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:
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 of the ASME Code and SRP Section 3.9.3, "Core Support Structures," of Reference 5 and 7 is acceptable . In lieu of such a commitment, 39 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 components. This includes a list of the design and service stress limits used for all of the applicable loading conditions. The reviewer verifies that the asymmetric blowdown loadings upon reactor internals resulting from pipe ruptures (at postulated locations not excluded based upon leak-before-break analyses) have been evaluated by the applicant and are accommodated in the design, consistent with criteria identified in specific criterion II.e.40 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 exceed the specified limits. 3.9.5-7 DRAFT Rev. 3 - April 1996 Any deviations that have not been adequately justified are identified and findings to