials 7/1/16 NOV SL III EA-16-057Exelon Generation Co., LLC (Oyster Creek )

Reactor 7/6/16NOV White SDP ~nding resulting in plant inspections EA-15-173 ACUREN USA Materials 7/7/16Problem/CP SL III-$7,000 IA-16-025Troy Morehead Individual 7/11/16Con~rmatory Order result of an ADR mediation IA-16-026 Kyle Dickerson Individual 7/11/16Con~rmatory Order result of an ADR mediation EA-16-075Patriot Engineering and Environment Materials 7/12/16 NOV/CP SL III-$3,500 EA-16-109MEDSTAR Washington Hospital Center Materials 7/19/16 NOV SL III EA-16-074 QHG of Indiana, Inc.

Materials 7/23/16 NOV SL III EA-16-046Applied Technical Services, Inc.

Materials 7/28/16Problem/CP SL III-$7,000 IA-15-081Justin Hubbard Individual 7/28/16 NOV SL III IA-16-040Martin Ferenc Individual 7/28/16 NOV SL III APPENDIX USigni~cant Enforcement Actions Issued, 2016 Signi~cant (escalated) enforcement actions include notices of violation (NOVs) for severity level (SL)

I, II, or III violations; NOVs associated with inspection ~ndings that the signi~cance 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.

140 APPENDIX USigni~cant Enforcement Actions Issued, 2016 (continued)

EA-16-016AREVA NP, Inc.

Materials 8/4/16Con~rmatory Order result of an ADR mediation EA-16-100 City of Muskegon Materials 8/8/16 NOV SL III EA-16-022FirstEnergy Nuclear Operating Co.

(Davis-Besse )

Reactor 9/1/16Con~rmatory Order result of

an ADR mediation IA-16-039Franklin D. Hayden, Jr.

Individual 9/1/16Problem SL III EA-16-115Consumers Energy Materials 9/14/16 NOV SL III EA-16-128 R.E. Ginna Nuclear Power Plant, LLC Reactor 9/20/16 NOV White SDP ~nding resulting in plant inspections EA-16-135Ontonagon County Road Commission Materials 9/26/16 NOV SL III EA-16-140Ideker, Inc.

Materials 9/27/16 NOV SL III EA-16-010CB&I AREVA MOX Services Fuel Facility 9/28/16 NOV SL III EA-16-097Jenbo USA, LLC Materials 9/29/16NOV SL III; Problem SL III EA-16-051Power Resources, Inc.

Materials 9/30/16Con~rmatory Order result of an ADR mediation IA-16-043Kevin Brainard Individual 9/30/16 NOV SL III EA-16-163Southern Nuclear Operating Co., Inc. (Hatch)

Reactor 10/3/16Con~rmatory Order result of an

ADR mediation EA-16-099Florida Power & Light Co. (Turkey Point 3, Turkey Point 4 )

Reactor 10/10/16 NOV SL III EA-16-136Southern Nuclear Operating Co., Inc.

(Hatch 1 )

Reactor 10/19/16 NOV SL III EA-16-154 CQM, Inc.Materials 11/14/16 NOV SL III EA-16-064Tennessee Valley Authority (Browns Ferry)

Reactor 11/28/16 NOV/CP SL III-$140,000 EA-16-172Hartford Quality Assurance Materials 12/2/16 NOV SL III EA-16-153Lehigh Cement Company, LLC Materials 12/7/16 NOV SL III EA-16-175Northern States Power Company (Monticello)

Reactor 12/12/16NOV White SDP ~nding resulting in plant inspections EA-16-138EMSI Engineering, Inc.

Materials 12/15/16 NOV/CP SL III-$14,000 EA-16-179 Romeo RIM Materials 12/15/16Problem SL III EA-16-168 Paci~c Gas & Electric Co.

(Diablo Canyon 2 )

Reactor 12/28/16 NOV White SDP ~nding resulting in plant inspections EA-13-190 Plus, LLC Materials 5/3/2016 8/8/2016 3 NOV/CP SL III Order Imposing Civil Penalty

of $21,000 EA-15-230Tetra Tech EC, Inc.

Materials 7/28/2016

10/11/2016 NOV/CP SL III-$7,000 Con~rmatory Order result of

an ADR mediation EA-16-055International Cyclotron, Inc.

Materials8/30/2016 11/17/2016NOV/CP SL III-$14,000 Order Imposing Civil Penalty of

$14,000Notes: Reactor facilities in a decommissioning status are listed as materials licensees. The NRC report on Issued Signi~cant Enforcement Actions can be found on the NRC Web site at https://www.nrc.gov/about-nrc/regulatory/enforcement/current.html.

141 APPENDIX VLaws 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. West Valley Demonstration Project Act of 1980 (Pub. L.96-368)

7. 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) 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 Nonproliferation

1. Nuclear Non-Proliferation Act of 1978 Fundamental Laws Governing the Processes of Regulatory Agencies

1. Administrative Procedure Act (5 U.S.C. Chapters 5 through 8)

2. National Environmental Policy Act 142 APPENDIX WInternational 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 (U.S.) is a party to the Treaty

2. Treaty for the Prohibition of Nuclear Weapons in Latin America (Tlatelolco Treaty), entry into force for each government individually, the United States is a party to the speci~c protocols appended to the Treaty

3. Three to four other treaties specifying nuclear weapons-free zones in Africa, the South Paci~c (Rarotonga), and Southeast Asia, including one being negotiated on the Middle East; the United States is only bound by speci~c protocols

4. Convention on Early Noti~cation of a Nuclear Accident, entry into force October 27, 1986; the United States is a party

5. Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, entry into force February 26, 1987; the U.S. is a party

6. Convention on Nuclear Safety, entry into force October 24, 1996; the U.S.

is a party

7. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, entry into force June 18, 2001, the U.S. is a party

8. Convention on the Physical Protection of Nuclear Material (CPPNM), entry into force February 8, 1987; the U.S. is a party

9. Amendment to the CPPNM, entry into force May 8, 2016; the U.S. is a party

10. Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, entry into force August 30, 1975; the U.S. 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 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)

11. Convention on Supplementary Compensation for Nuclear Damage

12. Agreement between the United States of America and the Agency for the Application of Safeguards in the United States of America (INFCIRC/288), entry into force December 9, 1980

13. Model Protocol Additional to the Agreement Between State(s) 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; U.S. is a party

14. Protocol Additional to the Agreement between the United States of America and the 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 July 2017; the next printed update will be in August 2018.

