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:
d and compared to those of previously licensed similar plants. The applicant should demonstrate that any significant changes in design or operating conditions do not affect the comprehensive vibration analysis described in RG 1.20 and SRP Section 3.9.2. 2. As to the design and analysis of reactor internals, the applicant should demonstrate that they are designed and analyzed in accordance with Subsection NG of the ASME BPV Code as incorporated by reference in 10 CFR 50.55a, and as discussed in SRP Section 3.9.3. In lieu of such a demonstration, the reviewer must determine whether the design and analysis of these components are consistent with the requirements addressed in Subsection II of this SRP section by reviewing the applicant’s description of the procedures and criteria for the design of these components, including the design and service stress limits for all of the applicable loading conditions. The stresses at adverse 3.9.5-9 Revision 4 – March 2017 flow and operating conditions should be treated as primary stresses while satisfying the ASME BPV Code service stress limits. 3. The reviewer verifies whether the asymmetric blowdown loadings upon reactor internals from pipe ruptures (at postulated locations not excluded by leak-before-break analyses) have been acceptably evaluated by the applicant and are accommodated in the design, consistent with criteria in Subsection II of this SRP section. 4. The deformation limits specified for these components are reviewed as part of a DC, COL, or operating license application to verify whether the applicant has demonstrated that these deflections will not interfere with the function of related components (e.g., control rods and standby cooling systems) and whether the stresses induced by these displacements are less than the specified limits for the core support structures. 5. For the review of a DC application, the NRC staff reviewer should follow the above procedures to verify that the design, including