Document: NUREG-0800
Document ID: 48fcca4d-4efe-4600-b4ca-9911efb87843
Document Type: srp
Title: and 5.2.1.2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070446.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.1.1
CFR Part: 
CFR Title: 

Content:
egulatory guides constitute an acceptable basis for meeting in part the requirements of General Design Criteria 1, 14, 15, and 31, and Appendix B, 10 CFR Part 50. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.53 V. IMPLEMENTATION 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 54 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.55 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criteriaon 1, "Quality Standards and 56 Records.," 57 2. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure 58 Boundary.," 3. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant System Design.," and 4. 10 CFR Part 50, Appendix A, General Design Criterion 31, "Fracture Prevention of the Reactor Coolant Pressure Boundary." 5.4.2.1-13 DRAFT Rev. 3 - April 1996 58. Appendix B, 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants