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:
, and other systems that may contain radioactivity shall be designed to ensure adequate safety under normal and postulated accident conditions. These systems shall be designed (1) with a capability to permit appropriate periodic inspection and testing of components important to safety, (2) with suitable shielding for radiation protection, (3) with appropriate containment, The underlying concept of establishing functional requirements for radioactivity control in fuel storage and fuel handling systems is independent of the design of non-LWR reactors. However, some advanced designs may use dry fuel storage that incorporates cooling 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, spaces containing components for primary system sodium and cover gas cleanup and processing, effluent discharge paths, and the plant environs for radioactivity that In NUREG-1368, Table 3.3 (page 3-25), the NRC staff recommended deleting the GDC 64 phrase “spaces containing components for recirculation of loss-of-coolant accident fluids.” Otherwise, the NRC staff noted that criterion requirements are independent of the design of SFRs (page 3-55). APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-29 VI. Fuel and Reactivity Control Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC may be released from normal operations, including anticipated operational occurrences, and from postulated accidents. The staff added text to identify other SFR plant areas that should also be included to maintain consideration of all potential discharge paths and areas subject to monitoring. Therefore, primary