ML20151U069
| ML20151U069 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 04/25/1988 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151T981 | List: |
| References | |
| R-066-A-016, R-66-A-16, NUDOCS 8804290245 | |
| Download: ML20151U069 (6) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555
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1 UNIVERSITY OF VIRGINIA DOCKET NO. 50-62 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 16 License No. R-66
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
l A. The application for amendment filed by the University of Virginia (the licensee), dated July 2, 1987, as supplemented, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations as set forth in l 10 CFR Chapter I; B. The facility will operate in conformity with the ap)11 cation, the provisions of the Act, and the regulatier.t. of t1e Comission; C. There is reasonable assurance: (i) that the activities authorized l by this amendment can be conducted without endangering the health i and safety of the public, and (ii) that such activities will be conducted in compliance with the Com'.:ssion's regulations set forth in 10 CFR Chapter I; 1
D. The issuance of this anendment will not be inimical to the comon i defense and security or to the health and safety of the public; E. The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and F. Publication of notice of this anendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2 106(a)(2).
8804290245 080425 2 DR ADOCK 0500
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license l amendment, and paragraph II.C.(2) of License No. R-66 is i hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 16, are hereby incorporated in the license. ;
The University of Virginia shall operate the facility in accordance j with the Technical Specifications
- 3. This license amendment is effective upon its date of issuance. )
FOR THE NUCLEAR REGULATORY COMMISSION Lester S. Rubenstein, Director Standardization and Non-Power ,
Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: April 25, 1988
ENCLOSURE TO LICENSE AMENDMENT NO. 16 FACILITY OPERATING LICENSE NO. R-66 DOCKET NO. 50-62 I
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Arnendment number and contain a vertical line indicating the area of change.
Remove Pages Insert Pages 12 12 12a 26 26 l
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. l 3.6 Limitation on Experiments !
l Applicability: This specification applies to experiments installed in the l reactor and its experimental facilities. !
Obfective: The objective is to prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure..
Specifications: The reactor shall not be operated unless the following ccnc:itions exist:
(1) The ructivity worths of all experiments shall be in conformance with j specifications in Section 3.1, 1 i
(2) Movable experiments must be worth less than 0.1% delta k/k. l (3) Experiments worth more than 0.1% delta k/k must be inserted or removed with the reactor shut down except as noted in Item (4). i (4) Previously tried experiments with measured worth less than 0.4% delta k/k may be inserted or removed with the reactor 2% or more suberitical.
(5) If any experiment worth more than 0.4% delta k/k is inserted in the reactor, a procedure apprmed by the Reactor Safety Committee shall be ;
followed. '
(6) All materials to be irradiated in the reactor shall be either corrosion resistant or encapsulated within corrosion resistant containers.
(7) Irradiation containers to be used in the reactor in which a static
)' pressure will exist or in which a pressure buildup is predicted shall be designed and tested for a pressure exceeding the maximum expected by a factor of 2.
(8) Explosive material shall not be allowe'd in the reactor unless specifically approved by the Reactor Safety Committee. Experiments reviewed by the Reactor Safety Committee in which the material is potentially explosive, either while contained er if it leaks from the container, shall be designed to prevent dt. mage to the reactor core or te the control rods or instrumentation, and to prevent any changes in reactivity.
(9) Cooling shall be provided to prevent the surface temperature of an experinent to be irradiated from exceeding the boiling point of the reactor pool water.
(10) Experimental apparatus, material, or equipment to be inserted in the reactor, shall not be positioned so as to cause shadowing of the nuclear instrumentation, interference with the control rods, or other perturbations that may interfere with the safe operation of the reactor.
12 Amendment No. 16
(11) The Co-60 rods possessed under the UVAR Operating License shall be used and. stored in the UVAR pool at distances greater than 5 feet from the operating UVAR reactor. Gamma irradiation facilities utilizing the Co-60 rods shall be designed to prevent physical damage to the Co-60 rods. UVAR pool water samples shall be subjected to gamma spectroscopy for the presence of Co-60 on a monthly frequency, (interval not to exceed six weeks) te assure that substantial leakage of Co-60 from the rods to reactor pool water does not occur.
Bases: (1-10) The lir.itations on experiments specified in Items 1-10 are based on the irradiation program authorized by Amendment No. 3 to License No.
R-66 dated August 13, 1962. The reactivity of less than 0.1% that can be inserted or removed with the reactor in operation is to accommodate experiments in the hydraulic rabbit.
(11) The Co-60 rods are to be kept a safe distance away from the UVAR reactor when it is operated, to avoid neutron activation and possible failure of the l rod cladding, which may result in leakage of Co-60 to the reactor pool water. The Co-60 rods and the gamma irradiation facilities in which they are.
used will not be used in conjunction with the UVAR.
The monthly reactor pool water sanpling frequency, adopted to monitor possible Co-60 leakage from the rods, is the same as that used in the U.S.
AEC Safety Evaluat'on that was performed for these rods by the Division of Reactor Licensing on August 4, 1971. This is a reasonable frequency, for the most likely damage to the rods would be caused by cladding corrosion leading to pin holes. Co-60 leakage under these circumstances would proceed very ,
slowly, into a large pool of water. Therefore, a monthly water sampling and j analysis frequency should be adequate to indicate contamination levels before i they become significant.
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12a Amendment No. 16
l (2) The occurrence shall be reported'to the Reactor Facility Director and the Chairman of the Reactur Safety Comittee, or their designee, as soon as possible, but not later than the next work day. Reports shall be made to the Comission in accordance with Section 6.7 of these specifications, l
(3) A written safety limit violation report shall be made that shall include ;
an analysis of the causes of the violation and extent of resulting' damage to facility components, systems, or structures; corrective actions taken; and recomendations for measures to preclude reoccurrence. l This report shall be submitted to the Reactor Safety Committee for )
review. ]
6.4.2. Action To Be Taken in the Event of a Reportable Occurrence j A rercrtable occurrence is any of the following conditions:
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(1) any safety system setting less conservative than specified in Section 2.2 of these specifications (2) operating in violation of an LCO established in these specifications, unless prompt remedial action is taken (3) safety system component malfunctions or other component or system malfunctions during reactor operation that could, or threaten to, render the safety system incapadle of performing its intended safety function, unless immediate shutdown of the reactor is initiated (4) an uncontrolled or unanticipated increase in reactivity in excess of 0.005 delta k/k (5) an observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy could have caused the existence or development of an unsafe condition in connection with the operation of the reactor (6) abnormal and signifiernt degradation in reactor fuel, and/or cladding, coolant boundary, or containment boundary (excluding minor leaks) where applicable that could result in exceeding prescribed radiation-exposure !
limits of personnel and/or environment (7) majordamagetotheCo-60 rods 5esultinginCo-60concentrationsinreactor pool water in excess of 1 x 10- uCi/ml.
In the event of a reportable occurrence, the following action shall be taken:
(1) The Director of the Reactor Facility shall be notified as soon as possible and corrective action shall be taken before resuming the operation involved.
(2) A written report of the occurrence shall be made which shall include an-analysis of the cause of the occurrence, the corrective action taken, and recommendations for measures to preclude or reduce the probability of reoccurrence. This report shall be submitted to the Director and the Reactor Safety Comittee for review.
(3) A report shall be submitted to the Nuclear Regulatory Comission in accordance with Section 6.7 of these specifications.
26 Amendment No. 16
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