Multi-canister overpack additional NRC requirements.

Multi-canister overpack [electronic resource] : additional NRC requirements.

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 equivalencỳ̀ to comparable U.S. Nuclear...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Westinghouse Hanford Company (Researcher), Hanford Site (Wash. ). (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy. Office of Environmental Restoration and Waste Management ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1995.
Subjects:
Spent Fuel Storage.
Regulations.
Hanford Reservation.
Us Nrc.
Containers.
Packaging.
Safety.
Nuclear Fuels.

MARC

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245 0 0 |a Multi-canister overpack  |h [electronic resource] :  |b additional NRC requirements. 
260 |a Washington, D.C :  |b United States. Dept. of Energy. Office of Environmental Restoration and Waste Management ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,   |c 1995. 
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500 |a 11/01/1995. 
500 |a "WHC-SD-SNF-DB--005" 
500 |a "DE97051216" 
500 |a Garvin, L.J. 
520 3 |a 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 equivalencỳ̀ 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. 
536 |b AC06-87RL10930. 
650 7 |a Spent Fuel Storage.  |2 local. 
650 7 |a Regulations.  |2 local. 
650 7 |a Hanford Reservation.  |2 local. 
650 7 |a Us Nrc.  |2 local. 
650 7 |a Containers.  |2 local. 
650 7 |a Packaging.  |2 local. 
650 7 |a Safety.  |2 local. 
650 7 |a Nuclear Fuels.  |2 edbsc. 
710 2 |a Westinghouse Hanford Company.  |4 res. 
710 2 |a United States.  |b Department of Energy.  |b Office of Environmental Restoration and Waste Management.  |4 spn. 
710 2 |a Hanford Site (Wash.  |b ).  |4 res. 
710 2 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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952 f f |p Can circulate  |a University of Colorado Boulder  |b Online  |c Online  |d Online  |e E 1.99:WHC-SD-SNF-DB--005  |h Superintendent of Documents classification  |i web  |n 1 

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