Document: NRC Regulatory Guide
Document ID: 111d9c37-d539-4042-97a1-8ddc5dd093dc
Document Type: regulatory_guide
Title: Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants + HISTORY –HISTORY 07/2020 – Periodic Review of Revision 2 – Reviewed with issues identified for future consideration 03/2018 – Periodic Review of Revision 2 – Revise 06/2015 – Periodic Review of Revision 2 – Revise 08/2000 – DG-1100 , Proposed Revision 2 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2019/ML20190A131.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.143
CFR Part: 
CFR Title: 

Content:
e, NRR/DRA 301-415-5345 July 29, 2020 Bowman, Gregory signing on behalf of Franovich, Michael on 07/29/20 SUBJECT: RESULTS OF PERIODIC REVIEW OF REGULATORY GUIDE 1.143, REVISION 2 DATED: DISTRIBUTION: Michael Franovich, NRR Greg Bowman, NRR Kevin Hsueh, NRR Edward Stutzcage, NRR Edward O’Donnell, RES ADAMS Accession No.: ML20190A131 NRR-106 OFFICE NRR/DRA/ARCB NRR/DRA/ARCB: BC NRR/DRA: D NAME EStutzcage KHsueh MFranovich /RA/ G.Bowman for DATE 7/21/2020 7/29/2020 7/29/2020 OFFICIAL RECORD COPY REGULATORY GUIDE PERIODIC REVIEW Regulatory Guide Number: 1.143, Revision 2 Title: Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light- Water-Cooled Nuclear Power Plants Office/Division/Branch: NRR/DRA/ARCB Technical Lead: Edward Stutzcage Staff Action Decided: Reviewed with issues identified for future consideration What are the known technical or regulatory issues with the current version of the 1. RG? RG 1.143, Rev. 2, was issued in November 2001 as part of an effort to update guidance on radioactive waste treatment and processing structures, systems, and components (SSCs). The revision addressed the design, construction, testing, and quality assurance guidance for these SSCs. Rev. 2 allows flexibility in the design requirements for these SSCs based on the potential radiological hazards associated with the SSCs (i.e., SSCs posing a lower radiological hazard can be less robust than SSCs posing a larger radiological hazard). The threshold for buildings is based on an unmitigated exposure for site personnel inside the protected area (i.e., worker dose) of 5 rem and an unmitigated release at the protected area boundary (public dose) of 500 mrem. However, the 500 mrem value is based the previous public dose limit from 10 CFR 20, which was changed to 100 mrem in the 1990s. This change should be addressed in a future update to the RG. In addition, there are other items that should be addressed in the future revision to RG