Document: NUREG-0800
Document ID: 8238d583-b5fc-4a78-9cf3-4407f130bbbd
Document Type: srp
Title: SYSTEM QUALITY GROUP CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190003.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.2
CFR Part: 
CFR Title: 

Content:
1.26 for the quality group classification of components of fluid systems important to safety. REFERENCES 1. Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant-Accident." 2. Regulatory Guide 1.11, "Instrument Lines Penetrating Primary Reactor Containment." 3. Regulatory Guide 1.26, "Quality Group Classification and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." 4. Regulatory Guide 1.72, "Spray Pond Piping Made from Fiberglass- Reinforced Thermosetting Resin." 5. Regulatory Guide 1.96, "Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants." 6. Regulatory Guide 1.137, "Fuel Oil Systems for Standby Diesel Generators." 7. Regulatory Guide 1.141, "Containment Isolation Provisions for Fluid Systems." 8. Regulatory Guide 1.143, "Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants." 9. Regulatory Guide 1.151, "Instrument Sensing Lines." 10. Branch Technical Position 6-3, "Determination of Bypass Leakage Paths in Dual Containment Plants." 11. NRC Letter to All Pressurized Water Reactor Licensees and Construction Permit Holders, "Resolution of Generic Issue 70, "Power-Operated Relief-Valve and Block Valve Reliability," and Generic Issue 94, "Additional Low-Temperature Overpressure Protection for Light-Water Reactors," (NRC Generic Letter No. 90-06)," June 25, 1990. 12. NRC Memorandum from E. S. Beckjord for F. P. Gillespie, "Resolutions of Generic Issue 70, "Power Operated Relief Valve and Block Valve Reliability," and Generic Issue 94, "Additional Low-Temperature Overpressure Protection for Light Water Reactors,"" November 16, 1989. 13. Boiler and Pressure Vessel Code, "Section III, Nuclear Power Plant Components," and "Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components," American Society of Mechanical