Document: NUREG-0800
Document ID: 28c03fd2-3542-41ec-bfd7-5df2087c4ee6
Document Type: srp
Title: FUEL SYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070407.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.2
CFR Part: 
CFR Title: 

Content:
Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors." 1041. Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants." 116. Regulatory Guide 1.77, "Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors." 1222. Regulatory Guide 1.126, "An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification." 13. Regulatory Guide 1.157, "Best-Estimate Calculations of Emergency Core Cooling System Performance."90 1411. WASH-1236 "Technical Report on Densification of Light Water Reactor Fuels," AEC Regulatory Staff Report WASH-1236 , November 14, 1972. 91 1531. NUREG-75/077, "The Role of Fission Gas Release in Reactor Licensing," USNRC Report NUREG-75/077, November 1975. 92 1621. NUREG-0085R. O. Meyer, "The Analysis of Fuel Densification," USNRC Report NUREG-0085, July 1976. 1734. NUREG-0308 Supp. 2, "Safety Evaluation Report Related to Operation of Arkansas Nuclear One, Unit 2," USNRC Report NUREG-0308, Supp. 2, September 1978. DRAFT Rev. 3 - April 1996 4.2-20 1835. NUREG-0303B. L. Siegel , "Evaluation of the Behavior of Waterlogged Fuel Rod 93 Failures in LWRs," USNRC Report NUREG-0308, March 1978. 1932. NUREG-0401B. L. Siegel and H. H. Hagen, "Fuel Failure Detection in Operating Reactors," USNRC Report NUREG-0401, March 1978. 2036. NUREG-0418R. O. Meyer, C. E. Beyer and J. C. Voglewede, "Fission Gas Release from Fuel at High Burnup," USNRC Report NUREG-0418, March 1978. 2140. NUREG-0609S. B. Hosford, et al., "Asymmetric Blowdown Loads on PWR Primary Systems," USNRC Report NUREG-0609, January 1981. 2210. NUREG-0630D. A. Powers and R. O. Meyer, "Cladding Swelling and Rupture Models for LOCA Analysis," USNRC Report NUREG-0630, April 1980. 2337. NUREG/CR-1018R. L. Grubb, "Review of LWR Fuel System Mechanical Response with Recommendations for Component Acceptance Criteria," Idaho National Engineering Laboratory, NUREG/CR-1018, September