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:
r Evaluating the Potential Radiological Consequences of Loss-of-Coolant Accident for Pressurized Water Reactors." 30. Regulatory Guide 1.25, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors." 31. "The Role of Fission Gas Release in Reactor Licensing," USNRC Report NUREG-75/077, November 1975. 32. B. L. Siegel and H. H. Hagen, "Fuel Failure Detection in Operating Reactors," USNRC Report NUREG-0401, March 1978. 33. W. J. Bailey, et al., "Assessment of Current Onsite Inspection Techniques for LWR Fuel Systems," Battelle Pacific Northwest Laboratory Report NUREG/CR-1380, Vol. 1, July 1980, Vol. 2, January 1981. 34. "Safety Evaluation Report Related to Operation of Arkansas Nuclear One, Unit 2," USNRC Report NUREG-0308, Supp. 2, September 1978. 4.2-16 Rev. 2 - July 1981 35. B. L. Siegel, "Evaluation of the Behavior of Waterlogged Fuel Rod Failures in LWRs," USNRC Report NUREG-0308, March 1978. 36. R. 0. Meyer, C. E. Beyer and J. C. Voglewede, "Fission Gas Release from Fuel at Sigh Burnup," USNRC Report NUREG-0418, March 1978. 37. R. L. Grubb, "Review of LWR Fuel System Mechanical Response with Recommendations for Component Acceptance Criteria," Idaho National Eftgineering Laboratory, NUREG/CR-1018, September 1979. 38. R. L. Grubb "Pressurized Water Reactor Lateral Core-Response Routine, FAMREC (Fuel Assembly Mechanical Response Code)," Idaho National Engineering Laboratory, NUREG/CR-1019, September 1979. 39. R. L. Grubb, "Technical Evaluation of PWR Fuel Spacer Grid Response Load Sensitivity Studies," Idaho National Engineering Laboratory, NUREG/CR-1020, September 1979. 40. S. B. flosford, et al., "Asymmetric Blowdown Loads on PWR Primary Systems," USNRC Report NUREG-0609, January 1981. 41. Regulatory Guide 1.60A "Design Response Spectra for Seismic Design of Nuclear Power Plants. 4.2-17 Rev. 2 - July 1981 U.S. Nuclear Regulatory