Document: NUREG-0800
Document ID: ed948426-dd77-4047-be5e-2b7ab22de3f5
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAK INSIDE AND OUTSIDE CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550009.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
trating that all credited instrumentation was available, and that actuations of protection systems, automatic and manual, occurred at values of monitored parameters that were within the instruments’ prescribed operating ranges. 2. The applicant meets GDCs 27 and 28 requirements by demonstrating minimal fuel damage, maintained ability to insert the control rod, and no loss of core cooling capability. The minimum DNBR for any fuel rod was _______ with the result of __ percent of the rods experiencing clad perforation. 3. The applicant meets GDC 31 requirements for demonstrating primary system boundary capability to withstand the postulated accident. 4. The applicant meets GDC 35 requirements for demonstrating emergency cooling system adequacy for abundant core cooling and reactivity control (via boron injection). 15.2.8-12 Revision 2 - March 2007 5. The analyses of effects of feedwater line break accidents inside and outside containment during various modes of operation with and without offsite power have been reviewed and evaluated by a mathematical model previously reviewed and found acceptable by the staff. 6. The input parameters for this model were reviewed and found suitably conservative. 7. The radioactivity release description has been evaluated by the computer code SARA for a conservative description of the plant response to the accident. We use a decontamination factor of ______ between the water and steam phases and a X/Q value of ______ sec/m3 in our evaluation of radiological consequences. The calculated doses are presented in Table _____. Technical specification limits on primary and secondary coolant activities limit potential doses to small fractions of the 10 CFR Part 100 exposure guidelines. The potential doses are within 10 CFR Part 100 exposure guidelines even if the accident occurs with an iodine spike. 8. The applicant meets 10 CFR 50.34(f)(1)(ii) and 10 CFR 50.34(f)(2)(xii) requirements for demonstrating the adequacy of the auxiliary feedwater