Document: NUREG-0800
Document ID: 34798f4a-fe75-475a-b41f-ffb023158358
Document Type: srp
Title: 2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070367.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2.15
CFR Part: 
CFR Title: 

Content:
, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP Section.47 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 48 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. 3.9.5-9 DRAFT Rev. 3 - April 1996 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.49 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulations.50 VI. REFERENCES51 1. 10 CFR Part 50, §50.55a, "Codes and Standards."52 12. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 23. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Basies for 53 Protection Against Natural Phenomena." 34. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and MissileDynamic Effects Design Bases." 54 45. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 6. NUREG-0609; "Asymmetric Blowdown Loads on PWR Primary Systems: Resolution of Generic Task Action Plan A-2;" Hosford, S.B.; Mattu, R.; Meyer, R.O.; Division of Safety Technology; January, 1981.55 57. ASME Boiler and Pressure Vessel Code, Section III, Division 1, "Nuclear Power Plant Components," American Society of Mechanical Engineers. 6. Standard Review Plan Section 3.9.2, "Dynamic Testing and Analysis of Systems, Components,