Document: NUREG-0800
Document ID: 55e187c7-8e17-41ed-a88e-0205d1317fb6
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A475.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
operation and site-specific design features. At a minimum, as part of the description of design and operational features for all applicable SSCs, the applicant should also describe plans for: limiting leakage, controlling the spread of contamination, detecting leaks early, allowing for appropriate and timely action to mitigate and control the spread of contamination by the future licensee, and reducing the time, effort and hazard to personnel during decommissioning activities. Where appropriate to the type of SSC being considered, the applicant should explicitly describe how these considerations are addressed in the design and operation of the SSC. General guidance on meeting the requirements of 10 CFR 20.1406 and examples have been developed and are included as Attachment A – “Evaluation and Scoping Information for Systems, Structures and Components 10 CFR 20.1406 Design Review” to this appendix. Attachment A provides scoping information for SSCs to assist the staff in evaluation of SSCs having a potential to release radioactive materials to the facility, site, or environment which could contaminate the soil or groundwater. Attachment B “Examples of Systems, Structures, A-2 Revision 5 – September 2013 and Components for 10 CFR 20.1406 Review,” to this appendix provides examples of typical SSCs that typically have a potential to release radioactive material to the facility, site, or environment. In addition, Attachment C cites operational experiences for various SSCs, including actual Event Notices and information included in the Liquid Radioactive Release Lessons Learned Task Force (ADAMS Accession No. ML062650312). Regulatory positions C.1 through C.4 in RG 4.21 are provided as specific guidance to applicants on meeting the requirements of 10 CFR 20.1406. C1 through C4 describe concepts to be implemented to provide reasonable assurance that inadvertent spills, leaks, and discharges of liquid, gaseous and solid radioactive effluents are prevented,