ML18226A120

From kanterella
Jump to navigation Jump to search
NUREG-1350, Vol. 30, Information Digest 2018-2019, Section 3 Reactors
ML18226A120
Person / Time
Issue date: 08/14/2018
From: Couret I L
Office of Public Affairs
To:
Meyd, Donald
Shared Package
ML18226A101 List:
References
NUREG-1350 V30
Download: ML18226A120 (224)
v • d • e


Text

23 24U.S. Electricity Generated by Commercial Nuclear Power In 2017, NRC-licensed nuclear reactors generated 20 percent of U.S. gross electricity, or about 805 billion kilowatt-hours (see Figure 8. U.S. Gross Electric Generation by Energy Source, 2017, and Figure 9. U.S. Electric Share and Generation by Energy Source, 2012-2017).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 the electric power grid.

According to the U.S. Energy Information Administration (EIA), in 2017, each of the following States generated more than 40,000 thousand megawatt-hours of electricity from nuclear power: Illinois, Pennsylvania, South Carolina, Alabama, North Carolina, and New York. Illinois ranked ~rst in the Nation in both generating capacity and net electricity generation from nuclear power.Illinois nuclear power plants accounted for 12 percent of the Nation's nuclear power generation. The 2017 data cited reect the total net generation electricity from nuclear sources in each of these States (see Figure 10. Gross Electricity Generated in Each State by Nuclear Power). As of June 2018, 30 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 A-Z 25Figure 9.

U.S. Electric Share and Generation by Energy Source, 2012-2017Note: Figures are rounded. Source: DOE/EIA, June 22, 2018 , https://www.eia.gov

- Table 7.2A Electricity Net Generation: Total (All Sectors)Year Billions of Kilowatthours Coal Gas*Natural Gas Nuclear Figure 13. U.S. Net Electric Generation by Energy Source, 2002-2011Petroleum 05 06 07 08 09 1 0 1 1 1 2 1 3 1 4 1 5 0 500 1,000 1,500 2,000 0 400 1,200 800 1,600 2,000 percent share net generation (in billions of KWh) 2012 2013 2014 2015 2016 50%40%30%20%10%0%Hydroelectric**

Nuclear Renewable***Non-hydroelectric renewablehydroelectric 2017Figure 8. U.S. Gross Electric Generation by Energy Source, 2017 Renewable 17%Petroleum 0.5%Nuclear 20%Natural Gas 32.1%Coal 30.1%Hydroelectric 7.3%Solar 1.3%Note: Figures are rounded. Source: DOE/EIA, June 22, 2018 , https://www.eia.gov

- Table 7.2A Electricity Net Generation: Total (All Sectors)

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

None 20 States< less than 20,000 16 States 20,001 to 40,000 8 States 40,001 to 60,000 4 States> more than 60,001+2 StatesTotal Nuclear Power Generated (in thousand megawatt-hours)

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 NC Net Electricity Generated in Each State by Nuclear PowerSource: DOE/EIA, "Monthly Nuclear Utility Generation by State and Reactor," Annual December 2017, EIA-923 and EIA-860 Reports, https://www.eia.govNote: *U.S. Territories not pictured. American Samoa, Guam, Northern Mariana Islands, Puerto Rico, U.S. Virgin Islands, and Minor Outlying Islands do not generate nuclear power.

Illinois 97,191 Pennsylvania 83,199S. Carolina 54,344 Alabama 42,651 N. Carolina 42,374New York 42,167 Texas 38,581 New Jersey 34,032 Georgia 33,708 Michigan 32,381 Arizona 32,340 Tennessee 31,817 Virginia 30,533 Florida 29,146 California 17,901 Ohio 17,687 Connecticut 16,499 Louisiana 15,409 Maryland 15,106 Minnesota 13,904 Arkansas 12,691 Kansas 10,647 New Hampshire 9,990Wisconsin 9,648 Washington 8,128 Missouri 8,304 Nebraska 6,912 Mississippi 7,364 Massachusetts 5,047 Iowa 5,213 27houses the 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.

The United States has two types of commercial reactors.

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 designs.

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, 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 T 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 2 2 2 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= 2 units= 1 unit= 3 units 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 2 3 2 2 2 2 3 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3 3 2 2 2 2 2 2 2 2 U.S. Operating Commercial Nuclear Power Reactors 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 WV OH MI PA NY ME V T NH IN GA FL AK HI SC NC MD DC DE NJ RI CT MANote: NRC-abbreviated reactor names listed. Data are as of June 2018. 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 START Have a safe day!3 1 Resident inspectors play a very important role for the NRC. They are the agency's on-the-ground eyes and ears.Inspectors routinely inspect safety systems, discuss safety issues with plant employees, and submit publicly available reports.

