New Plant Process and Players Overview. George Rombold. Scientech Nuclear Regulatory Services

Transcription

1 New Plant Process and Players Overview George Rombold Scientech Nuclear Regulatory Services

2 Objectives Reactor Licensing History/Background Certified Design Early Site Permit Combined Operating License Current Players / Schedule

3 Evolution of Nuclear Power Generation I Generation II Generation III Generation III+ Generation IV Early Prototype Reactors Commercial Power Reactors Advanced LWRs - Shippingport - Dresden 1 - Fermi 1 - LWR PWR, BWR - CANDU - VVER - AGR - ABWR - System AP600 Generation III Evolutionary Designs offering improved Economics -AP ESBWR - EPR - PBMR - Highly Economical - Enhanced Safety - Minimize Waste - Proliferation Resistant Gen I Gen II Gen III Gen III+ Gen IV

4 Reactor Licensing - History In the past five decades, the NRC has issued 126 nuclear operating licenses 104 currently in operation 22 reactors have been shutdown (various stages of decommissioning) 100 additional plants began licensing process but did not complete

5 Reactor Licensing Process In the past, plants were licensed under a twostep process Construction Permit Stage Operating License Stage

6 Reactor Licensing Process In 1989, NRC established an alternative process Established Early Site Permit Process Approval for site and bank it for future use Established process for Standard Design Certification Process off-the-shelf designs Combined construction permit and operating license stages into one license

7 Standardization The NRC has long sought standardization 10 CFR Part 52 provides a predictable licensing process including certification of new nuclear plant designs. The design certification process provides for early public participation and resolution of safety issues prior to an application to construct a nuclear power plant.

8 Benefits of Standardization The NRC believes that the use of standardized certified designs should: Enhance plant safety Increase the efficiency of NRC review process Reduce regulatory complexity and uncertainty

9 Current Fleet Experiences Variability has introduced significant differences in the operation and licensing of the current fleet. Reduced effectiveness of operational experiences Variable Tech Specs Different Operating procedures

10 Benefits of Standard Designs Concentrate NRC resources Standardized programs: Construction QA Training Maintenance

11 Design Certification Pre-Application Review Process The NRC has conducted pre-application reviews of advanced reactor designs to identify: major safety issues that could require Commission policy guidance to the staff, major technical issues that the staff could resolve under existing regulations or NRC policy, and research needed to resolve identified issues.

12 Design Certification Application Reviews NRC can certify reactor design for 15 years through the rulemaking process. The NRC review will address the safety issues of an essentially complete nuclear power plant design, independent of a specific site.

13 Design Certification Application for Standard Design Certification must contain: Design information and proposed Inspections, Tests, Analysis and Acceptance Criteria (ITAAC) for the proposed standard design ACRS Reviews each application NRC Issues SER Public Meeting Design will be certified through a rulemaking

14 Early Site Permits (ESP) An ESP is a partial construction permit, and is therefore subject to all procedural requirements in 10 CFR 2 applicable to construction permits.

15 Early Site Permit (Continued) NRC will document its finding regarding site safety characteristics in a safety evaluation report SER will state whether there is reasonable assurance that the site can safely host a future nuclear power plant or plants. Emergency planning suitability Environmental impact statement (EIS)

16 Early Site Permit (Continued) Early site permits are good for 10 to 20 years Renewed for an additional 10 to 20 years Address: Safety issues Environmental protection issues Emergency Plans Independent of the review of a specific nuclear plant design

17 Benefits of an Early Site Permit Resolve safety and environmental issues related to siting Before an applicant needs to make large commitments of resources. Having obtained an ESP A combined license (COL) need only reference the ESP in the COL application.

18 Combined Operating License (COL)

19 Combined Operating License (COL) A COL authorizes construction and conditional operation of a nuclear power facility. Subpart C of 10 CFR Part 52.

20 Combined Operating License (COL) COL application - Contains basically same information required by an application for an Operating License issued under 10 CFR 50 Financial and antitrust information Assessment of the need for power Must describe Inspections, Tests, Analysis and Acceptance Criteria (ITAAC) To ensure that the plant has been properly constructed and will operate safely

21 Combined Operating License (COL) Application for COL may reference A standard Design Certification An early site permit Both Or neither

22 Combined Operating License (COL) If application references a standard design certification Must perform ITAAC for certified design and site specific design features If application does not reference standard design certification Must provide complete design information including information they would otherwise have submitted for standard design certification.

