Document: NUREG-0800
Document ID: 28c03fd2-3542-41ec-bfd7-5df2087c4ee6
Document Type: srp
Title: FUEL SYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070407.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.2
CFR Part: 
CFR Title: 

Content:
sing this 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 those 86 cases in which the applicant roposes 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.87 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. 4.2-19 DRAFT Rev. 3 - April 1996 VI. REFERENCES88 13. 10 CFR Part §50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors." 22. 10 CFR Part 100, "Reactor Site Criteria." 31. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants."General Design Criterion 10, "Reactor Design."89 4. 10 CFR Part 50, Appendix A, General Design Criterion 27, "Combined Reactivity Control Systems Capability." 5. 10 CFR Part 50, Appendix A, General Design Criterion 35, "Emergency Core Cooling." 69. 10 CFR Part 50, Appendix K, "ECCS Evaluation Models." 728. Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors." 829. Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of Loss-of-Coolant Accident for Pressurized Water Reactors." 930. Regulatory Guide 1.25, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors." 1041. Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants." 116.