143 APPENDIX XInternational Activities: LIST OF THE NRC'S PARTICIPATION WITH MULTILATERAL ORGANIZATIONSInternational Commission on Radiological ProtectionInternational Atomic Energy Agency (IAEA)Commission on Safety Standards (CSS)

Emergency Preparedness and Response Standards Committee (EPReSC)Nuclear Safety Standards Committee (NUSSC)

Nuclear Security Guidance Committee (NSGC)

Radiation Safety Standards Committee (RASSC)

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) specialized agency 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 Radiation Protection and Public Health (CRPPH)

The Nuclear Law Committee (NLC)

Multinational Design Evaluation Programme (MDEP)Source: https://www.oecd-nea.org/general/about/committee.htmlUnited Nations Scienti~c Committee on the Effects of Atomic Radiation (UNSCEAR)

UNSCEAR reports to the United Nations General Assembly. It assesses global levels and effects of ionizing radiation and provides a scienti~c basis for radiation protection.Source: http://www.unscear.org/

144BILATERAL INFORMATION EXCHANGE AND COOPERATION AGREEMENTS WITH THE NRCNotes: The country's short-form name is used. The NRC's technical arrangements are initiated and renewed for 5-year terms.Data are current as of July 2017; the next printed update will be in August 2018.EURATOM is the European Atomic Energy Community.Tecro (Taiwan) is the Taipei Economic and Cultural Representative Of~ce in the United States.

Argentina Armenia Australia Belgium Brazil Bulgaria Canada China Croatia Czech Republic

Finland France Germany Greece Hungary India Indonesia

Israel Italy Japan Jordan Kazakhstan Lithuania

Mexico Netherlands

Philippines

Poland Romania Slovakia Slovenia South Africa South Korea

Spain Sweden Switzerland Tecro (Taiwan)

Thailand Turkey United Arab Emirates

Ukraine United Kingdom Vietnam EURATOMAgreement Country APPENDIX XInternational Activities: (continued) 145 APPENDIX YInternational Activities:LIST OF IMPORT AND EXPORT LICENSES ISSUED FOR 2016 License Number Applicant Docket Number PXB114.04 Baker Hughes Oil~eld Operations 11006026 PXB139.03Schlumberger Technology 11006027 PXB14b.06Source Production & Equipment Co., Inc.

11006034 PXB169.02 Baker Hughes Oil~eld Operations 11006064 PXB17b.10 Industrial Nuclear Company 11006012 PXB208.01Halliburton Energy Services, Inc.

11006226 PXB209.00 Karmanos Cancer Center 11006232 PXB210.00Halliburton Energy Services, Inc.

11006245 PXB212.00University of Kentucky, Radiation Safety Of~ce 11006250 PXB3.08Nordion (Canada), Inc.

11006070 PXB6.20 Alpha Omega Services 11006027 PXB6.21 Alpha Omega Services 11006027 License Number Applicant Docket Number IW016/03Eastern Technologies, Inc.

11006602 IW017/03EnergySolutions 11005621 IW033 Perma-Fix Northwest Richland, Inc. (PFNW) 11006229 XB1329/03 Rapiscan Systems, Inc.

11005838 XCOM1209/01Enrichment Technology US, Inc.

11006127 XCOM1228/01 Flowserve US, Inc.

11005934 XCOM1255/01Westinghouse Electric Company, LLC 11006060 XCOM1274Holtec International 11006128 XCOM1295Technetics Group Columbia 11006208 XCOM1296Technetics Group Columbia 11006209 XCOM1297NDA Technologies Incorporated 11006196 XCOM1298Westinghouse Electric Company, LLC 11006217 XCOM1299ATI Specialty Alloys and Components 11006218 XCOM1300Mirion Technologies (IST) Corporation 11006221 XCOM1301 Materion Brush, Inc.

11006222 XCOM1302Harper International Corp.

11006223 XCOM1303 Materion Brush, Inc.

11006227 XCOM1305 Materion Brush, Inc.

11006242Appendix P licenses 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 or import, use, resale, and import or export back to the supplier for recycling. These combined licenses are no longer appropriate and can no longer be amended going forward, given the authorization for imports of Appendix P materials under a general license (see 10 CFR 110.27, "General License for Import"). These combined import/export licenses needing amendment are converted to export-only licenses. The 2010 changes to 10 CFR Part 110 generally necessitate speci~c licenses for only Appendix P, Category 1 and 2 exports.LIST OF IMPORT AND EXPORT LICENSES: NON-APPENDIX P 146 XCOM1307 Materion Brush, Inc.

11006247XMAT415/02Linde Electronics and Specialty Gases, a Division of Linde Gas North America, LLC 11005907XMAT418/02 Sigma-Aldrich Co., LLC 11005977XMAT419/02 Cambridge Isotope Laboratories, Inc.

11005993XMAT419/02-R Cambridge Isotope Laboratories, Inc.

11005993XMAT424Graftech International Holdings, Inc.

11006032XMAT436 Cambridge Isotope Laboratories, Inc.

11006225XMAT437Linde Electronics and Specialty Gases, a Division of Linde Gas North America, LLC 11006238 XR178Westinghouse Electric Company, LLC 11006216 XSNM3643/02 TN Americas, LLC 11005864 XSNM3722/01AREVA, Inc.

11006109 XSNM3747/02AREVA, Inc.

11006110 XSNM3754 Thermo Fisher Scienti~c 11006166 XSNM3757U.S. Department of Energy-National Nuclear Security Administration 11006187 XSNM3763/01Edlow International Co.

11006195 XSNM3766Edlow International Co.

11006219 XSNM3767Louisiana Energy Services, LLC 11006224 XSNM3767-RLouisiana Energy Services, LLC 11006224 XSNM3768Edlow International Co.

11006228 XSNM3770Edlow International Co.

11006234 XSNM3770-REdlow International Co.

11006234 XSNM3773 Global Nuclear Fuel-Americas, LLC 11006237 XSOU8780/07AREVA Nuclear Materials, LLC 11005211 XSOU8798/06 RSB Logistic Services, Inc.

11005445 XSOU8826/01Honeywell International, Inc.

11005938 XSOU8840Iluka Resources, Inc.

11006220 XW010/03 Duratek Services, Inc.

11005620 XW016/02Eastern Technologies, Inc.

11005825 XW022 Perma-Fix Northwest Richland, Inc. (PFNW) 11006230 License Number Applicant Docket Number Non-Appendix P Components Guide (XSNM) denotes export of special nuclear material (plutonium, uranium-233, or uranium enriched above 0.711 percent, by weight, in the isotope uranium-235).(XCOM) denotes export of minor reactor components or other nuclear facility (e.g., nuclear fabrication) components under NRC jurisdiction (refer to Title 10 CFR Part 110, "Export and Import of Nuclear Equipment and Material", Appendix A, Items (5)-(9), for minor reactor components and Appendices B-K and N-O for other nuclear facility

components).(XSOU) denotes export of source material (natural or depleted uranium; thorium; a mixture of uranium and thorium other than special nuclear material; or certain ores [e.g., tantalum and niobium that contain, by weight, 0.05 percent or more of the aforementioned materials for nonnuclear end use]).(XB) denotes export of byproduct material, 10 CFR Part 110, Appendix L, for an illustrative list of byproduct materials under NRC jurisdiction.(XR) denotes export of reactor facilities, 10 CFR Part 110, Appendix A, items (1)-(4).(IW) denotes import of radioactive waste.

(XW) denotes export of radioactive waste.

