Document: NUREG-0800
Document ID: 62485d6f-6b2a-4360-acb5-f874d2adc406
Document Type: srp
Title: PIPING SYSTEMS AND COMPONENTS - INSPECTIONS, TESTS,
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1808/ML18088A069.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.3
CFR Part: 
CFR Title: 

Content:
ses, and Acceptance Criteria.” 2. The adequacy of the approach to classify fluid systems important to safety and identify their applicable construction codes and standards depending on the system or component function and relative importance to safety is determined in accordance with SRP Section 3.2.2, “System Quality Group Classification.” 3. The confirmation that there is appropriate protection of structures, systems, and components (SSCs) relied upon for safe reactor shutdown or to mitigate the consequences of a postulated pipe rupture is performed under SRP Section 3.6.2, “Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping.” 4. The criteria, testing procedures, and dynamic analyses employed to ensure the structural and functional integrity of piping systems, mechanical equipment, reactor internals, and their supports (including supports for conduit and cable trays, and ventilation ducts) under vibratory loadings are reviewed under SRP Section 3.9.2, “Dynamic Testing and Analysis of Systems, Structures, and Components.” The vibratory loadings consider in this review include those due to fluid flow (and especially loading caused by adverse flow conditions, such as flow instabilities over standoff pipes and branch lines in the steam system) and postulated seismic events. 5. The structural integrity of pressure-retaining components, their supports, and core support structures that are designed in accordance with the rules of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel (BPV) Code and Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production And Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” are reviewed under SRP Section 3.9.3, “ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures.” 6. The review of the functional design, qualification, and