Document: NUREG-0800
Document ID: a20ea81d-33c2-4a0c-a3b4-216d45d6fccd
Document Type: srp
Title: FEEDWATER SYSTEM PIPE.BREAKS INSIDE AND OUTSIDE CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350148.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
g the adequacy of the emergency cooling systems to provide abundant core cooling and reactivity control (via boron injection). (d) The analyses and effects of feedwater line break accidents inside and outside containment, during various modes of operation and with and without offsite power, have been reviewed and 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. The calculated doses are presented in Table . Technical specification limits on primary and secondary coolant activities will limit potential doses to 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. (g) The applicant met the requirements of TMI Action Plan Items II.E.1, II.K.2.1, II.E.1.2, and II.K.2.8 with respect to demonstrating the adequacy of the auxiliary feedwater design to remove decay heat following feedwater piping failures. (h) The applicant met the requirements of TMI Action Plan Items II.K.2.16, II.K.3.25 and II.K.3.40 with respect to'demonstrating the integrity and operation of the reactor coolant pumps to withstand the postulated accident. (i) The applicant met-the requirements of TMI Action Plan Item II.K.3.5 with respect to the operation and tripping of the reactor coolant pumps. The assumptions used are conservative and consistent with the generic resolution.to Item II.K.3.5. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for