99-22767. Environmental Assessment, Finding of No Significant Impact, and Notice of Opportunity for a Hearing for Remediation of the Lakehurst, NJ Site  

  • [Federal Register Volume 64, Number 169 (Wednesday, September 1, 1999)]
    [Notices]
    [Pages 47872-47877]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 99-22767]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 40-08980]
    
    
    Environmental Assessment, Finding of No Significant Impact, and 
    Notice of Opportunity for a Hearing for Remediation of the Lakehurst, 
    NJ Site
    
    Summary and Conclusions
    
        The environmental assessment (EA) reviews the environmental impacts 
    of the decommissioning actions proposed by Heritage Minerals, 
    Incorporated (HMI) of their Lakehurst, New Jersey facility. Based upon 
    the NRC staff evaluation of the HMI Final Status Survey Plan (FSSP), 
    dated November 3, 1997, it was determined that the proposed 
    decommissioning can be accomplished in compliance with the NRC public 
    and occupational dose limits, effluent release limits, and residual 
    radioactive material limits. In addition, the approval of the proposed 
    action, i.e., decommissioning of HMI's Lakehurst, New Jersey facility 
    in accordance with the commitments in NRC license SMB-1541 and the FSSP 
    (decommissioning plan), will not result in significant adverse impact 
    on the environment.
    
    1.0  Introduction
    
    1.1  Background
        Heritage Minerals, Inc. is the current holder of NRC radioactive 
    source materials license SMB-1541 (NRC Docket 40-08980) for the 
    possession of radioactive material resulting from operations at their 
    facility located in Lakehurst, New Jersey. The license authorizes HMI 
    to possess at any one time a maximum of 300 kg of uranium in the form 
    of natural uranium as monazite and 15,000 kg of thorium in the form of 
    natural thorium as monazite. Processing of licensed material is not 
    authorized except incident to facility decommissioning activities and 
    packaging materials for shipment.
        In December 1996, HMI informed the NRC staff that it intended to 
    decommission the Lakehurst, New Jersey facility. The licensee submitted 
    the Final Status Survey Plan (FSSP or decommissioning plan) to the NRC 
    for review on November 3, 1997. The license was renewed on May 26, 1998 
    to authorize possession, packaging, storage, and decommissioning in 
    accordance with the FSSP and transfer of products and waste to 
    authorized recipients. Prior to the renewal, a safety evaluation report 
    (SER), which evaluated conformance of the proposed action with NRC 
    regulations and regulatory guidance was prepared and the opportunity 
    for a hearing was publicly noticed in the March 12, 1998, Federal 
    Register Notice (63 Federal Register 12114). In response to NRC 
    requests, in 1998-99, HMI provided additional information to clarify 
    certain planned remediation activities. The NRC is considering a 
    license amendment which include additional HMI commitments during 
    facility decommissioning.
    1.2  Purpose and Need for Proposed Action
        NRC is considering approval of the FSSP to allow Heritage Minerals, 
    Inc. to remove radioactive material attributable to licensed operations 
    at the site, to levels that permit release of the property for 
    unrestricted use and termination of radioactive source materials 
    license SMB-1541.
    1.3  Description of Proposed Action
        The objective of HMI is to decontaminate and decommission the 
    Lakehurst, NJ facility to permit release for unrestricted use and 
    termination of NRC license SMB-1541. Decommissioning will involve 
    remediation of buildings and other above-grade structures, 
    decontamination of process equipment and sumps, excavation of soil 
    containing monazite sands, and restoration of excavated areas. Soil and 
    other radioactively contaminated materials will be transported to 
    either a licensed disposal facility or recipient authorized to receive 
    such material.
        NRC staff reviewed the information provided by HMI in the FSSP 
    describing the proposed decommissioning actions and, by letter dated 
    March 16, 1999, requested additional information regarding specific 
    areas that needed clarification. NRC staff concluded that the 
    decommissioning plan (FSSP) and supplemental information (letters dated 
    November 30, 1998, June 24, 1999, July 13, 1999 and August 17, 1999) 
    from A.J. Thompson, Attorney for HMI, Inc., responding to NRC comments 
    provided an adequate information base for assessing potential 
    environmental impacts from the proposed action.
    
    2.0  Facility Description/Operating History
    
    2.1  Site Locale and Physical
        Description The Heritage Minerals, Inc. site is located on Route 70 
    in Lakehurst, Manchester Township (Ocean County), New Jersey, in the 
    Atlantic Coastal Plain. It encompasses an area of approximately 7000 
    acres, of which 1000-1200 acres were used for mining operations 
    involving monazite.
    