As part of their routine, inspectors proceed with inspection activities, observe plant workers, make sure the plant is following NRC rules, and report concerns.The inspector attends the plan-of-the-day meeting with plant of~cials to understand what activities are planned.

As with everyone at the plant, the inspector passes through security checkpoints.Each morning, the inspector visits the reactor's control room, gets information on the plant status, and relays this information to NRC of~ces.An NRC resident inspector is a specially trained expert who lives in the community around the plant.

Each plant has at least two inspectors.Learn 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 (13.7-meter) 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 on 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 V for a list of signi~cant enforcement actions.

31Hardened Vents Order Seismic WalkdownsFlooding Walkdowns Seismic Reevaluations FLEX EquipmentFLEX Offsite EquipmentEmergency Preparedness StaffingEmergency Preparedness CommunicationsFlooding Reevaluations Mitigation Strategies Order Mitigation of Beyond-Design-Basis Events RulemakingSpent Fuel Pool InstrumentationEmergency ProceduresNote: 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 50 years of improvements in nuclear industry performance. The process continues to improve approaches to inspecting and evaluating the safety and security performance of NRC-licensed nuclear plants. More ROP information is available on the NRC's Web site and in NUREG-1649, Revision 6, "Reactor Oversight Process"(see Figure 15.

Reactor Oversight Framework).

33Figure 14. Reactor Oversight Action Matrix Performance IndicatorsFigure 15. Reactor Oversight Framework GREEN WHITE YELLOW RED GREEN WHITE YELLOW REDPerformance Indicators Inspection FindingsINCREASING SAFETY SIGNIFICANCEINCREASING SAFETY SIGNIFICANCE GREEN WHITE YELLOW RED GREEN WHITE YELLOW REDPerformance Indicators Inspection FindingsINCREASING SAFETY SIGNIFICANCEINCREASING SAFETY SIGNIFICANCEProtect Public Health and Safety in the Use of Nuclear PowerReactor Safety Initiating Events Mitigating Systems Barrier IntegrityPublic Radiation SecuritySafety-Conscious Work EnvironmentResolutionHuman PerformanceMissionStrategic Performance AreasCornerstonesCross-Cutting AreasOccupational RadiationEmergency PreparednessRadiation SafetySafeguards 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 2018. 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 (see Figure 18. License Renewal Process).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. Subsequent License Renewal The NRC staff developed guidance and a standard review plan for "subsequent license renewals" that would allow plants to operate for more than 60 years (the 40 years of the original license plus 20 years in the initial license renewal). The Commission determined 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.

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 2 2 2 3 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3 3 3 2= 2 units= 1 unit= 3 units Licensed to Operate (99)

Original License (13) License Renewal Granted (8 6)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 17.

U.S. Commercial Nuclear Power Reactors-Years of Operation by the End of 2018Note: Ages are based on operating license issued date and have been rounded up to the end of the year. For the most recent information, go to the 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.

Data are as of May 2018. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets

/. Figure 21. Years of OperationNote: Ages have been rounded up to the end of the year.Source: U.S. Nuclear Regulatory Commission 1-19 years 20-29 years 30-39 years>40 years 1reactor 7reactors 41reactors 50reactors 36Figure 18. License Renewal ProcessNot applicable to the subsequent license renewal process Opportunities for public interaction If a request for a hearing is grantedAvailable at www.nrc.gov License Renewal Process DECISIONSTARTLore m ipsu Final Supplement to GEIS Issued**

Hearings*Environmental Review 10 CFR Part 51Site Environmental Audit NRC Decision on Application**

Draft Supplemental Environmental Inpact Statement Public Comment/Meeting Draft Supplement to Generic Environmental Impact Statement (GEIS) Issued**

License Renewal Process and Environmental Scoping Meeting License Renewal Application**

ACRS Letter Issued**Advisory Committee on Reactor Safeguards (ACRS) Review Safety Evaluation Report Issued**

Safety Evaluation Audit & Review Inspection Reports Issued**Onsite Inspection(s)

Safety Review 10 CFR Part 54The NRC published the ~nal guidance documents in the summer of 2017. The agency is reviewing an application for subsequent license renewal of the Turkey Point reactors in Florida. The NRC has also received letters of intent for Peach Bottom to apply for subsequent license renewal in 2018, Surry to apply in 2019, and North Anna to apply in 2020.

Public Involvement The public plays an important role in the license renewal process. Members of the public have several opportunities to contribute to the environmental review. The NRC shares information provided by the applicant 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.RTRs 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 RTRs (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) also 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.

LARGEST RESEARCH &

TEST REACTOR SMALLEST COMMERCIAL POWER REACTOR 1,500 Megawatts thermal 20 Megawatts thermalFigure 19. Size Comparison of Commercial and Research ReactorsNote: Nuclear research and test reactors, also known as "nonpower" reactors, do not produce commercial 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 Reactors 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 NCRTRs Licensed/Currently Operating (31)

U.S. Nuclear Research and T est Reactors 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 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 designs.

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. If the Commission ~nds that the acceptance criteria are met, a COL is valid for 40 years. 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.

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 including molten salts, liquid metals, and even gases such as helium.

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 in that a moderator (hydrogen) is chemically bonded to the fuel.

Capacity: These current licensed facilities range in size from 5 watts (less than a night light) to 20 MWt (equivalent to 20 standard medical X-ray machines).

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

Capacity:

These reactors 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 reactors are expected to provide enhanced margins of safety and use simplied, inherent, and passive means to ensure safety. They may not require an operator to shut down.

Fuel: These reactors require enriched uranium.

Fuel: These reactors require enriched uranium.

Fuel: These reactors could use enriched uranium, thorium, or used nuclear fuel.

41Figure 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 ReportSTART DECISION Location of Projected New Nuclear Power ReactorsFermi PSEG (ESP)Turkey Point North Anna Clinch River (ESP)

Shearon Harris*Vogtle William Lee Levy CountyV.C. SummerComanche 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 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, South Carolina Electric & Gas (SCE&G) announced its decision to cease construction on V.C. Summer nuclear power plant, Units 2 and 3; and the licensee has requested that the COLs be withdrawn. As of October 2017, Duke Energy has announced plans to cancel reactors at Levy County, FL, and William States Lee, SC. Applications were withdrawn for Calvert Cliffs, Grand Gulf, Nine Mile Point, Victoria County, and Callaway (COL and ESP). In June 2018, Nuclear Innovation North America submitted a letter requesting that the COLs South Texas Project, Units 3 and 4, be withdrawn. NRC-abbreviated reactor names listed. Data are as of July 2018. For the most recent information, go to the Dataset Index Web page at https://www.nrc.gov/reading-rm/doc-collections/datasets

/.

42Public 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 the agency should consider in its environmental review 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-Hitachi Nuclear Energy's (GEH'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, (US-APWR) and NuScale designs.

43The 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 are cooled by liquid metals, molten salt mixtures, or inert gases. Advanced reactors can also consider fuel materials and designs that differ radically from today's enriched-uranium dioxide pellets with zirconium cladding. While developing the regulatory framework for advanced reactor licensing, the NRC is examining policy issues in areas such as security and emergency preparedness. Small Modular Reactors Small modular reactors (SMRs) use water to cool the reactor core in the same way as 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 (660 MWt).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.The 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).

44New Commercial Nonpower Production and Utilization Facility Licensing Doctors worldwide rely on a steady supply of molybdenum-99 (Mo-99) to produce technetium-99m in hospitals, 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 permits for SHINE in February 2016, and for Northwest Medical Isotopes in May 2018.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.

45Nuclear 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 molten salts. 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, 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 additive manufacturing and accident-tolerant fuel)
  • experience gained from operating reactors
  • digital instrumentation and controls (such as analyzing digital system components, security aspects of digital systems, and probabilistic assessment of digital system performance)
  • earthquake and ooding hazards 46Figure 24. NRC Research Funding, FY 2018 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-$11 MReactor Program-$30 MMaterials and Waste-$1 M Note: Totals may not equal sum of components because of rounding.

Source: U.S. Nuclear Regulatory Commission New/Advanced Reactor Licensing-$11 MReactor Program-$30 MMaterials and Waste-$1 MTotal $42 Million (M)

  • 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 5 percent of the agency's personnel and uses about 11 percent of its contracting funds. The NRC's $42 million research budget for FY 2018 includes contracts with national laboratories, universities, research organizations, and other Federal agencies (e.g., the National Institute of Standards and Technology, the U.S. Army Corps of Engineers, and the U.S. Geological Survey). NRC research funds support access to a broader group of experts and international research facilities. Figure 24. NRC Research Funding, FY 2018, 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.

47The 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. Professor Douglass Henderson of the University of Wisconsin-Madison standing above the pool of the University's TRIGA research reactor.Photo courtesy: University of Wisconsin-Madison See Appendix U for States with Integrated University Grants Program recipients.

Retrieved from "https://kanterella.com/w/index.php?title=ML18226A120&oldid=1028196"