[Federal Register Volume 65, Number 221 (Wednesday, November 15, 2000)]
[Notices]
[Pages 69055-69057]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 00-29251]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 70-784]


The Office of Nuclear Material Safety and Safeguards 
Environmental Assessment, and Finding of No Significant Impact Related 
to the Approval of the Remediation (Decommissioning) Plan for the 
Formerly Licensed Union Carbide Corporation Facility (UCC), 
Lawrenceburg, Tennessee, License Nos. SNM-720 and SNM-724 (Terminated)

    The U.S. Nuclear Regulatory Commission (hereafter referred to as 
NRC staff) is considering approval of the remediation (decommissioning) 
plan (DP) for the formerly licensed Union Carbide Corporation facility 
(UCC), Lawrenceburg, Tennessee (UCAR, 1998). 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 (hereafter known as 
the SDMP Action Plan) (NRC, 1992), and 10 CFR part 20 subpart E.

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 (SNM-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 SMB-720 was superceded by the 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 UCAR 
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 UCAR facility and 
immediate vicinity have identified the presence of enriched and 
depleted uranium in soil excess of current radiological release 
criteria. Sampling identified soil/ sediments contamination in small 
areas around the processing buildings.
    Volumetric contaminations were found to be above the release 
criteria in four areas around Building 10: (1) Soil surrounding the 
incinerator pad; (2) sediment in the manholes and cooling water tanks; 
(3) laundry sump tank; and (4) the surface layer of concrete flooring. 
A number of core samples as well as near surface samples were taken 
near the incinerator pad and the range for total uranium concentration 
was 1.33 to 3,655 pCi/g. The estimated average depth of the soil 
contamination is one foot resulting in a contaminated soil volume 
estimate of 500 cubic feet. Volumetric contamination above the release 
critieria was found in three areas in and around Building 5: (1) Sink 
trap; (2) concrete flooring; and (3) asphalt outside exit.
    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 10 CFR part 
20 subpart E for unrestricted use (NRC 1997) 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 in soil to be below the NRC's 
unrestricted release criteria identified in 10 CFR part 20, subpart E 
(NRC, July, 1997). Soils which exceed the derived concentration 
guideline level (DCGL) will be removed and disposed of as low level 
radioactive waste.
    General exposure rate levels will be reduced to levels below 5 
microroentgen per hour (microR/hr) above background, measured at 1 
meter (m) above the surface.
    UCAR is proposing to conduct a final survey to demonstrate: (1) 
That uranium and thorium contamination levels in the soil are below the 
[25 millirem per year (mRem/yr)] DCGL's and (2) that exposure rate 
measurements are less than 5 microR/hr measured 1 meter above the 
surface. UCAR has committed to conducting the final survey in 
accordance with NRC approved site survey plan, as well as any 
applicable regulatory requirements.

[[Page 69056]]

The Need for 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. 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 microR/hr above background. 
Because the gamma exposure rate measurements are low, direct exposure 
to workers is not a significant radiological hazard.
    UCC will implement an occupational exposure monitoring program to 
ensure that internal and external exposures are well below the 
regulatory limits, and to ensure that no individual exceeds a 
regulatory limit. 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 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 10 CFR 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; 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 10 CFR part 
20, subpart E for unrestricted use (NRC, 1997).

Agencies and Individuals Consulted

    This environmental (EA) assessment 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 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 
effect 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 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 are 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 material 
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 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 reasonably achievable.
    NRC also believes that the remediation of the facility in 
accordance with 10 CFR part 20, subpart E for unrestricted use, 
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 Federal Register 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.

[[Page 69057]]

    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 the 
Finding of No Significant Impact is Appropriate.
    The EA and the document 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 9th day of November 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. 00-29251 Filed 11-14-00; 8:45 am]
BILLING CODE 7590-01-P