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:
e assumed in the safety analysis. The design limits of GDC 10 (i.e., the SAFDLs) accomplish these objectives. In a “fuel rod failure,” the fuel rod leaks and the first fission product barrier (the cladding) is breached. The dose analysis required by 10 CFR Part 100 for postulated accidents must account for fuel rod failures. “Coolability,” in general, means that the fuel assembly retains its rod-bundle geometry with adequate coolant channels to permit removal of residual heat even after a severe accident. The general requirements to maintain control rod insertability and core coolability appear repeatedly in the GDC found in Appendix A to 10 CFR Part 50 (e.g., GDC 27 and 35). In particular, 10 CFR 50.46 provides the specific coolability requirements for the loss-of-coolant accident (LOCA). Standard Review Plan (SRP) Section 4.2 describes all fuel damage criteria. SRP Section 4.4 provides specific thermal-hydraulic criteria for instances involving limits to the departure from nucleate boiling ratio (DNBR) and the critical power ratio (CPR). The available radioactive fission product inventory in fuel rods (i.e., the gap inventory expressed as a release fraction) is provided to the U.S. Nuclear Regulatory Commission’s (NRC) organization that is responsible for the review of design basis accident radiological consequence analyses for use in estimating the radiological consequences of plant releases. The specific areas of review are as follows: 1. Design Bases. Design bases for the safety analysis address fuel system damage mechanisms and provide limiting values for important parameters to prevent damage from exceeding acceptable levels. The design bases should reflect the safety review objectives as described above. The reviewer should evaluate established (past) 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,