Finding of No Significant Impact and Notice of Opportunity f
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Finding of No Significant Impact and Notice of Opportunity f
[Federal Register: May 17, 1995 (Volume 60, Number 95)] [Notices]
[Page 26464-26465]
>From the Federal Register Online via GPO Access [wais.access.gpo.gov]
NUCLEAR REGULATORY COMMISSION
[Docket 40-3392]
Finding of No Significant Impact and Notice of Opportunity for a Hearing; Renewal of Source Material License Sub-526 AlliedSignal, Inc. Metropolis, Illinois
The U.S. Nuclear Regulatory Commission is considering the renewal of Source Material License SUB-526 for the continued operation of the AlliedSignal, Inc. (Allied), UF<INF>6 conversion facility, located in Metropolis, Illinois.
Summary of the Environmental Assessment
Identification of the Proposed Action
The proposed action is the renewal of Allied's Source Material License SUB-526 for 10 years. With this renewal, the Metropolis facility will continue to convert natural uranium ore concentrates into UF<INF>6 for the commercial nuclear power industry. The production of UF<INF>6 is one phase in the fuel cycle resulting in production of fuel elements for nuclear reactors.
The Need for the Proposed Action
Allied performs a necessary service for the commercial nuclear power industry by converting natural uranium ore concentrates into UF<INF>6. The UF<INF>6 product is then shipped to gaseous diffusion plants for the enrichment of the uranium (U-235) isotope; following enrichment, the uranium is converted into fuel for use in nuclear power reactors. Currently, Allied is the only UF<INF>6 conversion facility operating within the United States. Denial of the license renewal for Allied's Metropolis facility is an alternative available to the NRC, but would require the construction of a new facility at another site.
Environmental Impacts of the Proposed Action
The radiological impacts of the continued operation of the Metropolis facility were assessed by calculating the radiation dose to the maximally exposed individual located at the nearest residence and the collective radiation dose to the local population living within 80 kilometers (50 miles) of the plant site.
Doses From Routine Airborne Releases
Atmospheric releases were determined for three locations at the Metropolis facility: (1) the feed material building, (2) the uranium recovery facility, and (3) the ore sampling plant. Based on information provided in the application, the projected annual average quantity of uranium released from each emission point was estimated. The isotopic distribution of the uranium and the solubility class of the uranium were also determined. Relatively small amounts of thorium-230 and radium-226 are also released from the Metropolis facility. The radiation doses resulting from atmospheric releases were estimated using the XOQDOQ and GENII computer codes. The maximally exposed individual was located at the nearest residence, which was 564 meters (1,850 feet) north northeast of the Metropolis facility. The radiation dose Total Effective Dose Equivalent (TEDE) to the nearest resident is estimated to be 1.5 mrem per year. This estimated radiation dose is less than the limit of 10 mrem per year established by the U.S. Environmental Protection Agency (EPA) in 40 CFR Part 61 for the air pathway and less than the limit of 25 mrem per year established by the EPA in 40 CFR Part 190 for all pathways. It is also less than the 100 mrem per year limit established by the NRC in 10 CFR Part 20. The highest organ dose is to the lungs from insoluble forms of uranium. The estimated lung dose of 9.3 mrem per year is less than the dose limit established in 40 CFR Part 190; the thyroid doses were also an insignificant fraction of the 75 mrem per year thyroid dose limit established in 40 CFR Part 190.
The population surrounding Allied's facility is about 471,410 people, based on 1990 census data. The collective dose to the surrounding population is estimated to be 4.1 person-rem per year. Based on an average background radiation dose of 0.360 rem per year for individuals in the U.S., the same population would receive about 170,000 person-rem per year from background radiation. Thus, the collective radiation dose associated with atmospheric releases from Allied's facility is a very small percentage (0.0024) of the collective radiation dose from background radiation for these same people.
Doses From Aqueous ReleasesThe projected annual average quantity of radionuclides released to the Ohio River from the Metropolis facility was estimated using information provided by the applicant. The GENII computer code was used to estimate radiation doses through ingestion, shoreline exposure, and water submersion pathways. The estimated radiation dose (TEDE) to the maximally exposed individual located 8 kilometers (5 miles) downstream of the Metropolis facility is estimated to be 0.0013 mrem per year. This estimated radiation dose is far less than the 100 mrem per year limit established by the NRC in 10 CFR Part 20 and the 25 mrem per year limit established by EPA in 40 CFR Part 190. The estimated radiation dose of 0.0013 mrem per year is also far less than the dose of 4 mrem per year that is the basis for the drinking water standards contained in 40 CFR Part 141.
