Advisory Committee on Reactor Safeguards (ACRS) Subcommittee Meeting on Materials, Metallurgy & Reactor Fuels; Revised, 8123 [E9-3753]

Download as PDF Federal Register / Vol. 74, No. 34 / Monday, February 23, 2009 / Notices jlentini on PROD1PC65 with NOTICES Based on its review, the staff has determined that the affected environment and any environmental impacts associated with the proposed action are bounded by the impacts evaluated by the ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities’’ (NUREG– 1496) Volumes 1–3 (ML042310492, ML042320379, and ML042330385). The staff finds there were no significant environmental impacts from the use of radioactive material at the Facility. The NRC staff reviewed the docket file records and the final status survey report to identify any non-radiological hazards that may have impacted the environment surrounding the Facility. No such hazards or impacts to the environment were identified. The NRC has identified no other radiological or non-radiological activities in the area that could result in cumulative environmental impacts. The NRC staff finds that the proposed release of the Facility for unrestricted use and the termination of the NRC materials license is in compliance with 10 CFR 20.1402. Based on its review, the staff considered the impact of the residual radioactivity at the Facility and concluded that the proposed action will not have a significant effect on the quality of the human environment. Environmental Impacts of the Alternatives to the Proposed Action Due to the largely administrative nature of the proposed action, its environmental impacts are small. Therefore, the only alternative the staff considered is the no-action alternative, under which the staff would leave things as they are by simply denying the amendment request. This no-action alternative is not feasible because it conflicts with 10 CFR 30.36(d), requiring that decommissioning of byproduct material facilities be completed and approved by the NRC after licensed activities cease. The NRC’s analysis of the Licensee’s final status survey data confirmed that the Facility meets the requirements of 10 CFR 20.1402 for unrestricted release. Additionally, denying the amendment request would result in no change in current environmental impacts. The environmental impacts of the proposed action and the no-action alternative are therefore similar, and the no-action alternative is accordingly not further considered. Conclusion The NRC staff has concluded that the proposed action is consistent with the VerDate Nov<24>2008 16:31 Feb 20, 2009 Jkt 217001 NRC’s unrestricted release criteria specified in 10 CFR 20.1402. Because the proposed action will not significantly impact the quality of the human environment, the NRC staff concludes that the proposed action is the preferred alternative. Agencies and Persons Consulted NRC provided a draft of this Environmental Assessment to the Bureau of Radiation Control, Florida Department of Health for review on December 2, 2008. On December 9, 2008, the Florida Bureau of Radiation Control responded by electronic mail. The State agreed with the conclusions of the EA, and otherwise had no comments. The NRC staff has determined that the proposed action is of a procedural nature, and will not affect listed species or critical habitat. Therefore, no further consultation is required under Section 7 of the Endangered Species Act. The NRC staff has also determined that the proposed action is not the type of activity that has the potential to cause effects on historic properties. Therefore, no further consultation is required under Section 106 of the National Historic Preservation Act. III. Finding of No Significant Impact The NRC staff has prepared this EA in support of the proposed action. On the basis of this EA, the NRC finds that there are no significant environmental impacts from the proposed action, and that preparation of an environmental impact statement is not warranted. Accordingly, the NRC has determined that a Finding of No Significant Impact is appropriate. IV. Further Information Documents related to this action, including the application for license amendment and supporting documentation, are available electronically 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 Documents Access and Management System (ADAMS), which provides text and image files of NRC’s public documents. The documents related to this action are listed below, along with their ADAMS accession numbers. 1. NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance;’’ 2. Title 10 Code of Federal Regulations, Part 20, Subpart E, ‘‘Radiological Criteria for License Termination;’’ 3. Title 10, Code of Federal Regulations, Part 51, ‘‘Environmental Protection Regulations for Domestic PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 8123 Licensing and Related Regulatory Functions;’’ 4. NUREG–1496, ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities;’’ and 5. United States Environmental Protection Agency letter dated September 3, 2008 [ML082690377]. If you do not have access to ADAMS, or if there are problems in accessing the documents located in ADAMS, contact the NRC Public Document Room (PDR) Reference staff at 1–800–397–4209, 301– 415–4737, or by e-mail to pdr.resource@nrc.gov. These documents 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. Dated at Region I, 475 Allendale Road, King of Prussia this 10th day of February 2009. For the Nuclear Regulatory Commission. James P. Dwyer, Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety Region I. [FR Doc. E9–3750 Filed 2–20–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Subcommittee Meeting on Materials, Metallurgy & Reactor Fuels; Revised The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels scheduled for Wednesday, March 4, 2009, has been moved to the Commission Hearing Room, 01–F16/01– G16, 11555 Rockville Pike, Rockville, Maryland, 20852. All other items pertaining to this meeting remain the same as published previously in the Federal Register on Tuesday, February 10, 2009. For future information contact: Michael L. Benson, Designated Federal Officer (Telephone: 301–415–6396) between 7 a.m. and 5 p.m. (ET) or by email Michael.Benson@nrc.gov. Dated, February 17, 2009. Cayetano Santos, Branch Chief Reactor Safety Branch A, Advisory Committee on Reactor Safeguards. [FR Doc. E9–3753 Filed 2–20–09; 8:45 am] BILLING CODE 7590–01–P E:\FR\FM\23FEN1.SGM 23FEN1

Agencies

[Federal Register Volume 74, Number 34 (Monday, February 23, 2009)]
[Notices]
[Page 8123]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-3753]


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NUCLEAR REGULATORY COMMISSION


Advisory Committee on Reactor Safeguards (ACRS) Subcommittee 
Meeting on Materials, Metallurgy & Reactor Fuels; Revised

    The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels 
scheduled for Wednesday, March 4, 2009, has been moved to the 
Commission Hearing Room, 01-F16/01-G16, 11555 Rockville Pike, 
Rockville, Maryland, 20852. All other items pertaining to this meeting 
remain the same as published previously in the Federal Register on 
Tuesday, February 10, 2009.
    For future information contact: Michael L. Benson, Designated 
Federal Officer (Telephone: 301-415-6396) between 7 a.m. and 5 p.m. 
(ET) or by e-mail Michael.Benson@nrc.gov.

     Dated, February 17, 2009.
Cayetano Santos,
Branch Chief Reactor Safety Branch A, Advisory Committee on Reactor 
Safeguards.
[FR Doc. E9-3753 Filed 2-20-09; 8:45 am]
BILLING CODE 7590-01-P
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