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:
jackets that can be liquid cooled or air cooled to remove heat. This modification to this GDC allows for both liquid and air cooling of the dry fuel storage containers. 62 Prevention of criticality in fuel storage and handling. Same as GDC 63 Monitoring fuel and waste storage. Same as GDC 64 Monitoring radioactivity releases. Means shall be provided for monitoring the reactor containment atmosphere, effluent discharge paths, and plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accidents. The phrase “spaces containing components for recirculation of loss- of-coolant accident fluids” was removed to allow for plant designs that do not have LOCA fluids but may have other similar equipment in spaces where radioactivity should be monitored. Appendix B to DG-1330, Page B-1 APPENDIX B SODIUM-COOLED FAST REACTOR DESIGN CRITERIA The table below contains the sodium-cooled reactor design criteria (SFR-DC). These criteria are applicable to SFRs of both pool- and loop-type designs. Applicants/designers may use the SFR-DC in this appendix to develop all or part of the principal design criteria (PDC) and may choose among the advanced reactor design criteria (ARDC) (Appendix A), SFR-DC (Appendix B), or modular high-temperature gas-cooled reactor design criteria (mHTGR)-DC (Appendix C) to develop each PDC. Applicants/designers may also develop entirely new PDC as needed to address unique design features in their respective designs. To develop the SFR-DC, the staff of the U.S. Nuclear Regulatory Commission (NRC) reviewed each general design criterion (GDC) in Appendix A, “General Design Criteria for Nuclear Power Plants,” to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities,” to determine its applicability to SFR designs. The NRC staff then determined what if any adaptation was appropriate for SFRs. The