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Title: Technical Review Report for the Justification for 233U Content Envelope Safety Analysis Report for Packaging Model 9975-85, Addendum 2

Abstract

This report documents the review of Addendum 2, Justification for {sup 233}U Content Envelope, Safety Analysis Report for Packaging, prepared by Savannah River Packaging Technology (SRPT) of Savannah River National Laboratory (SRNL),--the Submittal--at the request of the Department of Energy's (DOE) National Nuclear Security Agency's (NNSA) Albuquerque Operations Office, for the shipment of 233U-bearing material from Los Alamos National Laboratory (LANL), in support of the Technical Area 18 (TA-18) Materials Relocation Program. This Addendum supplements the Safety Analysis Report for Packaging (SARP), Revision 0, and Addendum 1 to Revision 0 of the 9975 SARP (called Revision 0 of the 9975 SARP in this Addendum). The {sup 233}U-bearing items are currently stored at TA-18, awaiting shipment in the Model 9975-85 Package as a new Content Envelope, C.9. Following acceptance of this Addendum by the DOE-Headquarters Certifying Official (EM-60), and subsequent revision to the current Certificate of Compliance (CoC), the new contents will be authorized for shipment in the Model 9975-85 Package. The new Content Configuration, C.9, along with the optional Shielded-Pig Convenience Container Configuration, will be incorporated into the next revision of the Model 9975-85 Package SARP. In addition to the {sup 233}U-bearing items stored at TA-18, kilogram quantities of {supmore » 233}U-bearing materials are stored at Oak Ridge National Laboratory (ORNL). About one quarter of the items is Highly Enriched Uranium (HEU) as U{sub 3}O{sub 8} with {sup 233}U and {sup 232}U. Highly Enriched Uranium implies a {sup 236}U enrichment of >93%. The remaining material located at ORNL is pure {sup 233}U (>90%) with varying amounts of {sup 232}U. The form of the material is U{sub 3}O{sub 8}, UO{sub 3}, UO{sub 2}, and U metal. Additional DOE Sites may also have {sup 233}U-bearing materials for shipment.« less

Authors:
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
951673
Report Number(s):
LLNL-TR-406687
TRN: US200913%%218
DOE Contract Number:  
W-7405-ENG-48
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
29 ENERGY PLANNING, POLICY AND ECONOMY; COMPLIANCE; CONFIGURATION; CONTAINERS; HIGHLY ENRICHED URANIUM; LANL; ORNL; PACKAGING; SAFETY ANALYSIS; SAVANNAH RIVER PLANT; SECURITY

Citation Formats

West, M. Technical Review Report for the Justification for 233U Content Envelope Safety Analysis Report for Packaging Model 9975-85, Addendum 2. United States: N. p., 2008. Web. doi:10.2172/951673.
West, M. Technical Review Report for the Justification for 233U Content Envelope Safety Analysis Report for Packaging Model 9975-85, Addendum 2. United States. https://doi.org/10.2172/951673
West, M. 2008. "Technical Review Report for the Justification for 233U Content Envelope Safety Analysis Report for Packaging Model 9975-85, Addendum 2". United States. https://doi.org/10.2172/951673. https://www.osti.gov/servlets/purl/951673.
@article{osti_951673,
title = {Technical Review Report for the Justification for 233U Content Envelope Safety Analysis Report for Packaging Model 9975-85, Addendum 2},
author = {West, M},
abstractNote = {This report documents the review of Addendum 2, Justification for {sup 233}U Content Envelope, Safety Analysis Report for Packaging, prepared by Savannah River Packaging Technology (SRPT) of Savannah River National Laboratory (SRNL),--the Submittal--at the request of the Department of Energy's (DOE) National Nuclear Security Agency's (NNSA) Albuquerque Operations Office, for the shipment of 233U-bearing material from Los Alamos National Laboratory (LANL), in support of the Technical Area 18 (TA-18) Materials Relocation Program. This Addendum supplements the Safety Analysis Report for Packaging (SARP), Revision 0, and Addendum 1 to Revision 0 of the 9975 SARP (called Revision 0 of the 9975 SARP in this Addendum). The {sup 233}U-bearing items are currently stored at TA-18, awaiting shipment in the Model 9975-85 Package as a new Content Envelope, C.9. Following acceptance of this Addendum by the DOE-Headquarters Certifying Official (EM-60), and subsequent revision to the current Certificate of Compliance (CoC), the new contents will be authorized for shipment in the Model 9975-85 Package. The new Content Configuration, C.9, along with the optional Shielded-Pig Convenience Container Configuration, will be incorporated into the next revision of the Model 9975-85 Package SARP. In addition to the {sup 233}U-bearing items stored at TA-18, kilogram quantities of {sup 233}U-bearing materials are stored at Oak Ridge National Laboratory (ORNL). About one quarter of the items is Highly Enriched Uranium (HEU) as U{sub 3}O{sub 8} with {sup 233}U and {sup 232}U. Highly Enriched Uranium implies a {sup 236}U enrichment of >93%. The remaining material located at ORNL is pure {sup 233}U (>90%) with varying amounts of {sup 232}U. The form of the material is U{sub 3}O{sub 8}, UO{sub 3}, UO{sub 2}, and U metal. Additional DOE Sites may also have {sup 233}U-bearing materials for shipment.},
doi = {10.2172/951673},
url = {https://www.osti.gov/biblio/951673}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jul 25 00:00:00 EDT 2008},
month = {Fri Jul 25 00:00:00 EDT 2008}
}