Document: NUREG-0800
Document ID: 577b52cf-90e2-467e-8165-a1ce02957947
Document Type: srp
Title: REACTOR WATER CLEANUP SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070438.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.8
CFR Part: 
CFR Title: 

Content:
ce criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.74 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using the SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in 75 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. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.76 DRAFT Rev. 3 - April 1996 5.4.8-12 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 20, "Standards for Protection Against Radiation."77 4.5. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and 78 Records." 5.6. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 6.7. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 7.8. 10 CFR Part 50, Appendix A, General Design Criterion 60, "Control of Releases of Radioactive Materials to the Environment." 8.9. 10 CFR Part 50, Appendix A, General Design Criterion 61, "Fuel Storage and Handling and