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Title: SNF project's MCO compliance assessment with DOE ''general design criteria,'' order 6430.1A and ''SNF project MCO additional NRC requirements,'' HNF-SD-SNF-DB-005

Abstract

This document is presented to demonstrate the MCOs compliance to the major design criteria invoked on the MCO. This document is broken down into a section for the MCO's evaluation against DOE Order 6430.1A General Design Criteria sixteen divisions and then the evaluation of the MCO against HNF-SD-SNF-DB-005 ''Spent Nuclear Fuel Project Multi-Canister Overpack Additional NRC Requirements.'' The compliance assessment is presented as a matrix in tabular form. The MCO is the primary container for the K-basin's spent nuclear fuel as it leaves the basin pools and through to the 40 year interim storage at the Canister Storage Building (CSB). The MCO and its components interface with; the K basins, shipping cask and transportation system, Cold Vacuum Drying facility individual process bays and equipment, and CSB facility including the MCO handling machine (MHM), the storage tubes, and the MCO work stations where sampling, welding, and inspection of the MCO is performed. As the MCO is the primary boundary for handling, process, and storage, its main goals are to minimize the spread of its radiological contents to the outside of the MCO and provide for nuclear criticality control. The MCO contains personnel radiation shielding only on its upper end, in themore » form of a shield plug, where the process interfaces are located. Shielding beyond the shield plug is the responsibility of the using facilities. The design of the MCO and its components is depicted in drawings H-2-828040 through H-2-828075. Not every drawing number in the sequence is used. The first drawing number, H-2-828040, is the drawing index for the MCO. The design performance specification for the MCO is HW-S-0426, and was reviewed and approved by the interfacing design authorities, the safety, regulatory, and operations groups, and the local DOE office. The current revision for the design performance specification is revision 5. The designs of the MCO have been reviewed and approved in a similar way and the reports are published under HNF-SD-SNF-DR-003. Independent reviews also have been conducted. As the MCO is an individual component, it is not a major facility. So the DOE general design criteria for facilities contain many requirements that go beyond the MCO's responsibility and are not directly applicable to the MCO. The NRC equivalency document was written for the MCO and also includes requirements common to the facility holding the MCO.« less

Authors:
Publication Date:
Research Org.:
Hanford Site (HNF), Richland, WA (United States)
Sponsoring Org.:
US DOE Office of Environmental Management (US)
OSTI Identifier:
782300
Report Number(s):
HNF-3750-REV0
TRN: US0203118
DOE Contract Number:  
AC06-96RL13200
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 12 May 1999
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATION; CASKS; COMPLIANCE; DESIGN; ELECTRON TUBES; IMAGE STORAGE TUBES; NUCLEAR FUELS; RADIATIONS; SHIELDING; SPECIFICATIONS; STORAGE; TRANSPORTATION SYSTEMS

Citation Formats

GOLDMANN, L H. SNF project's MCO compliance assessment with DOE ''general design criteria,'' order 6430.1A and ''SNF project MCO additional NRC requirements,'' HNF-SD-SNF-DB-005. United States: N. p., 1999. Web. doi:10.2172/782300.
GOLDMANN, L H. SNF project's MCO compliance assessment with DOE ''general design criteria,'' order 6430.1A and ''SNF project MCO additional NRC requirements,'' HNF-SD-SNF-DB-005. United States. https://doi.org/10.2172/782300
GOLDMANN, L H. 1999. "SNF project's MCO compliance assessment with DOE ''general design criteria,'' order 6430.1A and ''SNF project MCO additional NRC requirements,'' HNF-SD-SNF-DB-005". United States. https://doi.org/10.2172/782300. https://www.osti.gov/servlets/purl/782300.
@article{osti_782300,
title = {SNF project's MCO compliance assessment with DOE ''general design criteria,'' order 6430.1A and ''SNF project MCO additional NRC requirements,'' HNF-SD-SNF-DB-005},
author = {GOLDMANN, L H},
abstractNote = {This document is presented to demonstrate the MCOs compliance to the major design criteria invoked on the MCO. This document is broken down into a section for the MCO's evaluation against DOE Order 6430.1A General Design Criteria sixteen divisions and then the evaluation of the MCO against HNF-SD-SNF-DB-005 ''Spent Nuclear Fuel Project Multi-Canister Overpack Additional NRC Requirements.'' The compliance assessment is presented as a matrix in tabular form. The MCO is the primary container for the K-basin's spent nuclear fuel as it leaves the basin pools and through to the 40 year interim storage at the Canister Storage Building (CSB). The MCO and its components interface with; the K basins, shipping cask and transportation system, Cold Vacuum Drying facility individual process bays and equipment, and CSB facility including the MCO handling machine (MHM), the storage tubes, and the MCO work stations where sampling, welding, and inspection of the MCO is performed. As the MCO is the primary boundary for handling, process, and storage, its main goals are to minimize the spread of its radiological contents to the outside of the MCO and provide for nuclear criticality control. The MCO contains personnel radiation shielding only on its upper end, in the form of a shield plug, where the process interfaces are located. Shielding beyond the shield plug is the responsibility of the using facilities. The design of the MCO and its components is depicted in drawings H-2-828040 through H-2-828075. Not every drawing number in the sequence is used. The first drawing number, H-2-828040, is the drawing index for the MCO. The design performance specification for the MCO is HW-S-0426, and was reviewed and approved by the interfacing design authorities, the safety, regulatory, and operations groups, and the local DOE office. The current revision for the design performance specification is revision 5. The designs of the MCO have been reviewed and approved in a similar way and the reports are published under HNF-SD-SNF-DR-003. Independent reviews also have been conducted. As the MCO is an individual component, it is not a major facility. So the DOE general design criteria for facilities contain many requirements that go beyond the MCO's responsibility and are not directly applicable to the MCO. The NRC equivalency document was written for the MCO and also includes requirements common to the facility holding the MCO.},
doi = {10.2172/782300},
url = {https://www.osti.gov/biblio/782300}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed May 12 00:00:00 EDT 1999},
month = {Wed May 12 00:00:00 EDT 1999}
}