NRC Licensing Process for Review of SMRs

Transcription

1 NRC Licensing Process for Review of SMRs Small Modular Reactors for Nuclear Power LAS/ANS Symposium On Behalf of Commissioner William D. Magwood, IV Commissioner of the U.S. Nuclear Regulatory Commission John E. Kelly Deputy Assistant Secretary for Nuclear Reactor Technologies Office of Nuclear Energy US U.S. Department tof fenergy July 22, 2014

2 Outline NRC licensing process NRC efforts to prepare for SMR applications Policy and technical issues Overview of light water SMR designs Non-light water designs Conclusions 2

3 Licensing Process for Current Fleet (10 CFR Part 50) Construction Permit Application i Construction Permit Construction Begins Operating License Application Operating License Operation Begins Design effort proceeded throughout process Regulatory standards evolved as construction proceeded 3

4 New Licensing Process (10 CFR Part 52) LWA COL Issued 103(g) finding Early Site Permit Standard Design Certification Standard Design Approval Combined License Review, Hearing, and Decision Verification of Construction with ITAAC Load Fuel Manufacturing License Pre-Construction Construction Public Involvement Opportunity Mandatory Hearing Optional Hearing on ITAAC completion 4

5 Design Certifications Allows vendor/applicant to obtain pre-approval of an essentially complete nuclear plant design Achieves regulatory finality through rulemaking Facilitates standardization Reduces licensing uncertainty by resolving all design issues by Commission 15 year duration February 2012 Vogtle Signing Ceremony March 2012 Summer Signing Ceremony 5

6 NRC is Ready to Review Light Water SMR Applications Analyzed policies and guidance Identified overarching technical issues Prepared Design-Specific Review Standard Developed training courses and review tools Conducted formal Lessons-Learned review of 10 CFR Part 52 licensing process 6

7 Licensing Process for Light Water SMRs Same licensing process as currently used One-step or two-step Criteria and basic requirements will not change Applicants may request exemptions if justified Commission expectations are that designs will be safer 7

8 List of SMR Issues Part 1 These May Require Commission i Input SECY Line Item No. Issue Title Status References Use of PRAin the NRC developing preliminary i SECY licensing process guidance for multi-module risk Appropriate Source Ongoing technical Memo to Term, Dose Calculations discussions with NuScale Commission and Siting and mpower 6/20/ Offsite Emergency Planning Requirements NEI White Paper dated December 23, 2013 NRC letter to NEI 6/11/ Annual Fee for Multi- Module Facilities NRC CFO developing proposed rule Memo to Commission 2/7/ Insurance and Liability NRC beginning analysis SECY

9 List of SMR Issues Part 2 Resolved or Awaiting Applications SECY Line Item No. Issue Title Status References License for Prototype t No rulemaking needed d SECY Reactors 2.2 License Structure for Multi- Module Facilities 2.3 Manufacturing License Requirements 3.1 Implementation of Defensein-Depth NRC proposal to license each module No policy issues and no industry interest Evaluating in context of Risk Management Regulatory Framework SECY Memo to Commission 3/27/13 SECY Operator Staffing Guidance in place for exemption request, if justified SECY

10 List of SMR Issues Part 2 Continued SECY Line Item No. Issue Title Status References 4.2 Operational Programs No rulemaking or policy SECY changes needed 4.3 Installation of Reactor No rulemaking or policy SECY Modules During Operation changes needed 4.4 Co-location with Industrial Facilities No rulemaking or policy changes needed SECY Security and Safeguards Requirements 4.6 Aircraft Impact Assessments No rulemaking or policy changes needed No rulemaking or policy changes needed SECY SECY Decommissioning Funding Guidance in place for SECY exemption request, if justified 10

11 Policy Issue Control Room Staffing Issue Appropriate number of on-site licensed operators Proposed Resolution Near-term: Allow SMRs to deviate from existing regulations through exemption requests Task analysis will be critical to the staff s review of an applicant s human factors engineering (HFE) program Long-term: Potential rulemaking to change staffing requirements for SMRs NuScale Control Room Simulator 11

12 Policy Issue Physical Security SMRs should have an appropriate number of security staff and corresponding size of the protected area that reflect: Design and engineering features Reduced reliance on human actions Safety and security should be designed into plants irrespective of capacity Applicants should have a basis for approaches that apply design features and small security forces and NRC will be ready to listen The staff presented positive assessment of current regulatory framework to Commission in

13 Policy Issue Emergency Planning Issues: Appropriate size of the emergency planning zone Extent of onsite and offsite emergency planning Appropriate number of response staff needed Alert and notification requirements Proposed Resolution: NRC exploring possibility of generic resolutions to emergency planning requirement issues for SMRs The staff proposed a new, dose-based, approach for SMRs in 2011 Beginning discussions with NEI about new emergency action lists 13

