Document: NUREG-0800
Document ID: 6237521d-c825-4ed6-8fb7-7b3b8019a3fc
Document Type: srp
Title: SYSTEM QUALITY GROUP CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070297.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.2
CFR Part: 
CFR Title: 

Content:
, General Design Criterion 1 and 10 CFR Part 50, §50.55a, as they relate to the requirement that structures, systems, and components important to safety shall being designed, fabricated, erected, and tested to quality standards 23 commensurate with the importance of the safety function to be performed. To meet the requirements of General Design Criterion 1 and 10 CFR Part 50, §50.55a, the following regulatory guide is used: Regulatory Guide 1.26, "Quality Group Classification and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." This guide describes an 24 acceptable method for determining quality standards for Quality Group B, C, and D water- and steam-containing components important to safety of water-cooled nuclear power plants. Technical Rationale25 The technical rationale for application of the above acceptance criteria to the review of system quality group classification is discussed in the following paragraph: GDC 1 and 10 CFR 50.55a require that systems and components be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. 10 CFR 50.55a also incorporates by reference the applicable editions and addenda of the ASME Boiler and Pressure Vessel Code. Regulatory Guide 1.26 establishes an acceptable method for complying with these requirements by classifying fluid systems and components important to safety and applying corresponding quality codes and standards to such systems and components. Fluid systems important to safety may perform any of the following functions: fission product containment, core cooling, reactor shutdown, reactivity control, post-accident DRAFT Rev. 2 - April 1996 3.2.2-4 containment heat removal, post-accident containment atmosphere cleanup, post-accident fission product removal, residual heat removal from the reactor and/or from the spent fuel storage pool, and containment of