New Reactors Bill Borchardt Director, Office of New Reactors Nuclear Energy Worldwide • There are currently 435 commercial nuclear power reactors operating in 30 countries • Nuclear power provides over 16% of the world's electricity and 34% in the European Union. • 30 more power reactors are under construction, while over 60 are firmly planned 1 Conditions of the mid-1980s did not favor nuclear construction • • • • • • Energy efficiency improvements Economic restructuring Significant drop in electricity demand Excess generating capacity Oil (traded fossil energy) price collapse Electricity market liberalization & privatization • Regulatory interventions after TMI • High Interest rates • Chernobyl 2 Conditions of today are distinctly different from the mid-1980s • • • • • • • Strong energy demand growth Fossil fuels no longer cheap Energy supply security concerns Attractive life cycle costs of nuclear power Pollution control and climate change Excellent operating experience Renewables and efficiency improvements: Low hanging fruit already harvested 3 Human Development Index 1 0.9 0.8 Japan France Germany Australia US Sw eden Canada Finland Norw ay Iceland Argentina Hungary Philip p inesMexico Russia China Bulgaria Turkey 0.7 Egypt 0.6 India Pakistan 0.5 Nigeria 0.4 Mozambiqu 0.3 Niger 0.2 0 5000 10000 15000 kWh/capita 20000 25000 30000 4 Energy Policy Act of 2005 • Authorizes federal risk insurance for the next 6 nuclear plants for delays associated with NRC reviews ($500 M for first 2 plants, $250 M for next 4 plants) • Nuclear energy production tax credits for the first 6,000 megawatts of electricity from new advanced reactors • Authorizes $3 billion in nuclear research and development to support NGNP and NP2010 5 National Programs • NP2010(Nuclear Power 2010): A joint government/industry cost-shared effort to demonstrate key regulatory processes associated with siting and building new nuclear power plants • NGNP (Next Generation Nuclear Plant): A demonstration reactor at Idaho National Laboratory that will serve as a test for advanced reactor technologies and for cogeneration of hydrogen by nuclear energy. • GNEP (Global Nuclear Energy Partnership): A program to develop new proliferation-resistant recycling technologies in order to produce more energy, reduce waste, and minimize proliferation concerns. 6 NRC Mission NRC Mission Statement To regulate the nation's civilian use of byproduct, source, and special nuclear materials to ensure adequate protection of public health and safety, to promote the common defense and security, and to protect the environment. Office of New Reactors The Office of New Reactors serves the public interest by enabling the safe, secure, and environmentally responsible use of nuclear power in meeting the nation's future energy needs 7 Resurgence of Nuclear Power • 29 new plants at 20 sites proposed by the industry • Five different plant designs proposed – AP1000 – Economic Simplified Boiling Water Reactor – Evolutionary Power Reactor – Advanced Boiling Water Reactor – Advanced Pressurized Water Reactor 8 New Reactor Licensing Applications An estimated schedule by Fiscal Year 2005 2006 2007 2008 2009 2010 2011 2012 AP1000 Program Review TVA – Bellefonte (AL) Hearing Progress Energy - Harris (NC) Hearing Duke – Lee Station (SC) Hearing Hearing South Carolina E&G-Summer Progress Energy–Levy County (FL) Hearing Vogtle ESP Hearing Southern – Vogtle (GA) Hearing Design Cert ESBWR Program Review Design Certification North Anna ESP Hearing Dominion - North Anna (VA) Hearing Grand Gulf ESP Hearing Entergy – Grand Gulf (MS) Hearing Hearing Entergy – River Bend (LA) EPR Program Review Design Certification UniStar-Calvert Cliffs (MD) Hearing Hearing AmerenUE - Callaway Hearing Amarillo Power Hearing PPL - Susquehanna Hearing AEH – Bruneau, ID Hearing UniStar-Nine Mile Pt (NY) ABWR Program Review USAPWR Program Review NRG Energy – South Texas Project 2014 * Schedules depicted for future activities represent nominal assumed review durations based on submittal time frames in letters of intent from prospective applicants. Actual schedules will be determined when applications are docketed. Legend: Design Certification Early Site Permit Combined License Hearing Post SER/EIS Hearing (other hearing activities occur during ESP/COL safety and environmental reviews) Hearing DC – Mitsubishi USAPWR TXU Power –Comanche Peak (TX) COL Hearing Hearing DTE – Fermi - Vender TBD Hearing FPL - Site and Vendor TBD Hearing Exelon - Site and Vendor TBD Unspecified Clinton ESP 2013 Hearing 9 8/13/07 Potential New Reactor Applicants ESBWR Dominion Entergy NuStart EPR Amarillo Power Ameren UE PPL Generation UNISTAR US APWR TXU Power AP1000 US ABWR NRG Energy Duke NuStart Progress Energy S.C. Electric & Gas Southern Co. 10 Part 52 Licensing Process • Provide a more predictable licensing process • Resolve safety and environmental issues before authorizing construction • Provide for timely & meaningful public participation • Encourage standardization of nuclear plant designs • Reduce financial risk to nuclear plant licensees 11 Part 52 Licensing Process Pre-Construction Early Site Permit Or Equivalent Siting Information* Optional Pre-Application Review Standard Design Certification Or Equivalent Design information* Post-Construction Combined License Review, Hearing, and Decision* Verification Of Regulations