Sunshine Federal Register Notice, 13099-13100 [2013-04511]

Download as PDF Federal Register / Vol. 78, No. 38 / Tuesday, February 26, 2013 / Notices even if one or more of the criteria are not deemed to be adequate, the NRC staff may still decide that the overall IPEEE analysis is adequate to support its use for screening purposes. The NRC staff may conduct site visits to view IPEEE documentation referenced in support of the IPEEE adequacy submittal. tkelley on DSK3SPTVN1PROD with NOTICES Development of FIRS The SPID report does not discuss the development of FIRS used for performing soil-structure interaction analyses. Consistent with guidance described in DC/COL–ISG–017, ‘‘Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses,’’ the FIRS should be derived in a manner consistent with the site response used in the development of the site-specific GMRS. As such, the FIRS should be derived as performance-based sitespecific response spectra at the foundation level in the free field. The starting point for development of the FIRS should be the same hard rock elevation used as the starting point for developing the GMRS. As the engineering properties of soil are straindependent and can be highly non-linear, the characterization of soil layers and their associated properties used in the GMRS analysis should also be used for the derivation of the site-specific FIRS at the foundation elevation. The performance-based FIRS can be developed using either a full-column outcrop motion that includes the effect of the soil above, or as a geologic outcrop motion for which the soil layers above the foundation elevation have been removed. Updating the Central and Eastern United States (CEUS)-Seismic Source Characterization (SSC) Model Section 2.2 of the SPID report provides an overview of the CEUS–SSC model and explains why it is appropriate to use without update for the seismic reevaluations. Specifically, Section 2.2 states ‘‘for site-specific licensing applications or site-specific safety decisions, these seismic sources would be reviewed on a site-specific basis to determine if they need to be updated. Such evaluations would be appropriate in a licensing application, where focus could be made on sitespecific applications. However, for a screening-level study of multiple plants for the purpose of setting priorities, the use of these seismic sources as published is appropriate.’’ The NRC staff agrees that the CEUS– SSC model does not need to be updated for the seismic reevaluations, but the VerDate Mar<15>2010 16:35 Feb 25, 2013 Jkt 229001 staff’s rationale is different than that presented in the SPID report. Specifically, the staff has determined that the CEUS–SSC model does not need to be updated because the model is up-to-date and is sufficiently refined to allow a site-specific source model to be developed. To adequately respond to the 50.54(f) letter, a site-specific GMRS should be calculated for each plant so that an informed decision can be made regarding which plants will be required to complete a risk evaluation. Further, the site-specific GMRS will also be used in the risk evaluations. Prior to issuing the CEUS–SSC model, the Technical Integration Team considered potentially significant events (such as the 2011 Mineral, VA earthquake) that had occurred after the model was developed, and determined that those events did not change their interpretations of seismic sources or earthquake recurrence rates. If a significant earthquake in the CEUS were to occur or new information were to emerge during the reevaluation period that could require an update of the CEUS–SSC model, the staff expects licensees to evaluate the significance of the new information to determine if the CEUS–SSC model needs to be updated in order to appropriately respond to the 50.54(f) request. Site Response Section 2.4.1 and Appendix B of the SPID report provides guidance on how to develop the site response in cases where limited site response data exists. As stated in Appendix B, the NRC staff expects licensees to use available geologic, geotechnical, and geophysical data collected during the initial licensing or subsequent activities at the site to the extent practicable. Where limited site response data exists, information from core borings and data collected from site and regional evaluations should be used to develop the site response amplification. Section 4 of the SPID report states that licensees should provide the basis for the site responses used in the reevaluations. The NRC staff expects site-specific geology, geotechnical, and geophysical information to be a significant part of the basis. Non-Concurrence An NRC staff member did not agree with some content of the SPID report and submitted a non-concurrence on the SPID endorsement letter. In accordance with the NRC’s non-concurrence process, NRC management and staff worked to address the staff member’s concerns, and documentation of the non-concurrence can be found in PO 00000 Frm 00086 Fmt 4703 Sfmt 4703 13099 ADAMS at Accession No. ML12324A195. 60-Day Response In accordance with the 50.54(f) letter, each licensee is to submit to the NRC its intention to follow the NRC-endorsed seismic reevaluation guidance, or an alternative approach, 60 days after the issuance of the NRC-endorsed guidance. For the purpose of meeting this deadline, the 60-day response period commences on the date the endorsement letter is published in the Federal Register. Backfitting and Issue Finality This endorsement letter does not constitute backfitting as defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise inconsistent with the issue finality provisions in Part 52, ‘‘Licenses, Certifications, and Approvals for Nuclear Power Plants,’’ of 10 CFR. This endorsement letter provides guidance on an acceptable method for implementing the March 12, 2012, RFI. Applicants and licensees may voluntarily use the guidance in the SPID report, as clarified by the NRC staff in the endorsement letter, to comply with the RFI. Methods, analyses, or solutions that differ from those described in the SPID report may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative is acceptable. Congressional Review Act This endorsement letter is a rule as designated in the Congressional Review Act (5 U.S.C. 801–808). The Office of Management and Budget has found that this is a major rule in accordance with the Congressional Review Act. Dated at Rockville, Maryland, this 15th day of February 2013. For the Nuclear Regulatory Commission. David L. Skeen, Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation. [FR Doc. 2013–04396 Filed 2–25–13; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Sunshine Federal Register Notice AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission, [NRC–2013– 0001]. Weeks of February 25, March 4, 11, 18, 25, April 1, 2013. DATES: E:\FR\FM\26FEN1.SGM 26FEN1 13100 Federal Register / Vol. 78, No. 38 / Tuesday, February 26, 2013 / Notices PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. contact the Office of the Secretary, Washington, DC 20555 (301–415–1969), or send an email to darlene.wright@nrc.gov. Week of February 25, 2013 There are no meetings scheduled for the week of February 25, 2013. Dated: February 20, 2013. Rochelle C. Bavol, Policy Coordinator, Office of the Secretary. Week of March 4, 2013—Tentative There are no meetings scheduled for the week of March 4, 2013. Week of March 11, 2013—Tentative There are no meetings scheduled for the week of March 11, 2013. Week of March 18, 2013—Tentative There are no meetings scheduled for the week of March 18, 2013. Week of March 25, 2013—Tentative tkelley on DSK3SPTVN1PROD with NOTICES There are no meetings scheduled for the week of March 25, 2013. Week of April 1, 2013—Tentative Tuesday April 2, 2013 9:30 a.m. Meeting With Organization of Agreement States (OAS) and Conference of Radiation Control Program Directors (CRCPD) (Public Meeting) (Contact: Cindy Flannery, 301–415–0223) This meeting will be Webcast live at the Web address—www.nrc.gov. * * * * * * The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)—301–415–1292. Contact person for more information: Rochelle Bavol, 301–415–1651. * * * * * The NRC Commission Meeting Schedule can be found on the Internet at: https://www.nrc.gov/public-involve/ public-meetings/schedule.html. * * * * * The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format (e.g. braille, large print), please notify Kimberly Meyer, NRC Disability Program Manager, at 301–287–0727, or by email at kimberly.meyerchambers@nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. * * * * * This notice is distributed electronically to subscribers. If you no longer wish to receive it, or would like to be added to the distribution, please VerDate Mar<15>2010 16:35 Feb 25, 2013 Jkt 229001 [FR Doc. 2013–04511 Filed 2–22–13; 4:15 pm] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Project No. 753; NRC–2012–0280] Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF–535, Revision 0, ‘‘Revise Shutdown Margin Definition To Address Advanced Fuel Designs,’’ Using the Consolidated Line Item Improvement Process Nuclear Regulatory Commission. ACTION: Notice of availability. AGENCY: SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is announcing the availability of Technical Specifications (TSs) Task Force (TSTF) Traveler TSTF– 535, Revision 0, ‘‘Revise Shutdown Margin Definition to Address Advanced Fuel Designs,’’ for plant-specific adoption using the Consolidated Line Item Improvement Process (CLIIP). Additionally, the NRC staff finds the proposed TS (Volume 1) and TS Bases (Volume 2) changes in Traveler TSTF– 535 acceptable for inclusion in the following Standard Technical Specifications (STS): NUREG–1433, ‘‘Standard Technical Specifications General Electric Plants BWR/4,’’ and NUREG–1434, ‘‘Standard Technical Specifications General Electric Plants, BWR/6.’’ ADDRESSES: Please refer to Docket ID NRC–2012–0280 when contacting the NRC about the availability of information regarding this document. You may access information related to this document, which the NRC possesses and are publicly available, using any of the following methods: • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2012–0280. Address questions about NRC dockets to Carol Gallagher; telephone: 301–492–3668; email: Carol.Gallagher@nrc.gov. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at https://www.nrc.gov/readingrm/adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and PO 00000 Frm 00087 Fmt 4703 Sfmt 4703 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 pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced. TSTF–535, Revision 0, includes a model application and is available in ADAMS under Accession No. ML112200436. The model safety evaluation (SE) of TSTF–535, Revision 0, is available under ADAMS Accession No. ML12355A772. No public comments were received from the Notice of Opportunity for Public Comment announced in the Federal Register on November 19, 2012; 77 FR 69507. • 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. FOR FURTHER INFORMATION CONTACT: Ms. Michelle C. Honcharik, Senior Project Manager, telephone: 301–415–1774 or email at Michelle.Honcharik@nrc.gov; or Mr. Ravinder Grover, Reactor Systems Engineer, telephone: 301–415–2166 or email at Ravinder.Grover@nrc.gov. Both of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC, 20555– 0001. Congressional Review Act In accordance with the Congressional Review Act of 1996, the NRC has determined that this action is not a major rule and has verified this determination with the OMB Office of Information and Regulatory Affairs. SUPPLEMENTARY INFORMATION: TSTF– 535, Revision 0, is applicable to all boiling water reactor (BWR) power plants. The change revises the STS, NUREG–1433, ‘‘Standard Technical Specifications General Electric Plants BWR/4,’’ and NUREG–1434, ‘‘Standard Technical Specifications General Electric Plants, BWR/6.’’ Specifically, the change revises the STS definition of shutdown margin (SDM) to require calculation of SDM at the reactor moderator temperature corresponding to the most reactive state throughout the operating cycle (68 °F or higher). The purpose is to address newer BWR fuel designs, which may be more reactive at shutdown temperatures above 68 °F. This STS improvement is part of the CLIIP. The NRC staff has reviewed the model application for TSTF–535 and has found E:\FR\FM\26FEN1.SGM 26FEN1