APPENDIX YInternational Activities: (continued)LIST OF IMPORT AND EXPORT LICENSES: NON-APPENDIX P (continued) 147

149Source Surface Gauge Detectors Radiation Depth Bioshield Figure 31. Moisture Density Guage 150Reactors that differ from today's 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 today's 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.The energy that is released through a nuclear reaction or radioactive decay process. One kind of nuclear reaction is ~ssion, 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.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 per year.

NEUTRON NUCLEUS FRAGMENT NEW NEUTRON NUCLEUS Nuclear Reaction 151How Nuclear Reactors WorkIn a typical design concept of a commercial BWR, the following proce ss occurs:

1. The nuclear fuel core inside the reactor vessel creates heat from nuclea r fission.

2. A steam-water mixture is produced when very pure water (reactor coolant) moves upward through the core, absor bing 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 reactor's 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 electric power. BWRs contain between 370-800 fuel a ssemblies.

Control RodsTurbineGenerator SteamlineReactor VesselCoreSeparators

& DryersFeedwater Condenser Heater Condensate PumpsDemineralizerEmergency Water Supply SystemsRecirculation Pumps Feed Pumps Containment Cooling System 4 5 3 1, 2 ContainmentStructure Typical Boiling-Water Reactor Source: U.S. Nuclear Regulatory CommissionWalls made of concrete and steel

3-5 feet thick (1-1.5 meters)A nuclear reactor in which water is boiled using heat released from ~ssion. 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 ~ssion in the reactor core.

152A 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 iridiu m-1 92 or iodin e-125, which are regulated by the NRC and Agreeme nt States.As de~ned by NRC regulations, byproduct material includes any radioactive material (except enriched uranium or plutonium) produced by a nuclear reactor, through the use of a particle accelerator, or any discrete source of radiu m-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, 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 Unit ed States.CanisterSee Dry cas k storage.

The maximum load that a generating unit, generating station, or other electrical apparatus can carry under speci~ed conditions for a given period of time without exceeding approved limits of temperature and stress.The amount of electric power that a generator, turbine transformer, transmission, circuit, or system is able to produce, as rated by the manufacturer.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 ti me period.A percentage that a generating unit ful~lled its capacity in generating electric power over a given time period. This percentage is de~ned as the margin between the unit's 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 multiplyi ng by 100.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, and/or steel. Casks must meet regulatory requirements.

153The categories for radiation sources are de~ned by the International Atomic Energy Agency's Code of Conduct on the Safety and Security of Radioactive Sources. This helps ensure that suf~cient controls are being used to achieve safety and security. Only Categories 1 and 2 for radiation sources are de~ned by NRC requirements. The

~ve categories are a s follows:* 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.

• 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 possibly-although it is unlikely-be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in ~xed industrial gauges such as level gauges, dredger gauges, conveyor gauges, spinning pipe gauges, and well loggi ng 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 ~xed or portable gauges, static eliminators, or low dose brachytherapy.

• Category 5 sources cannot cause permanent injury. They are used in X-ray uorescence devices and electron captur e devices.The NRC categorizes 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 signi~cance." The three categories are a s follows:

• Category I, high strategic si gnificance

• Category II, moderate strategic s igni~cance* Category III, low strategic si gnificanceThe NRC's 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.

154Information that has been determined pursuant to an executive order to require protection against unauthorized disclosure and is marked to indicate its classi~ed status when in documentary form. The NRC has two types of classi~ed information. The ~rst type, known as national security information, is information that is classi~ed 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 of~ci al duties.An NRC-issued license that authorizes a licensee to construct and (with certain speci~ed conditions) operate a nuclear power facility, such as a nuclear plant at a

spec ific site.A facility that uses high doses of radiation to sterilize or treat products, such as food and spices, medical supplies, and wood ooring. Irradiation can be used to eliminate harmful bacteria, germs, 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., cobal t-60), an x-ray machine, or an electron beam.A group of two or more U.S. States that have formed alliances to dispose of low-level radioactive waste (LLW).The maximum number of years that could be added to a nuclear power plant's license expiration date to recapture the period between the date the NRC issued the plant's construction permit and the date it granted an operating license. A licensee must submit an application to request this extension.

Figure 34.

Commercial IrradiatorSource: U.S. Nuclear Regulatory Commission Radiation Shield Control Console Storage Pool RadiationSource Irradiation Room Loading Conveyor System UnloadingProcessedProductPhoto courtesy: Nordion 155A resilient gas-tight shell or other enclosure around a nuclear reactor to con~ne ~ssion 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.ContaminationUndesirable 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.The condition involving ~ssion of nuclear materials when the number of neutrons produced equals or exceeds the nuclear containment. During normal reactor operations, nuclear fuel sustains a ~ssion chain reaction or criticality. A reactor achieves criticality (and is said to be critical) when each ~ssion event releases a suf~cient number of neutrons to sustain an ongoing series of reactions.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 ENTOMB an d SAFSTOR.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 unrestr icted use.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, ~ltering 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.An approach to designing and operating nuclear facilities that prevents and mitigates accidents that release 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.

156Uranium with a percentage of uraniu m-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 rea ctor fuel.A description of the type, composition, and capabilities of an adversary that a security system is designed to protect against. 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.Certi~cation and approval by the NRC of a standard nuclear power plant design independent of a speci~c site or an application to construct or operate a plant. A design certi~cation is valid for 15 years from the date of issuance but can be renewed for an additional 10 to 15 years.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) from all radiation sources, a level that has not been shown to cause humans any harm. Of this total, natural background sources of radiation-including radon and thoron gas, natural radiation from soil and rocks, radiation from space, and radiation sources that are found naturally within the human body-account 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.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.

157A permit granted by the NRC to approve one or more proposed sites for a nuclear power facility, independent of a speci~c 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.A 4,500-megawatt thermal nuclear reactor design, which has passive safety features and uses natural circulation (with no recirculation pumps or associated piping) for normal operation. The NRC certi~ed the ESBWR standard design submitted by GE-Hitachi Nuclear Energy on October 15, 2014.The percentage of the total energy content of a power plant's thermal energy that is converted into electricity. The remaining energy is lost to the environmen t as heat.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.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 are not considered electric utilities.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 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 who operate certain nuclear facilities, such as nuclear power plants, must develop and maintain EP plans that meet NRC requirements.The agency within the U.S. Department of Energy that provides policy-neutral statistical data, forecasts, and analyses to promote sound policymaking, ef~cient markets, and public understanding regarding energy and its interaction with the economy and the environment.

158 See Uranium e nrichment.A method of decommissioning a nuclear power plant in which radioactive contaminants are encased in a structurally long-lived material, such as concrete. The entombed structure is maintained and surveillance is continued until the radioactive waste decays to a level that permits termination of the license and unrestricted release of the property.An automated system used by the NRC to document incoming noti~cations of signi~cant nuclear events with an actual or potential effect on the health and safety of the public and the environment. Signi~cant events are reported to the NRC by licensees, Agreement States, other Federal agencies, the public, and other countries.Absorption of ionizing radiation or the amount of a hazardous substance that has been ingested, inhaled, or contacted 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 Occupati onal dose.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 m itigation.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 lique~ed 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, competiti ve market.

