Document: 10 CFR Part 52
Document ID: 3ab5015e-d63f-44de-9ba7-180a7b64b644
Document Type: cfr
Title: Contents of applications; technical information.
Source: 10 CFR Part 52
Source URL: https://www.ecfr.gov/current/title-10/part-52/section-52.17
Revision Date: 
Chapter: 
Section ID: 52.17
CFR Part: 52
CFR Title: 10

Content:
section. In performing this assessment, an applicant shall assume a fission product release [ 1 ] from the core into the containment assuming that the facility is operated at the ultimate power level contemplated. The applicant shall perform an evaluation and analysis of the postulated fission product release, using the expected demonstrable containment leak rate and any fission product cleanup systems intended to mitigate the consequences of the accidents, together with applicable site characteristics, including site meteorology, to evaluate the offsite radiological consequences. Site characteristics must comply with part 100 of this chapter . The evaluation must determine that: ( A ) An individual located at any point on the boundary of the exclusion area for any 2 hour period following the onset of the postulated fission product release, would not receive a radiation dose in excess of 25 rem [ 2 ] total effective dose equivalent (TEDE). ( B ) An individual located at any point on the outer boundary of the low population zone, who is exposed to the radioactive cloud resulting from the postulated fission product release (during the entire period of its passage) would not receive a radiation dose in excess of 25 rem TEDE; ( x ) Information demonstrating that site characteristics are such that adequate security plans and measures can be developed; ( xi ) For applications submitted after September 27, 2007, a description of the quality assurance program applied to site-related activities for the future design, fabrication, construction, and testing of the structures, systems, and components of a facility or facilities that may be constructed on the site. Appendix B to 10 CFR part 50 sets forth the requirements for quality assurance programs for nuclear power plants. The description of the quality assurance program for a nuclear power plant site shall include a discussion of how the applicable requirements of appendix B to part 50 of this chapter will be satisfied;