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Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Source Materials License No. STC-133, for Unrestricted Release of the Defense Logistics Agency's Facility in Binghamton, New York

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Information about this document as published in the Federal Register.

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This document has been published in the Federal Register. Use the PDF linked in the document sidebar for the official electronic format.

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AGENCY:

Nuclear Regulatory Commission.

ACTION:

Issuance of environmental assessment and finding of no significant impact for license amendment.

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FOR FURTHER INFORMATION CONTACT:

Dennis Lawyer, Health Physicist, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610-337-5366; fax number 610-337-5393; or by e-mail: drl1@nrc.gov.

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SUPPLEMENTARY INFORMATION:

I. Introduction

The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of a license amendment to Source Materials License No. STC-133. This license is held by Defense Logistics Agency (the Licensee), for its Defense National Stockpile Center Binghamton Depot, located at Hoyt Avenue in Binghamton, New York (the Facility). Issuance of the amendment would Start Printed Page 7479authorize release of the Facility for unrestricted use. The Licensee requested this action in a letter dated October 16, 2006. The NRC has prepared an Environmental Assessment (EA) in support of this proposed action in accordance with the requirements of Title 10, Code of Federal Regulations (CFR), Part 51 (10 CFR Part 51). Based on the EA, the NRC has concluded that a Finding of No Significant Impact (FONSI) is appropriate with respect to the proposed action. The amendment will be issued to the Licensee following the publication of this FONSI and EA in the Federal Register.

II. Environmental Assessment

Identification of Proposed Action

The proposed action would approve the Licensee's October 16, 2006, license amendment request, resulting in release of the Facility for unrestricted use. License No. STC-133 was issued on July 27, 1983, pursuant to 10 CFR Part 40, and has been amended periodically since that time. This license authorized the Licensee to use unsealed byproduct material for purposes of storage, sampling, repackaging, and transferring materials.

The Facility is situated on 57 acres of land and consists of warehouse and office space. The Facility is located in a mixed residential/industrial area. Within the Facility, use of licensed materials was confined to the fire station and warehouses 8, 10, 11, 12, 13, and 14. The area of use totaled approximately 34,000 square feet.

On December 10, 2004, the Licensee ceased licensed activities and initiated a survey and decontamination of the Facility. Based on the Licensee's historical knowledge of the site and the conditions of the Facility, the Licensee determined that only routine decontamination activities, in accordance with their NRC-approved, operating radiation safety procedures, were required. The Licensee was not required to submit a decommissioning plan to the NRC because worker cleanup activities and procedures are consistent with those approved for routine operations. The Licensee conducted surveys of the Facility and provided information to the NRC to demonstrate that it meets the criteria in Subpart E of 10 CFR Part 20 for unrestricted release.

Need for the Proposed Action

The Licensee has ceased conducting licensed activities at the Facility, and seeks the unrestricted use of its Facility.

Environmental Impacts of the Proposed Action

The historical review of licensed activities conducted at the Facility shows that such activities involved use of the following radionuclides with half-lives greater than 120 days: Natural uranium and thorium. Prior to performing the final status survey, the Licensee conducted decontamination activities, as necessary, in the areas of the Facility affected by these radionuclides.

The Licensee conducted a final status survey on November 7-10, 2005, June 15-23, 2006, July 4-6, 2006, and August 3 and 4, 2006. This survey covered the areas of use as stated in the Final Status Survey Plan, dated February 2006. The final status survey report was enclosed with the Licensee's amendment request dated October 16, 2006, and an additional information letter dated December 19, 2006. The Licensee elected to demonstrate compliance with the radiological criteria for unrestricted release as specified in 10 CFR 20.1402 by developing derived concentration guideline levels (DCGLs) for its Facility. The Licensee conducted site-specific dose modeling using input parameters specific to the Facility and a conservative assumption that all residual radioactivity is in equilibrium. Federal Guidance Report Number 13 was used to modify the dose conversion factors because it is based on an improved, more realistic dosimetry model. The selected critical age group is adults as the expected future use of this facility will be industrial. Based on the type of building, railroad distribution, and truck access, there is no compelling evidence to indicate that the building will be used for anything other than industrial activities. The Licensee thus determined the maximum amount of residual radioactivity on building surfaces, equipment, materials, and soils that will satisfy the NRC requirements in Subpart E of 10 CFR Part 20 for unrestricted release. The NRC previously reviewed the Licensee's methodology and proposed DCGLs, and concluded that the proposed DCGLs are acceptable for use as release criteria at the Facility. The NRC's approval of the Licensee's proposed DCGLs was published in the Federal Register on Tuesday, August 22, 2006, Volume 71, No. 162, pages 48952 and 48953. The Licensee's final status survey results were below these DCGLs, and are thus acceptable.

The NRC staff conducted a confirmatory survey June 15-16, 2006. None of the confirmatory sample results exceeded the DCGLs established for the Facility. 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 NRC-Licensed 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 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 40.42(d), requiring that decommissioning of source 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 NRC's unrestricted release criteria Start Printed Page 7480specified 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 State of New York's Department of Environmental Conservation for review on December 27, 2006. On January 29, 2007, New York State 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 http://www.nrc.gov/​reading-rm/​adams.html. From this site, you can access the NRC's Agencywide Document 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 Licensing and Related Regulatory Functions;”

4. NUREG-1496, “Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRC-Licensed Nuclear Facilities;”

5. “Radiological Historical Site Assessment Report, Defense National Stockpile Center, Binghamton Deport, Binghamton, NY” dated February 2006 [ML060730408];

6. “Final Status Survey Plan, DNSC, Binghamton Depot, Binghamton, NY” dated February 2006 [ML060730389];

7. “Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Source Materials License No. STC-133 Authorizing the Use of Site-Specific Derived Concentration Guideline Levels for Unrestricted Release of the Defense Logistics Agency, Defense Nuclear Supply Center Depot in Binghamton, NY” published in the Federal Register Volume 71, Number 162 on August 22, 2006, pages 48952 and 48953;

8. Defense Logistics Agency, Submittal of Final Status Survey Report for the Defense National Stockpile, Binghamton, NY Depot dated October 16, 2006 [ML062970211];

9. Defense Logistics Agency, Deficiency Response Letter dated December 19, 2006 [ML063540612]; and

10. Defense Logistics Agency, Deficiency Response Facsimilie dated January 3, 2007 [ML070040099].

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@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.

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Dated at Region 1, 475 Allendale Road, King of Prussia, this 5th day of February 2007.

For the Nuclear Regulatory Commission.

James P. Dwyer,

Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region 1.

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[FR Doc. E7-2641 Filed 2-14-07; 8:45 am]

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