Document: NUREG-0800
Document ID: 694a6d46-6a73-4dcf-afa8-2ea3a4a0181a
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340641.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
sign and service loadings, and combination of loadings as applied to the design of the reactor internals structures and components provide reasonable assurance that in the event of an earthquake or of a system transient during normal plant operation, the resulting deflections and associated stresses imposed on these structures and components would not exceed allowable stresses and deformation limits for the materials of construction. Limiting the stresses and deformations under such loading combinations provides an acceptable basis for the design of these structures and components to withstand the most adverse load- ing events which have been postulated to occur during service life- time without loss of structural Integrity or impairment of function. 3.9.5-4 Rev. 2 - July 1981 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alterna- tive method for complying with specified portions of the Conmission's regula- tions, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design and Records." 2. 10 CFR Part 50, Appendix A, General Design Protection Against Natural Phenomena." 3. 10 CFR Part 50, Appendix A, General Design and Missile Design Bases." Criterion 1, "Quality Standards Criterion 2, uDesign Basis for Criterion 4, "Environmental 4. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 5. 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, and Equipment." 7. Standard Review Plan Section 3.9.3, "ASME Code Class 1, 2, and 3 Compo- nents, Component Supports, and Core Support