Document: NUREG-0800
Document ID: 5c84a1c2-9405-4849-8c5f-415a0bb66a22
Document Type: srp
Title: in connection with reactor internals.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070337.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
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.98 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 99 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. The positions stated in Section C.1.1, 4th and 100 5th paragraphs of Appendix A to this SRP section to address stress and fatigue evaluation/analyses for ASME Code Class piping (including susceptible Class 2 and 3 piping) subject to thermal stratification, oscillation, striping, etc. apply to new applications only.101 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and, NUREGs, and Bulletins . 102 3.9.3-17 DRAFT Rev. 2 - April 1996 VI. REFERENCES 1. 10 CFR Part 50, 50.55a, "Codes and Standards." 2. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants": 103 (a) General Design Criterion 1, "Quality Standards and Records"; (b) General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena"; (c) General Design Criterion 4,