    [[Page 47873]]
    
    Other areas remained undisturbed. The plant and production areas 
    including mill tailings containing monazite (produced as a result of 
    previous operations) occupied an estimated 500 acres. The monazite pile 
    is located within a security fence and occupies approximately 700 cubic 
    meters. Areas adjacent to the site are predominantly rural, with bands 
    of existing or recently developed residential communities within 
    Manchester Township.
        In the Hydrogeologic Investigation Report prepared for HMI, 
    Fellows, Read, & Associates, Inc. (1989) characterized the geology and 
    hydrogeology of the facility. Geologic deposit formations consist of 
    underlying sediments of stratified clay, silt, sand, and gravel on 
    well-indurated bedrock. The topography is relatively flat, recontoured 
    by surface mining of ilmenite surface deposits. Wetlands form the 
    drainage of adjacent Wrangel Brook, which has an easterly streamflow. 
    Two lakes were created along the Green Branch of Wrangel Brook as a 
    result of mine dredging operations.
        Groundwater flow occurs from areas located north and west of the 
    site to east and northeast towards the tributaries of the Toms River. 
    The Toms River and its tributaries represent the major groundwater 
    discharge zones for the region. Local groundwater flow is from upland 
    areas to lower areas where groundwater discharges to streams and 
    wetlands. Site groundwater is recharged by precipitation and flows 
    unconfined through underlying sands. The Green Branch, Michaels Branch, 
    and Davenport Branch of Wrangel Brook serve as local discharge zones 
    for shallow ground water, with subsequent discharge to the Toms River 
    or Barnegat Bay.
    2.2  Descriptions of Facility Operations
        Between 1973 and 1982 the site was operated by ASARCO, Inc., for 
    dredging and processing sand deposits to extract heavy minerals. The 
    titanium mineral, ilmenite, was the primary mineral recovered by 
    various physical separation methods. There was no chemical separation 
    involved in the extraction and concentration processes. Heavy minerals, 
    including monazite were pumped as slurry to a Wet Mill. At the Wet 
    Mill, the heavy minerals were separated from the slurry, then 
    stockpiled for dewatering, while the lighter fraction was returned to 
    the dredge pond. The heavy mineral concentrate was heated in a Dry 
    Mill, then screened to remove coarse material. The high conductivity of 
    the titanium dioxide bearing minerals allowed electrical separation 
    from other heavy minerals. Further magnetic refinement produced the 
    final ilmenite product. The dry mill tailings containing essentially 
    all the monazite from the heavy minerals concentrate were mixed with 
    water and pumped to an area east of the dry mill building.
        ASARCO ceased operations in 1982. Evaluation of residual materials 
    by private companies for commercial use continued until the property 
    was purchased by HMI in 1986. Plant facilities were leased to Mineral 
    Recovery, Inc. (MRI), who performed operational testing for titanium 
    recovery until 1987.
        HMI assumed property control, conducting site operations under NRC 
    license until 1990 when all production stopped. Operations were 
    comparable to the ASARCO process, utilizing dry mill tailings as feed 
    material. The tailings were mixed with water, pumped to the wet mill 
    for mineral separation according to their conductive properties, 
    proceeding through a dewatering and drying process. Minerals were 
    recovered and sold as leucoxene and rutile (titanium dioxide products) 
    and zircon. Licensable amounts of monazite were present throughout the 
    electrical and magnetic separation processes. In early 1990, processing 
    of feed materials continued followed by recycle of tailings from the 
    MRI operations. Mill tailings containing monazite were deposited in a 
    stockpile east of the dry mill. Due to economic conditions, HMI 
    terminated all operations in August 1990. Approximately 700 cubic 
    meters of stockpiled tailings remain licensed to HMI.
    
