[Federal Register Volume 64, Number 150 (Thursday, August 5, 1999)] [Notices] [Pages 42730-42732] From the Federal Register Online via the Government Publishing Office [www.gpo.gov] [FR Doc No: 99-20124] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-89 and 50-163] General Atomics TRIGA Mark I and Mark F Research Reactors; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of a license amendment to Amended Facility License No. R-38 and Facility License No. R-67, issued to General Atomics (GA or the licensee), for decommissioning of the GA TRIGA Mark I and TRIGA Mark F Research Reactors, located at General Atomics in San Diego, San Diego county, California. Environmental Assessment Identification of Proposed Action The proposed action would approve the licensee's decommissioning plan. GA submitted their decommissioning plan in accordance with 10 CFR 50.82(b) for the GA TRIGA Mark I and TRIGA Mark F Research Reactors which occupy parts of the TRIGA Reactor Facility within GA's Torrey Mesa site. The TRIGA Mark I license was amended on October 29, 1997, and the TRIGA Mark F license was amended on March 22, 1995, to remove authority to operate the reactors. Fuel from both reactors have been placed in the TRIGA Mark F fuel storage canal which is in the same pool as the TRIGA Mark F reactor. The proposed decommissioning plan would authorize immediate dismantlement of the TRIGA Mark I Research Reactor. To protect the stored fuel from potential damage due to decommissioning activities, only limited dismantlement of the TRIGA Mark F Research Reactor [[Page 42731]] will occur with fuel in the TRIGA Mark F fuel storage canal. This would be followed by a period of fuel storage. After fuel is removed from the TRIGA Mark F fuel storage canal, dismantling will be completed on the TRIGA Mark F Research Reactor. The soonest that the Department of Energy can accept fuel from GA is 2003. Domestic spent nuclear fuel receipts at the Idaho National Engineering and Environmental Laboratory have been severely constrained because of a settlement agreement of a lawsuit concerning spent nuclear fuel and nuclear waste. The site will be decontaminated to meet unrestricted release criteria. After the Commission verifies that the release criteria have been met, the reactor license will be terminated. The licensee will continue with their health physics program, and approved emergency and security plan during the decommissioning and their operator requalification plan until fuel is removed from the facility. A ``Notice of Application for Decommissioning Amendment'' was published in the Federal Register on December 11, 1997 (62 FR 65288), in accordance with the requirements of 10 CFR 50.82(b)(5). The proposed action is in accordance with the licensee's application for amendment dated April 18, 1997, as supplemented on November 20, 1998, and January 28 and 29, February 3, April 22, May 3 and 12, and June 15, 16, and 22, 1999. The Need for the Proposed Action The proposed action is needed because of GA's decision to cease reactor operations permanently at the Torrey Mesa site. As specified in 10 CFR 50.82, any licensee may apply to the NRC for authority to surrender a license voluntarily and to decommission the affected facility. Once the licensee permanently ceases operation, 10 CFR 50.82(b)(1) requires the licensee to make application for license termination within two years following permanent cessation of operations, and in no case later than one year prior to expiration of the operating license. GA is planning to use the area that would be released for unrestricted use for other purposes. Environmental Impact of the Proposed Action The Commission has completed its evaluation of the proposed action and concludes that the radiological effects of decommissioning the TRIGA Mark I and Mark F Research Reactors will be minimal. The licensee will continue with their health physics program, and approved emergency and security plans. Until fuel is removed from the site, the licensee will also continue to meet the requirements of their operator requalification plan. All proposed operations in connection with decommissioning and decontaminating of the GA reactors will be carefully planned and controlled, all contaminated components will be removed, packaged, and shipped offsite in accordance with the regulations, and radiological control procedures will be in place and implemented to ensure that releases of radioactive wastes from the facility are within the limits of 10 CFR Part 20 and are as low as reasonably achievable (ALARA). All decontamination will be performed by trained personnel in accordance with previously reviewed procedures and will be overseen by experienced health physics staff. No new postulated accidents have been identified during decommissioning activities or storage of the reactor fuel that would have greater radiological impact than previously evaluated accidents. The GA staff has calculated that the total dose to workers for the decommissioning project will be about 20 person-rem over the period 1999 to 2004 (assuming fuel is removed from the facility in 2003). The GA staff estimates that the dose to members of the public from decommissioning activities will be negligible. These doses are consistent with those given in NUREG-0586, ``Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities,'' for the reference research reactor. While on site, fuel will be stored in approved storage locations under the restrictions of the facility license. The license will continue to maintain systems necessary for safe storage of the fuel. The proposed action will not increase the probability or consequences of accidents, no changes are being made in the types of any effluents that may be released off site, and there is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action. With regard to potential non-radiological impacts, the proposed action does not involve any historic sites. Hazardous materials such as lead and asbestos will be handled and disposed of in accordance with all applicable regulations and, therefore, will not result in any significant release of non-radiological plant effluents and has no other environmental impact. Therefore, there are no significant non- radiological environmental impacts associated with the proposed action. Accordingly, the Commission concludes that there are no significant environmental impacts associated with the proposed action. Alternatives to the Proposed Action The alternatives to the proposed action for the GA TRIGA research reactors are SAFSTOR, ENTOMB and no action. ENTOMB is the alternative in which radioactive contaminates are encased in a structurally long- lived material, such as concrete, the entombed structure is appropriately maintained and continued surveillance is carried out until the radioactivity decays to a level permitting release of the property for unrestricted use. SAFSTOR is the alternative in which the facility is placed and maintained in a condition that allows the facility to be safely stored and subsequently decontaminated to levels that permit release for unrestricted use. The ENTOMB alterative could not be put into place until the fuel was removed from the facility and would require the facility to remain on site for an extended period of time. Likewise, the SAFSTOR alternative would require continued surveillance for an extended period of time. However, GA wants to use the space that will become available for other purposes and wants to enter into the decommissioning activities as soon as possible. The alternative of not decommissioning reactors was rejected in NUREG-0586. The no action alternative would leave the facility in its present configuration. Denial of the application would result in no significant change in current environmental impacts. The environmental impacts of the proposed action and the alternative actions are similar. Alternative Use of Resources The action does not involve the use of resources different from previously committed for construction and operation of the GA TRIGA reactors. Agencies and Persons Consulted In accordance with its stated policy, on July 20, 1999, the staff consulted with the State of California official, R. Lupo of the Radiologic Health Branch of the California Department of Health Services regarding the environmental impact of the proposed action. The state official had no comments. Finding of No Significant Impact On the basis of the environmental assessment, the Commission concludes that the proposed action will not have [[Page 42732]] a significant effect on the quality of the human environment. Accordingly, the Commission has determined not to prepare an environmental impact statement for the proposed action. For further details with respect to this proposed action, see the licensee's letter dated April 18, 1997, as supplemented by letter dated November 20, 1998, and January 28 and 29, February 3, April 22, May 3 and 12, and June 15, 16, and 22, 1999. These documents are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, D.C. 20003-1527. Dated at Rockville, Maryland, this 29th day of July 1999. For the Nuclear Regulatory Commission. Ledyard B. Marsh, Chief, Events Assessment, Generic Communications and Non-Power Reactors Branch, Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation. [FR Doc. 99-20124 Filed 8-4-99; 8:45 am] BILLING CODE 7590-01-P