Document: NUREG-0800
Document ID: 63f62189-691f-402d-9ac9-41fb60ec2261
Document Type: srp
Title: DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1423/ML14230A035.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2
CFR Part: 
CFR Title: 

Content:
t arrangement and applicable design considerations for high- and moderate-energy fluid systems inside and outside of containment, including the RCPB, provide adequate assurance that the safety-related or risk significant SSCs that are in close proximity to the postulated pipe rupture will be appropriately protected. The proposed design appropriately mitigates the consequences of pipe ruptures so that the reactor can be safely shut down and maintained in a safe shutdown condition in the event of a postulated rupture of a high- or moderate-energy piping system inside or outside of containment. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. 3.6.2-13 Draft Revision 3 – August 2015 In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications, COL applications, and license applications submitted by applicants pursuant to 10 CFR Part 50, or 10 CFR Part 52. The staff will use the method described herein to evaluate conformance with Commission regulations. NRC regulations state, in part, that the DC, COL, or ESP application must contain an evaluation (of the design, facility, or site, respectively) against the Standard Review Plan (SRP) revision in effect 6 months before the docket date of the application. The content of this SRP section has been accepted as an alternative method for complying with those regulations (10 CFR 52.47(a)(9), 10 CFR 52.79(a)(41), or 10 CFR 52.17(a)(1)(xii), as applicable) as long as the DCD/FSAR does not deviate significantly from the design/facility/site assumptions made by the NRC staff while preparing this SRP section. The plants for