Document: NUREG-0800
Document ID: 81a2e18b-7311-4c4e-822e-8dfe1b0ba7aa
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230009.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
e staff demonstrate that the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis for the piping. Application of GDC 4 to the reactor internals provides assurance that asymmetric loading effects of postulated pipe ruptures are either accommodated in the design (with assurance of the functionality and integrity of reactor internals) or demonstrated to be extremely unlikely to occur and 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. 4. GDC 10 requires that the reactor core and its 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 or may (through their failure) affect the performance of safety functions like reactivity control and core cooling essential for assurance that specified acceptable fuel design limits are not exceeded. Application of GDC 10 to the reactor internals provides assurance of design with sufficient margin to ensure functionality and integrity during any condition of normal operation, including the effects of anticipated operational occurrences, to achieve a high likelihood of performance of these safety functions. Assured performance of these safety functions in turn assures that specified acceptable fuel design limits for 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 material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For