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:
ces from the spent fuel cask drop accident and (3) the staff's independent analysis using conservative assumptions including those in Regulatory Guide 1.25 Position C.1.d, e, and f with respect to gap inventory. If the cask drop height is less than 30 feet, this will be stated in the AEB Safety Evaluation Report, but no evaluation finding with respect to radiological consequences need be included. V. IMPLEMENTATION The following provides guidance to applicants and licensees regarding the staff's plans for using this SRP aection. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. 15.7.5-4 Rev. 2 - July 1981 VI. REFERENCES 1. 10 CFR Part 100, §100.11, "Determination of Exclusion Area, Low Population Zone, and Population Center Distance." 2. 10 CFR Part 50, Appendix A, General Design Criterion 61, "Fuel Storage and Handling and Radioactivity Control." | 3. 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." 15.7.5-5 Rev. 2 - July 1981