Document: NUREG-0800
Document ID: dbd67338-fe87-44c6-8578-3715167e447b
Document Type: srp
Title: SPENT FUEL CASK DROP ACCIDENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350315.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.7.5
CFR Part: 
CFR Title: 

Content:
ng or whether ventilation Rev. 2 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commisulon's policy to Inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the CommissIon's regulations and compliance with them Is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for Improvement will be considered and should be sent to the U.S. Nuclear Regulatory Corimisslon. Office of Nuclear Reactor Regulation. Washington. D.C. 5 systems should be operating and whether the building leaktightness would be violated by the cask drop). 3. The SAR and technical specifications are reviewed and the relevant plant parameters are evaluated for incorporation into the dose computation model. The model incorporates conservative transport mechanisms and rates from the fuel release to the atmosphere, suitable breathing rates, dose conver- sion factors, and other data that may affect the dose. The X/Q data are obtained from the assigned meteorologist. 4. The Effluent Treatment System Branch (ETSB) provides the filter efficiencies for the ESF atmospheric cleanup systems to AEB for use in the analysis of the radiological consequences resulting from spent fuel cask drop accidents. This is a secondary review effort by ETSB. 5. The calculated doses are compared with exposure guidelines to determine the acceptability