Document: NUREG-0800
Document ID: 22884f18-189e-46a8-81b2-45db11edf145
Document Type: srp
Title: SYSTEM QUALITY GROUP CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1422/ML14227A641.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.2
CFR Part: 
CFR Title: 

Content:
s leakage will be considered on a case-by-case basis. e. RG 1.137, “Fuel Oil Systems for Standby Diesel Generators,” describes a method acceptable for complying with regulations regarding fuel-oil systems for standby diesel generators. The Regulatory Guide describes positions with 3.2.2-18 Draft Revision 3 – August 2015 respect to the design and fabrication of diesel fuel oil systems which are supplemental to those indicated by the Quality Group C classification including the application of additional standards. f. SRP Section 9.3.3 provides criteria used to determine the safety-related portions of the equipment and floor drainage system and indicates that the safety-related portions of the system should be verified to be classified Quality Group C or higher. g. Components of the reactor coolant system, including those comprising the RCPB, should be quality group classified accordingly. PORVs and associated components should be classified as safety-related where necessary to perform a safety-related function (e.g., mitigation of a design-basis steam generator tube rupture accident, low temperature overpressure protection of the reactor vessel, and/or plant cooldown as described in GL 90-06, “Resolution of Generic Issues 70, “PORV and Block Valve Reliability,” and Generic Issue 94, “Additional Low-Temperature Over Pressure Protection for PWRs”). As described in Reference 12, the safety-related classification should address redundant and diverse control systems designed to meet Seismic Category I criteria and those improvements that were imposed subsequent to the TMI-2 accident, such as criteria to be powered from Class 1E buses and to provide valve position indication in the control room. The PORVs and block valves should be included within a quality assurance program that is in compliance with 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” For PWR plants licensed before the revision