159The 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 2017 runs from October 1, 2016, through September 30, 2017.Fissile materialA nuclide that is capable of undergoing ~ssion after capturing neutrons. Although sometimes used as a synonym for ~ssionable material, this term has acquired its more restrictive interpretation with the limitation that the nuclide must be ~ssionable by thermal neutrons. With that interpretation, the three primary ~ssile materials are

uraniu m-2 33, uraniu m-2 35, and plutoniu m-239. This de~nition excludes natural uranium and depleted uranium that have not been irradiated or have only been irradiated in thermal reactors.FissionThe 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 ~ssion, 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.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.An on-the-job training program sponsored by the NRC for assignees from other countries, usually under bilateral information exchange arrangements with their respective regulatory organizations. The assignees' regulatory authorities generally identify the individuals participating and pay their salaries.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 b usinesses.A structured group of fuel rods (long, slender, metal tubes containing pellets of ~ssionable 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.

160The 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 hexa uo ride (UF 6)* enrichment to increase the concentration of uran ium in UF 6* fuel fabrication to convert enriched UF 6 into fuel for nuclear reactors* use of the fuel in reactors (nuclear power research or naval propulsion)

• interim storage of spent nu clear fuel

• reprocessing of spent fuel to recover the ~ssionable material remaining in the spent fuel (currently not done in the Unit ed States)

• ~nal disposition disposal of high-level radioac tive waste

• transportation of the uranium in all forms, including spent fuelThe NRC regulates these processes, as well as the fabrication of mixed-oxide (MOX) nuclear fuel, which is a combination of uranium and plutoni um oxides.The processing of reactor fuel to separate the unused ~ssionable 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, the U.S. Department of Energy operates reprocessing facilities at Hanford, WA, and Savannah River, SC, for national defense purposes.A long, slender, zirconium metal tube containing pellets of ~ssionable material, which provide fuel for nuclear reactors. Fuel rods are assembled into bundles called fuel assemblies, which are loaded individually into the reactor core.A human resources measurement equal to one person working full time for 1 year.Uranium enrichment technology that uses many rotating cylinders that are connected in long lines to increase the concentration of uraniu m-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.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 ~nely divided solid that may be coated with a liquid ~lm. Gas chromatography devices are used to analyze air pollutants, blood alcohol content, essential oils, and food products.

161A uranium enrichment process used to increase the concentration of uraniu m-235 in uranium for use in fuel for nuclear reactors by separating its isotopes (as gases) based on their slight difference in mass. (Lighter isotopes diffuse faster through a porous membrane or vessel than do heavier isotopes.) This process involves ~ltering UF 6 gas to separate uraniu m-2 34 and uraniu m-235 from uraniu m-238, increasing the percentage of ura niu m-235.

In May 2013, the last remaining gaseous diffusion plant in operation in the United States 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 b y the NRC.Devices used to measure, monitor, and control the thickness of sheet metal, textiles, paper napkins, newspaper, plastics, photographic ~lm, and other products as they are manufactured. Gauges mounted in ~xed locations are designed for measuring or controlling material density, ow, 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 ~eld locations. These gauges contain a gamma-emitting sealed source, usually cesiu m-137, or a sealed neutron source, usually americiu m-2 41 and beryllium.

The total amount of electric energy produced by a power generating station, as measured at the generator terminals.Source Surface Gauge Detectors Radiation Depth Bioshield Figure 31. Moisture Density GuageMoisture Density Gauge Fixed Fluid GaugeGaseous Diffusion Process Enriched Stream Depleted Stream Low Pressure Low Pressure High-Pressure Feed Source: U.S. Nuclear Regulatory Commission Detector Shutter Control Material Flow Shielding Source Shutter Pipe Figure 35.

Cross-Section of Fixed Fluid Gauge 162The gross amount of electric energy produced by a generating station, minus the amount used to operate the station. Net generation is usually measured in w att-hours.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.An excavated, underground facility that is designed, constructed, and operated for safe and secure permanent disposal of high-level radioactive waste (HLW). A geological repository uses an engineered barrier system and a portion of the site's natural geology, hydrology, and geochemical systems to isolate the radioactivity of the waste.A unit of power equivalent to one billion (1,000,000,0

00) watts.One billion (1,000,000,000) w att-hours. See Electric p ower grid.The time required for half the atoms of a particular radioactive material to decay. A speci~c 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.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 environmental hazards to permit the safe use of technologies that produce ionizing radiation.A method for extracting uranium from ore. 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. 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 y ellowcake.

Figure 36. The Heap Leach Uranium Recovery Process Heap Dried Yellow-cake Acid Recirculation Liner System Collection

Basin Processing Plant PROCESSING PLANTExtractedConcentrated StrippedDrying Acid Drip Slope 163The 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 ~ssion 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 isolationUranium enriched to at least 20 percent uraniu m-235 (a higher concentration than exists in natural uranium ore).A common method currently used to extract uranium from ore bodies without physical excavation of the ore. ISR is also known as "solution mining" or in

situ leaching.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.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.A United Nations agency established in 1957 to serve as a world center of cooperation in the nuclear ~eld. The agency works with nearly 170 member States and multiple partners worldwide to promote safe, secure, and peaceful nuclear

technology.An association established in January 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, Japan, the Republic of South Korea, Spain, Sweden, the United Kingdom, and the United States ar e members.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.

164Two or more forms (or atomic con~gurations) 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, carbo n-12, carbo n-1 3, and carbo n-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 con~guration. For example, carbo n-1 2 and carbo n-13 are stable, but carbo n-1 4 is unstable and ra dioactive.A unit of power equivalent to 1, 000 watts.Source material, byproduct material, or special nuclear material that is received, possessed, used, transferred, or disposed of under a general or speci~c license issued by the NRC or Agreement States and is not otherwise exempt from r egulation.A company, organization, institution, or other entity to which the NRC or an Agreement State has granted a general or speci~c license to construct or operate a nuclear facility, or to receive, possess, use, transfer, or dispose of source, byproduct, or special nuclear material.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.A term used to describe reactors using ordinary water as a moderated coolant, including boiling-water reactors and pressurized-water reactors (PWRs), the most

common types used in the Unit ed States.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, ~lters, and reactor water treatment residues; equipment and tools; medical tubes, swabs, and hypodermic syringes; and carcasses and tissues from laborator y animals.

165A potential accident in which a breach in a reactor's pressure boundary causes the coolant water to rush out of the reactor faster than makeup water can be added back in. Without suf~cient coolant, the reactor core could heat up and potentially melt the zirconium fuel cladding, causing a major release of radioactivity.A unit of power equivalent to 1,000, 000 watts.A unit equals 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 />.About 2,2 00 pounds.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 uraniu m-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 con stituents.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 before it is irradiated in a reactor. Using plutonium reduces the amount of enriched uranium needed to produce a controlled reaction in commercial light-water reactors. However, plutonium exists only in trace amounts in nature and, therefore, must be produced by neutron irradiation of uraniu m-238 or obtained from other manufactured sources. As directed by Congress, the NRC regulates the fabrication of MOX fuel by DOE, a program that is intended to dispose of plutonium from excess nuclea r weapons.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.The guiding principles, roles, and structures that enable all domestic incident response partners to prepare for and provide a uni~ed 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 framework, which became effective March 22, 2008, builds upon the National Incident Management System, which provides a template for managing incidents.

