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Other Related Documents for New Reactors

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In February 2001, the Commission issued a staff requirements memorandum (SRM), directing the staff to assess its technical, licensing, and inspection capabilities and identify any enhancements needed to ensure that the U.S. Nuclear Regulatory Commission (NRC) would be prepared to review applications for early site permits or the construction of new nuclear power plants. On May 1, 2001, the staff provided its SRM response, describing its planned activities, and providing a schedule for fulfilling the Commission's directive. Then, on October 12, 2001, the staff provided the Commission with its final response in SECY-01-0188, "Future Licensing and Inspection Readiness Assessment." The attachment to that Commission (SECY) paper contains the Future Licensing and Inspection Readiness Assessment (FLIRA) Report, which the staff has since updated in subsequent SECY papers. For detail, see the following topics on this page:

For more history related to the New Reactor Licensing Program, see the Advanced Reactor Policy Statement. In addition, the NRC has assembled a package of 100 documents that comprise the Regulatory History of Design Certifications for the Advanced Boiling-Water Reactor (ABWR), System 80+, and Advanced Passive 600 (AP600) standard plant designs. This history, spanning a 15-year period, is unique because the NRC simultaneously developed (1) the regulatory standards for reviewing these next-generation reactor designs and (2) the form and content of the rules that would certify the designs.

Commission Papers and Staff Requirements Memoranda

The following table presents a chronological listing of SECY papers and SRMs related to New Reactor Licensing, with the most recent first.

