[Federal Register Volume 65, Number 145 (Thursday, July 27, 2000)]
[Notices]
[Pages 46185-46187]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 00-19005]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos.: 70-784 and 40-7044]


Finding of No Significant Impact Related to Approval of the 
Remediation (Decommissioning) Plan for the Formerly Licensed Union 
Carbide Corporation Facility Lawrenceburg, TN, License Nos. SMB-720 and 
SNM-724 (Terminated)

    The U.S. Nuclear Regulatory Commission (NRC) is considering 
approval of the remediation (decommissioning) plan (DP) for the 
formerly licensed Union Carbide Corporation (UCC) facility in 
Lawrenceburg, Tennessee, 1988. This DP was submitted by UCAR Carbon 
Company, Inc. (UCAR) to NRC on August 19, 1998. UCAR is obligated to 
remediate the UCC site to meet the release criteria established in the 
Action Plan to Ensure Timely Remediation of Sites Listed in the Site 
Decommissioning Management Plan (NRC, 1992), and CFR Part 20 Subpart E.

Environmental Assessment

Introduction

    On August 26, 1963, UCC was issued Special Nuclear Materials 
License No. SNM-724 (SNM-724), for testing equipment and nuclear fuels 
development. License No. SMB-720 (SMB-720), which authorized the 
possession of source material, was also held by the site. SNM-724 was 
terminated on June 4, 1974, and the U.S. Atomic Energy Commission (AEC) 
released the site for unrestricted use. SMB-720 was superceded by the 
State of Tennessee License No. S-5002-H8 and was terminated on August 
28, 1975.
    SNM-724 authorized possession of up to 500 grams (g) of fully-
enriched (94 percent ) uranium for testing of equipment and processes 
in the Lawrenceburg Fuel Development Facility located at Highway 43 
South, Lawrenceburg, Tennessee. On May 22, 1964, the license was 
amended to authorize possession of 150 kilograms (kg) of U\235\ to make 
graphite-coated uranium-thorium carbide particles and graphite-matrix 
fuel elements. The possession limit was increased to 475 kg on June 12, 
1964.
    By letter dated February 4, 1974, the UCC submitted ``closeout'' 
survey information and requested that SNM-724 be terminated and the 
facility be released for unrestricted use. On April 5, 1974, Region II 
performed a closeout inspection which was documented in their 
Inspection Report 70-784/74-1. Region II recommended that the license 
be terminated, and the facility be released for unrestricted use. By 
AEC letter dated June 4, 1974, SNM-724 was terminated, and the UCC 
facility released for unrestricted use.
    In 1991, Oak Ridge National Laboratory (ORNL) was contracted by NRC 
to review and evaluate all nuclear material licenses terminated by NRC 
or its predecessor agencies, since inception of material regulation in 
the late 1940s. One of the objectives of this review was to identify 
sites with potential for residual contamination, based on information 
in the license documentation. NRC evaluated the available survey data 
to determine if the information was sufficient to conclude that the 
site meets the existing guidelines for unrestricted use.
    Radiological assessments performed at the UCC facility and 
immediate vicinity have identified the presence of enriched and 
depleted uranium on building surfaces in excess of current radiological 
release criteria. Sampling identified contamination in three buildings 
on the UCC site: (1) Building 10; (2) Building 5 Annex; and (3) the 
Metallurgy Laboratory. Surface contamination in Building 10, Building 5 
Annex, and in the Metallurgy Laboratory was primarily present as fixed 
contamination.
    Surface contamination for  and / 
activity above the release guidelines was identified in 11 rooms in 
Building 10 (Rooms 106-2, 120, 121, 122, 124, 126, 128-1, 129, 132, 
133, and 134) ranging from background to 106,469 dpm/100 square 
centimeter direct beta/gamma. For each sample containing significant 
contamination, results indicated the presence of enriched uranium. This 
is consistent with process knowledge of the operational history. For 
this reason, thorium is considered an insignificant indicator for 
evaluating surface activity data.
    Uranium was also the primary contaminant in Building 5 Annex. 
Surface contamination was found in four rooms in Building 5 (Rooms 106, 
107, 108, 110), ranging from background to 428,698 dpm/100 square 
centimeters direct beta/gamma.
    Contamination in the Metallurgy Laboratory consists of localized 
surface contamination on the tops of the cabinets. There was no 
indication of radioactive material above the release criteria beyond 
the former restricted area boundary in the ground water, settling 
basins, or former sanitary sewer system.
    UCAR will be conducting remediation activities without a license, 
because its license was terminated in 1974. However, remediation will 
be performed in accordance with current regulations and release limits 
(UCAR, 1998).

