Document: NUREG-0800
Document ID: 603129ef-5cf1-4ba3-af49-a2cd45a08210
Document Type: srp
Title: FUEL SYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.2
CFR Part: 
CFR Title: 

Content:
design-basis limits and associated SAFDLs to determine whether they remain applicable to the new fuel design (including the introduction of new materials) given the operating conditions (temperature, burnup, and power). If they do not apply, new limits must be established based on appropriate data. 2. Description and Design Drawings. The reviewer examines the fuel system description and design drawings. In general, the description will emphasize product specifications rather than process specifications. 3. Design Evaluation. The reviewer evaluates the performance of the fuel system during normal operation, AOOs, and postulated accidents to determine whether all design bases are met. The fuel system components, as listed above, are reviewed not only as separate components but also as integral units such as fuel rods and fuel assemblies. New fuel designs, new operating limits (e.g., rod burnup and power), and the introduction of new materials to the fuel system require a review to verify that existing design-basis limits, analytical models, and evaluation methods remain applicable for the specific design for normal operation, AOOs, and postulated accidents. The review also evaluates operating experience, direct experimental comparisons, detailed mathematical analyses (including fuel performance codes), and other information. 4.2-3 Revision 3 - March 2007 4. Testing, Inspection, and Surveillance Plans. The licensee performs testing and inspection of new fuel to ensure that the fuel is fabricated in accordance with the design and that it reaches the plant site and is loaded in the core without damage. Online fuel rod failure monitoring and postirradiation surveillance should be performed to detect anomalies or confirm that the fuel system is performing as expected; surveillance of control rods containing B4C should be performed to preclude reactivity loss. The organization responsible for reactor systems reviews the testing, inspection, and surveillance plans, along