[Federal Register Volume 75, Number 217 (Wednesday, November 10, 2010)]
[Notices]
[Pages 69140-69141]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2010-28401]
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NUCLEAR REGULATORY COMMISSION
[NRC-2010-0344]
NUREG-1953, Confirmatory Thermal-Hydraulic Analysis To Support
Specific Success Criteria in the Standardized Plant Analysis Risk
Models--Surry and Peach Bottom; Draft Report for Comment
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of availability and request for comments.
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SUMMARY: The Nuclear Regulatory Commission has issued for public
comment a document entitled: NUREG-1953, ``Confirmatory Thermal-
Hydraulic Analysis to Support Specific Success Criteria in the
Standardized Plant Analysis Risk Models--Surry and Peach Bottom, Draft
Report for Comment.''
DATES: Please submit comments by December 15, 2010. Comments received
after this date will be considered if it is practical to do so, but the
NRC staff is able to ensure consideration only for comments received on
or before this date.
ADDRESSES: You may submit comments by any one of the following methods.
Please include Docket ID NRC-2010-0344 in the subject line of your
comments. Comments submitted in writing or in electronic form will be
posted on the NRC Web site and on the Federal rulemaking Web site
Regulations.gov. Because your comments will not be edited to remove any
identifying or contact information, the NRC cautions you against
including any information in your submission that you do not want to be
publicly disclosed.
The NRC requests that any party soliciting or aggregating comments
received from other persons for submission to the NRC inform those
persons that the NRC will not edit their comments to remove any
identifying or contact information, and therefore, they should not
include any information in their comments that they do not want
publicly disclosed.
Federal Rulemaking Web site: Go to http://www.regulations.gov and
search for documents filed under Docket ID NRC-2010-0344. Address
questions about NRC dockets to Carol Gallagher 301-492-3668; e-mail
[email protected].
Mail comments to: Cindy Bladey, Chief, Rules Announcements and
Directives Branch (RADB), Division of Administrative Services, Office
of Administration, Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, or by fax to RADB at 301-492-
3446.
You can access publicly available documents related to this notice
using the following methods:
NRC's Public Document Room (PDR): The public may examine and have
copied, for a fee, publicly available documents at the NRC's PDR,
Public File Area O1 F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
Publicly available documents created or received at the NRC are
available electronically at the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain
entry into ADAMS, which provides text and image files of NRC's public
documents. If you do not have access to ADAMS or if there are problems
in accessing the documents located in ADAMS, contact the NRC's PDR
reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to
[email protected]. NUREG-1953 is available electronically under
ADAMS Accession Number ML102940233.
Federal Rulemaking Web site: Public comments and supporting
materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID: NRC-2010-0344.
FOR FURTHER INFORMATION CONTACT: Donald Helton, Division of Risk
Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear
Regulatory
[[Page 69141]]
Commission, Washington, DC 20555-0001. Telephone: 301-251-7594, e-mail:
[email protected].
SUPPLEMENTARY INFORMATION: NUREG-1953, ``Confirmatory Thermal-Hydraulic
Analysis to Support Specific Success Criteria in the Standardized Plant
Analysis Risk Models--Surry and Peach Bottom, Draft Report for
Comment,'' investigates specific thermal-hydraulic aspects of the Surry
and Peach Bottom Standardized Plant Analysis Risk models, with the goal
of further strengthening the technical basis for decisionmaking that
relies on the SPAR models. This analysis employs the MELCOR computer
code to analyze a number of scenarios with different assumptions.
Dated at Rockville, Maryland, October 27, 2010.
For the Nuclear Regulatory Commission.
Kevin A. Coyne,
Chief, Probabilistic Risk Assessment Branch, Division of Risk Analysis,
Office of Nuclear Regulatory Research.
[FR Doc. 2010-28401 Filed 11-9-10; 8:45 am]
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