Document: NRC Regulatory Guide
Document ID: 8291b9eb-e4a7-4806-8b5b-1deca2ff1fe2
Document Type: regulatory_guide
Title: Control Room Habitability at Light-Water Nuclear Power Reactors
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0207/ML020790125.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.196
CFR Part: 
CFR Title: 

Content:
r Conditioning Users Group). In 1992, Zion became the first nuclear power plant to rigorously test its CRE for integrity. Since then, approximately 30 percent of the licensed facilities have performed integrated inleakage testing and have measured inleakage rates greater than that assumed in the original design analyses, in some cases by several orders of magnitude. RA-2 In March 1998, the staff briefed the Office of Nuclear Reactor Regulation (NRR) Executive Team (ET) on its concerns regarding control room habitability. The ET directed the staff to work with NEI to resolve the issues. The staff co-hosted a control room habitability workshop in July 1998 with NEI and the Nuclear Heating, Ventilation, and Air Conditioning Users Group (NHUG). NEI prepared draft versions of a report entitled ”Control Room Habitability Assessment Guidance,” NEI 99-03. The staff reviewed the October 13, 2000, revision and determined that, while there was much agreement on positions taken in the document, areas remained in which the staff and industry were in disagreement. It was determined at that time that the staff would prepare and issue formal guidance. A task action plan was prepared. The action plan called for the preparation of a generic letter and four supporting regulatory guides, including the guide considered here. II. OBJECTIVE OF THE REGULATORY ACTION This proposed guide would provide guidance and criteria acceptable to the Nuclear Regulatory Commission (NRC) staff for implementing the NRC's regulations in Appendix A to 10 CFR Part 50 regarding control room habitability (CRH). The guide outlines a process that licensees may apply to CREs that are modified, newly designed, or those that need to reconfirm their conformance to the regulations. III. EXISTING REGULATORY FRAMEWORK In Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," General Design Criteria (GDC) 1, 3, 4, 5, and 19