    3.0  Radiological Status of the Facility
    
    3.1  Structures and Equipment
        HMI performed decontamination of building surfaces and disposed of 
    contaminated equipment in 1990-1991. Subsequent radiation (screening) 
    surveys were conducted of the interiors of the wet mill and dry mill. 
    Process trains within each building were characterized according to 
    their monazite content and operating history as affected or unaffected 
    areas using NUREG/CR-5849, ``Manual for Conducting Radiological Surveys 
    in Support of License Termination'' criteria. The methods used to 
    dismantle and decontaminate process equipment in affected areas and for 
    disposition of resultant materials are described in the FSSP. The same 
    methods will be used for decontamination of building interiors prior to 
    the final radiological survey and will serve as the basis for 
    termination of NRC Source Material License SMB-1541.
        The final release status surveys described in the FSSP will be 
    performed in accordance with NUREG/CR-5849 criteria. Residual 
    radioactive materials that exist in affected areas will meet current 
    guidelines described in ``Guidelines for Decontamination of Facilities 
    and Equipment Prior to Release for Unrestricted Use for Termination of 
    Byproduct, Source, and Special Nuclear Material Licenses,'' (U.S. 
    Nuclear Regulatory Commission, Policy and Guidance Directive FC 83-23, 
    1983). Details regarding the radiological status of affected areas 
    within the Wet and Dry Mill buildings are described in the next 
    sections. At present, contaminated material containing monazite is 
    being stored in the outdoor tailings pile. A final survey of affected 
    areas will be required by NRC after residual material is removed and 
    decontamination is complete.
        Following review of the Heritage Minerals, Inc. site radiological 
    characterization of structures and equipment, the NRC staff finds 
    characterization was performed in accordance with NUREG/CR-5849. The 
    NRC staff review of the FSSP also finds it adequate for remediating 
    structures and equipment to radiological levels below the NRC 
    guidelines for unrestricted release (Nuclear Regulatory Commission, 
    1983). The staff concludes no adverse environmental impacts will result 
    from planned remediation of the site structures and equipment.
        3.1.1  Wet Mill Building. The Wet Mill Building process equipment 
    used to extract product materials from raw feed was grouped into 
    affected and unaffected survey units. The majority of survey units 
    including floors, lower walls, and western mill areas are unaffected. 
    Mechanical separation units and feed sumps involving transfer or 
    processing of product material containing monazite were identified in 
    the FSSP as affected areas. Final radiological surveys of interior 
    surfaces will be within allowable release limits for natural thorium, 
    the primary contaminant of concern. Prior to release of equipment in 
    affected areas for unrestricted use, the NRC release limit of 1,000 
    dpm/100 cm2 for average surface contamination and maximum release limit 
    of 3,000 dpm/100 cm2 will be met.
        3.1.2  Dry Mill Building. Equipment in the Dry Mill Building was 
    used to extract product materials from the Wet Mill process feed. 
    Consistent with Wet Mill Building survey units, Dry Mill Building 
    equipment was also grouped into affected and unaffected areas. Most
    
    [[Page 47874]]
    
    areas of the Dry Mill involving monazite including floors, ceiling, and 
    lower walls (up to two meters above floor level) are affected. These 
    include dryers, high tension separators, and sumps. NRC surface 
    contamination release limits are the same as those used for Wet Mill 
    equipment.
    3.2  Surface and Subsurface Soils
        Radionuclide concentrations and direct radiation levels for surface 
    and subsurface soils at the facility have been measured in the Wet 
    Mill, Dry Mill, dust collectors, tailings (monazite) pile, and at 
    various outdoor locations.
        Direct radiation levels inside buildings and outdoor areas were 
    routinely measured by HMI personnel since 1990. Direct gamma exposure 
    rates at ground level and 1 meter above the surface were reported for 
    the monazite pile and areas in and around the Wet and Dry Mills. 
    Average monazite pile perimeter readings ranged between 300-1700 
    R/hr up to 2000 R/hr on the pile. Readings at outdoor 
    locations around buildings were at or near background levels. The 
    highest exposure rates were measured on storage drums located inside 
    the security fence surrounding the pile, at levels up to 3000 
    R/hr. Small amounts of residual material (unlicensed) exists 
    from recycled ASARCO tailings deposits in adjoining owner controlled 
    property locations. These areas showed direct gamma radiation readings 
    ranging between 10-150 R/hr and will not be included in the 
    remediation. Normal background radiation levels for other facility 
    production areas is 7-20 R/hr.
        In July 1996, Radiation Science, Inc. issued a Report of Site 
    Background for HMI which included soil samples at a depth of six inches 
    from undisturbed environment, representative of natural site 
    conditions. Background levels were established by performing gamma 
    spectral analysis for U-238 and Th-232 on 32 samples. Mean values 
    reported for background samples was 0.31 pCi/gm for U-238 concentration 
    and 0.25 pCi/gm for Th-232 concentration. Average dose rates 
    measurements from areas where samples were taken was 3.0 R/hr.
        Sample analysis of soils taken from recycled tailings, an unused 
    settling pond, plant tailings, and new feed materials did not exceed 
    NRC limits for total uranium and thorium (i.e., 10 pCi/g above 
    background) for unrestricted release. Only soil in the monazite pile 
    was measured above licensable source material quantities, and showed 
    total concentrations of Ra-226 and Ra-228 up to 1376 pCi/gm. The FSSP 
    identifies these soils as the material to be considered for remediation 
    activities.
        Following review of the HMI site radiological characterization 
    studies for soils, the NRC staff finds the characterization effort and 
    FSSP adequate for determining areas of elevated radioactivity in soils 
    that require remediation to limit concentrations to the NRC limits for 
    unrestricted release (46 Federal Register 52061-52063).
    3.3  Surface Water and Groundwater
        Analyses for radioactivity of surface water samples collected from 
    existing site monitoring wells and offsite streams were reported by 
    Camp Dresser & McKee, Inc. in 1997 as part of the Mine Tailings 
    Radiological Assessment Plan prepared for the New Jersey Department of 
    Environmental Protection. Concentrations measured for groundwater 
    samples were 2.0-7.0 pCi/l for gross alpha and under 2.0-5.0 pCi/l for 
    gross beta. Results of surface water samples were 2.0-3.9 pCi/l gross 
    alpha and 2.0-4.2 pCi/l gross beta. Due to the insoluble properties of 
    monazite and generally low levels of radiological contamination 
    identified in samples, no concern was found regarding dissolution of 
    radioactivity into groundwater and surface water.
        Following staff review of the characterization of surface waters 
    and groundwater around the HMI site, the NRC staff concludes the 
    characterization is adequate and radiological contamination of surface 
    waters and groundwater is below levels that would be a concern for 
    environmental impacts.
    3.4  Air
        HMI reported results from 1990 air sampling measurements in three 
    locations of the Dry Mill taken by their contractor, Teledyne Isotopes. 
    Air filters were analyzed for gross alpha activity using an alpha 
    scintillation counter. Activity detected was assumed to be Th-232, with 
    reported concentrations less than 1.6  x  10-12 Ci/
    ml. These concentrations were less than effluent concentrations limits 
    allowed in 10 CFR Part 20, Appendix B, and are therefore found by NRC 
    to be below levels that could lead to adverse environmental impacts. 
    Dust and security control measures provide confidence that air quality 
    will not be degraded during decommissioning activities to levels that 
    exceed NRC limits in 10 CFR Part 20.
    
