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:
s and to maintain it in a safe condition under accident conditions. Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent, as defined in § 50.2 for the duration of the accident. Adequate habitability measures shall be provided to permit access and occupancy of the control room during normal operations and under accident conditions. Adequate protection against sodium aerosols shall be provided to permit access and occupancy of the control room under accident conditions. Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures. The criterion was updated to remove specific emphasis on LOCAs, which may be not appropriate for advanced designs such as the SFR. Reference to “whole body, or its equivalent to any part of the body” has been updated to the current total effective dose equivalent standard as defined in § 50.2. A control room habitability requirement beyond that associated with radiation protection has been added to address the concern that nonradionuclide accidents, including accidental sodium leakage and sodium fire, which could release sodium aerosols, may also affect control room access and occupancy. The last paragraph of the GDC has been eliminated for the SFR-DC because it is not applicable to future applicants. APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-9 III. Reactivity Control Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC 20 Protection system functions. Same as GDC 21 Protection system reliability and