Document: NRC Regulatory Guide
Document ID: cf1737d6-2a8a-4765-aaf5-f5f2a617ef91
Document Type: regulatory_guide
Title: Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740263.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.96
CFR Part: 
CFR Title: 

Content:
ntrol system should permit the conduct of inservice examina tions required by the rules of Section XI of the ASME Boiler and Pressure Vessel Code, and the extent of examinations during each inspection interval should provide 100 percent volumetric examination of the piping welds within this portion of piping. 1.96-5