Document: NUREG-0800
Document ID: b6b57a00-5b85-4f0c-965c-ca89ef4265e7
Document Type: srp
Title: DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16088A041.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2
CFR Part: 
CFR Title: 

Content:
ceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC regulations identified above are as follows for review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. With respect to meeting the relevant requirements of GDC 4: 1. Postulated Pipe Rupture Locations Inside Containment. Acceptable criteria to identify postulated pipe rupture locations and configurations inside containment are specified in Branch Technical position (BTP) 3-4, “Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment.” 2. Postulated Pipe Rupture Locations Outside Containment. Acceptable criteria to identify postulated rupture locations and plant layout considerations for protection against postulated pipe ruptures outside containment are specified in BTP 3-4. 3.6.2-5 Revision 3 – December 2016 3. Methods of Analysis. Detailed acceptance criteria covering pipe-whip dynamic analysis, including determination of the forcing functions of jet thrust and jet impingement, are included in Subsection III, “Review Procedures,” of this SRP section. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. Compliance with GDC 4 requires that nuclear power plant SSCs important to safety be designed to accommodate the effects of, and be compatible with, the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant