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:
g a single failure. In most advanced reactor designs, a single system (i.e the residual heat removal system) is provided to perform both the residual heat removal and emergency core cooling functions. In this case, the single system would be designed to meet the requirements of SFR- DC 34 and SFR-DC 35. (for more discussion see NUREG-0968 (Ref. 5) and NUREG-1368 (Ref. 4)) However, the staff acknowledges that this may not be the case for every advanced reactor design. Therefore, to allow current and future non-LWR designers the flexibility to provide a single system or multiple systems to perform residual heat removal and emergency core cooling, the staff decided to keep the SFR-DC 34 and SFR-DC 35 separate in lieu of combining them into a single criterion. Effective core cooling may include maintaining the primary coolant boundary in a condition necessary for adequate postulated accident heat removal. The staff’s approach to provide two separate criteria is consistent with the approach taken in the LWR GDCs. This change removes the light-water reactor emphasis on loss of coolant accidents that may not apply to every design. Loss of APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-17 IV. Fluid Systems Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC coolant accidents may still require analysis in conjunction with postulated accidents if they are relevant to the design. The discussion related to sodium leakage and required barriers was moved to a new SFR-DC 78. The GDC reference to electric power was removed. Refer to SFR- DC17 concerning those systems that require electric power. 36 Inspection of residual heat removal system. Same as ARDC A system that provides emergency core cooling shall be designed to permit appropriate periodic inspection of important components to ensure the integrity and capability of the system. In most advanced reactor designs, a single system (i.e the residual heat removal system) is