ML20249A594
| ML20249A594 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 06/15/1998 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20249A593 | List: |
| References | |
| R-66-A-23, NUDOCS 9806170117 | |
| Download: ML20249A594 (8) | |
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'j NUCLEAR REGULATORY COMMISSION ] WASHINGTON, D.C. 20665-0001 / l UNIVERSITY OF VIRGINIA -{ 4 DOCKET NO. 50-62 AMENDMENT TO AMENDED FACILITY OPERAIlNG LICENSE l Amendment No. 23 Liceny.e No. R-66 1 4 1. The U.S. Nuclear Regulatory Commission (the Commissions nas found that A. The application for an amendment to Amended Facility Operating Ucense No R-66 filed by the University of Virginia (the licensee) on February 26,1998, as 'I supplemented on April 6,1998, conforms to the standards and requirements.of j the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the 4 Commission as stated in Chapter I of Title 10 of the Code o/Federa/ 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; C. There is reasonable assurance that (i) the activities ' uthorized by this amendment - a cm be conducted without endrsngering 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. 9806170117 980615 _PDR ADOCK 05000062 P PDR
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( e; i 1 L l~ hf .2. Accordingly, the license is amended by changas to *he Techrical Specifications as l' 1 indicated in the erselosoa to this license amendment, and paragraph II.C.(2) of Amended Facility Operatint) Uctnse No. R-66 is hereby amend.ed to read es follows: (2), Technica; Sogdliggitons t; 'The Technical Specifications contained in Appendix A. La revised through l ' Annandment No. 23, are hareby incorporated in the license. The licensee shall onerate the facility in accordance with the TechnictJ Specifications. q-1
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~ y-3. This license amondment is effective es of July 1,1998. FOR THE NUCLEAR REGULATORY COMMISSION f 'A , 1/ ' Geymo'ur H.- Weiss, Director { Non Power Reactors er.d Decommissioning Project Directorate Division of Reactor P.*ogram fAanagement i Office of Nuclear Reactor Regulation
Enclosure:
Appendix A, Technical Specifications Changes ' Date'of issuance: June 15, 1998-. 1 s.
0 EtrLQSURE TO LICENSE AMENDMENT NQR AMffipED FACILITY OPERATING LICt2- {SE}[Q,H-51 4 ,QOCKET NO. SQ-12 Replace th's following pages of Appendix A, " Technical Specifications," with the enclosed L ' pages. The revised pages are identified by amendrnent nusabar and contain vertical lines indicating the areas of r.hange. 80m020. IMfAt1 42 42 44 44 46 46 56 56 57 57 l 1 l! k + 1 l l l I L'
16. l UVAR Tech. Specs. l 3 6.0. ADMINISTRATIVE COfGROLS i 6.1. Organization Aeolicability: The specifications listed below in TS 6.1.1 through TS 6.1.4. apply to the organizational structure of the University of Virginia as it relates to the operation of the Reactor Facility. Obiectivg; The objective is to describe the chain of command having responsibility for the safe operation of the Reactor Facility. At the various administration levels, the functions, assignments, responsibilities and associated professional background, training and requalification requirements are listed, as applicable. Specifications: 6.1.1. Structure The Reactor Facility shall be an integral part of the University of Virginia. The l organizational structure of U.VA. relating to the Reactor Facility is shown in - Figure 6.1. The Vice Provost for Research will have overall responsibility for l management of the Facility (Level 1). 6.1.2. Responsibility The Reactor Facility Director shall be responsible for the overall facility operation (Level 2). During periods when the Reactor Facility Director is absent, his responsibilities are delegated to the Reactor Supervisor (Level 3). The Reactor Facility Director shall have at least a bachelor's degree in science or engineering and have a minimum of 5 years of experience in the nuclear field. A graduate degree may fulfill 4 years of experience on a one-for-one time basis. t The Reactor Supervisor (s) shall be responsible for the day-to-day operation of the UVAR and for ensuring that all operations are conducted in a safe manner and within the limits prescribed by the facility license and the provisions of the Reactor Safety Committee. During periods when the Reactor Supervisor (s)is l (are) absent, his responsibilities are delegated to a person holding a Senior Reactor Operator license (Level 4). A Reactor Supervisor shall have the equivalent of a bachelor's degree in science or engineering and have_ at least 2 years of experience in Reactor Operations at this facility, or an equivalent facility, or at least 6 years of experience in Reactor Operations. Equivalent education or experience may be substituted for a degree. Within niae months after being assigned to the position, the Reactor Supervisor shall obtain and' maintain an NRC Senior Operator license. l - Amendment a. 23
