Document: NUREG-0800
Document ID: a416cfea-d766-4e80-9d15-6ac4918475fa
Document Type: srp
Title: REACTOR COOLANT SYSTEM COMPONENT AND SUBSYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070610167.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4
CFR Part: 
CFR Title: 

Content:
ions 7.1, “Instrumentation and Controls - Introduction,” and Section 7.6, “Interlock Systems Important to Safety,” and Branch Technical Positions in SRP Appendix 7-A. 9. Reactor Coolant System Pressure Relief Devices / Reactor Coolant Depressurization Systems A. The organization responsible for review of reactor thermal-hydraulic systems in BWRs reviews setpoints and capacities of RCS safety and relief valves, and low- temperature overpressure protection systems / cold overpressure mitigation systems under SRP Section 5.2.2. B. The organization responsible for mechanical engineering reviews evaluates the structural integrity and methods of analysis of RCS pressure relief devices / reactor coolant depressurization systems under SRP Sections 3.9.1, 3.9.2, and 3.9.3. C. The organization responsible for the review of component performance and testing reviews the functional design and qualification provisions and IST programs for RCS pressure relief devices / reactor coolant depressurization systems typically designated as Class 1, 2, or 3 under Section III of the ASME Code under SRP Section 3.9.6. D. The organization responsible for mechanical engineering reviews (primary reviewer), and the organization responsible for reviews of electrical engineering and instrumentation and controls (secondary reviewer), assess the methods of test and analysis used to ensure the operability of safety and relief valves and associated electrical equipment, and instrumentation and controls, under the full range of normal and accident loadings (including seismic). These assessments are conducted under SRP Section 3.10. 5.4-9 Revision 2 - March 2007 E. The organization responsible for the review of component integrity issues related to reactor coolant pressure boundary (primary reviewer), and the organization responsible for the review of component integrity issues related to reactor vessels (secondary reviewer), evaluate the inservice inspection of ASME Code Class 1 RCS pressure