Document: NUREG-0800
Document ID: ff5838f8-986a-4d8b-a039-fb26df280426
Document Type: srp
Title: – 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070725.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
NTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using 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 70 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.71 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 2. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant System Design." 3. 10 CFR Part 50, Appendix A, General Design Criterion 17, "Electric Power Systems."72 4. 10 CFR Part 50, Appendix A, General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 5. Regulatory Guide 1.53, "Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems."73 15.5.1-11 DRAFT Rev. 2 - April 1996 61. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 7. Regulatory Guide 1.105, "Instrument Setpoints for Safety-Related Systems."74 8. NUREG-1503, "Final Safety Evaluation Report (FSER) Related to the Certification of the Advanced Boiling Water Reactor (ABWR) Design." July 1994.75 9. NUREG-1503, "Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design." July 1994. Section 15.2, "Trip of All Reactor Internal Pumps and Pressure Regulator Down-Scale Failure."76 10. NUREG-1462,