Document: NUREG-0800
Document ID: 855b2438-2ddf-48e9-8762-e39097109e12
Document Type: srp
Title: FUEL SYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340660.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.2
CFR Part: 
CFR Title: 

Content:
e that conservatisms that were incorporated for calculating temperatures do not introduce nonconservatisms with regard to fuel rod pressures. (g) Metal/Water Reaction Rate: To meet the requirements of Appendix K of 10 CFR Part 50 (Ref. 9) as it relates to metal/water reaction rate, the rate of energy release, hydrogen generation, and cladding oxidation from the metal/water reaction should be calculated using the Baker-Just equation (Ref. 27). For non-LOCA applications, other correlations may be used if justified. (h) Fission Product Inventory:. To meet the guidelines of Regulatory Guides 1.3, 1.4, 1.25 and 1.77 (Refs. 6, 28-30) as they relate to fission product release, the available radioactive fission product inventory in fuel rods (i.e., the gap inventory) is presently specified by the assumptions in those Regulatory Guides. These assumptions should be used until improved calculational methods are approved by CPB (see Ref. 31). D. Testing, Inspection, and Surveillance Plans Plans must be reviewed for each plant for testing and inspection of new fuel and for monitoring and surveillance of irradiated fuel. 4. 2-11 Rev. 2 - July 1981 1. Testing and Inspection of New Fuel Testing and inspection plans for new fuel should include verification of cladding integrity, fuel system dimensions, fuel enrichment, burnable poison concentration, and absorber composition. Details of the manufacturer's testing and inspection programs should be documented in quality control reports, which should be referenced and summarized in the Safety Analysis Report. The program for onsite inspection of new fuel and control assemblies after they have been delivered to the plant should also be described. Where the overall testing and inspection programs are essentially the same as for previously approved plants, a statement to that effect should be made. In that case, the details of the programs need not be included in the Safety Analysis Report, but an appropriate reference should be cited and