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:
Interfaces When the primary coolant system interfaces with a structure, system, or component containing fluid that is chemically incompatible with the primary coolant, the interface location shall be designed to ensure that the primary coolant is separated from the chemically incompatible fluid by two redundant, The consequence of leakage between the primary coolant system and a heat removal system (i.e. RHR system, intermediate coolant system) is more significant for primary coolant system (potentially impacting the fuel design limits or integrity of the primary coolant boundary) than it is for the heat removal system (coolant drawdown or introduction of radioactive sodium). APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-33 VII. Additional SFR-DC Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC passive barriers. When the primary coolant system interfaces with a structure, system, or component containing fluid that is chemically compatible with the primary coolant, then the interface location may be a single passive barrier provided that the following conditions are met: (1) postulated leakage at the interface location does not result in failure of the intended safety functions of structures, systems or components important to safety or result in exceeding the fuel design limits (2) the fluid contained in the structure, system, or component is maintained at a higher pressure than the primary coolant during normal operation, AOOs, shutdown, and accident conditions. Rather than creating two parallel requirements for the two systems, SFR-78 was created to discuss leakage and required barriers as a generic criterion. The criterion allows for double walled steam generators, intermediate coolant systems connected to steam power system, and systems similar to the PRISM Direct Reactor Auxiliary Cooling System (DRACS). A paragraph from NUREG 1368 (page 3-41) was added describing the characteristics of the residual