    4.0  Evaluation of Proposed Methods for Decontamination and 
    Dismantlement of Structures, Buildings, and Equipment
    
    4.1  Decontamination of Buildings, Equipment, and Outdoor Areas
        HMI's proposal for decontamination of buildings, equipment, and 
    outdoor areas is provided in the FSSP, supplemented by additional 
    letters clarifying remediation activities in response to NRC's request 
    for additional information. In 1991, process equipment, Wet and Dry 
    Mill buildings, and survey units with operating equipment suspected to 
    contain radioactive material were cleaned and decontaminated. 
    Decontamination methods used for mill equipment included high pressure 
    washing, steaming, general wipe down and scrubbing, blowing, and 
    dusting and sweeping of surfaces. Radiation surveys of buildings and 
    areas around the monazite pile have been performed routinely by HMI 
    since that time.
        The FSSP describes the proposed decommissioning activities and 
    methods for protecting workers and the public during removal of 
    monazite contaminated soil. Residual radioactivity remaining inside 
    buildings is confined to fine sand grains present on equipment 
    surfaces. Affected survey units may require further decontamination 
    prior to performing the final status survey. Areas that contain only 
    loosely adhered contamination will be HEPA vacuumed to remove 
    contaminants. Fixtures, tanks, pumps, high tension separators, piping, 
    and heavy equipment will be isolated, disassembled, and decontaminated 
    as necessary, then resurveyed prior to release for unrestricted use. 
    Equipment that cannot be economically decontaminated will be 
    resurveyed, and all equipment with contamination above the NRC limits 
    for unrestricted release or equipment suspected to contain radioactive 
    material will be treated as radioactive waste.
        When removal of process equipment from mill buildings is completed, 
    building characterization surveys will be conducted. Walls up to two 
    meters and floors are to be surveyed in accordance with the FSSP. Those 
    buildings that contain residual contamination will be decontaminated 
    below NRC guideline values using the most economical and reliable 
    methods available. HMI's objective is to free release all buildings 
    above grade to allow demolition (if deemed necessary) of clean 
    buildings. Decontamination of ground-level floors will include the top 
    surface of the concrete slabs, if needed.
    
