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:
of the CRE may be contained in a number of plant documents. These documents might include the Updated Final Safety Analysis Report (UFSAR), the original Final Safety Analysis Report (FSAR), the Safety Evaluation for the Operating License (OL), system descriptions, plant drawings, operating procedures, plant amendment requests, NRC safety evaluations, TMI Action Item III.D.3.4 submittals, and responses to staff questions at the construction permit and OL stages. 2.1.2 Determination of the Licensing Bases In demonstrating the habitability of a facility's CRE, it is essential that the licensee know the facility's licensing bases for their CRHSs. The sources of the licensing bases of the CRHSs should be identified. Licensees should consider the documents identified in Section 4.3 of NEI 99-03 (Ref. 2) as potential sources that define the licensing bases for CRHS. Focusing on the events that may have established or changed these bases may help narrow this search. Over the facility's lifetime the licensing bases change. The staff may have reviewed and approved the licensing bases of facilities licensed before the issuance of this guide. The original licensing basis may have been submitted as part of the construction permit application. Licensees may have modified it in response to NRC questions. In addition, the licensing bases were part of the application for the OL (FSAR). Depending on the plant vintage, licensees may have modified their licensing bases in response to TMI Action Item lIl.D.3.4. Amendments to the OL may have resulted in changes to the licensing bases of the CRHSs. Licensees should review the applicable plant changes to their licensing bases to determine the current bases. A group of reactors received their construction permits or OLs before the GDCs were promulgated. During this time, proposed GDCs (sometimes called "Principal Design Criteria") were published in the Federal Register for comment. These proposed GDCs addressed CRH. Although facilities may