Nuclear Regulatory Commission.
Issuance of Environmental Assessment and Finding of No Significant Impact for License Amendment.Start Further Info
FOR FURTHER INFORMATION CONTACT:
Steve Hammann, Health Physicist, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610-337-5399; fax number 610-337-5269; or by e-mail: firstname.lastname@example.org.End Further Info End Preamble Start Supplemental Information
The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of a license amendment to Byproduct Materials License No. 47-00260-02. This license is held by Union Carbide Corporation (the Licensee) for its South Charleston Technology Park and South Charleston Plant located, respectively, at 3200 Kanawha Turnpike in South Charleston, West Virginia, and at 437 MacCorkle Avenue in South Charleston, West Virginia (the Facilities). Issuance of the amendment would authorize release of the Facilities for unrestricted use and termination of the NRC license. The Licensee requested this action in a letter dated March 7, 2008. 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 March 7, 2008, license amendment request, resulting in release of the Facilities for unrestricted use and the termination of its NRC materials license. License No. 47-00260-02 was issued on August 15, 1956, pursuant to 10 CFR part 30, and has been amended periodically since that time. This license authorized the Licensee to use sealed and unsealed byproduct material for purposes of conducting research and development activities, sample analysis and instrument calibration.
The Facilities are situated on approximately 850 acres of land and consists of undeveloped land and numerous buildings used for a variety of purposes, including office space and laboratories, storage, and manufacturing. The Facilities are located in a mixed commercial and industrial area. Within the Facilities, use of licensed materials was confined to Buildings 701, 707, 712, 720, 722, 725, 727, 740, 741, 747, 770, 771, 773, 776, 777, 778, and 785.
In April, 2008, the Licensee ceased licensed activities and initiated a survey and decontamination of the Facilities. Based on the Licensee's historical knowledge of the sites and the condition of the Facilities, 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 Facilities and provided information to the NRC to demonstrate that it meets the criteria in subpart E of Start Printed Page 2973110 CFR part 20 for unrestricted release and for license termination.
Need for the Proposed Action
The Licensee has ceased conducting licensed activities at the Facilities, and seeks the unrestricted use of its Facilities and the termination of its NRC materials license. Termination of its license would end the Licensee's obligation to pay annual license fees to the NRC.
Environmental Impacts of the Proposed Action
The historical review of licensed activities conducted at the Facilities show that such activities involved use of the following radionuclides with half-lives greater than 120 days: hydrogen-3, carbon-14, iron-55, cobalt-60, nickel-63, strontium-90, cadmium-109, cesium-137, and polonium-210. Prior to performing the final status survey, the Licensee conducted decontamination activities, as necessary, in the areas of the Facilities affected by these radionuclides.
The Licensee finished conducting a final status survey on November 17, 2008. This survey covered all buildings which used unsealed materials. The final status survey report was attached to the Licensee's amendment request dated March 7, 2008. The Licensee elected to demonstrate compliance with the radiological criteria for unrestricted release as specified in 10 CFR 20.1402 by using the screening approach described in NUREG-1757, “Consolidated NMSS Decommissioning Guidance,” Volume 2. The Licensee used the radionuclide-specific derived concentration guideline levels (DCGLs), developed there by the NRC, which comply with the dose criteria in 10 CFR 20.1402. These DCGLs define the maximum amount of residual radioactivity on building surfaces, equipment, and materials, and in soils that will satisfy the NRC requirements in subpart E of 10 CFR part 20 for unrestricted release. The Licensee's final status survey results were below these DCGLs and are in compliance with the As Low As Reasonably Achievable (ALARA) requirement of 10 CFR 20.1402. The NRC thus finds that the Licensee's final status survey results are acceptable.
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 Facilities. 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 Facilities. 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 Facilities for unrestricted use and the termination of the NRC materials license is in compliance with 10 CFR 20. Based on its review, the staff considered the impact of the residual radioactivity at the Facilities 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 Facilities meets the requirements of 10 CFR 20.1402 for unrestricted release and for license termination. 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.
The NRC staff has concluded that the proposed action is consistent with the 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 State of West Virginia Office of Environmental Health Services for review on April 9, 2009. On June 4, 2009, the State responded by telephone. 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 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 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. Termination Request Letter dated March 7, 2008 (ML083520561);Start Printed Page 29732
6. Request For Additional Information dated April 30, 2008 (ML081260393); and
7. Deficiency Response Letter dated December 11, 2008 (ML083520561).
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 email@example.com. 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.Start Signature
Dated at Region I, 475 Allendale Road, King of Prussia, Pennsylvania this 15th day of June 2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I.
[FR Doc. E9-14684 Filed 6-22-09; 8:45 am]
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