with ITAAC *A combined license application can reference an early site permit, a standard design certification, both, or neither. If an early site permit and/or a standard design certification is not referenced, the applicant must provide an equivalent level of information in the combined license application. December 13, 2005 Reactor Operation Decision Early Site Permits (ESPs) 10 CFR Part 52, Subpart A • An ESP is a license (“partial construction permit”) • Review scope – Site safety – Environmental – Emergency preparedness • Mandatory hearing • Permit good for 10-20 years • Allows applicant to “bank” a site • Two ESPs issued (Clinton and Grand Gulf), 2 under review (North Anna and Vogtle) 13 Standard Design Certifications • Allows an applicant to obtain pre-approval of a standard nuclear plant design through rulemaking • Reduces licensing uncertainty by resolving design issues early in the licensing process • Facilitates standardization • Higher degree of regulatory finality • Certification good for 15 years • 4 designs approved: (C-E System 80+; GE Advanced Boiling Water Reactor (ABWR); Westinghouse AP600; Westinghouse AP1000), • 1 design under review (General Electric ESBWR), • 2 designs in pre-application activities (Areva EPR and 14 the Mitsubishi US APWR). Combined Licenses 10 CFR Part 52, Subpart C • Combined License (COL) = a combined construction permit and operating license with conditions • A COL is the fundamental licensing process in Part 52 for reducing the financial risks for electric companies building nuclear power plants • COL can reference ESP, DCR, both, or neither • Must meet technical standards in Parts 50, 100, etc. • 40 year duration 15 New Construction • Nuclear plants will be built more rapidly than their predecessors • Detailed engineering will be essentially complete by start of construction • Modular construction techniques will be used • Fabrication of components may begin before COL issuance • Components and modules will be fabricated in other countries 16 Security for New Reactors • Commission Policy Statement modified to encourage applicants to consider security early in the design • Staff to perform aircraft impact assessments on new designs • Part 52 to be revised to require applicants to perform aircraft impact assessments • Sharing insights with other countries 17 Digital Instrumentation & Controls • Key Technical Issues: – Cyber security – diversity and defense-in-depth – highly integrated control rooms - human factors – highly integrated control rooms communications – risk-informed digital I&C 18 Multinational Design Evaluation Program • Stage 1 – Trilateral agreement to share information and reviews on EPR design – Finland, France, and U.S. • Stage 2 – 10 countries participating – Exploring opportunities for convergence of safety goals and regulatory practices • Stage 3 – implementation stage 19 Challenges for New Construction • Ability of the grid to support new construction • Large component manufacturing • Workforce / staffing 20 ABWR • Design Certification - May 1997 • 1350 MWe evolutionary design • Vessel mounted internal recirc pumps • Fine motion control rod drives • Digital I&C • 3 full train ECCS 34 30 31 32 26 21 25 27 29 33 24 23 28 4 5 1 20 22 11 13 3 10 2 17 7 8 12 19 6 9 18 14 15 16 1 Reactor Pressure Vessel 2 Reactor Internal Pumps 3 Fine Motion Control Rod Drives 4 Main Steam Isolation Valves 5 Safety / Relief Valves 6 SRV Quenchers 7 Lower Drywell Equipment Platform 8 Horizontal Vents 9 Suppression Pool 10 Lower Drywell Flooder 11 Reinforced Concrete Containment Vessel 12 Lower Drywell Equipment Hatch 13 Wetwell Personnel Lock 14 Hydraulic Control Units 15 Control Rod Drive Hydraulic System Pumps 16 RHR Heat Exchanger 17 RHR Pump 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 HPCF Pump RCIC Steam Turbine and Pump Diesel Generator Standby Gas Treatment Filter and Fans Spent Fuel Storage Pool Refueling Platform Shield Blocks Steam Dryer and Separator Storage Pool Bridge Crane Main Steam Lines Feedwater Lines Main Control Room Turbine-Generator Moisture Separator Reheater Combustion Turbine-Generator Air Compressor and Dryers Switchyard 21 System 80+ • Design Certification - May 1997 • 1350 MWe evolutionary design • Complete plant design based on System 80 NSSS and Cherokee/Perkins BOP • Advanced Control Room • Severe accident prevention and mitigation 22 AP600 • Design Certification – December 1999 • 600 MWe advanced reactor design • Digital I&C • Passive Safety Systems – Passive safety injection – Passive residual heat removal – External reactor vessel cooling 23 AP1000 • 1117 MWe • Passive containment cooling system with steel containment vessel and natural circulation air flow • Gravity drain core makeup tanks and refueling water storage tanks • Natural circulation heat exchangers connected to RCS • Design Certification Rule December 2005 24 ESBWR • “Economic and Simplified BWR” • 1390 MWe GE reactor based on Simplified BWR and Advanced BWR • Natural circulation • Passive safety systems • Design Certification Application submitted and staff review underway 25 EPR • 1600 MWe evolutionary design • Four 100% capacity engineered safety feature trains • Double-walled containment • Corium spreading area for severe accident mitigation • Pre-application review beginning • Design certification application planned for late CY 2007 26