[Federal Register Volume 67, Number 71 (Friday, April 12, 2002)]
[Notices]
[Pages 18041-18043]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 02-8864]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 40-6563]


Finding of No Significant Impact Related to Approval of the 
Mallinckrodt C-T Project Decommissioning Plan, Part 1 Mallinckrodt 
Chemical, Inc. St. Louis, MO, License No. STB-401

    The U.S. Nuclear Regulatory Commission (NRC) is considering 
approval of the Mallinckrodt C-T Project Decommissioning Plan (DP), 
Part 1, originally submitted to NRC on November 20, 1997, and revised 
on January 18, 2001, February 13, 2002, and March 8, 2002. In the DP, 
Mallinckrodt Chemical Inc. (Mallinckrodt) is proposing to remediate the 
above-grade portion of buildings, and equipment. Mallinckrodt is 
proposing (1) to release columbium-tantalum (C-T) project process 
equipment in accordance with NRC's ``Guidelines for Decontamination of 
Facilities and Equipment Prior to Release for Unrestricted Use or 
Termination of Licenses for Byproduct, Source, or Special Nuclear 
Material,'' (2) to release building surfaces in accordance with 10 CFR 
20, subpart E and, (3) to release building waste material which meets 
the requirements of NRC Policy and Guidance Directive FC 83-23, 
``Termination of Byproduct, Source, and Special Nuclear Material 
Licenses,'' November 1983, in accordance with license condition 16, or 
future NRC regulations on clearance of materials, or under the 
provisions of 10 CFR 20.2002. To demonstrate compliance with these 
documents, Mallinckrodt has derived beta release criteria based solely 
on measured beta emission.
    Below is a summary of the Environmental Assessment (EA) prepared by 
the staff to support approval of the Mallinckrodt Phase 1 DP. The 
complete EA is available through NRC's Public Document Room.

Environmental Assessment

Introduction

    Mallinckrodt has been operating at the St. Louis Plant since 1867 
producing various products including metallic oxides and salts, 
ammonia, and organic chemicals. From 1942 to 1957, Mallinckrodt was 
under contract with the Manhattan Engineering District and the Atomic 
Energy Commission (MED-AEC) to process uranium ore to produce uranium 
for development of atomic weapons. From 1961 to 1985, Mallinckrodt 
extracted C-T from natural ores and tin slags.
    Radiological contamination at the site resulted from MED-AEC and C-
T processing activities. MED-AEC contamination is being removed by the 
U.S. Army Corps of Engineers (USACE) under the Formerly Utilized Sites 
Remedial Action Program (FUSRAP). USACE developed a preferred cleanup 
approach for the MED-AEC contamination, based on the data and findings 
presented in four documents: (1) Remedial Investigation Report; (2) 
Baseline Risk Assessment; (3) Initial Screening of Alternatives, and 
(4) Feasibility Study.

Purpose and Need for the Proposed Action

    Mallinckrodt has requested that NRC terminate License No. STB-401. 
Before the license can be terminated, NRC must be assured that the 
areas of the Mallinckrodt facility associated with the C-T project meet 
NRC's release criteria.
    Mallinckrodt is planning to conduct the C-T decommissioning project 
in two phases. In Phase 1, Mallinckrodt will decommission buildings and 
equipment used during C-T production. C-T project buildings and 
equipment remaining on-site will be cleaned and released for 
unrestricted use. In Phase 2, Mallinckrodt will remediate building 
slabs and foundations, paved surfaces, and all subsurface materials. 
This EA addresses only Phase 1 of decommissioning.
    Mallinckrodt has proposed a two-phase decommissioning approach. The 
two-phase approach is needed because:
     The facility is an operating facility with limited areas 
for staging decommissioning activities. Removal of buildings and 
equipment in Phase 1 will provide staging areas necessary for Phase 2 
decommissioning.
     On-site workers have access to buildings containing 
residual contamination. Removal of buildings and equipment in Phase 1 
reduces the potential that workers will be exposed to residual 
radioactive material. Further, some of the C-T process buildings have

[[Page 18042]]

not been used for several years, and the buildings are starting to 
physically deteriorate.

Proposed Action

    The ultimate goal of the C-T project decommissioning is to 
remediate those areas of the site associated with C-T production, to 
the extent necessary, to terminate License STB-401. Mallinckrodt is 
proposing to decommission the C-T Project areas, on the site, in two 
phases. In Phase I, Mallinckrodt will decommission the buildings and 
equipment, to the extent necessary, to meet NRC's unrestricted release 
criteria as presented in 10 CFR part 20, Subpart E. Phase 1 remediation 
is expected to take approximately two years. Phase II will include the 
remediation, of the building slabs and foundations, paved surfaces, and 
all subsurface materials. Mallinckrodt will submit the DP for Phase II 
to the NRC for review and approval in 2003.
    Mallinckrodt is proposing (1) to release C-T process equipment in 
accordance with NRC's ``Guidelines for Decontamination of Facilities 
and Equipment Prior to Release for Unrestricted Use or Termination of 
Licenses for Byproduct, Source, or Special Nuclear Material,'' (2) to 
release buildings in accordance with 10 CFR 20, subpart E, and (3) to 
release building waste material which meets the requirements of NRC 
Policy and Guidance Directive FC 83-23, ``Termination of Byproduct, 
Source, and Special Nuclear Material Licenses,'' November 1983, in 
accordance with license condition 16, or future NRC regulations on 
clearance of materials, or under the provisions of 10 CFR 20.2002. To 
demonstrate compliance with these documents, Mallinckrodt has derived 
beta release criteria based solely on measured beta emission. Section 
2.2, of the DP, provides the release criteria for equipment and 
materials.
    Mallinckrodt's rationale for developing release criteria based on 
beta emission is: (1) Direct measurement of alpha particles can be 
unreliable if the contaminated surface is painted, (2) direct 
measurement of gamma concentration on equipment and building surfaces 
will not be representative due to significant gamma contributions from 
subsurface areas, and (3) the minimum detectable activity for beta will 
be lower than for combined beta-gamma, since background is about one-
third of the combined beta-gamma background.

Alternatives to the Proposed Action

    The remediation approach proposed by Mallinckrodt provides for the 
systematic remediation, of the C-T process areas, at the St. Louis 
Plant. This approach provides Mallinckrodt the opportunity to remove C-
T process building material and equipment from the site, and release 
usable buildings and equipment for unrestricted use. Removal of C-T 
process buildings from the site will provide Mallinckrodt necessary 
staging areas for Phase 2 remediation activities. There are two 
alternatives to the proposed action; (1) no action, and (2) prepare a 
single DP and conduct all C-T process decommissioning activities in 
accordance with it.
    The no action alternative is not acceptable because the C-T process 
buildings, equipment and surrounding areas contain residual 
contamination exceeding NRC's release criteria. Although, the second 
alternative would be an acceptable decommissioning approach, this 
alternative does not provide Mallinckrodt the advantages discussed 
above.

Affected Environment

    As stated in the Introduction, MED-AEC contamination at 
Mallinckrodt facility is being removed by USACE under FUSRAP. USACE 
developed a preferred cleanup approach for the MED-AEC contamination, 
based on the data and findings presented in four documents: (1) 
Remedial Investigation Report; (2) Baseline Risk Assessment; (3) 
Initial Screening of Alternatives, and (4) Feasibility Study.
    Section 2.2, of the Feasibility Study provides an evaluation, of 
the affected environment, surrounding the Mallinckrodt facility. The 
findings in Section 2.2, of the Feasibility Study, also apply to 
remediation of the C-T process areas. The following issues are 
addressed: (1) Land use and recreational and Asthetic resources; (2) 
Climatology, meteorology, and air quality; (3) Geology and soils; (4) 
Water resources; (5) Biological resources; (6) Threatened and 
endangered species; (7) Wetlands and flood plains; (8) Population and 
socioeconomics, and (9) Historical, archeological, and cultural 
resources.

