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:
o 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 within that system and should be provided with the capability to detect and quantify small leakage rates (e.g., several gallons per week) from each zone. g. For areas not readily or frequently accessed, consideration should be given to the use of remote monitoring systems such as television cameras. Use of such remote monitoring would aid in the early identification of leaks, which could serve to minimize contamination of plant areas. The use of cameras could also result in lower radiation exposures to personnel during operations. h. Monitoring instrumentation (e.g., level sensors, flow meters, pressure sensors, temperature indicators) should be designed to allow replacement. i During design and/or process selection, where applicable, processes should be selected that eliminate streams that have the potential for the encrustation of precipitates or crystallization at ambient temperatures. The latter would eliminate the need for heat tracing, the failure of which could result in line blockages. Appendix A to RG 4.21, Page A-2 j. Pipes should be adequately sized to minimize the potential for blockage by the encrustation of precipitates and to facilitate the removal of such blockage from the pipes. k. The initial facility design should include system decontamination facilities/provisions that enable the timely reduction of the buildup of radioactive source terms that could potentially lead to facility contamination. l. Radioactive SSCs should be designed for the lifetime of the facility, thus avoiding the necessity to replace these SSCs and lessening the potential for system leakage and contamination of nonradioactive systems/components. Materials used in radioactive SSCs should be compatible with processing/disposal options. m. Considering the expected life cycle of the