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:
ical 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 of the exclusion area and low population zone (LPZ) distances and to confirm the adequacy of engineered safety features (ESF) provided for the purpose of mitigating potential doses from spent fuel cask drop accidents. .6. ASB is consulted for verification that a cask drop or tipping will not damage fuel in either the spent fuel storage building or in the contain- ment building, if applicable. If the handling procedures are such that spent fuel can be damaged, an analysis of the resulting offsite doses will be performed under SRP Section 15.7.4. II. ACCEPTANCE CRITERIA The AEB acceptance criteria for this SRP section are based on the requirements of 10 CFR Part 100 (Ref. 1) with respect to the calculated radiological conse- quences of a spent fuel cask drop accident and General Design Criterion 61 (Ref. 2) with respect to appropriate containment, confinement and filtering systems. 1. The plant site and dose mitigating ESF systems are acceptable with respect to the radiological consequences of a postulated spent fuel cask drop accident if the calculated whole-body and thyroid doses at the exclusion area and low population zone boundaries are well within the exposure guideline values of 10 CFR Part 100, paragraph 11. "Well within" means 25 percent or less of the 10 CFR Part 100 exposure guideline values, i.e., 75 rem for the thyroid and 6 rem for the whole-body doses. 2. The radioactivity control features of the fuel storage and spent fuel cask handling system in the fuel building are acceptable if they meet the requirements of General Design Criterion 61, "Fuel Storage and Handling and Radioactivity Control," (Ref. 2) with respect to appropriate containment, confinement 'and filtering systems. 3. The model for calculating the whole-body and thyroid doses is acceptable if