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:
elium is not needed in a mHTGR to remove heat from the core during postulated accidents and does not have the same importance as water does for LWR designs to ensure that fuel integrity is maintained. Therefore, a specific reference to LOCAs is not applicable to all designs. LOCAs may still require analysis in conjunction with postulated accidents if relevant to the design. The phrase “the environmental conditions associated with anticipated operational occurrences” has been added to ensure that APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-3 I. Overall Requirements Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC with postulated pipe ruptures in nuclear power units may be excluded from the design basis when analyses reviewed and approved by the Commission demonstrate that the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis for the piping. Chemical consequences of accidents, such as sodium leakage, shall be appropriately considered for the design of structures, systems, and components important to safety, which must be protected. the criterion would apply to all SFR design-basis events, as suggested in NUREG-1368. A new sentence is added to ensure the designer considers the effects of sodium leakage and associated chemical reactions with SSCs important to safety, which must be protected. 5 Sharing of structures, systems, and components. Same as GDC II. Multiple Barriers Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC 10 Reactor design. Same as GDC 11 Reactor inherent protection. Same as ARDC The reactor core and associated systems that contribute to reactivity feedback shall be designed so that, in the power operating range, the net effect of the prompt inherent nuclear feedback characteristics tends to compensate for a rapid increase in reactivity. The wording has been changed to broaden the applicability from “coolant