Document: NRC Regulatory Guide
Document ID: c94378e6-d5f2-4911-8d1d-2a16783d9866
Document Type: regulatory_guide
Title: Installation of Overpressure Protection Devices
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1306/ML13064A109.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.67
CFR Part: 
CFR Title: 

Content:
"5 ":1 5,' October 1973 U.S. ATOMIC ENERGY COMMISSION DREGULATO RY DIRECTORATE OF REGULATORY STANDARDS GUIDES REGULATORY GUIDE 1.67 INSTALLATION OF OVERPRESSURE PROTECTION DEVICES A. INTRODUCTION General Design Criterion I, "Quality Standards and Records," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," reauires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. This Regulatory Guide describes a method acceptable to the AEC Regulatory stalT for implementing Ihis criterion with regard to the design of piping for safety valve and relief valve stations which have open discharge systems with limited discharge pipes and which have inlet piping that neither contains a water seal nor is subject to slug flow of water upon discharge of the valves. This guide applies to light-water-cooled reactors. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position. B. DISCUSSION Pressure relief valves are required to be installed on the reactor coolant system pressure boundary of nuclear power plants to provide overpressure protection. Failure of the valve or piping to the valve, however, can constitute the equivalent of an open-ended rupture of the piping. The Working Group on Piping of the ASME Boiler and Pressure Vessel Code, Section III,' has developed a ('ode Case which includes requirements and guidance for the design of piping for pressure relief valve stations. This Case was approved on March 3, 1973, as Case 1569, Interpretations of the ASME Boiler and Pressure Vessel Code. ' American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, "'Nuclear Power Plant Components," hereinafter referred to as the Code. For those pressure relief valve