Document: NUREG-0800
Document ID: 5e3dbec9-a39f-4531-9eb9-705982190066
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16134A059.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
ll approval of Section III, Division 1 rules without condition. In this manner, approval of Subsection NG is similar to regulatory guidance provided in RGs in that it provides an acceptable method for meeting NRC requirements and, in this particular case, 10 CFR Part 50, Appendix A, GDC 1. An applicant may propose means other than those specified by the provisions in Subsection NG for meeting the applicable regulations. 3. The design criteria, loading conditions, and analyses that provide the bases for the design of reactor internals other than the core support structures should meet the guidelines of NG-3000 and be constructed not to affect the integrity of the core support structures adversely (NG-1122). If other guidelines (e.g., manufacturer standards or empirical methods based on field experience and testing) are the bases for the stress, deformation, and fatigue criteria, those guidelines should be identified and their use justified. 4. Deformation limits for reactor internals should be established by the applicant and presented in the safety analysis report. The basis for these limits should be included. The stresses induced by these displacements should not exceed the specified limits. 3.9.5-7 Revision 4 – March 2017 The provisions for dynamic analysis of these components are addressed in SRP Section 3.9.2. 5. The reactor internals should be designed to accommodate asymmetric blowdown loads from postulated pipe ruptures. The applicant's evaluation of such loads should demonstrate that they do not exceed the limits imposed by the applicable codes and standards. Where double-ended guillotine break of reactor coolant piping is postulated, criteria for evaluating loading transients and structural components are specified in NUREG-0609. SRP Section 3.6.2 provides additional guidance on transient and dynamic loading effects from postulated pipe ruptures. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of