Environmental Impacts

    Remediation of the C-T process buildings and equipment creates a 
potential for radiological environmental impacts. Radiological 
environmental impacts that could result from remediation activities 
include exposure, inhalation, and ingestion hazard to workers and the 
public. These hazards could occur during the decontamination and 
demolition of buildings.
    Mallinckrodt has committed to perform work activities in accordance 
with a Health and Safety Program as described in Section 3 of the DP. 
The Health and Safety Program will consist of: (1) An Industrial Safety 
Program; (2) a Radiation Protection Program, and (3) an Environmental 
Safety Program. The Radiation Protection Program will contain controls 
to monitor exposures to workers. Action levels have been established 
based on 10 CFR 20, Appendix B. If action levels are exceeded, 
Mallinckrodt will take corrective action, as necessary. The Radiation 
Protection Program will keep exposures due to ingestion and inhalation 
ALARA by controlling and monitoring airborne releases in work areas, 
and by utilizing respiratory protection, as necessary.
    Mallinckrodt will implement an Environmental Safety Program to 
monitor air and water effluents discharged during decommissioning. 
Mallinckrodt is proposing to collect air and water samples on-site, and 
off-site routinely to determine the extent of environmental discharges. 
Mallinckrodt does not anticipate the need for effluent air monitoring, 
since there will likely be no point sources of effluent air. However, 
if Mallinckrodt uses a decommissioning process exhaust ventilation 
system, the effluent air will be sampled and analyzed. Mallinckrodt 
will provide environmental monitoring stations to verify that there are 
no significant adverse impacts to the workers or the environment.
    Mallinckrodt has committed to minimize the production of 
contaminated liquids. There are three potential sources of contaminated 
liquids: sink and shower water; decontamination fluids; and water used 
for dust suppression. Sink and shower water is expected to contain 
insignificant amounts, of radioactivity, and will be discharged into 
the sewer in accordance with 10 CFR part 20.2003. Aqueous waste from 
decontamination fluids and dust suppression containing potentially 
significant concentrations of radionuclides will be filtered to remove 
the solids, sampled and analyzed to estimate the concentration in the 
sewerage. The concentration will be compared with 10 CFR part 20, 
concentration limits, and the total inventory discharged will be 
calculated. All contaminated liquids will be disposed to the 
Metropolitan St. Louis Sewer District (MSD) following confirmation that 
MSD specifications for sampling, analysis, and pre-treatment have been 
met.
    Mallinckrodt has also committed to monitor direct radiation using 
TLDs. TLDs will be placed at various locations around the perimeter of 
the restricted

[[Page 18043]]

area to ensure that direct radiation in unrestricted areas does not 
exceed the limits specified in 10 CFR 20.1301.
    Mallinckrodt has established action levels for air and water 
effluents based on the levels provided in 10 CFR 20, Appendix B, Tables 
2 and 3. The action levels for environmental air, effluent water, and 
sewage are 0.75, 0.6, and 0.6, of the limits, respectively. If action 
levels are exceeded, Mallinckrodt will take corrective actions.
    Mallinckrodt has performed dose assessments to determine an 
occupational exposure estimate, and the dose associated with credible 
accident scenarios. The occupational exposure estimate for a 
representative worker during Phase 1 decommissioning is 43.4 mrem. The 
dose estimate to a maximum exposed worker as a consequence, of the 
worst case hypothetical accident, is less than 0.1 percent, of the 
annual limit of uptake (ALI), of 10 CFR part 20.
    The St. Louis Plant is located in an area which is completely 
developed with no pre-settlement vegetation existing. Land use within a 
one mile radius from the site is a mixture of commercial, industrial, 
and residential. Commercial or industrial properties in the area 
include McKinley Iron Company, Thomas and Proetz Lumber company, and 
several railroad properties. The USACE Feasibility Study states that 
there was no sign of federal or state designated endangered, or 
threatened species present at the Mallinckrodt facility. The 
Feasibility Study also states that the Mallinckrodt facility does not 
contain any historic buildings. Further, available data indicate that 
there are no archeological sites in the area.
    The residential population within one mile, of the site, is 
approximately 10,000, with most of the residences located on the 
opposite side of Interstate 70. Mallinckrodt estimates that 
approximately 14 workers will be required to Phase 1 decommissioning 
activities. Due to the small number of workers required for 
decommissioning, and the short duration of the project, this effort 
should have minimal socioeconomic impact on the local community.
    NRC staff performed an environmental justice review of the 
Mallinckrodt site. The review concluded that, since Phase 1 
decommissioning activities result in an insignificant risk to the 
public health and safety, and the human environment, then there are no 
environmental justice issues with this site.
    Air quality and noise impacts will result from demolition of 
buildings and transport of waste. Mallinckrodt will use appropriate 
dust control measures during building demolition. Asbestos abatement 
work will be performed in accordance with EPA, OSHA, State, and City 
regulations. These activities will be sporadic in nature and short in 
duration, therefore, will have minimal impact on the surrounding 
community and environment.
    The St. Louis Plant can be serviced by road, rail, and river barge. 
Interstate 70 (east and west) can be accessed within one mile from the 
St. Louis Plant. Rail lines from the Chicago, Burlington and Quincy 
Railroad, the Norfolk and Western Railroad, and the St. Louis Terminal 
Railroad Association, transect the St. Louis Plant from north to south. 
Waste will be transported from the site by rail. Mallinckrodt estimates 
that the volume of waste to be transported will be approximately 
126,000 ft\3\. This volume of waste will require less than 100 rail 
cars spread over a one year time period. Therefore, the impact of 
transporting waste from the site should be insignificant.

