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:
ructure” is added to each of these SFR-DC to clearly convey the understanding that this criterion only applies to designs employing containment structures. 54 Piping systems penetrating containment. Piping systems penetrating the reactor containment structure shall be provided with leak detection, isolation, and containment capabilities that have redundancy, reliability, and performance capabilities necessary to perform the containment safety function and that reflect the importance to safety of preventing radioactivity releases from containment through these piping systems. Such piping systems shall be designed with the capability to verify, by testing, the operational readiness of any isolation valves and associated apparatus periodically and to confirm that valve leakage is within acceptable limits. The word “structure” was added to this SFR-DC to clearly convey the understanding that this criterion only applies to designs employing containment structures. Not all penetrations will provide a release path to the atmosphere. Piping that may be of interest in the case of an SFR design is for the intermediate heat transport system and the residual heat removal system. Based on stakeholder input, a designer may be able to satisfactorily demonstrate that containment isolation valves are not required for an SFR design. This rewording for the SFR-DC provides a designer the opportunity to present the safety case without containment isolation valves and the associated need for testing. Otherwise, NUREG-1368 (page 3-51) indicated that GDC 54 was applicable as written. American National Standards Institute/American Nuclear Society (ANSI/ANS)-54.1-1989 recommended revising the phrase “…containment capabilities having redundancy, reliability, and performance capabilities which reflect the importance to safety of isolating these piping systems.” to “…containment capabilities as required to perform the containment safety function.” APPENDIX B. SODIUM-COOLED