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:
andling 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 it incorporates the appropriate conservative assumptions in Regulatory Guide 1.25 (Ref. 3) with respect to gap. inventory as stated in positions C.1.d,e, and f of the guide. The acceptability of the atmospheric dispersion factors, X/Q values, is determined under SRP Section 2.3.4. 15.7.5-2 Rev. 2 - July 1981 4. An ESF grade atmospheric cleanup system is required for the fuel handling building to reduce the potential radiological consequences of the fuel cask drop accident. 5. The plant design with regard to spent fuel cask drop accidents is acceptable without calculation of radiological consequences if potential cask drop distances are less than 30 feet and appropriate impact limiting devices are employed during cask movements, as determined by ASB. III. REVIEW PROCEDURES The reviewer selects and emphasizes specific aspects of this SRP section as are appropriate for a particular plant. The areas to be given attention and emphasis in the review are determined by the similarity of the information provided in the SAR to that recently reviewed on other plants and whether items of special safety significance are involved. Upon request from the AEB reviewer, the ASB and ETSB as secondary review branches will provide input for the areas of review stated in subsection I of this SRP section. The AEB reviewer obtains and uses such input as required to assure that this review procedure is complete. The first step in the review procedure is to determine, with the assistance of the ASB as described in subsection I, whether radiological consequences of a spent fuel cask drop accident need be evaluated. If a radiological consequence calculation is found to be necessary, the procedure is as follows: 1. The fuel element gap inventory is determined in a manner similar to that for a fuel