23 Combined Operating License (COL) If the application references Early Site Permit Must demonstrate that design of plant is compatible with ESP Must also include information on those issues that were not required with ESP Such as the need for power from the proposed plant If application does not reference ESP Must provide site information that would be included in an ESP Must complete Emergency Plan

24 Combined Operating License (COL) Upon successful completion of inspections, tests and analysis (At least 180 days before scheduled fuel load date) NRC publishes a notice for opportunity for a hearing. Hearing take place only if request demonstrates that the licensee has not met the acceptance criteria in COL

25 COL Licensing Process Early Site Permit (or equiv Environmental information) Optional Preapplication Review Standard Design Certification or Equivalent Design Information Combined License Review, Hearing and Decision Verification of Inspections, Tests, Analysis, and Acceptance Criteria Reactor Operations

26 New Plant Timeline Early Site Permit NRC COL Issued Application Development NRC Review/ Approval of Application (27 48 Months) Design Certification Site prep. and Limited Authorized Work Plant Construction/ ITAAC Verification Application Submitted Commercial Operation 0

27 New Reactors Current Players/Schedules Who Are they? What is planned schedule?

28 Current Players Design Certification Advanced Boiling Water Reactor (ABWR) NRC Approved GE Nuclear Energy (Approved -May 1997) System 80+ AP600 AP1000 APWR ESBWR EPR NRC Approved NRC Approved NRC Approved* Under Review Under Review Under Review Westinghouse (formerly ABB-Combustion Engineering) (Approved - May 1997) Westinghouse (Approved - December 1999). Westinghouse (Approved Feb, 2006) * Amendment Under Review Mitsubishi Heavy Industry announced intent for Design Certification for APWR Economic Simplified Boiling Water Reactor by General Electric Pressurized Water Reactor by AREVA (Similar Plant being built in Finland)

29 AP 1000 Westinghouse Design 1117 to 1154 MWe Two Loop PWR Based on ~ 600 MWe AP 600 design Certified February 2006 (Amendment under review) Passive Core Cooling Systems

30 AREVA Design ~ 1600 MWe 4 Loop PWR Design Certification submitted in December 2007 Four 100% capacity ESF trains (n+2) Core Catcher to respond to severe accidents US EPR

31 GE Hitachi Nuclear Energy s (GEH) Design Economic Simplified Boiling Water Reactor ~1,575 MWe gross Design Certification Applied 2005 Passive Safety Features Leverages ABWR Technology Builds on Existing BWR Experience ESBWR

32 Mitsubishi Nuclear Design ~ 1,700 MWe four Loop PWR Design Certification Application submitted 1/7/2008 Optimized combination of active and passive components CDF 1/10 of prior value US - APWR

33 GE Hitachi Nuclear Energy s (GEH) Advanced BWR Design Certified May 2, MWe gross The First ABWR began operation in Japan in 1996; 3 more operating Technology Enhancements to Improve Performance (ECCS, CRD) ABWR

34 New Plant Players - ESP Company Details Dominion North Anna site Approved 11/2007 Entergy Grand Gulf site - Approved 3/2007 Exelon Clinton Site - Approved 3/2007 Southern Nuclear Submitted 8/ Vogtle site Duke Assessing Option (Oconee or Davie County) Announced Applicant Intent letter in 4/2007 Potential ESP 6/2010 6/2012

35 Sites by Selected Reactor Type Site Rx Type # units Bellefonte (NuStart) AP Harris AP Levy County AP Vogtle AP Turkey Point AP Lee AP Summer AP1000 2

36 Sites by Selected Reactor Type Site Rx Type # Units UniStar (Calvert, Nine Mile) EPR 2 Bell Bend EPR 1 Callaway EPR 1 Amarillo EPR 2 Bruneau EPR 1

37 Sites by Selected Reactor Type Site Rx Type # units North Anna ESBWR 1 Fermi ESBWR 1

38 Sites by Selected Reactor Type Site Rx Type # Units Comanche Peak USAPWR 2

39 Sites by Selected Reactor Type Site Rx Type # Units South Texas ABWR 2

40 Sites by Selected Reactor Type Site Rx Type # Units Victoria County TBD 2 Grand Gulf (NuStart) TBD 1 River Bend TBD 1 Undecided TBD 4

41 Location of Projected New Nuclear Power Reactors

42 Nuclear Renaissance Total Applications Total Units

43 Summary 17 COL applications have been submitted to date. Fabrication of large components beginning about 18-months after a COL application is submitted. Approximately 35 new units to be constructed

44 Summary Four design certifications approved by NRC ESBWR, EPR, APWR and Westinghouse s AP1000 amendment reviews ongoing

45 New Plant Process and Players Overview