Document: 10 CFR Part 52
Document ID: 9805c5dc-79e7-4f14-88c7-530acc92c17e
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-52.79
Revision Date: 
Chapter: 
Section ID: 52.79
CFR Part: 52
CFR Title: 10

Content:
with the manufacturing license, provided, however, that the final safety analysis report must either include or incorporate by reference the manufacturing license final safety analysis report and must contain, in addition to the information and analyses otherwise required, information sufficient to demonstrate that the site characteristics fall within the site parameters specified in the manufacturing license. In addition, the plant-specific PRA information must use the PRA information for the manufactured reactor and must be updated to account for site-specific design information and any design changes or departures. ( 2 ) The final safety analysis report must demonstrate that the interface requirements established for the design have been met. ( 3 ) The final safety analysis report must demonstrate that all terms and conditions that have been included in the manufacturing license, other than those imposed under § 50.36b , will be satisfied by the date of issuance of the combined license. Any terms or conditions of the manufacturing license that could not be met by the time of issuance of the combined license, must be set forth as terms or conditions of the combined license. ( f ) Each applicant for a combined license under this subpart shall protect Safeguards Information against unauthorized disclosure in accordance with the requirements in §§ 73.21 and 73.22 of this chapter , as applicable. [ 72 FR 49517 , Aug. 28, 2007, as amended at 73 FR 63571 , Oct. 24, 2008; 74 FR 13970 , Mar. 27, 2009; 74 FR 28147 , June 12, 2009; 76 FR 72600 , Nov. 23, 2011; 78 FR 34249 , June 7, 2013; 84 FR 63568 , Nov. 18, 2019; 88 FR 80078 , Nov. 16, 2023] Footnotes - 52.79 [ 5 ] The fission product release assumed for this evaluation should be based upon a major accident, hypothesized for purposes of site analysis or postulated from considerations of possible accidental events. These accidents have generally been assumed to result in substantial meltdown of the core with subsequent