The estimated collective radiation dose to the population (4,846 people) located in Cairo, Illinois, as a result of liquid releases is estimated to be 0.0030 person-rem per year. Based on an average background radiation dose of 0.360 rem per year for individuals in the U.S., this same population would receive about 1,700 person-rem per year from background radiation; the collective radiation dose associated with liquid releases from Allied's Metropolis facility thus is a small percentage of the collective radiation dose from background.Accident Evaluation
In the Environmental Assessment, the NRC evaluated a suite of five accident scenarios. Four of the five scenarios [[Page 26465]] evaluated the accidental release of radioactive materials. The intakes and predicted doses for three of the radiological accident scenarios were small with negligible associated health impacts. The fourth radiological accident, rupture of a UF<INF>6 cylinder (liquid), produced a dose of 3.9 rem at the nearest resident. While the potential consequences of such an event would be severe, the likelihood of such an event is low because of design and procedural controls. The fifth accident analyzed, the release of gaseous ammonia, would be expected to produce noticeable, but non-life-threatening effects both onsite and offsite. Given the low likelihood for these accidents, it is concluded that the proposed license renewal will not have a significant impact on the general population.
Alternatives to the Proposed Action
Alternatives to the proposed action include denial of Allied's renewal application. Not granting a license renewal for the facility would cause Allied to cease production of UF<INF>6 at this site. The only benefits to be gained by nonrenewal would be the cessation of the minor environmental impact from operation of the facility. Because Allied's site is the only operating facility to convert uranium ore to UF<INF>6, denial of a license for Allied would result in the transfer of the activity and associated environmental impact to an alternative site.
Agencies and Persons Consulted
The staff utilized the application dated July 11, 1994, and additional information dated September 6, and November 16, 1994. Discussions were held with the Agreement States of Illinois and Kentucky. The Region III inspectors and Allied representatives were also consulted in preparing this document.
Conclusion
The staff concludes that the environmental impacts associated with the proposed license renewal for continued operation of Allied's Metropolis facility are expected to be insignificant.
Finding of No Significant Impact
The NRC has prepared an Environmental Assessment related to the renewal of Source Material License SUB-526. On the basis of the assessment, NRC has concluded that environmental impacts that would be created by the proposed licensing 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 Environmental Assessment and the documents related to this proposed action are available for public inspection and copying at NRC's Public Document Room at the Gelman Building, 2120 L Street NW, Washington, DC.Opportunity for a Hearing
Any person whose interest may be affected by the issuance of this renewal may file a request for a hearing. Any request for hearing must be filed with the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555, within 30 days of the publication of this notice in the Federal Register; be served on the NRC staff (Executive Director for Operations, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852), and on the licensee (AlliedSignal, Inc., Route 45 North, P.O. Box 430, Metropolis, IL 62960); and must comply with the requirements for requesting a hearing set forth in the Commission's regulation, 10 CFR Part 2, Subpart L, ``Informal Hearing Procedures for Adjudications in Materials Licensing Proceedings.''
These requirements, which the requestor must address in detail, are:
- The interest of the requestor in the proceeding;
- How that interest may be affected by the results of the proceeding, including the reasons why the requestor should be permitted a hearing;
- The requestor's areas of concern about the licensing activity that is the subject matter of the proceeding; and
- The circumstances establishing that the request for hearing is timely, that is, filed within 30 days of the date of this notice. In addressing how the requestor's interest may be affected by the proceeding, the request should describe the nature of the requestor's right under the Atomic Energy Act of 1954, as amended, to be made a party to the proceeding; the nature and extent of the requestor's property, financial, or other (i.e., health, safety) interest in the proceeding; and the possible effect of any order that may be entered in the proceeding upon the requester's interest. Dated at Rockville, Maryland, this 11th day of May 1995.
For the Nuclear Regulatory Commission. Robert C. Pierson,
Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards, NMSS.
[FR Doc. 95-12103 Filed 5-16-95; 8:45 am] BILLING CODE 7590-01-P
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