ML20057F103
| ML20057F103 | |
| Person / Time | |
|---|---|
| Site: | 05000047 |
| Issue date: | 10/05/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057F091 | List: |
| References | |
| NUDOCS 9310140118 | |
| Download: ML20057F103 (3) | |
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wassiuorou, o.c. romoooi SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE ORDER TERMINATING AMENDED FACILITY LICENSE NO. R-65 U.S. ARMY MATERIALS TECHNOLOGY LABORATORY RESEARCH REACTOR DOCKET NO. 50-47
1.0 INTRODUCTION
By letter dated October 8,1991, as supplemented on March 16 and March 31, 1992, the U.S. Army Materials Technology Laboratory (AMTL or the licensee) submitted a plan to dismantle and decontaminate its reactor facility The letter of October 8, 1991, contained a request for termination of Amended Facility License No. R-65.
Following U.S. Nuclear Regulatory Commission (NRC) staff review, the plan was approved on June 3, 1992, and the licensee commenced dismantlement and decontamination. On June 23 and November 3, 1992, as supplemented on November 24, 1992, the licensee requested approval for changes to the decommissioning plan. These changes were approved on July 16, 1992, and January 21, 1993.
Upon completion of the dismantlement and decontamination, the licensee submitted, by letter dated March 30, 1993, as supplemented on May 24, 1993, t
and July 14, 1993, the final survey report for decommissioning the reactor as a basis for license termination.
On April 26 through 29, 1993, representatives from the Oak Ridge Institute for Science and Education (0 RISE) performed a confirmatory survey at the facility under an interagency agreement and in accordance with a request for technical assistance from NRC Region I.
This termination applies to Reactor Building 100 and the reactor yard (see Figure 1).
Building 97 of the AMTL is not under Facility License No. R-65 and is not part of this termination action.
Parts of Building 97 were under the facility license when the facility was in operation. The Deactivation Report of the Army Materials Research Reactor dated February 3, 1970, as supplemented on December 8, 1970, stated that equipment and areas in Building 97 had been transferred to AMTL Byproduct Material License No. 20-01010-04 (Docket No. 030-04593). The facility license for the AMTL was amended to possession only status on April 3,1971. The technical specifications issued with that amendment reflect the information in the deactivation report; the plant is described as the area within the reactor containment shell. The area for the materials license is described as the AMTL, Arsenal Street, Watertown, Massachusetts. This description includes Building 97. The materials license is subject to the Facility Decommissioning Plan dated April 1992, which clearly commits to the decontamination and survey by the licensee of Building 97.
It will be confirmed by the NRC that the radiological condition of Building 97 meets NRC release criteria before the 9310140118 931005 PDR ADOCK 05000047 H
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! i materials license is terminatt.4. This ensures that all areas that were under the reactor license are subject to NRC approval to be returned to unrestricted
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use.
f 2.0 EVALUATION r
In a memorandum dated July 9,1993, from James H. Joyner, Chief, facilities Radiological Safety and Safeguards Branch, Region I, to Seymour H. Weiss, Director, Non-Power Reactors and Decommissioning Project Directorate, the Region I staff concluded that (1) the decommissioning has been performed in accordance with the approved decommissioning plan and the order authorizing decommissioning and (2) the termination radiation surveys and associated documentation demonstrate that the reactor facility is suitable for release for unrestricted use. The regional staff based its conclusions on (1) a walkover dose rate survey conducted by a regional inspector (Inspection Report No. 50-47/93-01), (2) the confirmatory radiological survey performed by the ORISE that verified the licensee results, and (3) the NRC review of a confirmatory survey performed by the U.S. Army Environmental Hygiene Agency and additional information submitted by the licensee (Inspection Report No. 50-47/93-02).
The residual contamination levels for the reactor facility comply with the criteria of Regulatory Guide 1.86, Table 1, which established acceptable residual surface contamination levels; direct radiation levels are below 5-microR/hr above background at 1 meter, which is the exposure limit established by the NRC staff; and material licensed under Amended Facility License No. R-65 has been removed from site. Therefore, the facility can be released for unrestricted use and the amended facility license terminated.
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3.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and i
finding of no significant impact has been prepared and published in the Federal Reaister on october 4,1993 (58 FR 51654). Accordingly, based upon the environmental assessment and the above safety evaluation, the Commissio-has determined that no environmental impact statement is required and that issuance of the order terminating the license will have no significant adverse effect on the quality of the human environment.
4.0 CONCLUSION
On the basis of the foregoing considerations, the staff concludes that Amended Facility License No. R-65 can be terminated without undue risk to the health and safety of the public or workers and without any significant impact on the public or the environment.
Principal Contributor: Alexander Adams, Jr.
Date:
October 5, 1993 1
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