Planned Decommissioning Action

    Decommissioning of the UCAR facility shall comply with the SDMP 
Action (NRC, 1992) Plan criteria. The conduct of decommissioning and 
decontamination in compliance with these criteria provides adequate 
protection of the public health and safety and of the environment. In 
implementing the decommissioning plan, UCAR shall reduce residual 
contamination on building surfaces to be below the NRC's unrestricted 
release criteria (NRC, April 1992) for uranium. Building surfaces will 
be decontaminated with pneumatic needle-scalers, floor scabblers, 
vacuums and/or similar equipment. Structures that cannot be cost-
effectively decontaminated (e.g., counter tops, wooden drawers, duct 
work, and Room 134 penthouse) will be mechanically removed, reduced in 
volume/minimized, and packaged for disposal.
    General exposure rate levels will be reduced to levels below 5 
microroentgen per hour (uR/hr) above background, measured at 1 meter 
(m) above the surface.
    UCAR is proposing to conduct a final survey to demonstrate: (1) 
That surface contamination levels meet the guideline levels for uranium 
established in ``Guidelines for Decontamination of Facilities and 
Equipment Prior to Release for Unrestricted Use or

[[Page 46186]]

Termination of Licenses for Byproduct, Source or Special Nuclear 
Material;'' and (2) that exposure rate measurements are less than 5 uR/
hr measured 1 meter above the surface. UCAR has committed to conducting 
the final survey in accordance with the NRC approved site survey plan, 
as well as any applicable regulatory requirements.

The Need for the Planned Action

    The former UCAR facility is currently being used to manufacture 
non-radiological carbon products. The planned action is necessary to 
reduce residual contamination at the site to meet NRC's unrestricted 
release criteria.

Alternative to the Planned Action

    The alternative to the proposed action is to take no action. A no-
action alternative would mean the site would not be remediated now. 
Although there is no immediate threat to the public health and safety 
from this site, not undertaking remediation, at this time, does not 
solve the regulatory and potential long-term health and safety problems 
associated with having residual contamination on site. In addition, 
pursuing no action would delay remediation until some time in the 
future, when remediation costs could be much higher than they are 
today. Therefore, the no-action alternative is not acceptable.

Environmental Impacts of the Planned Action

    Radiological impacts that could result from the remediation of the 
former UCC site are direct exposure, inhalation, and ingestion hazards 
to workers. These hazards could occur during decontamination of 
building surfaces and excavation and packaging of contaminated soil.
    The radioactive material of concern at this site is enriched 
uranium. Surface contamination in Buildings 10 and 5 Annex, and the 
Metallurgy Laboratory is primarily fixed. Gamma exposure rate 
measurements taken at locations throughout the site do not exceed 
background levels, with the exception of five locations near the 
incinerator pad. The highest radiation exposure rate detected near the 
incinerator pad is 26 uR/hr above background. Because the gamma 
exposure rate measurements are low, direct exposure to workers is not a 
significant radiological hazard.
    Building surfaces, such as concrete floors, walls, and ceilings, 
will be decontaminated with equipment, such as pneumatic needle-
scalers, floor scabblers, vacuums, and/or similar equipment. This 
equipment will be equipped with the appropriate health and safety 
devices, such as high-efficiency particulate air filters. If determined 
necessary by the Radiation Safety Officer (RSO), containment enclosures 
will be constructed for contamination control. UCAR will implement an 
occupational exposure monitoring program to ensure that internal and 
external exposures of workers are well below the regulatory limits. 
Respiratory protection will be required for workers when airborne 
radioactivity could result in exposures above the administrative action 
levels set in the health and safety plan.
    Although the potential for external exposure to workers is low, 
UCAR will survey work areas for direct radiation whenever remediation 
is being performed. If dose rates exceed 5 mrem/hr, or if the RSO 
determines that worker exposure could exceed 10 percent of the 
regulatory limits found in Part 20, Subpart C ``Occupational Dose 
Limits,'' worker exposure will be monitored with thermoluminescent 
dosimeters.
    UCAR has committed to implement a contamination monitoring and 
control program to detect and minimize the spread of contamination. 
Contamination monitoring will be accomplished by: (1) Conducting 
routine surveys; (2) use of access controls to prevent inadvertent 
personnel access to contaminated areas; (3) use of radiation work 
permits in areas where there is potential for workers to exceed 10 
percent of the regulatory limits; (4) use of personal protection 
equipment; and (5) employee training.
    UCAR has committed to implementing a contaminant monitoring and 
control program to detect and minimize off-site effluent releases 
(UCAR, in its DP Section 3.3.4, 1998). The primary pathway for off-site 
release of radioactive material is airborne effluent. Inhalation and 
ingestion impacts will be minimized to the workers and public by 
controlling airborne material levels. Routine and special environmental 
monitoring will be conducted to detect, assess, and limit potential 
airborne releases. Air monitoring will be performed in work areas using 
Breathing Zone Air (BZA) samplers or high-volume air samplers. 
Administrative action levels at 10 percent of the regulatory limits for 
airborne effluents have been established. Investigations will be 
performed if administrative action levels are exceeded. No liquid 
wastes have been identified and none are expected.
    Radioactive waste will be segregated from non-radioactive waste and 
stored in a controlled, fenced area. Radioactive waste will be stored 
inside, if possible. Otherwise, it will be stored outside and covered 
to protect against the weather. Radioactive waste will be packaged, 
labeled, manifested, and shipped in accordance with NRC and U.S. 
Department of Transportation requirements.
    This site is being remediated to the criteria listed in the SDMP 
Action Plan (NRC, 1992). The exposure to the public from the remediated 
site is expected to be within the limits stipulated in Part 20, Subpart 
D.

