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:
by the applicant and presented in his safety analysis report. The basis for these limits should be included. The stresses associated with these dis- placements should not exceed the specified limits. The requirements for dynamic analysis of these components are discussed in SRP Section 3.9.2. III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below as may be appropriate for a particular case. The configuration and general arrangement of all mechanical and structural internal elements covered by this SRP section are reviewed and compared to those of previously licensed similar plants. Any significant changes in design are noted and the applicant is asked to verify that these changes do not affect the flow-induced vibration test results required by SRP Section 3.9.2. With respect to the design and analysis of reactor internals, a statement by the applicant that they are designed in accordance with Subsection NG and SRP Section 3.9.3, "Core Support Structures,' of Reference 5 and 7 is acceptable. In lieu of such a commitment, the reviewer must determine that the design and analysis of these components are consistent with the requirements discussed in subsection II, above. This is accomplished by requiring that the applicant describe the design procedures and criteria used in the design of these compo- nents. This includes a list of the design and service stress limits used for all of the applicable loading conditions. 3.9.5-3 Rev. 2 - July 1981 The deformation limits specified for these components are reviewed to verify that the applicant has stated that these deflections will not interfere with the functioning of related components, e.g., control rods and standby cooling systems, and that the stresses associated with these displacements are less than the specified limits for the core support structures. At the operating license stage, the calculated stresses and deformations are reviewed to determine that they do not