Document: NUREG-0800
Document ID: 42e7682f-df25-4a6a-94f4-7d44ea029702
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070677.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
ed 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 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. (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 10 CFR 50.34(f)(1)(ii) and 10 CFR 50.34(f)(2)(xii) with respect to demonstrating the adequacy of the auxiliary feedwater design to remove decay heat following steam system piping failures.65 (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 10 CFR 50.34(f)(1)(iii) with respect to demonstrating the integrity and operation of the reactor coolant pumps to withstand the postulated accident.66 (i) The applicant has met the requirements of Task 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. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.67 V. IMPLEMENTATION The following is intended to