166A 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.Uranium containing the relative concentrations of isotopes found in nature: 0.7 percent uraniu m-235, 99.3 percent uraniu m-238, and a trace amount of uraniu m-234 by mass. In terms of radioactivity, however, natural uranium contains about 2.2 percent uraniu m-235, 48.6 percent uraniu m-238, and 49.2 percent

uraniu m-234. Natural uranium can be used as fuel in nuclear reactors or as feedstock for uranium enrichment f acilities.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 otherw ise noted.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 ~eld of science, including physics, chemistry, biology, medicine, geology, archeology, and ecology.The primary center of communication and coordination among the NRC, its licensees, State and Tribal agencies, and other Federal agencies regarding 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 a ctivities.See Atomic energy.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 scienti~c, technological, and legal bases for safe, environmentally friendly, and economical use of nuclear energy for peaceful purposes. The NEA's current membership consists of 31 countries in Europe, North America, and the Asia-Paci~c region, which account for about 86 percent of the world's installed nuclear capacity.

167Fissionable material that has been enriched to a composition that will support a self-sustaining ~ssion 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.See Special nuclear material, Source material, and Byproduct material.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.In reactor physics, a substance (other than ~ssionable 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 ~ssion 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.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. e lectrical power.An annex to the National Response Framework, which provides for a timely, coordinated response by Federal agencies to nuclear or radiological accidents or incidents within the United States. This annex covers radiological dispersal devices and improvised nuclear devices, as well as accidents involving commercial reactors or weapons production facilities, lost radioactive sources, transportation accidents involving radioactive material, and foreign accidents involving nuclear or

radioactive material.

168The heart of a nuclear power plant or nonpower reactor, in which nuclear ~ssion 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 ~ssionable material as fuel, a moderator (such as water) to increase the likelihood of ~ssion (unless reactor operation relies on fast neutrons), a reector to conserve escaping neutrons, coolant provisions for heat removal, instruments for monitoring and controlling reactor operation, and protective devices (such as control rods and s hielding).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.

Speci~cally, 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.)The internal and external dose 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.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. The primary goal of OECD and its member countries is to support sustainable economic growth, boost employment, raise living standards, maintain ~nancial stability, assist other countries' economic development, and contribute to growth in world trade. In addition, OECD is a reliable source of comparable statistics and economic and social data. OECD also monitors trends, analyzes and forecasts economic developments, and researches social changes and evolving patterns in trade, environment, agriculture, technology, taxation, and other areas.

169Sealed 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 c onditions:

• 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 th e materialThe period during which a generating unit, transmission line, or other facility is out of service. Outages may be forced or scheduled and full o r partial.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 identi~cation of the problem, if there had been a strong commercial desire to do so. In particular, the following problems may result in force d outages:

• any failure of mechanical, fuel handling, or electrical equipment or controls within the generator's ownership or direct responsibility (i.e., from the point the generator is responsible for the fuel through to the electrical connect ion point)

• a failure of a mine or fuel transport system dedicated to that power station with a resulting fuel shortage that cannot be economical ly managed

• inadvertent or operator error

• limitations caused by fu el qualityForced outages do not include scheduled outages for inspection, maintenance, or refueling.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 fail ed starts.

170The 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.A thimble-sized ceramic cylinder (about 3/8-inch in diameter and 5/8-inch in length), consisting of uranium (typically uranium oxide), which has been enriched to increase the concentration of uraniu m-2 35 (U-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 a ssemblies.A regulatory approach that focuses on desired, measurable outcomes, rather than prescriptive processes, techniques, or procedures. Performance-based regulation leads to de~ned results without speci~c direction regarding 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.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 plant's pe rformance.A license, issued by the NRC, that authorizes the licensee to possess speci~c nuclear material but does not authorize its use or the operation of a nuclear facility.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 plant's operating license and technical speci~cations. 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 con~guration. When all requisite conditions are ful~lled, the NRC may grant the power uprate by amending the plant's operating license and technical speci fications.

171A common nuclear power reactor design in which very pure water is heated to a very high temperature by ~ssion, 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 nuclear reactor power plants in the United States are PWRs.

Typical Pressurized-Water ReactorWalls made of concrete and

steel 3-5 feet thick (1-1.5 meters)

SteamlineCore Containment Cooling SystemTurbineGenerator Condenser Heater Condensate

PumpsDemineralizer Reactor Coolant PumpsPressurizerEmergency Water

Supply Systems Steam Generator Reactor Vessel Control Rods Coolant Loop Feed Pumps 4 Containment Structure Source: U.S. Nuclear Regulatory Commission 3 2 1How Nuclear Reactors WorkIn a typical design concept of a commercial PWR, the following process occ urs: 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 reactor's 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, alsoneed electric power. PWRs contain between 120-200 fuel assemblies.

172A systematic method for assessing three questions that the NRC uses to de~ne "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-signi~cant 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 po wer plant.Production expense is one component of the cost of generating electric power, which includes costs associated with fuel, as well as plant operation and ma intenance.One of the two units used to measure the amount of radiation absorbed by an object or person, known as the "absorbed dose," which reects 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 t o 100 rad.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 bene~cial 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.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 atom's 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.

173All 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.A radioactive material or byproduct that is speci~cally 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 manmade capsule, sealed between layers of nonradioactive material, or ~rmly bonded to a nonradioactive substrate to prevent radiation leakage. Other radiation sources include devices such as accelerators and x-ray g enerators.Exposure limits; permissible concentrations; rules for safe handling; and regulations regarding receipt, possession, use, transportation, storage, disposal, and industrial control of radioactive material.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 healt hy tissue.An of~cially 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.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.

174The 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 suf~cient quantity of the same radionuclide is present, depends on the half-life of the radionuclide. Some radionuclides (e.g., hydroge n-3, also known as "tritium") decay to stable daughters that are not radioactive. However, other radionuclides (e.g., uraniu m-238) decay to radioactive daughters (e.g., thoriu m-234) and may be part of a radioactive decay chain consisting of two or more radionuclides linked in a cascading series of

radioactive decay.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 p er second.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 ~lm that has been placed behind the material, and the differences in blackening suggest aws and unevenness in the material.An unstable isotope of an element that decays or disintegrates spontaneously, thereby emitting radiation. About 5,000 natural and arti~cial radioisotopes have been

i dentified.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 s hort time.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 ~ssion ta kes place.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 ~ndings and performance indicators to assess each plant's safety pe rformance.

