Document: NUREG-0800
Document ID: d0a29cc6-24fb-443d-8b43-655916964d83
Document Type: srp
Title: REACTOR WATER CLEANUP SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340638.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.8
CFR Part: 
CFR Title: 

Content:
the portion of the RWCS extending from the reactor vessel and recirculation loops to the outermost primary containment isolation valves to seismic Category I. 3. The applicant has met the requirements of General Design Criterion 14 by meeting the positions of Regulatory Guide 1.56 in maintaining reactor water purity and material compatibility to reduce corrosion probabilities, and thus reducing the prob- ability of reactor coolant pressure boundary failure. 4. The applicant has met the requirements of General Design Criteria 60 and 61 by designing a system containing radio- activity with confinement, by venting and collecting drainage from the RWCS components through closed systems. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using the 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 conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." 2. Regulatory Guide 1.29, "Seismic Design Classification." 3. Regulatory Guide 1.56, "Maintenance of Water Purity in Boiling Water Reactors." 4. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 5. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 6. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 5.4.8-7 Rev. 2 - July 1981 7. 10 CFR Part 50, Appendix A, General Design Criterion 60, "Control of Releases of Radioactive