Notice of Availability of Documents Regarding Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario, 72681-72682 [E5-6892]

Download as PDF Federal Register / Vol. 70, No. 233 / Tuesday, December 6, 2005 / Notices Amendment No.: 246. Renewed Facility Operating License No. NPF–4: Amendment revises the Technical Specifications. Public comments requested as to proposed no significant hazards consideration (NSHC): No. The Commission’s related evaluation of the amendment, finding of emergency circumstances, state consultation, and final NSHC determination are contained in a Safety Evaluation dated November 4, 2005. Attorney for licensee: Ms. Lillian M. Cuoco, Esq., Senior Counsel, Dominion Resources Services, Inc., Millstone Power Station, Building 475, 5th Floor, Rope Ferry Road, Rt. 156, Waterford, Connecticut 06385. NRC Section Chief: Evangelos Marinos. Dated at Rockville, Maryland, this 28th day of November, 2005. For the Nuclear Regulatory Commission. Catherine Haney, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 05–23553 Filed 12–5–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Notice of Availability of Documents Regarding Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario Nuclear Regulatory Commission. ACTION: Notice of availability. AGENCY: FOR FURTHER INFORMATION CONTACT: Allen Hansen, Thermal Engineer, Criticality, Shielding and Heat Transfer Section, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20005– 0001. Telephone: (301) 415–1390; fax number: (301) 415–8555; e-mail: agh@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction Under contract with the Nuclear Regulatory Commission (NRC), the Pacific Northwest National Laboratory prepared the draft NUREG/CR–6886 report, ‘‘Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire (BTF) Scenario.’’ The BTF was chosen for the study because it represents a severe historical accident, even though it is a very low frequency event. This NUREG/CR documents the thermal analyses of three different spent fuel transportation packages exposed to the BTF scenario: Transnuclear’s TN– 68, Holtec’s HI-STAR 100 and the NAC’s LWT. To date comments have been received from the State of Nevada, Office of the Governor, Agency For Nuclear Projects and the Western Interstate Energy Board. These comments do not need to be re-submitted. The format of this NUREG/CR has been modified since original posting on the NRC Electronic Reading Room at https://www.nrc.gov/reading-rm/ adams.html in September 2005. The modified draft NUREG/CR is now posted on the NRC Web site at the following URLs: https://www.nrc.gov/reading-rm/doccollections/nuregs/ docs4comment.html. https://www.nrc.gov/reading-rm/doccollections/nuregs/contract/cr6886/. These links include access to the formal comment template. The results of this study strongly indicate that neither spent nuclear fuel (SNF) particles nor fission products would be released from a spent fuel shipping cask involved in a severe tunnel fire such as the Baltimore Tunnel Fire. None of the three cask designs analyzed for the Baltimore Tunnel fire scenario experienced internal temperatures that would result in rupture of the fuel cladding. Therefore, the radioactive material (i.e., SNF 72681 particles or fission products) would be retained within the fuel rods. For two of the casks, the TN–68 and the NAC–LWT, the maximum temperatures experienced in the regions of the lid, vent and drain ports exceeded the seals’ rated service temperatures, making it possible to get a small release from the CRUD 1 that might spall off of the surfaces of the fuel rods. However, any release is expected to be very small due to a number of factors. These include: (1) The tight clearances maintained between the lid and cask body; (2) the low pressure differential between the cask interior and the outside; (3) the tendency of the small clearances to plug; and (4) the tendency of CRUD particles to settle or plate out. The potential releases calculated in Chapter 8 for the TN–68 rail cask and the NAC–LWT truck cask indicate that the release of CRUD from either cask, if any, would be very small. There would be no release from the HI–STAR 100 because the inner welded canister remains leak tight. II. Summary The purpose of this notice is to provide the public an opportunity to review and comment on the Draft NUREG/CR–6886 thermal analyses, the consequence analyses and the conclusions. III. Further Information The draft NUREG/CR can also be viewed at the NRC’s Electronic Reading Room at https://www.nrc.gov/readingrm/adams.html. From this site you can access the NRC’s Agencywide Document Access and Management System (ADAMS), which provides text and image files of NRC’s public documents. The ADAMS accession number for the edited (format only) NUREG is ML053200024. This file is in ‘‘black and white.’’ The original draft is in color and can be accessed at the following accession numbers: NUREG/CR Files ADAMS accession No. Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario .................................................................... Appendix A—Material Properties for COBRA–SFS Model of TN–68 Package ................................................................................. Appendix B—Material Properties for ANSYS Model of HI–STAR 100 Package ............................................................................... Appendix C—Material Properties for ANSYS Model of Legal Weight Truck Package ...................................................................... Appendix D—Blackbody View Factors for COBRA–SFS Model of TN–68 Package ......................................................................... Appendix E—HOLTEC HI–STAR 100 Component Temperature Distributions .................................................................................. ML052500391 ML052490246 ML052490258 ML052490264 ML052490268 ML052490270 1 CRUD is an abbreviation of Chalk River Unknown Deposit, a generic term for various VerDate Aug<31>2005 17:44 Dec 05, 2005 Jkt 205001 residues deposited on fuel rod surfaces, originally coined by Atomic Energy of Canada, Ltd. to PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 describe deposits observed on fuel removed from the test reactor at Chalk River. E:\FR\FM\06DEN1.SGM 06DEN1 72682 Federal Register / Vol. 70, No. 233 / Tuesday, December 6, 2005 / Notices If you do not have access to ADAMS or if there are problems in accessing the document, you may contact the NRC Public Document Room (PDR) Reference staff at 1–800–397–4209, 301–415–4737, or by e-mail to pdr@nrc.gov. This document may also be viewed electronically on the public computers located at the NRC’s PDR, O 1 F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. Comments and questions on draft NUREG/CR–6886 should be entered in the comment box (see URLs above) or directed to the NRC contact listed below by December 30, 2005. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. Contact: Allen Hansen, Thermal Engineer, Criticality, Shielding and Heat Transfer Section, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20005– 0001. Telephone: (301) 415–1390; fax number: (301) 415–8555; e-mail: agh@nrc.gov. Dated at Rockville, Maryland this 30th day of November, 2005. For the Nuclear Regulatory Commission. M. Wayne Hodges, Deputy Director, Technical Review Directorate, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards. [FR Doc. E5–6892 Filed 12–5–05; 8:45 am] Based on a review of the application that BS&Co. submitted, the Commission has determined that the application meets the requirements of Appendix E. The Commission also has determined that TBSCI is in compliance with the terms of its undertakings, as provided to the Commission under Appendix E. The Commission, therefore, finds that approval of the application is necessary or appropriate in the public interest or for the protection of investors. Accordingly, It Is Ordered, under paragraph (a)(7) of Rule 15c3–1 (17 CFR 240.15c3–1) to the Exchange Act, that BS&Co. may calculate net capital using the market risk standards of Appendix E to compute a deduction for market risk on some or all of its positions, instead of the provisions of paragraphs (c)(2)(vi) and (c)(2)(vii) of Rule 15c3–1, and using the credit risk standards of Appendix E to compute a deduction for credit risk on certain credit exposures arising from transactions in derivatives instruments, instead of the provision of paragraph (c)(2)(iv) of Rule 15c3–1. By the Commission. Jonathan G. Katz, Secretary. [FR Doc. E5–6858 Filed 12–5–05; 8:45 am] BILLING CODE 8010–01–P SECURITIES AND EXCHANGE COMMISSION BILLING CODE 7590–01–P [Release No. 34–52853; File No. SR–FICC– 2005–14] SECURITIES AND EXCHANGE COMMISSION Self-Regulatory Organizations; Fixed Income Clearing Corporation; Order Granting Approval of a Proposed Rule Change Relating to the Federal Reserve’s National Settlement System [Release No. 52857/November 30, 2005] Securities Exchange Act of 1934; Order Regarding Alternative Net Capital Computation for Bear, Stearns & Co. Inc., Which Has Elected To Be Supervised on a Consolidated Basis Bear Stearns & Co., Inc. (‘‘BS&Co.’’), a broker-dealer registered with the Securities and Exchange Commission (‘‘Commission’’), and its ultimate holding company, The Bear Stearns Companies Inc. (‘‘TBSCI’’), have indicated their desire to be supervised by the Commission as a consolidated supervised entity (‘‘CSE’’). BS&Co., therefore, has submitted an application to the Commission for authorization to use the alternative method of computing net capital contained in Appendix E to Rule 15c3–1 (17 CFR 240.15c3–1e) to the Securities Exchange Act of 1934 (‘‘Exchange Act’’). VerDate Aug<31>2005 17:44 Dec 05, 2005 Jkt 205001 November 29, 2005. I. Introduction On September 9, 2005, Fixed Income Clearing Corporation (‘‘FICC’’) filed with the Securities and Exchange Commission (‘‘Commission’’) proposed rule change SR–FICC–2005–14 pursuant to Section 19(b)(1) of the Securities Exchange Act of 1934 (‘‘Act’’).1 Notice of the proposal was published in the Federal Register on October 26, 2005.2 No comment letters were received. For the reasons discussed below, the Commission is granting approval of the proposed rule change. 1 15 U.S.C. 78s(b)(1). Exchange Act Release No. 52631, (October 18, 2005), 70 FR 61859. 2 Securities PO 00000 Frm 00078 Fmt 4703 Sfmt 4703 II. Description The proposed rule change amends the rules of FICC’s Government Securities Division (‘‘GSD’’) so that funds-only settlement obligation payment processing occurs through the Federal Reserve’s National Settlement System (‘‘NSS’’).3 GSD’s funds-only settlement process is set forth in GSD Rule 13. On a daily basis, FICC reports a funds-only settlement amount, which is either a debit amount or a credit amount, to each netting member. Each netting member that has a debit is required to satisfy its obligation by the applicable deadline. Netting members with credits are subsequently paid by FICC by the applicable deadline. All payments of funds-only settlement amounts by netting members to FICC and all collections of funds-only settlement amounts by netting members from FICC are done through depository institutions that are designated by netting members and FICC to act for them with regard to such payments and collections. All payments are made by fund wires from one depository institution to the other. In 1997, the Commission approved an enhancement to GSCC’s 4 funds-only settlement payment processing (‘‘1997 Filing’’).5 That enhancement gave members the option to participate in an auto-debit arrangement. Under the autodeposit arrangement, GSCC, the netting member, and the netting member’s depository institution would enter into a ‘‘funds-only settlement procedures agreement’’ whereby the depository institution would pay or collect fundsonly settlement amounts on behalf of the netting member and GSCC through accounts of the member at the depository institution. As a result, the need to send fund wires for the satisfaction of funds-only settlement payments would be eliminated.6 The rule change replaces the autodebit process of the 1997 Filing and 3 This is consistent with the manner in which FICC’s affiliates, The Depository Trust Company (‘‘DTC’’) and the National Securities Clearing Corporation (‘‘NSCC’’), handle their funds settlement process. DTC and NSCC currently use NSS for the processing of funds debits and not for funds credits whereas FICC will use NSS both for the funds debits and funds credits of GSD’s fundsonly settlement process. 4 The Government Securities Clearing Corporation (‘‘GSCC’’) was the predecessor to GSD. GSCC became the GSD division of FICC when GSCC and the Mortgage Backed Securities Clearing Corporation were merged to create FICC in 2002. 5 Securities Exchange Act Release No. 39309 (November 7, 1997), 62 FR 61158 (November 14, 1997) [File No. SR–GSCC–97–06]. 6 This voluntary arrangement auto-debit was never implemented because until recently GSCC and then GSD continued to make manual adjustments to the final funds-only settlement amounts of netting members. Recently, these manual adjustments have largely been eliminated. E:\FR\FM\06DEN1.SGM 06DEN1

