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:
se 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. Any deviations that have not been adequately justified are identified and find- ings to that effect are transmitted to the applicant with a request for conformr ance with'the requirements discussed in subsection II, above, or additional technical justification. IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided in accord- ance with this SRP section and that his evaluation supports conclusions of the following type, to be included in the staff's safety evaluation report: The staff concludes that the design of reactor internals is acceptable and meets the requirements of General Design Criteria 1, 2, 4, and 10 and 10 CFR Part 50, §50.55a. This conclusion is based on the following: 1. The applicant has met the requirements of GDC I and 10 CFR Part 50, §50.55a with respect to designing the reactor internals to quality standards commensurate with the' importance of the safety functions to be performed. The design procedures and criteria used for the reactor internals are in conformance with the requirements of Subsection NG of the ASME Code, Section III. 2. The applicant has met the requirements of GDC 2, 4, and 10 with respect to designing components important to safety to withstand the effects of earthquake and the effects of normal operation, mainte- nance, testing, and postulated loss-of-coolant accidents with suffi- cient margin to assure that capability to perform its safety func- tions is maintained and the specified acceptable fuel design limits are not exceeded. The specified design transients, design 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