Document: NRC Regulatory Guide
Document ID: 05969442-49ea-4f4a-a9e2-de3a14628b5e
Document Type: regulatory_guide
Title: Minimization of Contamination and Radioactive Waste Generation:  Life-Cycle Planning - HISTORY 07/2013 – Periodic Review of Revision 0 – No issues identified
Source: NRC Regulatory Guide Division 4
Source URL: https://www.nrc.gov/docs/ML0805/ML080500187.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-4.21
CFR Part: 
CFR Title: 

Content:
inimize facility contamination, 10 CFR 20.1406 applicants should consider the following specific measures (or a combination thereof): a. The interface between structures, systems, and components (SSC) important to radiological safety and nonradioactive SSCs should be minimized. Necessary interfaces should have a minimum of two barriers, including one that can be a pressure differential, and should have instrumentation for prompt detection and control of cross-contamination. b. Processing areas for radioactive material should be isolated from other areas within the facility through the use of compartmentalization and access controls to reduce the potential for cross- contamination. c. A maintenance and inspection program should be applied to radioactive SSCs that have a potential for leakage of radioactive material to the site environs (i.e., onsite and offsite locations outside of the facility SSCs). d. Leak or spill collection systems should be provided to protect against leakage and/or to isolate the release of liquid contamination using redundancy concepts such as the use of multiple piping enclosures with pans/trays or drainage to channel contamination for collection and processing. e. Floor liners and catch basins should be used for SSCs that have a high potential for periodic leakage during routine operations and/or maintenance. Floor liners and catch basins should be impermeable, durable, and have readily cleanable surfaces. Concrete structures and walls near these SSCs should be sealed to facilitate cleaning and decontamination. f. A leak identification program should be developed for components containing radioactive materials to prevent unnecessary contamination of equipment and surrounding areas and to minimize radioactive waste. Provision should be made to allow for the timely identification of leak locations. Structures and components, such as a spent fuel pool and associated piping, should be designed to permit the isolation of clearly defined zones