Document: NUREG-0800
Document ID: 6e757273-b12b-4603-aace-b01e49e5a6da
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF FUEL HANDLING ACCIDENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350313.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.7.4
CFR Part: 
CFR Title: 

Content:
be requested to verify the number of rods assumed damaged. Reference 6 may also be consulted in this regard. 3. Fuel handling accident in fuel buildings: The applicant's SAR is examined to assure that an ESF atmospheric cleanup system is included in the 15.7.4-3 Rev. 1 - July 1981 design of the fuel storage facility to mitigate the radiological consequences of a fuel handling accident. Verification of acceptability and efficiencies of the atmosphere cleanup system are provided by the ETSB through the review of SRP Section 6.5.1. The reviewer should examine those pertinent aspects of the accident, especially with regard to the operational modes of the ventilation systems and location and response time of the radiation detectors to assure that any accidental release will be detected in sufficient time to be appropriately ducted and exhausted via ESF filters. 4. Fuel handling accident inside containment: The systems to mitigate the consequences are reviewed. If an applicant proposes that fuel handling will occur only when the containment is isolated, no radiological conse- quences need be calculated. If fuel handling operations occur only when the containment is exhausted to the environment via an ESF filter system, the radiological consequences should be calculated giving appropriate credit for this system. If the containment will be open during fuel handling operations, as with a containment purge exhaust system, the reviewer should verify that a prompt radiation detection and automatic containment isolation capability are provided and that the resulting doses are within the acceptance criteria given in subsection II.1 above. For a plant design with the containment open during the fuel movements, a review should be made of the applicant's analysis. This should include an examination of the type, location and redundancy of the radiation monitors intended to detect an activity release inside the containment and verification that detection is followed by automatic