O UVAR Tech. Specs. 6.2. Reactor Safety Committee Applicability,: The specifications 6.2.1 through 6.2.3 apply to the expert group who will provide specific reviews and audits of Reactor Facility operations. Objective: To describe the makeup, responsibilities, and authority of the Reactor Safety Committee. Specifications: 6.2.1. Composition and Qualification There shall be a Reactor Safety Committee (R,SC) to review and audit reactor operations and ensure that the Reactor Facility is operated in a safe manner within the terms of the reactor license. Collectively, the committee members shall represent a broad spectrum of expertise in the research-reactor field. The members may be drawn from within or outside the operating organization. The R,SC reviews and audits are designed to uncover deficiencies that affect reactor safety. The Reactor Safety Committee is part of the Radiation Safety Committee and shall report to the Chair of the Radiation Safety Committee, who is the coordinator for all licenses involving the use of radioactive materials and radiation producing equipment. The R,SC shall advise the The Vice Provost for Research and the Director of the Reactor Facility on safety concerns in the operation of the facility. The Committee shall be composed of at least five members, and shall include the Radiation Safety Officer of the University and the Director of the Reactor Facility. The Reactor Director shell be the sole reactor staff representative on the Committee. The membership of the Committee shall be such as to maintain a d: gree of technical proficiency in areas relating to reactor operation and reactor safety. 6.2.2. Charter and Rules (1) A quorum of the Committee shall consist of not less than the majority of the full committee. The Chair can designate another member from the Committee to preside in his absence. (2) The Committee shall meet at least semiannually and shall be on call by the Chair. Minutes of all meetings shall be disseminated as designated by the Chair. (3) The Committee shall have a written charter defm' ing such matters as the authority of the Committee, the subjects within its purview, and other administrative provisions as are required for effectise functioning of the Committee. (rest of page intentionally left blank) Amendment No. 23 - 44 _.
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UVAR Tech. Specs. 6.7. Reportinz Requirements _A_policability: The specifications 6.7.1 and 6.7.2 listed below apply to routine and special reports made by the University of Virginia Reactor Facility to the U.S. Nuclear Regulatory Commission. Obiective: The objective is to provide the licensing agency (NRC) with relevant information concerning normal and abnormal reactor operations which are necessary for the fulfillment ofits mission to protect the public health and safety. A secondary objective is to comply with reporting requirements as given in the federal regulations. Soccificatiom: In addition to federal regulatory requirements (for example, follow 10 CFR 20,.30.50,40.60, and 70.50, as applicable), reports should be made to the U.S. Nuclear Regulatorv Commission as follows: 6.7.1. Repo_rting oflagigents (1) Immediate notification should be made by telephone, to the U.S. Nuclear Regulatory Commission Headquarters Operations Center of: (a) Personnel total effective dose equivalent of 25 rem or more. (b) ' Die release of radioactive material, inside or outside of a restricted area, that results, or could result, over a 24 hour period,in personnel intake of 5 times the annual limit on intake specified in 10 CFR 20. (2) A special report should be made by telephone as soon as possible, but no later than the next working day, to the U.S. Nuclear Regulatory Commission Headquarters Operations Center of: (a) Personnel exposures or releases of radioactive material greater than the limits in 10 CFR 20. (b) Reportable occurrences es defined in Section 6.6.2 of these specifications. (c) Violation of a safety limit. (3) A special written report should be sent by mail within 14 days to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 (a) Accidental off-site release of radioactivity above 10 CFR 20 limits, whether or not the release resulted in property damage, personal injury, or exposure. (b) Reportable occurrence as defined in Section 6.6.2 of these specifications. (c) Violation of a safety limit. (4) A special written report should be sent by mail within 30 days to the U.S. Nuclear - 56 Amendment no. 23
O UVAR Tech. Specs. Regulatory Commission, Document Control Desk, Washington, D.C. 20555, of: (a) Substantial variance from performance specifications contained in these specifications or in the UVAR SAR. (b) Significant change in the transient or accident analyses as described in the UVAR SAR. (c) Changes in personnel serving as Vice Provost for Research, Reactor Facility Director, or Reactor Supervisor. i (5) A written report should be sent within nine months after initial criticality of the i reactor or within 90 days of completion of the startup test programs, whichever is earlier, to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, upon receipt of a new facility license, an amendment to the license authorizing an increase in power level or the installation of a new I core with fuel elements of a design different design than previously used. The report will include the measured values of the operating conditions or characteristics of the reactor under the new conditions, including: J l (a) Total control rod reactivity worth. (b) Reactivity worth of the single control rod of highest reactivity worth. (c) Minimum shutdown margin both at ambient and operating temperatures. 6.7.2. Routine Reports i I A routine report will be made by March 31 of each year to the U.S. Nuclear l Regulatory Commission, Document Control Desk, Washington, D.C. 20555, providing the following information: (1) A narrative summary of operating experience (including experiments ) pet.'ormed), and of changes in reactor design, performance characteristics, and operating procedures related to the reactor safety occurring during the reporting period. i (2) A tabulation showing the energy generated by the reactor (in megawatt hours) i and the number of hours the reactor was critica' during the year. (3) A report of the results of the safety-related maintenance and inspections. The reasons for corrective maintenance of safety-related items will be included. l 1 Amendment to. 23 -}}