80 FR 80400 - Spent Fuel Transportation Package Response to the MacArthur Maze Fire Scenario

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 80, Issue 247 (December 24, 2015)

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG/CR, NUREG/CR-7206, ``Spent Fuel Transportation Package Response to the MacArthur Maze Fire Scenario.'' This report presents analyses that were performed to examine the hypothetical effects on a spent fuel transportation package from conditions during the MacArthur Maze accident in 2007. The analyses undertaken include FDS fire modeling, physical examination of material samples, ANSYS and COBRA-SFS code thermal modeling of a GA-4 package, ANSYS and LS-DYNA structural and thermal-structural modeling of the roadway and package, and fuel performance modeling using the FRAPTRAN- 1.4, FRAPCON-3.4, and DATING codes. The estimated release from the hypothetical scenario is below the prescribed limit for safety.

[Federal Register Volume 80, Number 247 (Thursday, December 24, 2015)]
[Notices]
[Pages 80400-80401]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2015-32514]


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NUCLEAR REGULATORY COMMISSION

[NRC-2015-0207]


Spent Fuel Transportation Package Response to the MacArthur Maze 
Fire Scenario

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft NUREG/CR; request for comment.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for 
public comment a draft NUREG/CR, NUREG/CR-7206, ``Spent Fuel 
Transportation Package Response to the MacArthur Maze Fire Scenario.'' 
This report presents analyses that were performed to examine the 
hypothetical effects on a spent fuel transportation package from 
conditions during the MacArthur Maze accident in 2007. The analyses 
undertaken include FDS fire modeling, physical examination of material 
samples, ANSYS and COBRA-SFS code thermal modeling of a GA-4 package, 
ANSYS and LS-DYNA structural and thermal-structural modeling of the 
roadway and package, and fuel performance modeling using the FRAPTRAN-
1.4, FRAPCON-3.4, and DATING codes. The estimated release from the 
hypothetical scenario is below the prescribed limit for safety.

DATES: Submit comments by February 22, 2016. Comments received after 
this date will be considered if it is practical to do so, but the 
Commission is able to ensure consideration only for comments received 
before this date.

ADDRESSES: You may submit comments by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject):
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0207. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     Mail comments to: Cindy Bladey, Office of Administration, 
Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Joseph Borowsky, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission 
Washington, DC 20555-0001; telephone: 301-415-7407; email: 
[email protected].

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0207 when contacting the NRC 
about the availability of information for this action. You may obtain 
publicly-available information related to this action by any of the 
following methods:
     Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0207.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
draft NUREG/CR, ``Spent Fuel Transportation Package Response to the 
MacArthur Maze Fire Scenario'' is available in ADAMS under Accession 
No. ML15350A213.

[[Page 80401]]

     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2015-0207 in your comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC posts all comment submissions at http://www.regulations.gov as well as entering the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment submissions into ADAMS.

II. Discussion

    The NRC is issuing draft NUREG/CR ``Spent Fuel Transportation 
Package Response to the MacArthur Maze Fire Scenario.'' This report 
presents analyses that were performed to examine the hypothetical 
effects on a spent fuel transportation package from conditions during 
the MacArthur Maze accident in 2007. The analyses undertaken include 
FDS fire modeling, physical examination of material samples, ANSYS and 
COBRA-SFS code thermal modeling of a GA-4 package, ANSYS and LS-DYNA 
structural and thermal-structural modeling of the roadway and package, 
and fuel performance modeling using the FRAPTRAN-1.4, FRAPCON-3.4, and 
DATING codes. The estimated release from the hypothetical scenario is 
below the prescribed limit for safety.
    The purpose of this notice is to provide the public with an 
opportunity to review and provide comments on draft NUREG/CR-7206, 
``Spent Fuel Transportation Package Response to the MacArthur Maze Fire 
Scenario''. Any comments received will be considered in the final 
version or subsequent revisions of the draft NUREG/CR.

    Dated at Rockville, Maryland, this 17th day of December, 2015.

    For the Nuclear Regulatory Commission.
Christian Araguas,
Chief, Containment, Structural, and Thermal Branch, Division of Spent 
Fuel Management, Office of Nuclear Materials Safety and Safeguards.
[FR Doc. 2015-32514 Filed 12-23-15; 8:45 am]
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