ML18038A981

NUREG-1350, Vol. 29, Rev. 01, Information Digest 2017-2018, Section 3, Nuclear Reactors

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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.