ML20216H775
| ML20216H775 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 03/16/1998 |
| From: | Mendonca M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216H772 | List: |
| References | |
| R-113-A-008, R-113-A-8, NUDOCS 9803230174 | |
| Download: ML20216H775 (5) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 2055!k4001 Y+,. . . . . ,o U.S. GEOLOGICAL SURVEY, DEPARTMENT OF THE INTERIOR I DOCKET NO. 50-274 j AMENDMENT TO FACILITY LICENSE Amendment No. 8 License No. R-113
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for an amendment to Facility License No. R-113 filed by the United States Geological Survey (USGS or the licensee) on May 5,1993, as supplemented on February 23 and August 17,1995, and July 16 and l
November 4,1997, conforms to the standards and requirements of the Atomic !
Energy Act of 1954, as amended (the Act), and the regulations of the Commission as set forth in Chapter I of Title 10 of the Code of Federal Regulations (10 CFR);
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i C. There is reasonable assurance (1) that the activities authorized by this
! amendment can be conducted without endangering the health and safety of the public and (2) 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.
9803230174 980316 PDR ADOCK 05000274 P PDR
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 3.B. of Facility License No. R-113 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 8, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear P.eactor Regulation
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Enclosure:
1 Appendix A Technical Specification Changes Date of issuance: March 16, 1998 I'
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ENCLOSURE TO LICENSE AMENDMENT NO. 8
. FACILITY LICENSE NO. R-113 DOCKET NO. 50-274 Replace the following pages of Appendix A Technical Specifications with the enclosed
. pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 4 4 Sa 5a l
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- 2. 'Ihe pool water shall be sanpled for corductivity at least weekly.
Conductivity averaged cwer a month shall not ervwi 5 miuwis per cm 2 , ,Ihis itan is not applicable if the reactor is l
l capletely defueled and the pool level is below the water treatment systan intake.
l D. Reactor Core
- 1. 'the core shall be an awmbly of 'mIGA stainless steel clad fuel-moderator elements, ncninally 8.5 to 12 wt% uranium, arrarged in a close-packed array except for (1) replacement of single individual elements with incere irradiation facilities or control rods; (2) two separated experiment positions in the D through E ,
l rings, eacti occupyirg a maxinn of three fuel element positions.
'Ibe reflector (excludirg experiments and experimental facilities) shall be water or a combination of graphite and water. 'Ibe reactor shall not be operated in any manner that would cause any fuel element to produce a calculated steady state power level in l excess of E2 kW.
- 2. 'Ihe excess reactivity above cold critical, withcut xenan, shall not eJ#vwi 4.9% delta k/k with experimats in place.
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- 3. Fuel tatperatures near the core midplane in either the B or C ring of elements shall be continuously recorded during the pulse made of operation usiry a stardard thermocouple fuel elemnt. 'Ibe ther-ple element shall be of 12 wt% uranium loading if any 12 wt% loaded elements exist in the core. 'Ihe reactor shall not be operated in a manner which would cause the measured fuel tenperature to exceed 8000C.
4 Power levels durirg pulse mode operation that exceed 2500 megawatts shall be cause for the reactor to the shut down pendirq an investigation by the reactor supervisor to determine the reason Amendment No. 8
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l Any element which exhibits a clad break as indicated by a l measunble release of fission products shall be loc:.ted and l
removed frun service before continuation of routine operaticn.
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- 7. The power produced by each fuel element while operating at the l
rated full power shall be calculated if the reactor is to be operated at greater than 100 W with less than 100 fuel elements in the core. Recalculations shall be performed:
a) at 6 i 1 nonth intervals, or b) whenever a core loading charrJe omurs.
Power per element calculations are not required at any time that i the core contains at least 100 fuel elements or if reactor power is limited to 100 W. If the calculations show that any fuel element would produce more than 22 W, the reactor shall not be operated with that core configuration.
E. Control and Safety Systens
- 1. The standard control rods shall have scram capability and the poison section shall contain borated graphite, or boren and its l
m_wris in solid form as a poison in an aluminum or stainless steel clad.
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l Amendment No. 8