175The process of removing older fuel and loading new fuel. These actions are all performed underwater in order to provide continuous cooling for the fuel and provide shielding from the radioactive s pent fuel.Reactor Building (Containment)Fuel BuildingRefueling BayFuel Transfer CanalRefueling BridgeRefueling BridgeReactor Building CraneRefueling BridgeFuel Storage PoolFuel Inspection StandSpent Fuel Storage RacksSpent Fuel Storage RacksRefueling CavitySteam Dryer and Separator Storage PoolNew Fuel Storage RacksFuel Transfer TubeReactor CoreReactor VesselReactor VesselContainment VesselTorusPWR Refueling SummaryBWR Refueling SummaryPWR Refueling Summary:As new fuel shipping canisters arrive in the fuel building, the reactor building crane (not shown) lifts them to the fuel inspection stand, where the fuel is removed from the canister and inspected for defects. Fuel in the new fuel storage area is moved into the fuel pool prior to refueling activities. The fuel can then be stored in either the new fuel storage racks (which are dry), or in the refueling pool, depending upon the needs of the site. Fuel in the new fuel storage area is moved into the fuel pool prior to refueling activities. To refuel the reactor, the vessel head is removed, the fuel transfer canals and transfer tube areas are ~ooded, 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.BWR Refueling Summary:As new fuel shipping canisters arrive in the reactor building, the reactor building crane lifts them to the refueling ~oor, where the fuel is removed from the canister and inspected for defects. The fuel can then be stored in either the new fuel storage area (which is dry), or in the refueling pool, depending upon the needs of the site. Fuel in the new fuel storage area is moved into the fuel pool prior to refueling activities. To refuel the reactor, the containment vessel lid and the reactor vessel head are removed, the refueling cavity above the reactor vessel is ~ooded, and the gates between the reactor cavity 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 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.

Spent Fuel Storage PoolPWR refuelingAs new fuel shipping canisters arrive in the fuel building, the reactor building crane (not shown) lifts them to the fuel inspection stand, where the fuel is removed from the canister and inspected for defects. Fuel in the new fuel storage area is moved into the fuel pool before refueling begins. The fuel can then be stored in either the new fuel storage racks (which are dry) or in the refueling pool, depending upon the needs of the site. Fuel in the new fuel storage area is moved into the fuel pool before refueling begins. To refuel the reactor, the vessel head is removed, the fuel transfer canals and transfer tube areas are ooded, 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.BWR refuelingAs new fuel shipping canisters arrive in the reactor building, the reactor building crane lifts them to the refueling oor, where the fuel is removed from the canister and inspected for defects. The fuel can then be stored in either the new fuel storage area (which is dry) or in the refueling pool, depending upon the needs of the site. Fuel in the new fuel storage area is moved into the fuel pool before refueling begins. To refuel the reactor, the containment vessel lid and the reactor vessel head are removed, the refueling cavity above the reactor vessel is ooded, and the gates between the reactor cavity 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 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.Reactor Building (Containment)Fuel BuildingRefueling BayFuel Transfer CanalRefueling BridgeRefueling BridgeReactor Building CraneRefueling BridgeFuel Storage PoolFuel Inspection StandSpent Fuel Storage RacksSpent Fuel Storage RacksRefueling CavitySteam Dryer and Separator Storage PoolNew Fuel Storage RacksFuel Transfer TubeReactor CoreReactor VesselReactor VesselContainment VesselTorusPWR Refueling SummaryBWR Refueling SummaryPWR Refueling Summary:As new fuel shipping canisters arrive in the fuel building, the reactor building crane (not shown) lifts them to the fuel inspection stand, where the fuel is removed from the canister and inspected for defects. Fuel in the new fuel storage area is moved into the fuel pool prior to refueling activities. The fuel can then be stored in either the new fuel storage racks (which are dry), or in the refueling pool, depending upon the needs of the site. Fuel in the new fuel storage area is moved into the fuel pool prior to refueling activities. To refuel the reactor, the vessel head is removed, the fuel transfer canals and transfer tube areas are ~ooded, 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.BWR Refueling Summary:As new fuel shipping canisters arrive in the reactor building, the reactor building crane lifts them to the refueling ~oor, where the fuel is removed from the canister and inspected for defects. The fuel can then be stored in either the new fuel storage area (which is dry), or in the refueling pool, depending upon the needs of the site. Fuel in the new fuel storage area is moved into the fuel pool prior to refueling activities. To refuel the reactor, the containment vessel lid and the reactor vessel head are removed, the refueling cavity above the reactor vessel is ~ooded, and the gates between the reactor cavity 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 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.

Spent Fuel Storage Pool 176The governmental function of controlling or directing economic entities through the process of rulemaking and adj udication.An annual NRC conference that brings together NRC staff, regulated utilities, materials users, and other interested stakeholders to discuss nuclear safety topics and signi~cant and timely regulatory activities through informal dialogue to ensure an open regulatory process.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.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 ef~ciency) tec hnologies.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-signi~cant scenarios.An approach to regulatory decisionmaking that considers only the results of a probabilistic risk a ssessment.An approach to regulatory decisionmaking in which insights from probabilistic risk assessment are considered with other engineering insights.

177An approach to regulation taken by the NRC that incorporates an assessment of safety signi~cance 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.The term referring to a facility's 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 signi~ca nce level.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) equipment and security forces. As used by the IAEA, this term also means verifying that the peaceful use commitments made in binding nonproliferation agreements, both bilateral and multilateral, are honored.A special category of sensitive unclassi~ed 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.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.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 signi~cance criterion.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 low-level waste requiring disposal.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 "react or trip").

178Information 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.A decrease in the rate of ~ssion (and heat or energy production) in a reactor (usually by the insertion of control rods into the core).Small reactors that use water to cool the reactor core in the same way as today's 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 today's large designs that can generate 1,000 MWe or more per reactor. The NRC's discussions to date with SMR designers involve modules generating less than 200 MWe.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.Plutonium, uraniu m-2 33, or uranium enriched in the isotopes uraniu m-233 or ur aniu m-2 35.An underwater storage and cooling facility for spent (depleted) fuel assemblies that have been removed from a reactor.Nuclear reactor fuel that has been used to the extent that it can no longer effectively sustain a chain reaction.The condition of a nuclear reactor system in which nuclear fuel no longer sustains a ~ssion chain reaction (i.e., the reaction fails to initiate its own repetition, as it would in a reactor's normal operating condition). A reactor becomes subcritical when its ~ssion events fail to release a suf~cient number of neutrons to sustain an ongoing series of reactions, possibly as a result of increased neutron leakage o r poisons.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 cobal t-60) projected from outside the body, it is often called "external beam radiotherapy."

179Code of Federal Regulations 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.A change in the reactor coolant system temperature, pressure, or both, attributed to a change in the reactor's 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 c onditions.Material contaminated with transuranic elements-arti

~cially made radioactive elements, such as neptunium, plutonium, americium, and others-that 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 nuclea r weapons.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 1 2.5 years.See Pow er uprate.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 uraniu m-235 and uraniu m-2 38. Uraniu m-235 is composed of 0.7 percent natural uranium and is ~ssile.

Uraniu m-238 is composed of 99.3 percent natural uranium, is ~ssionable by fast neutrons, and is fertile.

