Document: NUREG-0800
Document ID: eb937958-fe7c-410a-91e3-63f04734878a
Document Type: srp
Title: MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (BMR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350465.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.7
CFR Part: 
CFR Title: 

Content:
quirements of General Design Criterion 2 since the design is in accordance with position C.1 of Regulatory Guide 1.29 and position C.1 of Regulatory Guide 1.96. 2. The applicant's design meets General Design Criterion 4 with regards to pipe breaks and missiles since the design meets positions C.2 and C.r4 of Regulatory Guide 1.96. 3. The applicant's design also meets the requirements of General Design Criterion 54 as related to leak detection, isolation, and performance testing for system piping penetrating containment. The bases for acceptance is that the design meets positions C.3 and C.5 through.C.12 of Regulatory Guide 1.96. 6.7-6 Rev. 2 - July 1981 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of compliance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 2. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases." 3. 10 CFR Part 50, Appendix A, General Design Criterion 54, "Piping Systems Penetrating Containment." 4. Regulatory Guide 1.29, "Seismic Design Classification." 5. Regulatory Guide 1.96, "Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants." 6.7-7 Rev. 2 - July 1981