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:
re either accommodated in the design (with assurance of the functionality and integrity of reactor internals) or demonstrated to be extremely unlikely to occur. This provides assurance that overstress failures of the reactor internals that could cause loss of capability to monitor reactivity, fuel damage resulting from loss of reactivity control, structural damage to fuel cladding, or interference with core cooling are unlikely to occur. DRAFT Rev. 3 - April 1996 3.9.5-6 4. GDC 10 requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. The reactor internals perform and/or may affect the performance (through their failure) of safety functions including reactivity control and core cooling. These safety functions are essential to assure that specified acceptable fuel design limits are not exceeded. Application of GDC 10 to the reactor internals provides assurance that they are designed with sufficient margin to ensure their functionality and integrity during any condition of normal operation, including the effects of anticipated operational occurrences, such that a high likelihood of performance of these safety functions is achieved. Assured performance of these safety functions in turn assures that specified acceptable fuel design limits related to reactivity control and core cooling are not exceeded, thus assuring the integrity of the fuel and its cladding. 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