Document: NUREG-0800
Document ID: 228b9b6e-c81e-4d76-9b8e-12f6c3bd7fa1
Document Type: srp
Title: and Regulatory Guide 1.92,(Reference 10) "Combining Modal Responses
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070336.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.2
CFR Part: 
CFR Title: 

Content:
gn acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.68 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section.69 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. DRAFT Rev. 3 - April 1996 3.9.2-28 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. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 2. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 3. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and MissileDynamic Effects Design Bases." 72 4. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 5. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant System Design." 6. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," American Society of Mechanical Engineers. 7. Regulatory Guide 1.20, "Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing." 8. Regulatory Guide 1.68, "Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors." 9. Regulatory Guide 1.61, "Damping Values