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
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CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Accident Evaluation Branch.(AEB) Secondary - Auxiliary Systems Branch (ASB) Effluent Treatment Systems Branch (ETSB) I. AREAS OF REVIEW The review under this SRP section covers the radiological consequences of the release of fission products from irradiated fuel in a spent fuel cask that is postulated to drop during cask handling operations. SRP Section 15.7.4 covers the radiological consequences of fuel handling accidents in which an object is dropped onto irradiated fuel resulting in the release of fission products from the stored fuel. SRP Section 15.7.4 also includes the consequences of a fuel cask dropping or tipping onto irradiated fuel in the spent fuel pool. The ASB evaluates the spent fuel cask handling system under SRP Section 9.1.4. The AEB reviewer, as explained below, will verify various design and operations aspects of the system with the ASB as a secondary review branch. The points covered in the AEB review are as follows: 1. ASB is consulted to verify the potential drop height during handling of a loaded cask and the procedures for handling the cask with respect to the impact limiter. If the handling procedures meet all applicable criteria, then the radiological consequences of a spent fuel cask drop accident need not be estimated. 2. A design basis radiological analysis is performed if a cask drop exceeding 30 feet can be postulated or if limiting devices are removed during cask handling within the plant so the 30-foot drop height is exceeded. If the radiological consequences of a cask drop accident are to be computed, then information on whether building leaktightness can be expected after a cask drop is obtained from ASB (e.g., whether the technical specifications. require large doors to be closed during fuel handling 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