Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Reliability and PRA; Revision to Notice of Meetings, 40202 [2013-16005]

Download as PDF emcdonald on DSK67QTVN1PROD with NOTICES 40202 Federal Register / Vol. 78, No. 128 / Wednesday, July 3, 2013 / Notices NUHOMS® 24PHB DSCs under CoC No. 1004 at the Oconee Nuclear Station. These fuel assemblies have M5 cladding (a zirconium alloy), but the current TSs allow only ‘‘zircaloy’’ clad assemblies. Approval of the exemption request will allow the applicant to effectively manage its spent fuel inventory to meet decay heat zoning requirements throughout its scheduled loading campaigns. The applicant’s ability to load M5 clad fuel in its next scheduled loading campaign will mean that older ‘‘zircaloy clad’’ fuel assemblies will be available for future loadings, so that future loadings will not be restricted by the aggregate heat generated by hotter fuel and therefore contain fewer total assemblies. The proposed action enables the applicant to load the fewest possible DSCs by permitting cask loading of the hotter M5 fuel without later needing to ‘‘short load’’ casks due to heat load. Environmental Impacts of the Proposed Action: The staff has determined that the proposed action would not endanger life or property and would not have significant impacts on the human environment. The potential impact of using the TN Standardized NUHOMS® dry cask storage system was initially evaluated in the EA for the rulemaking to add the TN Standardized NUHOMS® Horizontal Modular Storage System for Irradiated Nuclear Fuel to the list of approved spent fuel storage casks in 10 CFR 72.214 (59 FR 28496, June 2, 1994 (Proposed Rule); 59 FR 65920, December 22, 1994 (Final Rule)). The exemption proposed to Amendment No. 9 to CoC 1004 would permit the loading of M5 clad B&W Mark B11 and B11A fuel. The proposed action does not result in any changes to the types or amounts of any radiological effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure as a result of the proposed action. Therefore, there are no significant environmental impacts associated with the proposed action. The proposed action only affects the requirements associated with the fuel assemblies to be loaded into the 24PHB DSCs and does not affect plant effluents, or any other aspects of the environment. Therefore, there are no significant impacts associated with the proposed action. Accordingly, the Commission concludes that there are no significant environmental impacts associated with the proposed action. Alternative to the Proposed Action: Because there is no significant environmental impact associated with the proposed action, alternatives with equal or greater environmental impact VerDate Mar<15>2010 17:48 Jul 02, 2013 Jkt 229001 were not evaluated. As an alternative to the proposed action, the staff considered denial of the proposed action. Denial of the proposed action would involve loading additional DSCs due to heat load restrictions, as described in the safety evaluation report. Denial of the exemption would result in an increase in radiological exposure to workers, potential additional radioactive releases to the environment, additional opportunities for accidents, and increased cost to the licensee. Therefore, the NRC staff has determined that approving the proposed action has a lesser environmental impact than denying the proposed action. Agencies and Persons Consulted: The EA associated with this exemption request was sent to Ms. Shelly Wilson of the South Carolina Department of Health and Environmental Control (SCDHEC) by email dated April 10, 2013 (ADAMS Accession No. ML13107B435). The state response was received by email dated April 11, 2013 (ADAMS Accession No. ML13107B441). The email states that SCDHEC reviewed the draft EA and has no comments. The NRC staff has determined that a consultation under Section 7 of the Endangered Species Act is not required, because the proposed action will not affect listed species or critical habitat. The NRC staff has also determined that the proposed action is not a type of activity that has the potential to impact historic properties, because the proposed action would occur within the established Oconee site boundary. Therefore, no consultation is required under Section 106 of the National Historic Preservation Act. III. Finding of No Significant Impact The environmental impacts of the proposed action have been reviewed in accordance with the requirements set forth in 10 CFR part 51. Based upon the foregoing Environmental Assessment, the Commission finds that the proposed action of granting the exemption from the requirements of 10 CFR 72.212(a)(2), 72.212(b)(3), 72.212(b)(5)(i), 72.214, and the portion of 10 CFR 72.212(b)(11) that states the licensee shall comply with the terms, conditions, and specifications of the CoC limited to the loading of the 24PHB DSCs with M5 clad B&W Mark B11 and Mark B11A fuel assemblies, will not significantly impact the quality of the human environment. Accordingly, the Commission has determined that preparation of an environmental impact statement for the proposed exemption is not warranted and that a finding of no significant impact is appropriate. PO 00000 Frm 00114 Fmt 4703 Sfmt 4703 Dated at Rockville, Maryland, this 19th day of June 2013. For the Nuclear Regulatory Commission. W. Christopher Allen, Acting Chief, Licensing Branch, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2013–16029 Filed 7–2–13; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Reliability and PRA; Revision to Notice of Meetings The Federal Register Notice for the ACRS Subcommittee Meeting on Reliability and PRA scheduled to be held on July 22, 2013, is being revised to notify the following: The meeting will be open to public attendance with the exception of a portion that may be closed pursuant to 5 U.S.C. 552b(c)(4) to discuss proprietary information of the voluntary site. The notice of this meeting was previously published in the Federal Register on Friday June 21, 2013 [78 FR 37596–37597]. Further information regarding these meetings can be obtained by contacting the Designated Federal Official (DFO), John Lai (Telephone 301–415–5197 or Email: John.Lai@nrc.gov) between 8:15 a.m. and 5:00 p.m. Dated: June 26, 2013. Antonio Dias, Technical Advisor, Advisory Committee on Reactor Safeguards. [FR Doc. 2013–16005 Filed 7–1–13; 8:45 am] BILLING CODE 7590–01–P OFFICE OF PERSONNEL MANAGEMENT National Council on Federal LaborManagement Relations Meeting Office of Personnel Management. ACTION: Notice of meeting. AGENCY: The National Council on Federal Labor-Management Relations plans to meet on Wednesday, September 18, 2013. The meeting will start at 10:00 a.m. EDT and will be held at the U.S. Office of Personnel Management, 1900 E Street NW., Room 1350, Washington, DC 20415. Interested parties should consult the Council Web site at SUMMARY: E:\FR\FM\03JYN1.SGM 03JYN1

Agencies

[Federal Register Volume 78, Number 128 (Wednesday, July 3, 2013)]
[Notices]
[Page 40202]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-16005]


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NUCLEAR REGULATORY COMMISSION


Advisory Committee On Reactor Safeguards (ACRS); Meeting of the 
ACRS Subcommittee On Reliability and PRA; Revision to Notice of 
Meetings

    The Federal Register Notice for the ACRS Subcommittee Meeting on 
Reliability and PRA scheduled to be held on July 22, 2013, is being 
revised to notify the following:
    The meeting will be open to public attendance with the exception of 
a portion that may be closed pursuant to 5 U.S.C. 552b(c)(4) to discuss 
proprietary information of the voluntary site.
    The notice of this meeting was previously published in the Federal 
Register on Friday June 21, 2013 [78 FR 37596-37597].
    Further information regarding these meetings can be obtained by 
contacting the Designated Federal Official (DFO), John Lai (Telephone 
301-415-5197 or Email: John.Lai@nrc.gov) between 8:15 a.m. and 5:00 
p.m.

    Dated: June 26, 2013.
Antonio Dias,
Technical Advisor, Advisory Committee on Reactor Safeguards.
[FR Doc. 2013-16005 Filed 7-1-13; 8:45 am]
BILLING CODE 7590-01-P