Agencies

[Federal Register Volume 70, Number 233 (Tuesday, December 6, 2005)]
[NOTIC]
[Pages 72681-72682]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-6892]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION


Notice of Availability of Documents Regarding Spent Fuel 
Transportation Package Response to the Baltimore Tunnel Fire Scenario

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of availability.

-----------------------------------------------------------------------

FOR FURTHER INFORMATION CONTACT: Allen Hansen, Thermal Engineer, 
Criticality, Shielding and Heat Transfer Section, Spent Fuel Project 
Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20005-0001. Telephone: (301) 415-
1390; fax number: (301) 415-8555; e-mail: agh@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    Under contract with the Nuclear Regulatory Commission (NRC), the 
Pacific Northwest National Laboratory prepared the draft NUREG/CR-6886 
report, ``Spent Fuel Transportation Package Response to the Baltimore 
Tunnel Fire (BTF) Scenario.'' The BTF was chosen for the study because 
it represents a severe historical accident, even though it is a very 
low frequency event. This NUREG/CR documents the thermal analyses of 
three different spent fuel transportation packages exposed to the BTF 
scenario: Transnuclear's TN-68, Holtec's HI-STAR 100 and the NAC's LWT.
    To date comments have been received from the State of Nevada, 
Office of the Governor, Agency For Nuclear Projects and the Western 
Interstate Energy Board. These comments do not need to be re-submitted.
    The format of this NUREG/CR has been modified since original 
posting on the NRC Electronic Reading Room at https://www.nrc.gov/
reading-rm/adams.html in September 2005. The modified draft NUREG/CR is 
now posted on the NRC Web site at the following URLs:

https://www.nrc.gov/reading-rm/doc-collections/nuregs/docs4comment.html.
https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6886/.

