Document: NUREG-0800
Document ID: fa6f6a6f-6b58-4b9d-bff6-146879b1bdbf
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340605.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.5
CFR Part: 
CFR Title: 

Content:
the leakage could increase to a level beyond the capability of the makeup system to replenish the coolant loss. The staff concludes that the design of the RCPB leakage detection systems is acceptable and meets the requirements of General Design Criterion 2 with respect to the capability to maintain and perform their safety functions in the event of earthquakes, and General Design Criterion 30 with respect to the detection, identification and monitoring of the source of reactor coolant leakage. This conclusion is based on the following: 1. The applicant has met the requirements of General Design Cri- terion 2 with respect to the systems capability to maintain and perform their safety functions in the event of earthquakes by meeting regulatory positions C-1 and C-2 of Regulatory Guide 1.29, and 5.2.5-4 Rev. 1 - July 1981 2. The applicant has met the requirements of General Design Cri- terion 30 with respect to the detection, identification, and monitoring of the source of reactor coolant leakage by meeting regulatory positions C-1 through C-9 of Regulatory Guide 1.45. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alter- native 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 conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein as contained is the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, Criterion 2, "Design Basis for Protec- tion Against Natural Phenomena." 2. 10 CFR Part 50, Appendix A, Criterion 30, "Quality of Reactor Coolant Pressure Boundary." 3. Regulatory Guide 1.29, "Seismic Design Classification." 4. Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection