Document: NUREG-0800
Document ID: 228b9b6e-c81e-4d76-9b8e-12f6c3bd7fa1
Document Type: srp
Title: and Regulatory Guide 1.92,(Reference 10) "Combining Modal Responses
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070336.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.2
CFR Part: 
CFR Title: 

Content:
is seismic and dynamic loads, in combination with other environmental loads and natural phenomena loads, without leakage, rapidly propagating failure, or gross rupture. Meeting the requirements of GDC 14 provides assurance that the reactor coolant pressure boundary will remain intact, thus preventing the spread of radioactive contamination.53 (5) Compliance with GDC 15 requires that the reactor coolant system be designed with sufficient margin to ensure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences. Staff positions are described in SRP Section 3.9.2 for design of the reactor coolant pressure boundary to resist seismic, LOCA, and other appropriate environmental loads, individually and in combination. Dynamic analyses are described to confirm the structural design adequacy of the reactor coolant pressure boundary. Vibration, thermal expansion, and dynamic effects testing is also described to verify the design. Meeting the requirements of GDC 15 provides assurance that the reactor coolant pressure boundary will remain intact, thus preventing the spread of radioactive contamination.54 DRAFT Rev. 3 - April 1996 3.9.2-20 III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case. General Design Criteria 1, 2, 4, 14, and 15 state that all structures, system and components important to safety should be designed and tested to assureensure that safety functions can be performed in the event of operational transients, earthquakes, and LOCA loadings. For new applications, test specifications should be in accordance with ASME OM-S/G-1990, "Standards and Guides For Operation of Nuclear Power Plants," Part 3, "Requirements for Preoperational and Initial Start-Up Vibration Testing of Nuclear Power Plant Piping Systems," and Part 7, "Requirements for Thermal