This means that it becomes ~ssile after absorbing one neutron. Natural uranium also includes a minute amount of ur aniu m-2 34.A piece of natural uranium ore 180The process of increasing the percentage of uraniu m-2 35 (U-235) from 0.7 percent in natural uranium to about 3 to 5 percent for use in fuel for nuclear reactors. Enrichment can be done through gaseous diffusion, gas centrifuges, or laser isotope s eparation.

Figure 39. Enrichment ProcessesA. Gaseous Diffusion ProcessB. Gas Centrifuge Process Enriched Stream Depleted Stream Low Pressure Low Pressure High-Pressure Feed UF 6 Feed Fraction Enriched in U-235 Fraction Depleted in U-235 Casing Rotor Electric Motor Source: U.S. Nuclear Regulatory CommissionGas 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 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. A facility that converts enriched UF 6 into fuel for commercial light-water power reactors, research and test reactors, and other nuclear reactors. The UF 6, in solid form in containers, is heated to a gaseous form and then chemically processed to form uranium dioxide (UO

2) 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 pe llet form.A facility that receives natural uranium in the form of ore concentrate (known as yellowcake) and converts it into UF 6, in preparation for fabricating fuel for nuclear reactors.

181The Federal agency established by Congress to advance the national, economic, and energy security of the United States, among other missions.The Federal agency responsible for leading the uni~ed 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 Secre t Service.The Federal agency responsible for protecting human health and safeguarding the environment. EPA leads the Nation's environmental science, research, education, and assessment efforts to ensure that attempts to reduce environmental risk are based on the best available scienti~c information. EPA also ensures that environmental protection is an integral consideration in U.S. p olicies.Viability assessmentA decisionmaking process used by DOE to assess the prospects for safe and secure permanent disposal of high-level waste in an excavated, underground facility known as a geologic repository. This decisionmaking process is based on (1) speci~c 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.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 waste, Low-level waste, and Spent nuc lear fuel.Classi~cation 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 U.S. 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.A unit of power (in the International System of Units) de~ned 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).

183 184Web Link IndexNRC: An Independent Regulatory AgencyMission, Goals, and Statutory Authority Strategic Plan (NUREG-1614)https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1614/

Statutory Authorityhttps://www.nrc.gov/about-nrc/governing-laws.html Major Activities Public Involvement https://www.nrc.gov/public-involve.htmlFreedom 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/

Rulemaking Actions https://www.regulations.govSigni~cant Enforcement Actionshttps://www.nrc.gov/reading-rm/doc-collections/enforcement/actions/Organizations and Functions Organization Charthttps://www.nrc.gov/about-nrc/organization/nrcorg.pdf The Commissionhttps://www.nrc.gov/about-nrc/organization/commfuncdesc.htmlCommission Direction-Setting and Policymaking Activities https://www.nrc.gov/about-nrc/policymaking.html NRC Regionshttps://www.nrc.gov/about-nrc/locations.html NRC BudgetPerformance Budget: Fiscal Year 2017 (NUREG-1100) https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1100/U.S. and Worldwide Nuclear EnergyU.S. Electricity U.S. Energy Information AdministrationOf~cial Energy Statistics from the U.S. Government https://www.eia.govWorldwide Electricity Generated by Commercial Nuclear PowerInternational Atomic Energy Agency (IAEA) https://www.iaea.org IAEA Power Reactor Information System (PRIS) https://www.iaea.org/pris/

185 Nuclear Energy Agency (NEA) https://www.oecd-nea.orgWorld Nuclear Association (WNA) http://www.world-nuclear.orgWorld Nuclear Power Reactors and Uranium Requirements http://www.world-nuclear.org/info/reactors.html WNA Reactor Databasehttp://www.world-nuclear.org/nucleardatabase/default.aspxNRC Of~ce of International Programs https://www.nrc.gov/about-nrc/organization/oipfuncdesc.htmlNRC Regulatory Information Conference (RIC) https://www.nrc.gov/public-involve/conference-symposia/ric/index.htmlInternational Activities Treaties and Conventionshttps://www.nrc.gov/about-nrc/ip/treaties-conventions.htmlCode of Conduct on the Safety and Security of Radioactive Sources http://www-ns.iaea.org/tech-areas/radiation-safety/code-of-conduct.asp Radiation Sources Regulatory Partnership http://rsrp-online.orgInternational Regulatory Development Partnership http://irdp-online.orgOperating Nuclear ReactorsU.S. Commercial Nuclear Power ReactorsCommercial Reactors https://www.nrc.gov/info-~nder/reactors/Oversight of U.S. Commercial Nuclear Power ReactorsReactor Oversight Process (ROP) https://www.nrc.gov/reactors/operating/oversight.htmlNUREG/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 Formhttps://www.nrc.gov/reactors/operating/oversight/contactus.htmlNew Reactors New Reactor Licensing https://www.nrc.gov/reactors/new-reactors.html 186Reactor License RenewalReactor License Renewal Process https://www.nrc.gov/reactors/operating/licensing/renewal/process.html10 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.htmlU.S. Nuclear Research and Test ReactorsResearch and Test Reactors https://www.nrc.gov/reactors/non-power.htmlNuclear Regulatory ResearchNuclear Reactor Safety Researchhttps://www.nrc.gov/about-nrc/regulatory/research/reactor-rsch.html State-of-the-Art Reactor Consequence Analyses (SOARCA) https://www.nrc.gov/about-nrc/regulatory/research/soar.html Risk Assessment in Regulationhttps://www.nrc.gov/about-nrc/regulatory/risk-informed.htmlDigital Instrumentation and Controls https://www.nrc.gov/about-nrc/regulatory/research/digital.html Computer Codeshttps://www.nrc.gov/about-nrc/regulatory/research/safetycodes.html Generic Issues Programhttps://www.nrc.gov/about-nrc/regulatory/gen-issues.htmlThe Committee To Review Generic Requirements https://www.nrc.gov/about-nrc/regulatory/crgr.htmlProbabilistic Flood Hazard Assessmenthttps://www.nrc.gov/public-involve/public-meetings/meeting-archives/

research-wkshps.html Cancer Studyhttps://www.nrc.gov/reading-rm/doc-collections/fact-sheets/bg-analys-cancer-risk-study.htmlNUREG-1925, Revision 3, "Research Activities"https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1925/r3/Nuclear MaterialsAgreement States Of~ce of Nuclear Material Safety and Safeguards State Communication Portal https://scp.nrc.govU.S. Fuel Cycle Facilities U.S. Fuel Cycle Facilitieshttps://www.nrc.gov/materials/fuel-cycle-fac.html 187Uranium Recovery Uranium Milling/Recovery https://www.nrc.gov/info-~nder/materials/uranium/U.S. Materials Licenses Materials Licensees Toolkits https://www.nrc.gov/materials/miau/mat-toolkits.html Domestic Licensing of Special Nuclear Material (10 CFR-Part 70)https://www.nrc.gov/reading-rm/doc-collections/cfr/part070/Medical Applications and Others Medical Applications and Others https://www.nrc.gov/materials/medical.htmlMedical Uses Medical Uses https://www.nrc.gov/materials/miau/med-use.htmlNuclear Gauges and Commercial Product Irradiators General License Uses https://www.nrc.gov/materials/miau/general-use.htmlIndustrial Uses of Nuclear Materials Industrial Applications https://www.nrc.gov/materials/miau/industrial.htmlExempt Consumer Product Uses https://www.nrc.gov/materials/miau/consumer-pdts.htmlRadioactive WasteU.S. Low-Level Radioactive Waste DisposalLow-Level Radioactive Waste https://www.nrc.gov/waste/low-level-waste.htmlU.S. High-Level Radioactive Waste Management:

