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:
operating and accident conditions. This renamed SFR-DC accounts for advanced reactor design system differences to include cooling requirements for SSCs, if applicable; this SFR-DC does not address the residual heat removal system required under SFR-DC 34, and ECCS system under SFR- DC 35. APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-22 IV. Fluid Systems Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC Suitable redundancy in components and features and suitable interconnections, leak detection, and isolation capabilities shall be provided to ensure that the system safety function can be accomplished, assuming a single failure. The GDC reference to electric power was removed. Refer to SFR- DC17 concerning those systems that require electric power. 45 Inspection of structural and equipment cooling systems. Same as ARDC The structural and equipment cooling systems shall be designed to permit appropriate periodic inspection of important components, such as heat exchangers and piping, to ensure the integrity and capability of the systems. This renamed ARDC accounts for advanced reactor system design differences to include possible cooling requirements for SSCs important to safety. 46 Testing of structural and equipment cooling systems. Same as ARDC The structural and equipment cooling systems shall be designed to permit appropriate periodic functional testing to ensure (1) the structural and leaktight integrity of their components, (2) the operability and performance of the system components, and (3) the operability of the systems as a whole and, under conditions as close to design as practical, the performance of the full operational sequences that bring the systems into operation for reactor shutdown and postulated accidents, including the operation of associated systems. This renamed ARDC accounts for advanced reactor system design differences to include possible cooling requirements for SSCs important to