Document: NUREG-0800
Document ID: 7ed8e5d3-fcfd-49cc-84ad-3b25caba06af
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550006.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
ed by any fuel rod was _________, resulting in __% of the rods experiencing cladding perforation. C. The applicant has met the requirements of GDC 31 with respect to demonstrating the integrity of the primary system boundary to withstand the postulated accident. 15.1.5-12 Revision 3 - March 2007 D. The applicant has met the requirements of GDC 35 with respect to demonstrating the adequacy of the emergency cooling systems to provide abundant core cooling and reactivity control (via boron injection). E. The analyses and effects of steam line break accidents inside and outside containment, during various modes of operation with and without offsite power (as required by GDC 17), have been reviewed and were evaluated using a mathematical model that has been previously reviewed and found acceptable by the staff. F. The parameters used as input to this model were reviewed and found to be suitably conservative. G. 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 χ/Q value of _____ sec/m3 has been used in our evaluation of radiological consequences. The 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. H. The applicant has met the requirements of 10 CFR 50.34(f)(1)(ii) and 10 CFR 50.34(f)(2)(xii) with respect to demonstrating the adequacy of the design of auxiliary feedwater or other qualified systems to remove decay heat following steam system piping failures. I. The applicant has met the requirements of 10 CFR 50.34(f)(1)(iii) with respect to demonstrating the integrity and operation of the reactor coolant pumps