Document: NUREG-0800
Document ID: 2ebe86ae-db20-4a1e-a55b-ccc9f5acefd0
Document Type: srp
Title: - 15.3.4-10
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
100 guidelines regarding radiological dose at the site boundary. This conclusion is based upon the following: 1. The applicant has demonstrated that the resultant fuel damage was limited such that the ability to insert control rods would be maintained, and that no loss of core cooling capability resulted. The minimum departure from nucleate boiling ratio (DNBR) or critical power ratio (CPR) experienced by any fuel rod was _____, resulting in ____% of the rods experiencing cladding perforation. 2. The applicant met the requirements of GDC 31 with respect to demonstrating the integrity of the primary system boundary to withstand the postulated accident. 3. The analyses and effects of pump rotor seizure and shaft breaks, during various modes of operation and with and without offsite power, have been reviewed. 4. The accidents analyzed were evaluated using a mathematical model that has been previously reviewed and found acceptable by the staff. 5. The parameters used as input to this model were reviewed and found to be suitably conservative. 6. The radioactivity release has been evaluated using the computer code SARA and a conservative description of the plant response to the accident. A decontamination factor of _____ between the water and steam phases and a X/Q value of _____ sec/m3 has