These links include access to the formal comment template.
    The results of this study strongly indicate that neither spent 
nuclear fuel (SNF) particles nor fission products would be released 
from a spent fuel shipping cask involved in a severe tunnel fire such 
as the Baltimore Tunnel Fire. None of the three cask designs analyzed 
for the Baltimore Tunnel fire scenario experienced internal 
temperatures that would result in rupture of the fuel cladding. 
Therefore, the radioactive material (i.e., SNF particles or fission 
products) would be retained within the fuel rods.
    For two of the casks, the TN-68 and the NAC-LWT, the maximum 
temperatures experienced in the regions of the lid, vent and drain 
ports exceeded the seals' rated service temperatures, making it 
possible to get a small release from the CRUD \1\ that might spall off 
of the surfaces of the fuel rods. However, any release is expected to 
be very small due to a number of factors. These include: (1) The tight 
clearances maintained between the lid and cask body; (2) the low 
pressure differential between the cask interior and the outside; (3) 
the tendency of the small clearances to plug; and (4) the tendency of 
CRUD particles to settle or plate out. The potential releases 
calculated in Chapter 8 for the TN-68 rail cask and the NAC-LWT truck 
cask indicate that the release of CRUD from either cask, if any, would 
be very small. There would be no release from the HI-STAR 100 because 
the inner welded canister remains leak tight.
---------------------------------------------------------------------------

    \1\ CRUD is an abbreviation of Chalk River Unknown Deposit, a 
generic term for various residues deposited on fuel rod surfaces, 
originally coined by Atomic Energy of Canada, Ltd. to describe 
deposits observed on fuel removed from the test reactor at Chalk 
River.
---------------------------------------------------------------------------

II. Summary

    The purpose of this notice is to provide the public an opportunity 
to review and comment on the Draft NUREG/CR-6886 thermal analyses, the 
consequence analyses and the conclusions.

III. Further Information

    The draft NUREG/CR can also be viewed at the NRC's Electronic 
Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this 
site you can access the NRC's Agencywide Document Access and Management 
System (ADAMS), which provides text and image files of NRC's public 
documents. The ADAMS accession number for the edited (format only) 
NUREG is ML053200024. This file is in ``black and white.'' The original 
draft is in color and can be accessed at the following accession 
numbers:

------------------------------------------------------------------------
              NUREG/CR Files                    ADAMS accession No.
------------------------------------------------------------------------
Spent Fuel Transportation Package          ML052500391
 Response to the Baltimore Tunnel Fire
 Scenario.
Appendix A--Material Properties for COBRA- ML052490246
 SFS Model of TN-68 Package.
Appendix B--Material Properties for ANSYS  ML052490258
 Model of HI-STAR 100 Package.
Appendix C--Material Properties for ANSYS  ML052490264
 Model of Legal Weight Truck Package.
Appendix D--Blackbody View Factors for     ML052490268
 COBRA-SFS Model of TN-68 Package.
Appendix E--HOLTEC HI-STAR 100 Component   ML052490270
 Temperature Distributions.
------------------------------------------------------------------------


[[Page 72682]]

If you do not have access to ADAMS or if there are problems in 
accessing the document, you may contact the NRC Public Document Room 
(PDR) Reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to 
pdr@nrc.gov.
    This document may also be viewed electronically on the public 
computers located at the NRC's PDR, O 1 F21, One White Flint North, 
11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction 
contractor will copy documents for a fee. Comments and questions on 
draft NUREG/CR-6886 should be entered in the comment box (see URLs 
above) or directed to the NRC contact listed below by December 30, 
2005. Comments received after this date will be considered if it is 
practical to do so, but assurance of consideration cannot be given to 
comments received after this date.
    Contact: Allen Hansen, Thermal Engineer, Criticality, Shielding and 
Heat Transfer Section, Spent Fuel Project Office, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20005-0001. Telephone: (301) 415-1390; fax number: (301) 
415-8555; e-mail: agh@nrc.gov.

    Dated at Rockville, Maryland this 30th day of November, 2005.

    For the Nuclear Regulatory Commission.
M. Wayne Hodges,
Deputy Director, Technical Review Directorate, Spent Fuel Project 
Office, Office of Nuclear Material Safety and Safeguards.
 [FR Doc. E5-6892 Filed 12-5-05; 8:45 am]
BILLING CODE 7590-01-P
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