Document: NRC Regulatory Guide
Document ID: 9c99a4b7-8619-41f0-b716-262bfdb03941
Document Type: regulatory_guide
Title: Developing Principal Design Criteria for Non-Light Water Reactors + HISTORY - HISTORY 02/2017 – DG-1330 , Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1630/ML16301A307.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.232
CFR Part: 
CFR Title: 

Content:
ive means to accomplish their safety and security functions.” The Advanced Reactor Policy Statement makes clear the Commission’s expectations that advanced reactor designs will address all current regulations, including those related to severe accidents, beyond-design-basis accidents, defense in depth, and probabilistic risk assessment requirements. Depending on the design attributes of the different non-LWR technologies, the NRC regulations and policies may be addressed in a different manner than for traditional LWRs. Role of the General Design Criteria for Non-LWRs As discussed in Section A of this RG, applications for a construction permit, design certification, combined license, standard design approval, or manufacturing license, respectively, must include the PDC for the facility. The PDC are derived from the GDC in Appendix A to 10 CFR Part 50. DG-1330, Page 7 Title 10 CFR 50.341 states: “Appendix A to 10 CFR part 50, general design criteria (GDC), establishes minimum requirements for the principal design criteria for watercooled nuclear power plants similar in design and location to plants for which construction permits have previously been issued by the Commission and provides guidance to applicants in establishing principal design criteria for other types of nuclear power units.” Appendix A to 10 CFR part 50 states: “These General Design Criteria establish minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission. The General Design Criteria are also considered to be generally applicable to other types of nuclear power units and are intended to provide guidance in establishing the principal design criteria for such other units.” Together, these requirements recognize that different requirements may be necessary for non- LWR designs. The non-LWR design criteria developed by the NRC staff and included in