Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
ucts from oxide fuel pellets during normal steady-state conditions. When used with nuclide yields, this model will define the inventory of volatile fission products that could be available for release from the fuel rod if the cladding were breached, sometimes referred to as gap inventory. Recent experimental data from RIA tests in Nuclear Safety Research Reactor (NSRR) and Cabri (Publication on NSRR/RIA Experiments with High Burnup PWR Duels, March 2-6, 1997, Publication on High-Burnup BWR Fuel Behavior Under Simulated Reactivity-Initiated Accident Conditions, Nuclear Technology Vol. 38, June 2002, and Publication on The Role of Grain Boundary Fission Gases in High Burn-Up Fuel Under Reactivity Initiated Accident Conditions, September 2000) suggest that the gap inventory for a BWR rod drop accident specified in RG 1.183 and for a PWR control rod ejection accident may need modification. The NRC has plans to issue new guidelines for gap inventory (fission product release) from these accidents. 4. 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. 4.2-19 Revision 3 - March 2007 A. Testing and Inspection of New Fuel Testing and inspection plans for new fuel should verify cladding integrity, fuel system dimensions, fuel enrichment, burnable poison concentration, and absorber composition. Quality control reports should document the details of the manufacturer’s testing and inspection programs and 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. When the overall testing and inspection programs are essentially the same as those for previously approved plants, a statement to that effect should be made. In that case, the safety analysis report need not include program details, but an appropriate