Document: NRC Regulatory Guide
Document ID: da269da5-7390-4252-b08f-bdb7aeb8beaf
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:
ting to discuss the public comments on October 11, 2016 (Ref. 23). The tables in Appendices A, B, and C of this RG represent the staff’s second draft version of the design criteria that incorporates many of the informal public comments. Key Assumptions and Clarifications Regarding the non-LWR Design Criteria The NRC staff applied the following key assumptions when developing the non-LWR design criteria: • The underlying safety objectives of the GDC still apply. • ARDC, SFR DC, and mHTGR DC apply to normal operations, anticipated operational occurrences, and postulated accidents (design basis). • The NRC has regulations and orders on severe accidents and beyond-design-basis events (BDBEs) for LWRs. Similar regulations for non-LWRs were not defined as part of this initiative. The current regulations may or may not be applicable to non-LWRs. It is the responsibility of the applicant to demonstrate compliance with applicable severe accident and BDBE regulations and orders, demonstrate why any that are not applicable do not apply, and demonstrate why other design specific severe accidents or BDBE that can occur will be mitigated. • While developing the non-LWR design criteria, the staff assumed that a core disruptive accident will be demonstrated to be a severe accident or a BDBE by the applicant. A core disruptive accident would result in a loss of a coolable geometry such that multiple non-LWR design criteria would be violated. • Safety design objectives for non-LWRs can differ substantially from those associated with LWRs. • Proposed GDC adaptations were focused on those needed for improved regulatory certainty and clarity. • The NRC intends the ARDC to apply to the six advanced reactor technology types identified in the DOE report; however, in some instances, the SFR-DC or mHTGR-DC may be more applicable to a design or technology than the ARDC. • The SFR-DC and mHTGR-DC are intended to apply to all designs of these technologies. Additional sets of