Document: NUREG-0800
Document ID: 2f527583-f167-477c-9a93-bc8f7db676b6
Document Type: srp
Title: for the LWMS and GWMS, respectively.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1307/ML13072A545.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
normal operation and AOOs. The RG 1.143 describes design guidance acceptable to the NRC staff related to seismic, safety, and quality group classifications and QA provisions for the systems and skid- mounted processing equipment, structures, and components of the SWMS for liquid, wet and solid wastes produced during normal operation and AOOs. The RG 1.143 provides guidance in assigning safety classifications to structures and radioactive waste management systems in protecting SSCs against natural phenomena and man-induced hazards. For unmitigated releases of radioactive materials, the acceptance criterion of RG 1.143 is 1 mSv (100 mrem) for members of the public assumed to be located at or beyond the restricted area or in unrestricted areas (whichever is most limiting). For unmitigated radiation exposures to site personnel, the acceptance criterion is 5 rem (50 mSv) for a plant worker assumed to be located in the restricted area. In classifying system components, the radioactivity inventories of components are compared to the acceptance criteria in determining the appropriate safety classification. In addition, RG 1.206, Part I, C.I.3, Sections 3.2.1 and 3.2.2 and SRP Section 3.8.4 identify applicable acceptance criteria in evaluating SSCs requiring seismic design considerations and discuss differences from the guidance of RG 1.143. 19. Operational Programs. For COL reviews, the description of the operational program and proposed implementation milestone for the PCP, as part of the process and effluent monitoring and sampling program, are reviewed in accordance with 10 CFR 20.1301, 10 CFR 20.1302, 10 CFR 50.34a, 10 CFR 50.36a, and 10 CFR Part 50, Appendix I, Sections II and IV. Its implementation is required by a license condition, as described in SRP Sections 13.4 and 13.5. The relevant RGs, ISG and BTP are as follows: 1. RG 1.109, as it relates to the use of acceptable methods for calculating annual doses to the maximally exposed individual in demonstrating