    [[Page 47875]]
    
    Material from demolition of ground-level floors and underlying soils 
    will be surveyed for contamination and remediated.
        Surface and subsurface soils with Th-232 concentrations greater 
    than 10 pCi/g is restricted to the monazite pile. HMI proposes two 
    excavations of materials with monazite concentrations greater than 10 
    pCi/g above background. Contaminated soil (monazite ore) will be 
    excavated, placed into a hopper, and transferred to shipping 
    containers. This will be followed by a second excavation of surface 
    layer soil to be removed in a similar manner. A fenced security area 
    near the existing pile will be established for staging of shipping 
    containers and contaminated equipment prior to transportation off-site. 
    After the second excavation, area radiation levels are expected to be 
    reduced to no more than twice background. Excavation of soil to meet 
    Th-232 cleanup criteria will also serve to remove residual uranium 
    contamination because both contaminants are contained in the monazite-
    rich soil. Once remediated, the remaining soil will be resurveyed in a 
    manner consistent with NRC-accepted methods to ensure residual thorium 
    and uranium contamination meet the NRC unrestricted release criteria. 
    Soil and other material will be transported from the site either to a 
    licensed disposal facility or exported under NRC Export License 
    XSOU8751, issued to HMI on May 2, 1997.
        Under Condition 15 of Materials License SMB-1541, HMI cannot 
    release for unrestricted use areas within plant buildings or the 
    monazite pile without specific, written authorization from the NRC. 
    Based on the NRC review of building and equipment decontamination 
    methods described in the FSSP and supporting documents, NRC concludes 
    that the methods are adequate for ensuring that equipment, buildings, 
    and outdoor areas will meet the NRC guidelines for unrestricted use and 
    no adverse environmental impacts will result from planned activities.
    
    5.0  Decommissioning Alternatives and Impacts
    
    5.1  No Action
        No decommissioning action by HMI would constitute a violation of 10 
    CFR 40.42(d) requirements, which requires that licensees begin site 
    decommissioning of buildings and outdoor areas that contain residual 
    radioactivity after permanently ceasing principal activities. Impacts 
    of the no-action alternative are maintaining an NRC license, which 
    would significantly reduce options for future property use, and require 
    perpetual care and security of the site in its current radiological 
    condition to prevent radiation exposure to monazite contamination and 
    unauthorized public access.
    5.2  Proposed Action
        The proposed action is the approval to implement the Heritage 
    Minerals, Inc. Final Status Survey Plan, for decommissioning activities 
    at the Lakehurst, New Jersey facility that will permit unrestricted use 
    of the site and termination of License No. SMB-1541. Decommissioning 
    the facility for unrestricted release allows productive use of the land 
    in the future. Site remediation is expected to mitigate potential 
    future environmental impacts attributable to existing radiological 
    contamination resulting from past operations.
    5.3  Alternatives to Proposed Action
        Two alternatives to the proposed action are considered. The first 
    alternative is to not release the site for unrestricted use and keep 
    the property under license. This alternative is unfavorable because 
    maintaining an NRC license for the site would provide negligible, if 
    any, environmental benefit, but would greatly reduce options for future 
    use of the property. The second alternative involves storage of 
    excavated soils on-site for an indefinite period should HMI be unable 
    to export or transfer the material for disposal. While on-site storage 
    defers the costs associated with disposal at a licensed facility, it 
    removes the property from productive use, resulting in a negative 
    impact to the economic potential of the local area.
        The NRC determines the proposed action to be more favorable than 
    either no-action or alternatives to the proposed action.
    
    6.0  Radiation Protection Program
    
    6.1  Radioactive Waste Management and Transportation Program
        The radioactive waste management program at the HMI site includes 
    identification, characterization, segregation, packaging, labeling, 
    manifesting, and transporting waste in accordance with NRC, U.S. 
    Department of Transportation (DOT), and other applicable federal, 
    state, and local regulations. Included as contaminated radioactive 
    waste materials from decommissioning activities will be equipment, 
    tools, process material, building debris, decontamination materials 
    (rags, wipes, filters), decontamination waste, soils, residual process 
    equipment waste (sludges), and used personal protective equipment.
        Since HMI intends to comply with all applicable requirements, NRC 
    finds the planned radioactive waste management and transportation 
    programs adequate for the materials at the site, and no adverse 
    environmental impacts are expected from waste management activities or 
    transfer of the material offsite.
    6.2  Technical and Environmental Specifications
        6.2.1  Unrestricted Use Guidelines. Guidelines for unrestricted use 
    for natural thorium and uranium for the Heritage Minerals, Inc. site 
    are Option 1 in the 1981 Branch Technical Position on ``Disposal or 
    Onsite Storage of Thorium or Uranium Wastes From Past Operations'' (46 
    FR 52061), and NRC ``Guidelines for Decontamination of Facilities and 
    Equipment Prior to Release for Unrestricted Use for Termination of 
    Byproduct, Source, and Special Nuclear Material Licensees,'' Policy and 
    Guidance Directive, FC 83-23. The unrestricted release criteria are 
    identified in the table below.
    
