Document: NRC Regulatory Guide
Document ID: 60ac4a53-3f72-4e92-9ad2-39c736cf2135
Document Type: regulatory_guide
Title: Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003739979.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.148
CFR Part: 
CFR Title: 

Content:
U.S. NUCLEAR REGULATORY COMMISSION ivarcn i198 ,,REGULATORY GUIDE OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1.148 (Task SC 704-5) FUNCTIONAL SPECIFICATION FOR ACTIVE VALVE ASSEMBLIES IN SYSTEMS IMPORTANT TO SAFETY IN NUCLEAR POWER PLANTS A. INTRODUCTION Criterion 1, "Quality Standards and Records," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Produc tion and Utilization Facilities," requires, in part, that components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Section III, "Design Control," of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 requires, in part, that measures be established to ensure that regulatory requirements and the design basis for applicable struc tures, systems, and components are correctly translated into specifications, drawings, procedures, and instructions. This guide delineates a procedure acceptable to the NRC staff for implementing the Commission's regulations with respect to the detailed specification of information pertinent to defining operating requirements for valve assemblies whose safety-related function is to open, close, or regulate fluid flow in light-water-cooled nuclear power plants. This guide will be applied to active valve assemblies in systems important to safety in light-water-cooled nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position. B. DISCUSSION The rules for construction of nuclear components given in Section III, "Nuclear Power Plant Components," of the ASME Boiler and Pressure Vessel Code 2 (the Code) do not, as indicated in NCA-2142(b) of the 1977 Edition, IAs identified in accordance with Section 3.9.3.2 of Regulatory Guide 1.70, Revision 3, "Standard Format and