ML20236K480
| ML20236K480 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 07/07/1998 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236K478 | List: |
| References | |
| R-123-A-008, R-123-A-8, NUDOCS 9807090340 | |
| Download: ML20236K480 (9) | |
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< S NUCLEAR REGULATORY COMMISSION f WAsHINoToN. D.C. 20565-0001
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UNIVERSITY OF VIRGINIA QOCKET NO. 50-396 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. R-123 l t
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for an amendment to Facility Operating License No. R-123 filed by the University of Virginia (the licensee), on April 6,1998, as supplemented on ,
June 18,1998, 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 Federal 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 authorized by this amendrnent 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.
I 9807090340 990707 PDR ADOCK 05000396 p PDR
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as Jndicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Facility
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Operating License No. R-123 is hereby amended to read as follows:
(2). Technical Specifications
- The Technical Specifications contained in Appendix A, as revised through
' Amendment No. 8, are hereby incorporated in the license. The licensee shall possess the facility in accordance with the Technical Specifications.
- 3. This licnnse amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/eymour S 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: July 7, 1998 l
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ENCLOSURE TO LICENSE AMENDMENT NO. 8 ,
FACILITY OPERATING LICENSE NO. R-123 DOCKET NO. 50-396 Replace the following pages of Appendix A, " Technical Specifications," with the enclosed '
pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.
1 Remove Insert 21 21 23 23 28 28 29 29 30 30 32 32 l
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i ea 21 Obiective The objective is to assure that fuel which is being stored will not -
become supercritical and will not reach unsafe temperatures.
l Specification (1)
All reactor fuel elements not in the reactor core shall be stored in a geometric array where k ett is less than 0.9 for all conditions of moderation. l (2)
Irradiated fuel elements.and fueled devices shall be stored in an array which will permit sufficient natural ^ convection cooling by water or air such that the fuel element or fueled device surface temperature 1 l
will not exceed the boiling point of water.
Bases Within these specifications, the fuel can be stored safely under all (
conditions. The UVAR storage facility was constructed to meet these specifications and will be used to store the CAVALIER elements. i 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization 6.1.1 Structure The reactor facility shall be an integral part of the University of Virginia. The organizational structure of UVA relating to the reactor facility is shown in Figure 6.1. The Vice Provost for Research will have overall responsibility for management of the facility (Level 1).
Amerdment 8
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< present at the controls is under the direct supervision of Senior Reactor Operator or Reactor Operator in the control room. (2) A
! licensed Senior Reactor Operator shall be on call, but not necessarily at the facility.
(3)
At least one other person, not necessarily licensed to operate the reactor, shall be present at the facility.
(4) Rearrangements of the core or other nonroutine actions shall be supervised by a licensed Senior Reactor Operator.
(5) A health physicist who is organizationally independent of the Reactor Facility Operations groups, as shown in Figure 6.1, shall be responsible for radiological safety at the facility.
6.2 Review and Audit There shall be a Reactor Safety Committee that shall review and audit reactor operations to ensure that the facility is operated in a manner consistent with public safety and within the terms of the facility license. The Reactor Safety Committee shall report to the Chair of the Radiation Safety Committee and advise the Vice Provost for Research, and the Reactor Facility Director on those areas of responsibility specified below.
6.2.1 Composition and Qualification The Committee shall be composed of at least five members, one of whom shall be the Radiation Safety Officer of the University. No more than two members will be from the organization responsible for Reactor Operations. The membership of the Committee shall be such as to maintain a degree of technical proficiency in areas relating to reactor operation and reactor safety.
Amendment 8
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- Ei 28 6.5.1 Records To Be Retained for a Period of at Least Five Years l
(1) normal plant operation (2) principal maintenance activities I t3) experiments performed with the reactor f
(4) reportable occurrences (5) equipment and component surveillance activity i (6) facility radiation and contamination surveys (7) transfer of radioactive material l
(8) changes to operating procedures l
6.5.2 l Records To Be Retained for the Life of the Facility i l
(1) gaseous and liquid radioactive effluents released to the environs (2) offsite environmental monitoring surveys l
(3) fuel inventories and transfers l (4) radiation exposures for all personnel (5) changes to reactor systems, components, or equipment that may affect reactor safety (6) updated and corrected drawings of the facility I
-(7) minutes of Reactor Safety Committee meetings
- 6. 6 Reportino Requirements' In addition to the requirements of applicable regulations (such as 10 CFR 20,.30.50, 40.60, and 70.50, as applicable), reports should be made i' to the U.S. Nuclear Regulatory Commission as follows:
6.6.1 Special Reports (1) A report should be made by telephone as soon as possible, but no i
-later than the next working day, to the U.S. NRC Operations Center, Amendment 8
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29 (a) any accidental offsite release of radioactivity above l
permissible limits, whether or not the release resulted in property damage, personal injury, or exposure (b) any reportable occurrences as defined in Section 6.4.2 of these specifications (c) any violation of a safety limit (2) A report shall be sent by mail within 14 days to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk,. Washington, DC 20555:
(a) any accidental offsite release of radioactivity above permissible limits, whether or not the release resulted in property damage, personal injury, or exposure (b) any reportable occurrence as defined in Section 6.4.2 of these specifications (c) any violation of a safety limit (3) A report shall be sent by mail within 30 days to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555:
(a) any substantial variance from performance specifications contained in these specificatic- or in the SAR (b) any significant change in the transient or accident analyses as described in the SAR Amendment 8
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30 (c) changes in personnel serving as Vice Provost for Research, Reactor Facility Director, or Reactor Supervisor i
! (4) A report within nine months after initial criticality of the reactor or within 90 days of completion of the startup test programs, whichever is earlier, to US NRC, ATTN: 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 core of a 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 (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.
6.6.2 Routine Reports A routine report will be made by march 31 of each year to the US NRC, ATTN: Document Control Desk, Washington, D.C. 20555 providing the following information:
(1) A narrative summary of operating experience (including experiments performed) and of changes in facility design, performance Amendment 8
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