                                               Soil Release Criterial \1\
    ----------------------------------------------------------------------------------------------------------------
                                                     Maximum soil
                     Radionuclide                    concentration                      Reference
                                                        (pCi/g)
    ----------------------------------------------------------------------------------------------------------------
    Natural Thorium (Th-232 plus Th-228) if all                 10  (46 Federal Register 52061-52063).
     daughters are in equilibrium.
    Natural Uranium Ores (U-238 plus U-234) if all              10  (46 FR 52061-52063).
     daughters are present and in equilibrium.
    ----------------------------------------------------------------------------------------------------------------
    \1\ If only one radionuclide is present, the maximum concentration is the value listed in this table. If more
      than one radionuclide is present, however, the ratio between the measured concentration and the corresponding
      limit listed in this table is determined. The sum of such ratios for all radionuclides present must not exceed
      one.
    
    
    [[Page 47876]]
    
        6.2.2  Radiological Health and Safety Program. HMI will select a 
    decommissioning contractor who will follow radiation protection 
    procedures sufficient to administer the radiation protection program 
    authorized by License SMB-1541. The radiation protection program has 
    been routinely inspected by NRC staff and found to be well implemented. 
    The proposed action is limited in scope and not expected to include 
    unique health and safety issues outside the scope of the radiation 
    protection program. NRC will conduct site inspections while 
    decommissioning activities are in progress. NRC determines the 
    radiation protection program adequate for the proposed action.
        6.2.3   Corporate Organization and Management. The HMI site manager 
    will function as the licensee representative of the decommissioning 
    project to provide oversight for all project activities. The site 
    manager's function is to coordinate scheduling and status reports with 
    the contractor Project Manager (PM) and HMI legal advisor. The PM will 
    maintain overall responsibility for performance of project operations 
    for the duration of the project until decommissioning activities are 
    completed. The PM and decommissioning workers report directly to the 
    HMI technical and legal staff for all project related activities, 
    management direction, and resolution of operational issues. Primary 
    responsibility of the PM includes on-site workforce management to 
    ensure agreed to work schedules are met. The HMI Radiation Safety 
    Officer (RSO) will report to the site manager and continue to perform 
    oversight of all radiological work-related activities throughout the 
    decommissioning project.
        From review of job descriptions and responsibilities involved in 
    radiological safety during decommissioning, NRC determines that the 
    designated functions are acceptable to implement the radiological 
    safety program during proposed decommissioning activities.
        6.2.4  Radiological Exposure Control. Areas where radioactive 
    materials are used and stored will be posted to control exposures to 
    workers and visitors and avoid the spread of contamination. Measures to 
    be taken to ensure control of contamination include donning of anti-
    contamination clothing, personnel monitoring, and frequent area 
    radiation surveys. External radiation monitoring will be conducted 
    through the use of environmental dosimeters placed at strategic 
    locations around the monazite pile and work areas. The need for and 
    type of dosimetry for workers and visitors in radiologically controlled 
    areas will be determined by the contractor, and may include issuance of 
    a radiation work permit. The primary dosimeter will be the 
    thermoluminescent dosimeter (TLD) for whole body exposure, however, 
    other types such as extremity TLD's will be employed, as conditions 
    warrant.
        For activities that have the potential to generate dusts, airborne 
    particulate monitoring will be performed to demonstrate compliance with 
    10 CFR Part 20 intake limits, determine whether precautionary measures 
    are needed (engineering controls, use of respiratory equipment), and 
    show how exposures are being maintained ALARA. To reduce the amount of 
    airborne particulates during excavations, the monazite pile will be 
    sprayed with water twice per day. For equipment decontamination within 
    affected survey units, HEPA air filtration in the immediate work area 
    will be used, as needed.
        Resuspension and airborne transport of contaminated soil during 
    excavations serves as the primary pathway for off-site releases from 
    decommissioning activities. HMI proposes to measure air particulates in 
    the downwind direction through the use of a high-volume air sampler. 
    Workers involved in excavations will be required to wear respiratory 
    protection until radiological airborne activity levels are determined. 
    HMI does not expect the proposed action will result in the generation 
    of off-site, airborne concentrations that would result in dose to a 
    member of the public in excess of the dose limits in 10 CFR Part 20. 
    Previous results of groundwater and surface water sampling have shown 
    negligible dose contribution due to the low levels of radionuclides 
    during site operations. Decommissioning activities will have no further 
    impact, therefore, additional water sampling is not needed.
        HMI's total dose estimates for a worker based on direct gamma 
    exposure rate from airborne soil releases from excavation activities of 
    the monazite pile of 1mR/h is 320 mRem, with dust inhalation dose at 6% 
    of the annual limit of intake (ALI) for the duration of the proposed 
    action. The off-site (public) annual dose limit in 10 CFR Part 20 is 
    100 mrem. Given the low estimated exposure beyond the site boundary, 
    the air sampling is adequate for off-site monitoring of potential 
    releases to ensure compliance with the dose limits of 10 CFR Part 20.
        Following review of radiological exposure controls, NRC determines 
    the proposed program methodologies are adequate for detecting potential 
    environmental impacts prior to license termination.
        6.2.5  Security. Security of radioactive material at the HMI 
    facility is maintained by a fence with a locked front entry gate around 
    the perimeter of the monazite pile. Security for mill buildings is 
    minimal, and other site areas are left unattended for long periods. 
    Equipment theft in mill buildings has been a known concern within 
    buildings, but missing equipment was believed to have been 
    decontaminated after operations shut down in 1990. These concerns 
    should be alleviated by the presence of on-site decommissioning 
    personnel. HMI has committed to establishing a fenced exclusion area 
    for shipping containers and equipment removed from buildings which 
    cannot be released for unrestricted use.
        NRC determines this is an adequate level of security to ensure 
    radiological safety will be maintained during decommissioning 
    activities at the site.
    6.3  Radiological Accident Analysis
        Potential accident scenarios considered include building fire and 
    loading or shipping incidents of radioactive materials. Due to the low 
    potential for fire or explosion in building structures and the limited 
    quantities of material used during transfer operations, accidental 
    releases of radioactive materials in quantities that could affect 
    public health and safety are unlikely. A 24-hour number will be 
    established to provide Radiation Safety Officer notifications in the 
    event emergency response is necessary.
        The NRC concludes that HMI has adequately addressed the potential 
    for radiological accidents.
    
