Source: https://www.federalregister.gov/documents/2006/10/10/E6-16647/notice-of-availability-of-environmental-assessment-and-finding-of-no-significant-impact-for-license
Timestamp: 2017-08-20 23:53:28
Document Index: 656752553

Matched Legal Cases: ['art 51', 'art 51', 'art 30', 'art 20', 'art 20', 'art 20', 'art 51']

Federal Register :: Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Materials License No. 47-00260-02, for the Unrestricted Release of Building B-747 and an Associated Storage Shed Located at the Union Carbide Corporation Site in South Charleston, WV
A Notice by the Nuclear Regulatory Commission on 10/10/2006
Docket No. 030-06652
https://www.federalregister.gov/d/E6-16647 https://www.federalregister.gov/d/E6-16647
Betsy Ullrich, Senior Health Physicist, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I, 475 Allendale Road, (610) 337-5040; fax number (610) 337-5269; or by e-mail: exu@nrc.gov.
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), located at 3200 Kanawha Turnpike in South Charleston, West Virginia. Issuance of the amendment would authorize release of Building B-747 and an associated storage shed (together identified herein as the Facility) at the South Charleston site for unrestricted use. The Licensee requested this action in a letter dated August 3, 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.
The proposed action would approve the Licensee's August 3, 3006, license amendment request, resulting in release of the Facility for unrestricted use. 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 unsealed hydrogen-3 (tritium) and carbon-14, and various sealed sources, for purposes of conducting research and development activities on laboratory bench tops and in hoods.
The Facility is situated on 600 acres and is surrounded by multiple buildings containing office space and laboratories. The Facility is located in a commercial area. Use of licensed materials occurred throughout the Facility, an area totaling 1,536 square feet.
In 2001, the Licensee ceased licensed activities within the Facility 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.
The Licensee has ceased conducting licensed activities in the Facility and seeks the unrestricted use of the Facility.
The historical review of licensed activities conducted at the Facility shows that such activities involved use of the following unsealed radionuclides with half-lives greater than 120 days: tritium and carbon-14. 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 July 27, 2006. The final status survey report was attached to the Licensee's amendment request dated August 3, 2006. 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 criterion 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 Facility. The NRC staff reviewed the docket file records and the final status survey Start Printed Page 59529report 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. Although the Licensee will continue to perform licensed activities at other areas of the South Charleston site, the Licensee must ensure that this decommissioned area does not become recontaminated. Before the license can be terminated, the Licensee will be required to show that its entire site, including previously-released areas, complies with the radiological criteria in 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.
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.
NRC provided a draft of this EA to the State of West Virginia for review on August 28, 2006. On September 15, 2006, the State of West Virginia Radiological Health program responded by electronic mail. The State agreed with the conclusions of the EA, and otherwise had no comments.
1. Letters dated August 3, 2006 [ML062220617], June 19, 2006 [ML061720331], and January 27, 2006 [ML060320507].
2. Facsimile dated January 31, 2006 [ML060320519].
3. NUREG-1757, “Consolidated NMSS Decommissioning Guidance.”
4. Title 10 Code of Federal Regulations, Part 20, Subpart E, “Radiological Criteria for License Termination.”
5. Title 10, Code of Federal Regulations, Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
6. NUREG-1496, “Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRC-Licensed Nuclear Facilities.”
Dated at 475 Allendale Road, King of Prussia, Pennsylvania this 29th day of September 2006.
[FR Doc. E6-16647 Filed 10-6-06; 8:45 am]