Agencies

[Federal Register Volume 78, Number 38 (Tuesday, February 26, 2013)]
[Notices]
[Pages 13099-13100]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-04511]


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NUCLEAR REGULATORY COMMISSION


Sunshine Federal Register Notice

AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission, [NRC-2013-
0001].

DATES: Weeks of February 25, March 4, 11, 18, 25, April 1, 2013.

[[Page 13100]]


PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, 
Maryland.

STATUS: Public and Closed.

Week of February 25, 2013

    There are no meetings scheduled for the week of February 25, 2013.

Week of March 4, 2013--Tentative

    There are no meetings scheduled for the week of March 4, 2013.

Week of March 11, 2013--Tentative

    There are no meetings scheduled for the week of March 11, 2013.

Week of March 18, 2013--Tentative

    There are no meetings scheduled for the week of March 18, 2013.

Week of March 25, 2013--Tentative

    There are no meetings scheduled for the week of March 25, 2013.

Week of April 1, 2013--Tentative

    Tuesday April 2, 2013

9:30 a.m. Meeting With Organization of Agreement States (OAS) and 
Conference of Radiation Control Program Directors (CRCPD) (Public 
Meeting) (Contact: Cindy Flannery, 301-415-0223)

    This meeting will be Webcast live at the Web address--www.nrc.gov.
* * * * *
    * The schedule for Commission meetings is subject to change on 
short notice. To verify the status of meetings, call (recording)--301-
415-1292. Contact person for more information: Rochelle Bavol, 301-415-
1651.
* * * * *
    The NRC Commission Meeting Schedule can be found on the Internet 
at: https://www.nrc.gov/public-involve/public-meetings/schedule.html.
* * * * *
    The NRC provides reasonable accommodation to individuals with 
disabilities where appropriate. If you need a reasonable accommodation 
to participate in these public meetings, or need this meeting notice or 
the transcript or other information from the public meetings in another 
format (e.g. braille, large print), please notify Kimberly Meyer, NRC 
Disability Program Manager, at 301-287-0727, or by email at 
kimberly.meyer-chambers@nrc.gov. Determinations on requests for 
reasonable accommodation will be made on a case-by-case basis.
* * * * *
    This notice is distributed electronically to subscribers. If you no 
longer wish to receive it, or would like to be added to the 
distribution, please contact the Office of the Secretary, Washington, 
DC 20555 (301-415-1969), or send an email to darlene.wright@nrc.gov.

    Dated: February 20, 2013.
Rochelle C. Bavol,
Policy Coordinator, Office of the Secretary.
[FR Doc. 2013-04511 Filed 2-22-13; 4:15 pm]
BILLING CODE 7590-01-P
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