    7.0  Environmental Impacts
    
    7.1  Radiological Impacts to the Public and Workers
        Potential sources of worker exposure from decommissioning 
    activities include characterization work, decontamination and 
    remediation of buildings and associated structures (piping, 
    foundations), and excavation of soils. Past NRC inspections showed 
    activities resulted in no measurable internal or external dose to 
    workers. These activities were similar to the proposed activities and 
    included equipment and building decontamination, radiological 
    characterizations, and monazite pile maintenance. NRC dose calculation 
    based upon excavation and packaging of 700 m3 of monazite 
    soil at an average thorium soil concentration of 25 pCi/g (highest 
    sample result obtained during
    
    [[Page 47877]]
    
    NRC inspection) project an occupational worker exposure under 10 mRem, 
    primarily due to external exposure. Based on the above, the staff 
    believes that worker exposures will be well within the 10 CFR Part 20 
    annual worker dose limit of 5000 mRem, and that no adverse impacts to 
    workers will result.
        Potential sources of radiological impacts to the public from 
    decommissioning activities at the HMI site are similar to those 
    pertaining to worker exposures (decontamination and excavation dusts), 
    but require transport over greater distances to reach off-site 
    receptors. As a result, lower concentrations and doses are expected for 
    members of the public than for workers. Previous NRC inspections showed 
    that worker exposures during past activities were undetectable. 
    Similarly, the public doses from these activities should be 
    undetectable. The NRC staff has determined that HMI has provided 
    adequate plans to ensure that potential radiological impacts to members 
    of the public from the proposed action will not exceed NRC limits and 
    are unlikely to result in adverse environmental impacts.
    7.2  Nonradiological Impacts
        There are no planned direct uses of chemicals in the proposed 
    action, only the excavation of soil, and remediation of equipment and 
    buildings. No other operations have a potential to affect the 
    environment. During scoping and characterization surveys, an assessment 
    of each building will be performed to identify the presence of 
    hazardous or mixed wastes. The survey will identify items requiring 
    management of hazardous substances, if found.
        The NRC staff has determined that HMI has acceptably addressed the 
    control of potential releases of nonradiological hazardous materials.
    
