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:
or coolant system, instrumentation and control systems, electrical systems, containment system, other engineered safety features, auxiliary and emergency systems, power conversion systems, radioactive waste handling systems, and fuel handling systems shall be discussed insofar as they are pertinent. The following power reactor design characteristics will be taken into consideration by the Commission: ( 1 ) Intended use of the manufactured reactor including the proposed maximum power level and the nature and inventory of contained radioactive materials; ( 2 ) The extent to which generally accepted engineering standards are applied to the design of the reactor; and ( 3 ) The extent to which the reactor incorporates unique, unusual or enhanced safety features having a significant bearing on the probability or consequences of accidental release of radioactive materials; ( d ) The safety features that are engineered into the reactor and those barriers that must be breached as a result of an accident before a release of radioactive material to the environment can occur. Special attention must be directed to reactor design features intended to mitigate the radiological consequences of accidents. In performing this assessment, an applicant shall assume a fission product release [ 11 ] 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 postulated site parameters, including site meteorology, to evaluate the offsite radiological consequences. The evaluation 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