Disposal and StorageHigh-Level Radioactive Waste https://www.nrc.gov/waste/high-level-waste.htmlSpent Nuclear Fuel Storage Spent Nuclear Fuel Storage https://www.nrc.gov/waste/spent-fuel-storage.htmlU.S. Nuclear Materials TransportationNuclear Materials Transportation https://www.nrc.gov/materials/transportation.htmlDecommissioning Decommissioninghttps://www.nrc.gov/waste/decommissioning.htmlStatus of the Decommissioning Program: 2016 Annual Reporthttps://www.nrc.gov/docs/ML1628/ML16285A207.pdf 188Nuclear Security and Emergency Preparedness Nuclear SecurityNuclear Security Nuclear Security https://www.nrc.gov/security.htmlDomestic SafeguardsDomestic Safeguards https://www.nrc.gov/security/domestic.htmlInformation Security Information Security https://www.nrc.gov/security/info-security.htmlRadioactive Material Security Radioactive Material Securityhttps://www.nrc.gov/security/byproduct.htmlEmergency Preparedness and Response Emergency Preparedness and Response https://www.nrc.gov/about-nrc/emerg-preparedness.htmlResearch and Test Reactors Security https://www.nrc.gov/reactors/non-power.htmlEmergency Preparedness Stakeholder Meetings and Workshops https://www.nrc.gov/public-involve/public-meetings/stakeholder-mtngs-wksps.html Emergency Action Level Developmenthttps://www.nrc.gov/about-nrc/emerg-preparedness/about-emerg-preparedness/emerg-action-level-dev.htmlHostile-Action-Based Emergency Preparedness Drills https://www.nrc.gov/about-nrc/emerg-preparedness/respond-to-emerg/

hostile-action.html NRC Participation Exercise Schedulehttps://www.nrc.gov/about-nrc/emerg-preparedness/about-emerg-

preparedness/exercise-schedules.htmlOther Web LinksDatasetsSpreadsheets of NRC-Regulated Licensee Information https://www.nrc.gov/reading-rm/doc-collections/datasets/Employment Opportunities NRC-A Great Place to Workhttps://www.nrc.gov/about-nrc/employment.htmlGlossaryNRC Basic Referenceshttps://www.nrc.gov/reading-rm/basic-ref/glossary/full-text.htmlGlossary of Energy Terms https://www.eia.gov/tools/glossary/

189Public Involvement NRC Library https://www.nrc.gov/reading-rm.htmlFreedom of Information Act and Privacy Acts 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 Public Document Room https://www.nrc.gov/reading-rm/pdr.html Licensing Support Network Library https://adamspublic.nrc.gov/navigator/

Public Meeting Schedulehttps://www.nrc.gov/pmns/mtg/

Documents for Commenthttps://www.nrc.gov/public-involve/doc-comment.htmlSmall Business and Civil Rights Contracting Opportunities for Small Businesses https://www.nrc.gov/about-nrc/contracting/small-business.htmlWorkplace Diversityhttps://www.nrc.gov/about-nrc/employment/workingatnrc.html Discrimination Complaint Activity 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 Pro~ciencyhttps://www.nrc.gov/about-nrc/civil-rights/limited-english.htmlMinority Serving Institutions Program https://www.nrc.gov/about-nrc/grants.html#msipNRC Comprehensive Diversity Management Plan Brochure https://www.nrc.gov/reading-rm/doc-collections/nuregs/brochures/br0316/Social Media Platforms NRC Bloghttps://public-blog.nrc-gateway.gov/ Twitterhttps://twitter.com/nrcgov/YouTubehttps://www.youtube.com/user/NRCgov/

Flickrhttps://www.ickr.com/photos/nrcgov/

Facebookhttps://www.facebook.com/nrcgov/

GovDeliveryhttps://www.nrc.gov/public-involve/listserver.html#gov RSShttps://www.nrc.gov/public-involve/listserver.html#rss 190 191 BIBLIOGRAPHIC DATA SHEET (See instructions on the reverse)

NRC FORM 335 (9-2004)NRCMD 3.7U.S. NUCLEAR REGULATORY COMMISSION

1. REPORT NUMBER (Assigned by NRC, Add Vol., Supp., Rev., and Addendum Numbers, if any.)

NUREG-1350, Vol. 21

3. DATE REPORT PUBLISHED MONTH August YEAR 2009 4. FIN OR GRANT NUMBER n/a 2. TITLE AND SUBTITLE U.S. Nuclear Regulatory Commission Information Digest 2008-2009 Edition

5. AUTHOR(S)

Ivonne Couret

6. TYPE OF REPORT Annual 7. PERIOD COVERED (Inclusive Dates) 2008 8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor, Public Affairs Staff

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, Same as 8, above p rovide name and mailing address.)

and mailing address.)

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less)

12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.)

Information Digest 2009-2010 Edition

NRC Facts Nuclear Regulatory Commission

14. SECURITY CLASSIFICATION

13. AVAILABILITY STATEMENT unlimited (This Page) unclassified (This Report) unclassified

15. NUMBER OF PAGES 190 16. PRICE NRC FORM 335 (9-2004)PRINTED ON RECYCLED PAPER Office of Public Affairs U.S. Nuclear Regulatory Commission Washington, DC 20555-0001The U.S. Nuclear Regulatory Commission (NRC) 2017-2018 Information Digest provides information about the agency and the industries it regulates. It describes the agency's responsibilities and activities and provides general information on nuclear-related topics. The 2017-2018 Information Digest includes NRC data in the appendices and non-NRC data (i.e., IAEA, EIA, and DOE data) throughout the publication this is updated as of May 2017 with revisions in October, including data associated with maps and graphics. The next Information Digest that will re~ect updated data will be published August 2019. In this edition we discontinued providing Industry Trends information because the program was discontinued. The Digest will remain an annual publication, with certain data being updated every two years.

Readers will be directed to the most current and updated information, which is available online. 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 nal unless otherwise noted. Corrections and updates will appear in the digital version of the publication on the NRC Website. The NRC welcomes comments or suggestions on the Information Digest. To submit comments, write to the Ofce of Public Affairs at U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or email at OPA.Resource@nrc.gov.Ivonne Couret, et al.There may be a supplementary document produced re~ecting specic sections of the document.

2017-2018 2017 December (2-89) NRCM 1102, 3201,3202NUREG-1350, Vol. 29, Rev. 1 2017-2018 Information Digest 2017-2018 Edition

NRC Facts Nuclear Regulatory Commission

10CFR

U.S. Nuclear Regulatory CommissionNUREG-1350, Volume 29, Rev. 1 December 2017