Document: 10 CFR Part 52
Document ID: e9c3b096-4c13-4284-8ed2-18c06d0500ef
Document Type: cfr
Title: Contents of applications; technical information in final safety analysis report.
Source: 10 CFR Part 52
Source URL: https://www.ecfr.gov/current/title-10/part-52/section-52.157
Revision Date: 
Chapter: 
Section ID: 52.157
CFR Part: 52
CFR Title: 10

Content:
valuation must determine that: ( 1 ) 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 [ 12 ] total effective dose equivalent (TEDE); ( 2 ) 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; and ( e ) The kinds and quantities of radioactive materials expected to be produced in the operation and the means for controlling and limiting radioactive effluents and radiation exposures within the limits set forth in part 20 of this chapter . ( f ) Information necessary to establish that the design of the reactor to be manufactured complies with the technical requirements in 10 CFR Chapter I , including: ( 1 ) An analysis and evaluation of the design and performance of structures, systems, and components with the objective of assessing the risk to public health and safety resulting from operation of the facility and including determination of the margins of safety during normal operations and transient conditions anticipated during the life of the facility, and the adequacy of structures, systems, and components provided for the prevention of accidents and the mitigation of the consequences of accidents. Analysis and evaluation of ECCS cooling performance and the need for high-point vents following postulated loss-of-coolant accidents shall be performed in accordance with the requirements of §§ 50.46 and 50.46a of this chapter ; ( 2 ) A description and analysis of the fire protection design features for the reactor necessary to comply with 10 CFR part 50, appendix A , GDC 3 and § 50.48 of this chapter ; ( 3 ) A description of protection provided against pressurized thermal shock