Document: 10 CFR Part 52
Document ID: fd69617e-7b5c-49e2-90ee-815727c55e10
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-52.137
Revision Date: 
Chapter: 
Section ID: 52.137
CFR Part: 52
CFR Title: 10

Content:
d 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; ( 3 ) The design of the facility including: ( i ) The principal design criteria for the facility. Appendix A to 10 CFR part 50, general design criteria (GDC), establishes minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have previously been issued by the Commission and provides guidance to applicants in establishing principal design criteria for other types of nuclear power units; ( ii ) The design bases and the relation of the design bases to the principal design criteria; and ( iii ) Information relative to materials of construction, general arrangement, and approximate dimensions, sufficient to provide reasonable assurance that the design will conform to the design bases with adequate margin for safety; ( 4 ) An analysis and evaluation of the design and performance of SSC 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 SSCs 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 10 CFR 50.46 and 50.46a ; ( 5 ) 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 ;