Document: NUREG-0800
Document ID: 4bd45d7d-29f4-4741-af71-92f8172245e1
Document Type: srp
Title: SOLID WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710397.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.4
CFR Part: 
CFR Title: 

Content:
The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 11.4-9 Revision 3 - March 2007 1. 10 CFR 20.1302 requires that surveys of radiation levels in unrestricted areas be performed to demonstrate system compliance with the 10 CFR 20.1301 dose limits to individual members of the public. 10 CFR 20.1302 identifies two approaches, either of which can demonstrate compliance with the 10 CFR 20.1301 dose limits. One of these approaches requires the following: A. Demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents at the boundary of the unrestricted area do not exceed the specified in Table 2 of Appendix B to 10 CFR Part 20; and B. Demonstrate that the annual and hourly doses from external sources to an individual continuously present in an unrestricted area will not exceed 0.5 millisievert (mSv) (0.05 rem) and 0.02 mSv (0.002 rem), respectively. Meeting the above requirements provides assurance that the 10 CFR 20.1301dose limits to individual members of the public will not be exceeded. The review in this SRP section will include an evaluation of whether the above-identified dose requirements are met. Meeting the requirements on gaseous and liquid effluent concentration limits in unrestricted areas from all plant sources of radioactivity (including that associated with the operation of the SWMS) is identified as an acceptance criterion in SRP Sections 11.2 and 11.3 and will be evaluated in those SRP sections as well. 2. Meeting the requirements of 10 CFR 50.34a, as it relates to adequate design information on the SWMS, provides a level of assurance that the SWMS will have the necessary equipment and design features to control radioactive effluent releases to the environment resulting from its operation, in accordance with the requirements of 10 CFR 20.1302, Appendix I to 10 CFR Part 50, and GDC 60 and