ML20195B659
| ML20195B659 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 11/10/1998 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195B651 | List: |
| References | |
| R-106-A-017, R-106-A-17, NUDOCS 9811160235 | |
| Download: ML20195B659 (5) | |
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p ce:u UNITED STATES
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4 WASHINGTON, D.c. 20066 0001 4,.....,o OREGON STATE UNIVERSITY DOCKET NO. 50-243 AMENDMENT TO AMENDED FACILITY OPERATING LICENSE Amendment No.17 License No. R-106 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that A.
The application for an amendment to Amended Facility Operating License No.
R-106 filed by Oregon State University (the licensee) on July 27,1998, as supplemented on September 30,1998, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in Chapter I of Title 10 of the Code of FederalRegulations (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; C.
There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) 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.
This amendment is issued in accordance with the regulations of the Commission as stated 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.
9811160235 981110 PDR ADOCK 05000243 P
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O 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Amended Facility Operating License No. R-106 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.17, 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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g d-Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosure:
Appendix A, Technical Specifications Changes Date of issuance: November 10, 1998 l
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.l ENCLOSURE TO LICENSE AMENDMENT NO.17 l
AMENDED FACILITY OPERATING LICENSE NO. R-106 DOCKET NO. 50-243 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 15 15 17 17 S
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1 Ragit. The minimum height cf 14 feet cf water ab:;ve the ccre guarantees that' there is sufficient water for effective cooling of the fuel and that the radiation levels at the top of the reactor are within acceptable levels (SAR). The bulk l
water temperature limit is necessary, according to the reactor manufacturer, to ensure that the aluminum reactor tank maintains its integrity and is not degrad-l ed.
L 3.8 LIMITATIONS ON EXPERIMENTS Aeolicabilitv. This specification applies to experiments installed in the reactor and its experimental facilities.
Oblective. The objective is to prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.
Soecifications. The reactor shall not be operated unless the following condi-tions governing experiments exist:
i Non-secured experiments shall have reactivity worths less than 1 dollar.
a.
b.
The reactivity worth of any single experiment will be less than 2.55 dollars.
Total experiment worth of all experiments will not exceed 3.00 dollars.
c.
l d.
Explosive materials, such as gunpowder, TNT, nitroglycerin, or PETN, in
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quantities greater than 25 milligrams shall not be irradiated in the reactor or experimental facilities. Explosive materials in quantities less than 25 milligrams may be irradiated provided the pressure produced upon detona-tion of the explosive has been calculated and/or experimentally demon-strated to be less than the design pressure of the container. EXCEPTION:
Explosive materials not exceeding 0.014 lbs. equivalent of TNT may be irradiated in the '# mtory area adjacent to the end of the OSTR tangen-tial beamport for the surpose of neutron radiography.
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e.
Where the possibility exists that the failure of an experiment (except fueled experiments) under (1) normal operating conditions of the experiment or i
reactor, (2) credible accident conditions in the reactor, or (3) possible accident conditions in the experiment could release radioactive gases or i
l aerosols to the reactor bay or the unrestricted area, the quantity and type of material in the experiment shall be limited such that the airbome radioactivity in the reactor bay or the unrestricted area will not result in exceeding the applicable dose limits in 10 CFR 20, assuming 100% of the gases or aerosols escape from the experiment.
f.
In ca!culations pursuant to e., above, the following assumptions shall be used:
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, Amendment No.17 l
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This specification is intended to prevent damage to reactor explosive materials. components resulting from failure of an experiment involving This specification is intended to meet the purpose of 10 CFR 20 by reducing e.
the likelihood that released airborne radioactivity to the reactor bay or unrestricted area surrounding the OSTR will result in exceeding the total dose limits to an individual as specified in 10 CFR 20.
f.
These assumptions are used along with additional assumptions and with facility and site chara'cteristics as described in the SAR and other pertinent analyses, submitted in accordance with 10 CFR 50.59 requirements. May 16, 1973.
g.
The 1.5-curie limitation on iodine 131-135 assures that in the event of a failure in a fueled experiment involving total release of the iodine, the dose in the reactor bay and in the unrestricted area will be less than that allowed by 10 CFR 20.
h.
Operation of the reactor with the reactor fuel or structure poteritially damaged is prohibited to avoid potential release of fission products.
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- I7-Amendment No.17
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