ML20035B610
| ML20035B610 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 03/25/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035B607 | List: |
| References | |
| R-056-A-018, R-56-A-18, NUDOCS 9304020222 | |
| Download: ML20035B610 (5) | |
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- UNITED STATES
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I UNIVERSITY OF FLORIDA
-l DOCKET NO. 50-83 l
AMENDMENT TO FACILITY OPERATING LICENSE ~
i Amendment No. 18 License No'.R-56 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
d A.
The application for amendment to Facility Operating License'No.
I R-56, filed'by the University of Florida (the licensee), dated September 28, 1992, complies with the standards and requirements of-_
i the Atomic Energy Act of 1954, as amended (the Act), and the j
Commission's regulations as set forth in 10 CFR Chapter I:
B.
The facility will operate in conformity with the application, the-provisions of the Act, and the rules and regulations of the t
Commission 1
C.
There is reasonable assurance: (1) that the activities authorized by l
this amendment can be conducted without endangering the health and
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safety of the public, and (ii) that such activities will be i
conducted in compliance with the Commission's regulations i
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; l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51
.j of the Commission's regulations' and all applicable requirements have i
been satisfied; and F.
Prior notice of this amendment was not required by 10 r.FR-2.105(a)(4) and publication of notice for.this amendment is not required by 10 CFR 2.106(a)(2).
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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 2.C.(2) of Facility Operating License No. R-56 is hereby amended to read as follows:
i (2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No.18, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the l
Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,W4 Seymour H. Weiss, Director Non-Power Reactors and Decommissioning i
Project Directorate i
Division of Operating Reactor Support Office of Nuclear Reactor Regulation l
Enclosure:
Appendix A Technical i
Specifications Changes Date of Issuance: March 25, 1993 l
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ENCLOSURE TO LICENSE AMENDMENT NO. 18 FACILITY OPERATING LICENSE NO. R-56 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 vertical lines indicating the area of changes.
Remove Paaes Insert Paces 36 36 37 37 9
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(a) applicable circumstances leading to the violation including, when known,
. the cause and contributing factors (b) effect of the violation upon reactor facility components, systems, or structures and cn the health and safety of personnel and the public (c) corrective action to be taken to prevent recurrence.
The report shall be reviewed by the RSRS and any fo!!owup report shall be submitted to the Commission when authorization is sought to resume operation of the reactor.
6.5.2 Action To Be Taken in the Event of an Occurrence of the Type Identified in Section 6.6.2.
(1)
Reactor conditions shall be returned to normal or the reactor shall be shut down. If it is necessary to shut down the reactor to correct the occurrence, operations shall not be i
resumed unless authorized by Level 2 or designated alternates.
(2)
Occurrence shall be reported to Level 2 or designated alternates and to the Commission as required.
(3)
Occurrence shall be reviewed by the review group at their next scheduled meeting.
6.6 Recorts In addition to the requirements of the applicable regulations, reports shall be made to the Commission as follows:
6.6.1 Operating Reports Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to the Commission with 4 months following the end of each prescribed year. The prescribed year ends August 31 for the UFTR. Each annual operating report shall include the following information (1) a narrative summary of reactor operating experience including the energy produced by the reactor and the hours the reactor was critical (2) the unscheduled shutdowns including, where applicable, corrective action taken to preclude recurrence (3) tabulation of major preventive and corrective maintenance operations having safety significance (4) tabulation of major changes in the reactor facility and procedures, and tabulation of new tests of experiments, that are significantly different from those performed previously and are not described in the Safety Analysis Report, including conclusions that no unreviewed safety questions were involved i
A=endment 18 36
(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 such release or discharge (The summary shallinclude to the extent practicable 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 allowed, a statement to this effect is sufficient.)
(6) a summarized result of environmental surveys performed outside the facility (7) a summary of exposure received by facility personnel and visitors where such exposures are greater than 25% of that allowed The annual report sha!! be submitted with a cover letter to Attention: Document Control Desk, U.S. NRC, Washington DC 20555 and to the U.S. NRC, Region !!,
101 Marietta Street, N.W., Suite 2900, Atlanta, GA 30323 6.6.2 Special Reports There shall be a report not later than the fo!!owing working day by telephone and confirmed in writing by telegraph or similar conveyance to the Commission, to be fo!! owed by a written report
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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 fo!!owing (a) operation witn actual 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 additien to those required by the Technical Specifications, the failure of the extra components or systems is not considered reportable provided that the minimum number of components or systems specified or required perform their intended reactor safety function).
l (d) an unanticipated or uncontrolled change in reactivity greater thanone do!!ar(Reactor I
trips resulting from a known cause are excluded).
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Amend =ent 18 37
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