ML20217A209
| ML20217A209 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 04/15/1998 |
| From: | Mendonca M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217A175 | List: |
| References | |
| R-113-A-009, R-113-A-9, NUDOCS 9804220197 | |
| Download: ML20217A209 (3) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20066-4001 o% ...../
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U.S. GEOLOGICAL SURVEY, DEPARTMENT OF THE INTERIOR DOCKET NO. 50-274 j AMENDMENT TO FACILITY LICENSE l
Amendment No. 9 l License No. R-113 1
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
l A. The application for an amendment to Facility License No. R 113 filed by the United States Geological Survey (USGS or the licensee) on March 6,1998, as supplemented on April 1,1998, conforms to the standards and requirements of l, the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the i Commission as set forth in Chapter i of Title 10 of the Code of Federal l Regulations (10 CFR); l B. The facility will operate in conformity with the application, the provisions of the j l
Act, and the rules and regulations of the Commission; )
i l C. There is reasonable assurance (i) that the activities authorized by this amendment I
l can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with the regulations of the Commission as set forth in 10 CFR Part 51, and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105, and publication of notice for this amendment is not required by 10 CFR 2.106.
9804220197 980415 PDR ADOCK 05000274 P PDR i
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- 2. Accordingly, the license is amended by changes to paragraph 3.D. of Facility License No. R-113, which is hereby amended to read as follows:
D. Reports in addition to reports otherwise required by applicable regulations:
(1) The licensee shall inform the Commission of any incident or condition relating to the operation of the reactor which prevented or could have prevented a nuclear system from performing its safety function as described in the Technical Specifications or in the safety analysis rep rt. For each such occurrence, the USGS shall promptly notify by telephone or facsimile the NRC Operations Center and shall submit within ten (10) days a report in writing to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington DC 20555.
(2) As promptly as practicable, but no later than sixty (60) days after the initial criticality of the facility, the USGS shall submit a written report to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington DC 20555, I describing the measured values of the operating conditions or characteristics listed below and evaluating any significant variation of a measured value from the corresponding predicted value:
- a. Maximum excess reactivity of the facility, not including the worth of control rods or other control devices such as burnable poison strips or soluble poison, or any experiments;
- b. Total control rod reactivity worth;
- c. Minimum shutdown margin both at room and operating temperatures;
- d. Maximum worth of the single control rod of highest reactivity value; and
- e. Maximum total and individual reactivity worth of any fixed or movable experiments inserted in the facility.
(3) The licensee shall report to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington DC 20555, in writing within thirty (30) days of its
- occurrence any substantial variance disclosed by operation of the reactor from performance specifications contained in the safety analysis report or in the l Technical Specifications.
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'(4) The licensee shall report to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington DC 20555, in writing within thirty (30) days of its occurrence, any significant change in the transient or accident analysis, as described in the safety analysis report.
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- 3. This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w-l l Marvin M. Mendonca, Acting Director l Non-Power Reactors and Decommissioning
! Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Date of issuance: April 15, 1998 l
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