Open AccessMulti-canister overpack: additional NRC requirements
Author(s) -
L.J. Garvin
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/449764
Subject(s) - engineering , spent nuclear fuel , radioactive waste , safety standards , civil engineering , transport engineering , waste management , reliability engineering
The U.S. Department of Energy (DOE) established in the K Basin Spent Fuel Project, Regulatory Policy, dated August 4, 1995 (hereafter referred to as the Policy), the requirement for new Spent Nuclear Fuel Project (SNFP) facilities to achieve ``nuclear safety equivalency`` to comparable U.S. Nuclear Regulatory Commission licensed facilities. For activities other than during transport, when the Multi-Canister Overpack (MCO) is used and resides in the Canister Storage Building (CSB), Conditioning Facility or K Basins Path Forward Projects, additional NRC requirements will also apply to the MCO based on the safety functions it performs and its interfaces with the SNFP facilities. An evaluation was performed in consideration of the MCO safety functions to identify any additional NRC requirements, to establish nuclear safety equivalency for the MCO