Document: NUREG-0800
Document ID: 3b714304-f91e-4999-917a-7d27866735e3
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350117.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
y fuel rod was _ resulting in __% of the rods experiencing cladding performatlon. (b) 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. (c) The applicant has met the requirements.of GDC 35 with respect to demonstrating the adequacy of the emergency cooling systems to 15.1.5-7 Rev. 2 - July 1981 provide abundant core cooling and reactivity control (via boron injection). (d) The analyses and effects of steam line break accidents inside and outside containment, during various modes of operation with and without offsite power, have been reviewed and 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/mP 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 guide-lines. 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 has met the requirements of Task 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 steam system piping failures. (h) The applicant has met the requirements of Task 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.