    8.0  Agencies and Individuals Consulted
    
        NRC transmitted the FSSP to the New Jersey Department of 
    Environmental Protection (NJDEP), US Environmental Protection Agency, 
    Region 2, and Township of Manchester by letters dated February 13, 
    1998, for review and comment. The response letter of March 18, 1998 
    from the NJDEP included comments regarding characterization of areas 
    with thorium levels below licensable quantities and extent of soil 
    removal, was forwarded to HMI for evaluation. HMI addressed the State's 
    comments in their letter of November 30, 1998 to NRC providing 
    acceptable responses to the NJDEP questions. No response was received 
    from the EPA or Manchester Township. HMI has committed to coordinate 
    with the NJDEP and comply with applicable State and local regulations 
    during decommissioning activities.
    
    9.0  Finding of No Significant Impact
    
        The Commission has prepared an EA related to the proposed 
    unrestricted release, and removal from license SMB-1541, of 700 
    m3 of monazite-rich soil from the Heritage Minerals, Inc., 
    Lakehurst, New Jersey site. On the basis of the EA, the Commission has 
    concluded that this licensing action would not significantly affect the 
    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.
        The NRC hereby provides notice that this is a proceeding on a 
    license amendment falling within the scope of Subpart L, ``Informal 
    Hearing Procedures for Adjudications in Materials and Operator 
    Licensing Proceedings,'' 10 CFR Part 2. Pursuant to Sec. 2.1205(a), any 
    person whose interest may be affected by this proceeding may file a 
    request for hearing in accordance with Sec. 2.1205 (d). A request for 
    hearing must be filed within thirty (30) days of the date of 
    publication of this Federal Register Notice.
        The request for a hearing must be filed with the Office of the 
    Secretary either:
        1. By delivery to the Docketing and Service Branch of the Secretary 
    at One White Flint North, 11555 Rockville Pike, Rockville , MD 20852-
    2738; or
        2. By mail or telegram addressed to the Secretary, U.S. Nuclear 
    Regulatory Commission, Washington, D.C., 20555. Attention: Docketing 
    and Service Branch.
        In addition to meeting other applicable requirements of 10 CFR Part 
    2 of the NRC's regulations, a request for a hearing filed by a person 
    other than an applicant must describe in detail:
        1. The interest of the requestor in the proceeding;
        2. How that interest may be affected by the results of the 
    proceeding, including the reasons why the requestor should be permitted 
    a hearing, with particular reference to the factors set out in Sec. 
    2.1205(h),
        3. The requestor's area of concern about the licensing activity 
    that is the subject matter of the proceeding; and
        4. The circumstances establishing that the request for a hearing is 
    timely in accordance with Sec. 2.1205(d).
        In accordance with Sec. 2.1205(f), each request for hearing must 
    also be served, by delivering it personally or by mail, to:
        1. Heritage Minerals, Inc., Attention: Anthony J. Thompson, 
    Esquire, ShawPittman, 2300 N Street, NW, Washington, DC 20037-1128; and
        2. The NRC staff, by delivery to the Executive Director for 
    Operations, One White Flint North, 11555 Rockville Pike, Rockville, MD 
    20852-2738 or by mail, addressed to the Executive Director for 
    Operations, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
        The documents related to this proposed action are available for 
    public inspection and copying at the NRC Public Document Room, 2120 L 
    Street NW., Washington, DC 20555 or at the NRC's Region I offices 
    located at 475 Allendale Road, King of Prussia, PA 19406.
    
    10.0  References
    
        Berger, J.D., ``Manual for Conducting Radiological Surveys in 
    Support of License Termination,'' NUREG/CR-5849, Washington, DC: 
    Nuclear Regulatory Commission. 1992.
        Nuclear Regulatory Commission, ``Guidelines for Decontamination 
    of Facilities and Equipment Prior to Release for Unrestricted Use 
    for Termination of Byproduct, Source, and Special Nuclear Material 
    Licenses,'' Policy and Guidance Directive FC 83-23, 1983.
        Nuclear Regulatory Commission, ``Final Generic Environmental 
    Impact Statement in Support of Rulemaking on Radiological Criteria 
    for License Termination of NRC Licensed Nuclear Facilities,'' NUREG-
    1496, Volume 2, 1997.
        Orlando, D., et al., ``NMSS Handbook for Decommissioning Fuel 
    Cycle and Materials Licensees,'' NUREG/BR-0241, Washington, DC: 
    Nuclear Regulatory Commission, 1997.
    
        Dated at King of Prussia, Pennsylvania this 20th Day of August 
    1999.
    
        For the Nuclear Regulatory Commission.
    George Pangburn,
    Director, Division of Nuclear Materials Safety.
    [FR Doc. 99-22767 Filed 8-31-99; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
09/01/1999
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
99-22767
Pages:
47872-47877 (6 pages)
Docket Numbers:
Docket No. 40-08980
PDF File:
99-22767.pdf