ASME Code requirements for multi-canister overpack design and fabrication

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Description

The baseline requirements for the design and fabrication of the MCO include the application of the technical requirements of the ASME Code, Section III, Subsection NB for containment and Section III, Subsection NG for criticality control. ASME Code administrative requirements, which have not historically been applied at the Hanford site and which have not been required by the US Nuclear Regulatory Commission (NRC) for licensed spent fuel casks/canisters, were not invoked for the MCO. As a result of recommendations made from an ASME Code consultant in response to DNFSB staff concerns regarding ASME Code application, the SNF Project will be ... continued below

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20 pages

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Smith, K. E. November 3, 1998.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

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  • Hanford Site (Wash.)
    Publisher Info: HNF Hanford Site (United States)
    Place of Publication: United States

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Description

The baseline requirements for the design and fabrication of the MCO include the application of the technical requirements of the ASME Code, Section III, Subsection NB for containment and Section III, Subsection NG for criticality control. ASME Code administrative requirements, which have not historically been applied at the Hanford site and which have not been required by the US Nuclear Regulatory Commission (NRC) for licensed spent fuel casks/canisters, were not invoked for the MCO. As a result of recommendations made from an ASME Code consultant in response to DNFSB staff concerns regarding ASME Code application, the SNF Project will be making the following modifications: issue an ASME Code Design Specification and Design Report, certified by a Registered Professional Engineer; Require the MCO fabricator to hold ASME Section III or Section VIII, Division 2 accreditation; and Use ASME Authorized Inspectors for MCO fabrication. Incorporation of these modifications will ensure that the MCO is designed and fabricated in accordance with the ASME Code. Code Stamping has not been a requirement at the Hanford site, nor for NRC licensed spent fuel casks/canisters, but will be considered if determined to be economically justified.

Physical Description

20 pages

Notes

INIS; OSTI as DE00011242

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  • Other Information: PBD: 3 Nov 1998

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  • Report No.: HNF--3255--REV0
  • Report No.: EW7040000
  • Grant Number: AC06-96RL13200
  • DOI: 10.2172/11242 | External Link
  • Office of Scientific & Technical Information Report Number: 11242
  • Archival Resource Key: ark:/67531/metadc623455

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • November 3, 1998

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 27, 2016, 4 p.m.

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Smith, K. E. ASME Code requirements for multi-canister overpack design and fabrication, report, November 3, 1998; United States. (digital.library.unt.edu/ark:/67531/metadc623455/: accessed October 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.