[Federal Register Volume 62, Number 232 (Wednesday, December 3, 1997)] [Notices] [Pages 63968-63969] From the Federal Register Online via the Government Publishing Office [www.gpo.gov] [FR Doc No: 97-31731] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket 70-7001] Notice of Amendment to Certificate of Compliance GDP-1 for the U.S. Enrichment Corporation, Paducah Gaseous Diffusion Plant, Paducah, Kentucky The Director, Office of Nuclear Material Safety and Safeguards, has made a determination that the following amendment request is not significant in accordance with 10 CFR 76.45. In making that determination the staff concluded that: (1) There is no change in the types or significant increase in the amounts of any effluents that may be released offsite; (2) there is no significant increase in individual or cumulative occupational radiation exposure; (3) there is no significant construction impact; (4) there is no significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents; (5) the proposed changes do not result in the possibility of a new or different kind of accident; (6) there is no significant reduction in any margin of safety; and (7) the proposed changes will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security programs. The basis for this determination for the amendment request is shown below. The NRC staff has reviewed the certificate amendment application and concluded that it provides reasonable assurance of adequate safety, safeguards, and security, and compliance with NRC requirements. Therefore, the Director, Office of Nuclear Material Safety and Safeguards, is prepared to issue an amendment to the Certificate of Compliance for the Paducah Gaseous Diffusion Plant. The staff has prepared a Compliance Evaluation Report which provides details of the staff's evaluation. The NRC staff has determined that this amendment satisfies the criteria for a categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for this amendment. USEC or any person whose interest may be affected may file a petition, not exceeding 30 pages, requesting review of the Director's Decision. The petition must be filed with the Commission not later than 15 days after publication of this Federal Register notice. A petition for review of the Director's Decision shall set forth with particularity the interest of the petitioner and how that interest may be affected by the results of the decision. The petition should specifically explain the reasons why review of the Decision should be permitted with particular reference to the following factors: (1) The interest of the petitioner; (2) how that interest may be affected by the Decision, including the reasons why the petitioner should be permitted a review of the Decision; and (3) the petitioner's areas of concern about the activity that is the subject matter of the Decision. Any person described in this paragraph (USEC or any person who filed a petition) may file a response to any petition for review, not to exceed 30 pages, within 10 days after filing of the petition. If no petition is received within the designated 15-day period, the Director will issue the final amendment to the Certificate of Compliance without further delay. If a petition for review is received, the decision on the amendment application will become final in 60 days, unless the Commission grants the petition for review or otherwise acts within 60 days after publication of this Federal Register notice. A petition for review must be filed with the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC, by the above date. For further details with respect to the action see (1) the application for amendment and (2) the Commission's Compliance Evaluation Report. These items are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC, and at the Local Public Document Room. Date of amendment request: October 6, 1997. Brief description of amendment: The amendment proposes to revise Technical Safety Requirement (TSR) 2.3.4.7 and TSR 2.4.4.2, Criticality Accident Alarm System (CAAS) for Product and Tails Withdrawal and Cascade Facilities, to provide a cross reference for the Required Actions in order to assure all necessary Required Actions are performed when the C-310 CAAS is inoperable. Basis for finding of no significance: 1. The proposed amendment will not result in a change in the types or significant increase in the amounts of any effluents that may be released offsite. The proposed changes are related to human factors and do not change any requirements. There are no associated [[Page 63969]] effluent releases. Thus, they will not affect any effluents that may be released offsite. 2. The proposed amendment will not result in a significant increase in individual or cumulative occupational radiation exposure. The proposed changes do not change or add any new requirements. The changes provide a cross reference between TSRs to ensure all required actions are performed when necessary. The changes do not relate to controls used to minimize occupational radiation exposures; therefore, the changes will not increase exposure. 3. The proposed amendment will not result in a significant construction impact. The proposed changes will not result in any construction, therefore, there will be no construction impacts. 4. The proposed amendment will not result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents. The proposed changes are administrative and serve only to relate the components of the CAAS in C-310. The changes do not change the current TSRs, only link separate sections more clearly. Therefore, the proposed changes do not represent an increase in the potential for, or radiological or chemical consequences from, previously evaluated accidents. 5. The proposed amendment will not result in the possibility of a new or different kind of accident. The proposed changes to the TSRs do not add or change any TSR requirements. Therefore, the changes would not create new operating conditions or new plant configuration that could lead to a new or different type of accident. 6. The proposed amendment will not result in a significant reduction in any margin of safety. The proposed changes attempt to rectify the situation in which an operator could overlook the linkage between the two TSRs that both contain required actions related to the CAAS. By including a cross reference, the changes try to ensure all required actions are performed. These changes do not decrease the margins of safety. 7. The proposed amendment will not result in an overall decrease in the effectiveness of the plant's safety, safeguards, or security programs. Implementation of the proposed changes do not change the safety, safeguards, or security programs. Therefore, the effectiveness of the safety, safeguards, and security programs is not decreased. Effective date: The amendment to Certificate of Compliance GDP-1 becomes effective 30 days after being signed by the Director, Office of Nuclear Material Safety and Safeguards. Certificate of Compliance No. GDP-1: The Amendment will provide cross references for two Technical Safety Requirements for the Criticality Accident Alarm System in Building C-310. Local Public Document Room location: Paducah Public Library, 555 Washington Street, Paducah, Kentucky 42003. Dated at Rockville, Maryland, this 25th day of November 1997. For the Nuclear Regulatory Commission. Carl J. Paperiello, Director, Office of Nuclear Material Safety and Safeguards. [FR Doc. 97-31731 Filed 12-2-97; 8:45 am] BILLING CODE 7590-01-P