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:
sure. ARDC 51–57 support ARDC 50, which specifically applies to non- LWR designs that use a fixed containment structure. Therefore, the word “structure” is added to each of these ARDC to clearly convey the understanding that this criterion applies to designs employing containment structures. 53 Provisions for containment testing and inspection. The reactor containment structure shall be designed to permit (1) appropriate periodic inspection of all important areas, such as penetrations, (2) an appropriate surveillance program, and (3) periodic testing at containment design pressure of the leak- tightness of penetrations that have resilient seals and expansion bellows. ARDC 51–57 support ARDC 50, which specifically applies to non- LWR designs that use a fixed containment structure. Therefore, the word “structure” is added to each of these ARDC to clearly convey the understanding that this criterion only applies to designs employing containment structures. 54 Piping systems penetrating containment. Piping systems penetrating the containment structure shall be provided with leak detection, isolation, and containment capabilities having redundancy, reliability, and performance capabilities that reflect the importance to safety of isolating ARDC 51–57 support ARDC 50, which specifically applies to non- LWR designs that use a fixed containment structure. Therefore, the word “structure” is added to each of these ARDC to clearly convey the understanding that this ARDC only applies to designs employing containment structures. The word “reactor” was APPENDIX A. ADVANCED REACTOR DESIGN CRITERIA Appendix A to DG-1330, Page A-22 V. Reactor Containment Criterion ARDC Title and Content NRC Rationale for Adaptions to GDC 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