Document: NUREG-0800
Document ID: ecb92ac6-97df-4e4b-a20a-81638c2d573b
Document Type: srp
Title: - 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350157.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
ritical power ratio (CPR) experienced by any fuel rod was , resulting in % of the rods experiencing cladding perforation. (b) The applicant met the requirements of GDC 31 with respect to demonstrating the integrity of the primary system boundary to withstand the postulated accident. (c) 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. (d) The accidents analyzed were evaluated using a mathematical model that has been previously reviewed and found acceptable by the staff. (e) The parameters used as input to this model were reviewed and found to be suitably conservative. (f) 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 been used in our evaluation of radiological consequences.-Tie calculated doses are presented in Table . Technical specification limits on primary and secondary coolant activities will limit potential doses to a small fraction of the 10 CFR Part 100 exposure guidelines. The potential doses are within 10 CFR Part 100 exposure guidelines even if the accident should occur coincident with an iodine spike. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposed an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance .with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the rpfprenced NUREGs. 15.3.3-6 Rev. 2 - July 1981 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 27, "Combined Reactivity