Agencies and Persons Consulted and Sources Used

    Much of the information contained in this EA was taken directly 
from the Mallinckrodt DP and the USACE Feasibility Study. In 
preparation of the Feasibility Study, USACE consulted with the U.S. 
Fish and Wildlife Service and the State Historic Preservation Office. 
Since Phase 1 decommissioning activities will be occurring at the same 
site as USACE decommissioning activities, with a much more limited 
scope, NRC has utilized the input of the U.S. Fish and Wildlife Service 
and the State Historic Preservation Office by reference to the 
Feasibility Study. NRC staff provided a draft of this EA to the State 
of Missouri for review.

Conclusion

    Radiological exposures to workers and the public will be in 
accordance with 10 CFR part 20 limits. NRC believes the DP contains 
sufficient controls to keep potential doses to workers and the public 
from direct exposure, airborne material, and released effluents, ALARA. 
The staff also believes that the remediation alternative proposed by 
Mallinckrodt minimizes the potential dose to workers and members of the 
public, and other environmental impacts.

List of References

    1. Mallinckrodt Chemical, Inc., Mallinckrodt C-T Project 
Decommissioning Plan (DP), Part 1, January 18, 2001.
    2. U.S. Army Corps of Engineers, Proposed Plan for the St. Louis 
Downtown Site, April 1998.
    3. U.S. Army Corps of Engineers, Feasibility Study for the St. 
Louis Downtown Site, April 1998.
    4. NRC, Policy and Guidance Directive FC 83-23, ``Termination of 
Byproduct, Source, and Special Nuclear Material Licenses,'' November 
1983.
    5. NRC, 10 CFR part 20, ``Radiological Criteria for License 
Termination: Final Rule,'' July 1997
    6. NRC, NUREG/CR-5512, ``Residual Radioactive Contamination From 
Decommissioning,'' October 1992.

Finding of No Significant Impact

    Pursuant to 10 CFR part 51, NRC has prepared this EA related to the 
approval of Mallinckrodt's DP. On the basis of this EA, NRC has 
concluded that this Federal action would not have any significant 
affect on the quality of the human environment and does not warrant the 
preparation of an Environmental Impact Statement. Accordingly, it has 
been determined that a Finding of No Significant Impact is appropriate.
    Since the conclusion of this EA is that the remediation of the C-T 
project areas of Mallinckrodt's St. Louis Plant represents no 
significant risk to the public health and safety, and the human 
environment, NRC concludes that there are no environmental justice 
issues related to remediation.
    The afforementioned documents related to this proposed action are 
available for public inspection and copying at NRC's Public Document 
Room at One White Flint North, 11555 Rockville Pike, Rockville, MD 
20852-2738.

FOR FURTHER INFORMATION CONTACT: John T. Buckley, Project Manager, 
Decommissioning Branch, Division of Waste Management, Office of Nuclear 
Material Safety and Safeguards. Telephone : (301) 415-6607.

    Dated at Rockville, Maryland, this 4th day of April 2002.

    For the Nuclear Regulatory Commission.
Claudia M. Craig,
Acting Chief, Decommissioning Branch, Division of Waste Management, 
Office of Nuclear Material Safety, and Safeguards.
[FR Doc. 02-8864 Filed 4-11-02; 8:45 am]
BILLING CODE 7590-01-P