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:
ntained within design limits assuming a single failure. If plugging of any cover gas line due to condensation or plate out of sodium aerosol or vapor could prevent accomplishing a safety function, the temperature control and the relevant corrective measures associated with that line shall be considered important to safety. The NRC considered DOE’s proposed SFR-DC 72 and made changes based on the “Response to NRC Staff Questions on the U.S. Department of Energy Report, ‘Guidance for Developing Principal Design Criteria for Advanced Non-Light Water Reactors’” (pages 13-14). NUREG-1368 (Ref. 4) (page 3-56)), Section 3.2.4.2, suggested the need for a separate criterion for sodium heating system. Also, a separate criterion was included in NUREG-0968 (Ref. 5) (Criterion 7, “Sodium Heating Systems”). The phrase “and the relevant corrective measures” has been added, in case the cover gas line design includes a feature for clearing an obstruction resulting from condensation or plate out of sodium aerosol or vapor. 73 Sodium leakage detection and reaction prevention and mitigation. Means to detect sodium leakage and to limit and control the extent of sodium-air and sodium-concrete reactions and to mitigate the effects of fires resulting from these sodium-air and sodium-concrete reactions shall be provided to ensure that the The NRC considered DOE’s proposed SFR-DC 73 and made changes based on the “Response to NRC Staff Questions on the U.S. Department of Energy Report, ‘Guidance for Developing Principal Design Criteria for Advanced Non-Light Water Reactors’” (pages 15–16). APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-31 VII. Additional SFR-DC Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC safety functions of structures, systems, and components important to safety are maintained. Special features, such as inerted enclosures or guard vessels, shall be provided for systems containing