Agencies and Individuals Consulted

    This environmental assessment (EA) was prepared by NRC staff. No 
other sources were used beyond those referenced in this EA. NRC staff 
provided a draft of the EA to the Tennessee Department of Environment 
and Conservation, Division of Radiological Health for review. By e-mail 
dated May 1, 2000, the Tennessee Department of Environment and 
Conservation Division of Radiological Health agreed with NRC's 
conclusion that the proposed action will not have any significant 
affect on the quality of the human environment.
    NRC contacted the U.S. Fish and Wildlife Service (FWS) to determine 
the potential impacts of the proposed action on threatened and 
endangered species near the UCAR facility. By letter dated September 
10, 1999, the FWS informed NRC that the proposed action would have no 
impact on threatened and endangered species.
    NRC staff provided a draft of the EA to the U.S. Environmental 
Protection Agency (EPA) Region IV for review. By e-mail dated June 27, 
2000, EPA did not have any comments on the proposed action. However, 
the EPA has noted the disagreement between the EPA and the NRC about 
the appropriate dose criteria to be used in decommissioning.
    NRC also contacted the Tennessee State Historical Preservation 
Office to determine if any historical properties would be impacted by 
the proposed action. The Tennessee State Historical Preservation Office 
informed the NRC, by letter dated May 2, 2000, that there is no 
national register of historic places listed or eligible properties 
affected by the project.

Conclusion

    During the decommissioning operation, radiological exposure to 
workers and annual average concentrations of radioactive materials 
released off-site will be in accordance with Part 20 limits. UCAR has 
committed to perform remediation in accordance with an acceptable 
Health and Safety Plan. The Health and Safety

[[Page 46187]]

Plan shall provide adequate controls to keep potential doses to workers 
and the public from direct exposure, airborne material, and released 
effluents as low as is reasonably achievable.
    NRC also believes that remediation of the facility according to the 
SDMP Action Plan criteria (NRC, 1992) adequately protects workers, 
members of the public, and the environment. The potential environmental 
impacts from the proposed action are not significant.

References

    1. NRC, ``Action Plan to Ensure Timely Remediation of Sites 
Listed in the Site Decommissioning Management Plan,'' 57 FR 13389, 
April 16, 1992.
    2. NRC, ``Radiological Criteria for License Termination,'' 10 
CFR Part 20, Subpart E, 62 FR 139, July 21, 1997.
    3. NRC, ``Multi-Agency Radiation Survey and Site Investigation 
Manual, (MARSSIM),'' NUREG-1575, December 1997.
    4. NRC, ``Draft Manual for Conducting Radiological Surveys in 
Support of License Termination,'' NUREG/CR-5849, June 1992.
    5. Union Carbide Company Inc., ``Remediation (Decommissioning) 
Plan for the Formerly Licensed Union Carbide Corporation Facility 
(UCC), Lawrenceburg, TN,'' August 19, 1998.

Finding of No Significant Impact

    NRC has prepared an EA related to the approval of UCAR's 
Remediation (Decommissioning) Plan, Terminated License No. SNM-724 and 
SMB-720. On the basis of this EA, NRC has concluded that the 
environmental impacts that would be created by the proposed action 
would not be significant and do not warrant the preparation of an 
Environmental Impact Statement. Accordingly, it has been determined 
that a Finding of No Significant Impact is appropriate.
    The EA and the documents related to this proposed action are 
available for public inspection and copying at NRC's Electronic Reading 
Room at http://www.nrc.gov/NRC/ADAMS/index.html.

FOR FURTHER INFORMATION CONTACT: Rebecca Tadesse, Project Manager, 
Decommissioning Branch, Division of Waste Management, Office of Nuclear 
Material Safety and Safeguards. Telephone: (301) 415-6221.

    Dated at Rockville, Maryland, this 20th day of July 2000.
    For the Nuclear Regulatory Commission.
Larry W. Camper,
Chief, Decommissioning Branch, Division of Waste Management, Office of 
Nuclear Material Safety and Safeguards.
[FR Doc. 00-19005 Filed 7-26-00; 8:45 am]
BILLING CODE 7590-01-P