ML20203C435
| ML20203C435 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 12/03/1997 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203C429 | List: |
| References | |
| R-056-A-022, R-56-A-22, NUDOCS 9712150307 | |
| Download: ML20203C435 (6) | |
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NUCLEAR REGULATORY COMMISSION t
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UNIVERSITY OF FLORIDA DOCKET NO. 50 83 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. R 50
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to Facility Operating License No. R 56, filed by the University of Florida (the licensee), dated August 21,1997 as supplemented on October 6,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter 1:
B.
The f acility will operate in conformity with the application, '.he 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 Comtnission's regulations; 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 10 CFR Part 51 of the Commission's' regulations 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 2.100.
- 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 Facility Operating License No. R 56 is hereby amended to read as follows; 9712150307 971203 PDR ADOCK 05000003 P
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 22, are hereby incorporated in the license. The licensee shall operate the facility in accord 3nce with the Technical Specifications.
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- 3. This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
f Soy our H. Weiss, Director Nori 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:
December 3, 1997 l
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ENCLOSURE TO LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. R 56 j
DOCKET NO. 50 83 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain verticallines Indicating the area of changes, Remove Pages insert Pages 30 30
' 32 32
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Level 1 Director, Environmental Health and Safety UFPresMent n
Dean, CollLie of Engineering Chaltman, Radiation chalemen, Nuclear & Radiological Control Committee Engineering Depenment a
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eview SubcommIHee Facility Director
, r Level 3 Radiati::n Contro:
Officer Reactor Manager e
, r ir Level 4 Radiation Safety Operating Stati Specialists Class A and B Operator Figure 6.1 UFTR Organizational Chart Amendment 22-30
4 (1)
Composition and Qualifications The RSRS shall be composed of a minimum of five members, including the Reactor Manager and Radiation Control Officer (both ex officio voting members), the Chairman of the Nuclear and Radiological Engir.eering Department and two other rnembers having expertise in reactor technology and/or radiological safety.
(2)
Charter and Rules The review and audit functions shall be conducted in accordance with the following established charter:
Designatinn The name of the Subcommittee is Reactor Safety Review Subcommittee (RSRS).
Accountability - The RSRS is a Subcommittee of and reports to the University Radletion Control Committee (URCC). The URCC provides radiological safety recommendations to the Director of Environmental Health and Safety.
Scope - The RSRS shall be responsible for the review of safety related issues pertaining to the University of Florida Training Reactor (UFTR).
Eurpose The purpose of the RSRS is to ensure the safe operation of the UFTR through the discharge of the Subcommittee review and audit function.
Membership (a) The RSRS shall consist of at least five members. Membership will include the Chairman of the Nuclear and Radiological Engineering Department, University Radiation Control Officer, Reactor Manager and two technical personnel familiar with the operation of reactors and with the design of the UFTR and radiological saftty, at least one of whom is from outside the Department of Nuclear and Radio'ogical Engineering. The two technical personnel will be recommended to the Chairman of the URCC by the Chairman of the Department of Nuclear and Radiological Engineering.
Any member may designate a duly qualified representative from a standing URCC approved list to act in his absence..
(b)
An Executive RSRS Committee will consist of the Reactor Manager, University Radiation Control Officer and Chairman of the RSRS.
(c) The Chairman of the RSRS will be appointed by the Chairman of the URCC. The Chairman of the RSRS is an ex officio voting member of the URCC and will serve as liaison between the RSRS and the URCC.
(d)
Members appointed to the RSRS shall be reviewed, and as appropriate, new appointments made by October 1 of each calendar year.
Amendment 22 32
d (5)
A summary of the nature and amount of radioactive effluents released or discharged to the' environs beyond the effective control of the facility operators as determined at or before the point of ruch release or discharge. (The summary shall include to the extent practiceble an estimate of individual radionuclides present in the effluent.
If the estimated average release after dilution or diffusion is less than 25% of the concentration allowad, a statement to this effect is sufficient.)
(C)
A summarized result of environmental surveys performed outside the facility.
'9 A summary of exposure rece1ved by facility personnel and visitors where such exposures are greater than 2G cf that allowed.
The annual report shall be submitted with a cover letter to:
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20b55 6.6.2 Special Reports There shall be a report not later than the following working day by telephone and confirmed in writing by telegraph or similar conveyance to the Commission, to be followed by a written report that describes the circumstances of the event within 14 days of any of the following:
(1)
Release of radioactivity from the site above allowed limits.
(2)
Violation of safety limits (see Section 6.5.1).
(3)
Any of the following:
(a)
Operation with actuai safety system settings for required systems less conservative than the limiting safety system settings specified in the Technical Specifications.
(b) Operation in violation of limiting conditions for operation established in the Technical Specifications unless prompt remedial action is taken.
(c)
A reactor safety system component malfunction that renders the reactor safety system incapable of performing its intended safety function, unless the malfunction or condition is discovered during maintenance test or periods of reactor shutdowns.
(Note: Where components or systems are provided in addition to those required by the Technical Specifications, the failure of the extra components or systems is not considered reportable plovided that the minimum number of components or systems specified or required perform their intended reactor safety function).
(d) An unanticipated or uncontrolled change in reactivity greater tha'n one dollar (reactor trips resulting from a known cause are excluded).
Amendment 22 37