2010-32140. 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:

Announcement of reopening of public comment period

SUMMARY:

The Nuclear Regulatory Commission is re-opening the public comment period for the 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.” This report was originally issued for public comment via Federal Register Notice [75 FR 69140-69141], dated November 10, 2010 (NRC-2010-0344).

DATES:

Please submit comments by February 28, 2011. 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: [e-mail].

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 [e-mail]. 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 Commission, Washington, DC 20555-0001. Telephone: [phone], e-mail: [e-mail].

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, this 15th day of December, 2010.

For the Nuclear Regulatory Commission.

Kevin A. Coyne,

Chief, Probabilistic Risk Assessment Branch, Division of Risk Analysis, Office of Nuclear Regulatory Research.