SECY Title SRM
12-0081 Risk-Informed Regulatory Framework for New Reactors 10/22/2012
12-0069 Process for Addressing Late-Breaking Issues During a Combined License Application Review 06/25/2012
12-0059 Construction Reactor Oversight Process Self-Assessment for Calendar Year 2011  
12-0030 Final Rule:  Requirements for Maintenance of Inspections, Tests, Analyses, and Acceptance Criteria (RIN 3150-AI77) 05/11/2012
12-0020 Fifth Report on the Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant, Unit 2  
11-0184 Security Regulatory Framework for Certifying, Approving, and Licensing Small Modular Nuclear Reactors (M110329)  
11-0181 Decommissioning Funding Assurance for Small Modular Nuclear Reactors  
11-0178 Insurance and Liability Regulatory Requirements for Small Modular Reactor Facilities  
11-0156 Feasibility of Including Risk Information in Categorizing Structures, Systems, and Components as Safety-Related or Nonsafety-Related  
11-0152 Development of an Emergency Planning and Preparedness Framework for Small Modular Reactors  
11-0115 Staff Statement in Support of the Uncontested Hearing for Issuance of Combined Licenses for the Virgil C. Summer Nuclear Station, Units 2 and 3 (Docket Nos. 52-027 and 52-028)  
11-0112 Staff Assessment of Selected Small Modular Reactor Issues Identified in 10-0034  
11-0111 Staff Progress in Resolving Issues Associated with Inspections, Tests, Analyses, and Acceptance Criteria  
11-0110 Staff Statement in Support of the Uncontested Hearing for Issuance of Combined Licenses and Limited Work Authorizations for Vogtle Electric Generating Plant, Units 3 and 4 (Docket Nos. 52-025 and 52-026)  
11-0106 Final Rule: U.S. Advanced Boiling-Water Reactor Aircraft Impact Design Certification Amendment (RIN 3150-AI84) 11/01/2011
11-0102 Fourth Report on the Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant, Unit 2  
11-0098 Operator Staffing for Small or Multi-Module Nuclear Power Plant Facilities  
11-0079 License Structure for Multi-Module Facilities Related to Small Modular Nuclear Power Reactors  
11-0024 Use of Risk Insights to Enhance the Safety Focus of Small Modular Reactor Reviews 05/11/2011
11-0006 Proposed Rule—Economic Simplified Boiling-Water Reactor Design Certification 03/08/2011
10-0166 Third Report on Status of Licensing for the Watts Bar Nuclear Plant, Unit 2  
10-0142 Proposed Rule:  U.S. Advanced Boiling Water Reactor Aircraft Impact Design Certification Amendment (RIN 3150‑AI84) 12/05/2010
10-0140 Options for Revising the Construction Reactor Oversight Process Assessment Program 03/21/2011
10-0137 Proposed Rule: Requirements for Access Authorization and Physical Protection During Nuclear Power Plant Construction (RIN 3150-AI65) 03/30/2011
10-0100 Staff Progress in Resolving Issues Associated with Inspections, Tests, Analyses, and Acceptance Criteria  
10-0038 Update Status on the Development of Construction Reactor Oversight Process Options  
10-0034 Potential Policy, Licensing, and Key Technical Issues for Small Modular Nuclear Reactor Designs  
10-0015 Second Annual Status of Reactivation of Construction and Licensing for the Watts Bar Nuclear Plant, Unit 2  
09-0182 Legal Constraints of Relying on Vendor Inspection Results of Foreign Regulators and the Need for Additional Resources to Achieve the Appropriate Number of NRC Vendor Inspections  
09-0119 Staff Progress in Resolving Issues Associated with Inspections, Tests, Analyses, and Acceptance Criteria  
09-0113 Update on the Development of Construction Assessment Process Policy Options and the Construction Inspection Program Information Management System  
09-0056 Staff Approach Regarding a Risk-Informed and Performance-Based Revision to Part 50 of Title 10 of the Code of Federal Regulationsand Developing a Policy Statement on Defense-in-Depth for Future Reactors  
09-0018 Streamlining Design Certification Rulemakings  
09-0012 Status of Reactivation of Construction and Licensing Activities for the Watts Bar Nuclear Plant Unit 2  
08-0142 Change in Staff Position Concerning Information in Plant-specific Technical Specifications That Combined License Applicants must Provide to Support Issuance of Combined Licenses  
08-0117 Staff Approach to Verify Closure of Inspections, Tests, Analyses, and Acceptance Criteria and to Implement Title 10 CFR 52.99, “Inspection During Construction,” and Related Portion of 10 CFR 52.103(g) on the Commission Finding 01/14/2009
08-0096 Training and Infrastructure Needs to Accomplish New Reactor Inspections and Operator Licensing  
07-0207 Multinational Design Evaluation Program - Stage 2 Pilot Project 01/03/2008
07-0152 Semiannual Update of the Status of New Reactor Licensing Activities and Future Planning for New Reactors  
07-0105 Enhancement to the Vendor Inspection Program Within the Office of New Reactors  
07-0101 Staff Recommendations Regarding a Risk-Informed and Performance-Based Revision to 10 CFR Part 50 (RIN 3150-AH81) 09/10/2007
07-0096 Possible Reactivation of Construction and Licensing Activities for the Watts Bar Nuclear Plant Unit 2 07/25/2007
07-0082 Rulemaking to Make Risk-Informed Changes to Loss-of-Coolant Accident Technical Requirements; 10 CFR 50.46a, "Alternative Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors" 08/10/2007
07-0081 Regulatory Options for Licensing Facilities Associated with the Global Nuclear Energy Partnership 06/27/2007
07-0049 Construction Inspection Roles and Responsibilities  
07-0047 Staff Approach To Verifying the Closure of Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Through a Sample-Based Inspection Program 05/16/2007
06-0220 Final Rule To Update 10 CFR Part 52 04/11/2007
11/13/2006
06-0114 Description of the Construction Inspection Program for Plants Licensed Under 10 CFR Part 52  
06-0041 Proposed Strategy To Support Implementation of New Reactor Construction Inspection Program 04/21/2006
06-0019 Semiannual Update of the Status of New Reactor Licensing Activities and Future Planning for New Reactors, dated January 31, 2006  
05-0197 Review Of Operational Programs in a Combined License Application and Generic Emergency Planning Inspections, Tests, Analyses, and Acceptance Criteria 02/22/2006
05-0139 Semiannual Update of the Status of New Reactor Licensing Activities and Future Planning for New Reactors dated August 4, 2005  
05-0130 Policy Issues Related to New Plant Licensing and Status of the Technology-Neutral Framework for New Plant Licensing 09/14/2005
05-0120 Security Design Expectations for New Reactor Licensing Activities 09/09/2005
05-0013 Semiannual Update of the Status of New Reactor Licensing Activities and Future Planning for New Reactors dated January 12, 2005  
04-0117 Semiannual Update of the Status of New Reactor Licensing Activities, dated July 9, 2004  
04-0103 Status of Response to the June 26, 2003, Staff Requirements Memorandum on Policy Issues Related to Licensing Non-light Water Reactor Designs  
04-0032 Programmatic Information Needed for Approval of a Combined License Without Inspection, Tests, Analysis, and Acceptance Criteria, dated February 26, 2004 05/14/2004
04-0001 Semiannual Update of the Status of New Reactor Licensing Activities, dated January 2, 2004  
03-0227 Review Standard RS-002, "Processing Applications for Early Site Permits" 03/15/2004
03-0113 Semiannual Update of the Status of New Reactor Licensing Activities, dated July 7, 2003  
03-0105 Early Site Permit (ESP) Application Readiness, dated June 24, 2003  
03-0059 NRC's Advanced Reactor Research Program," April 18, 2003  
03-0047 * Policy Issues Related to Licensing Non-Light Water Reactor Designs 06/26/2003
03-0005 Semiannual Update of the Status of New Reactor Licensing Activities  
02-0180 Legal and Financial Policy Issues Associated with Licensing New Nuclear Power Plants, dated October 7, 2002 03/31/2003
02-0139 * Plan for Resolving Policy Issues Related to Licensing Non-Light Water Reactor Designs  
02-0077 Proposed Rule of Update 10 CFR Part 52, "Early Site Permits, Standard Design Certifications, and Combined Licenses for Nuclear Power Plants" 05/06/2003
02-0076 Semi-Annual Update of the Future Licensing and Inspection Readiness Assessment (FLIRA)  
02-0067 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for Operational Programs (Programmatic ITAAC) 09/11/2002
02-0059 Use of Design Acceptance Criteria for the AP1000 Standard Plant Design  
01-0207 Legal and Financial Issues Related to Exelon's Pebble Bed Modular Reactor  
01-0188 Future Licensing and Inspection Readiness Assessment  

* Documents related to SECY-03-0047 and SECY-02-0139 can be found under Policy Issues Associated with Licensing Advanced Reactor Designs.

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Schedule of New Reactor Applications

The New Reactor Licensing Applications (An Estimated Schedule) is arranged by reactor design type and shows anticipated review schedules. The schedules depicted for non-docketed applications represent the nominal anticipated review durations. Actual schedules will be established after the applications are docketed. This estimated schedule is also available as a dataset in open format (Microsoft Excel) with an associated data dictionary.

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Page Last Reviewed/Updated Thursday, November 14, 2013