14 Early Interaction with Stakeholders Currently engaging with multiple vendors in pre-application review activities Need for meaningful pre-application engagement g Familiarize staff with design Minimize surprises Critical to ensuring regulatory stability and predictability 14

15 Generation mpower 180 MWe modules Integral nuclear system design Passive safety systems Underground containment Four-year operating cycle between refueling Less than five percent enriched uranium 2012 The Babcock & Wilcox Co. Used with permission. North American shop-manufactured 15

16 Generation mpower Schedule Received funding from DOE Design Certification application date is under review Status Significant pre-application interactions Robust testing program Topical Reports submitted for review with permission The Babcock & Wilcox Co. Used 16

17 TVA Clinch River Site Plan to build SMRs on site adjacent to Oak Ridge National Lab DOE cost-sharing through partnership with Bechtel and Generation mpower 17

18 TVA Clinch River Site Pre-application topics Flooding and groundwater analysis Geology, seismology, and geotechnical Emergency planning Environmental report 18

19 NuScale Power 45MWe net power/module Each module installed in own isolated bay Up to 12 modules Natural circulation Normal and post accident No reactor coolant pumps No emergency core cooling pumps 37 standard 17x17 PWR fuel assemblies (half height) Internal helical steam generator and pressurizer 19

20 NuScale Power Schedule Received funding from DOE Design Certification Application submittal expected late 2016 Ongoing meetings with NuScale to discuss design and technical reports System testing Thermal hydraulic testing at NuScale 1/3 scale test facility at Oregon State University Critical Heat Flux testing at Stern Labs in Canada Helical l Coil Steam Generator testing ti at SIET Labs in Italy 20

21 Holtec SMR

22 Holtec SMR-160 Expected Design Certification Application Submittal Date Reevaluating Ongoing Interactions Quality Assurance Topical Report under review Agreement with Public Service Electric and Gas and South Carolina Electric and Gas Potentially ti site first unit at Salem/Hope Creek site in New Jersey 22

23 Westinghouse SMR 800 MWt (>225 MWe) power 89 Standard 17X17 fuel assemblies (half height) Soluble boron for reactivity control Reactor Vessel 35m(OD)by247m(H) 3.5m 24.7m (H) Pressurizer: Integral to Reactor Vessel Steam Generator: Once-through, h straight tube Containment Vessel Size 9.8m (OD) by 27.1m (H) underground Modular construction Passive Safety Systems 23

24 Westinghouse SMR Schedule Design Certification Application Status Reevaluating Held technical meetings with staff Submitted several technical reports Project currently on hold 24

25 Design-Specific Review Standards Allow for risk-informed and integrated review Engaged designers, potential licensees, and stakeholders in meaningful interactions Generation mpower Published draft in May 2013 NuScale Published draft expected in July 2015 Final versions to be published following public comment after design certification application submissions 25

26 10 CFR Part 52 Lessons Learned Quality of Applications New Reactor Review Guidance Standardization Identification and Resolution of Technical Issues Knowledge Management Application Time and Sequencing Updates to Regulations 26

27 Training Courses and Review Tools Generation mpower course developed by NRC Technical Training Center Updating application guidance for vendors and potential licensees Updating thermal-hydraulic and severe accident codes 27

28 Advanced, Non-Light Water Reactor Designs High Temperature Gas-Cooled Reactors (HTGRs) Liquid Metal Reactors 4S (Super-Safe, Small and Simple)) PRISM (Power Reactor Innovative Small Module) 28

29 Advanced, Non-Light Water Reactor Designs Organizations i are developing guidance and standards d that would serve as the surrogate for regulatory criteria Generation IV International Forum (GIF) American Nuclear Society NRC recently reviewed and commented on Safety Design Criteria for GIF developed sodium fast reactor The NRC remains aware and engaged No near term license application expected 500º - 550º C 29

30 Licensing Strategy for Non-LWR Reactors Challenge: General Design Criteria in Appendix A are specific to LWRs NRC and DOE agreed on a 2-phase licensing strategy Phase 1 DOE Expertise applied to research, analysis, evaluation, documentation Deliverables technical reports to NRC Phase 2 NRC Initiate regulatory development process Issue regulatory documentation Interim Staff Guidance Standard Review Plan Regulatory Guide Rule making 30

31 International Interface on SMRs Several countries involved or interested in SMR licensing have proposed to pilot a forum for regulators with IAEA support Multinational Design Evaluation Program supports working groups for SMR designs Engagement with INPRO and GIF regarding advancements in standards for non light-water SMRs 31

32 Conclusions The NRC is committed to ensuring that policies, requirements, and internal and external guidance are in place to support reviews of SMRs Engagement from potential applicants and stakeholders throughout the process is critical The NRC will continue to focus on its mission of protecting public health and safety and the environment for reactors licensed under 10 CFR Part 50 or Part 52 32