Document: NUREG-0800
Document ID: 19023f05-18cc-4d01-bf98-d6ec2f98556a
Document Type: srp
Title: -9
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1233/ML12334A360.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.3
CFR Part: 
CFR Title: 

Content:
Draft Revision 3 – June 2013 should be fully evaluated and documented to demonstrate that normal plant operations and safety are not diminished. (v) Related Criteria for Snubber Functionality. SRP Section 3.9.3 addresses component support design, structural analysis, systems evaluation, material characteristics, design specifications, and use of additional snubbers during plant construction. As reviewed using SRP Section 3.9.6, the functional qualification of snubbers is performed in accordance with Section (QDR), “Qualification of Dynamic Restraints,” in ASME Standard (QME)-1-2007, “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants,” as accepted in Revision 3 to RG 1.100 (September 2009), “Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants.” The operational readiness of snubbers is verified in accordance with the preoperational examination and testing and inservice examination and testing provisions specified in Subsection ISTD, “Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants,” of the ASME Code for Operation and Maintenance of Nuclear Power Plants as incorporated by reference in 10 CFR 50.55a. 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. 10 CFR 50.55a requires, in part, that components and structures be designed, fabricated, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. Quality Group A, B, and C components must meet specific provisions of the Code. SRP Section 3.9.3 provides guidance for the staff's review of loading conditions, stresses, and stress limits for the subject components and structures. Loading conditions and