ML20149H063
| ML20149H063 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 11/04/1994 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149H060 | List: |
| References | |
| R-103-A-027, R-103-A-27, NUDOCS 9411090406 | |
| Download: ML20149H063 (6) | |
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- 7> UNITED STATES i? 'i NUCLEAR REGULATORY COMMISSION g ..... ,/ WASHINGTON, D.C. 2055SM1 UNIVERSITY OF MISSOURI-COLUMBIA DOCKET N0. 50-186 AMENDMENT TO AMENDED FACILITY LICENSE Amendment No. 27 License No. R-103
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to Amended Facility License No. R-103 filed by the University of Missouri-Columbia (the licensee), dated March 28, 1994, as supplemented on September 2, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission 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 Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that 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. The issuance of this amendment is in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied; and F. Prior notica of this amendment was not required by 10 CFR 2.105(a)(4) and publication of notice for this amendment is not required by 10 CFR 2.106(a)(2).
9411090406 941104 PDR ADOCK 05000186 P PDR
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 3.B. of Amended Facility License No. R-103 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ >
Seymour H. Weiss, Director Non. Dower Reactors and Decommissioning Project Directorate Division of Project Support Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: November 4, 1994 l
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ENCLOSURE TO LICENSE AMENDMENT NO. 27 AMENDED FACILITY LICENSE N0. R-103 DOCKET N0. 50-186 -
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 areas of change.
Remove Insert 3.3-2 3.3-2 3.3-3 3.3-3 4.4-1 4.4-1 l
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j'em\ TECHNICAL SPECIFICATION l Jt
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UNIVERSITY OF MISSOURI
\ _"y RESEARCH REACTOR FACILITY
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s 3.3
, Nu.mber .
Page 2 of 5 Date November 4,1994
SUBJECT:
Heactor Safet v System (continund)
Pool Coolant Flow 2 1 0 425(4) gpm (Min) for each 50%
capacity heat exchanger leg or 2 2 0 S50(4) gpm (Min) for one 100%
capacity heat exchanger DitTerential Pressure Across 2.52 psi (Min)
Reflector 1 0 0 8.00 psi (Max)
Differential Pressure Across 0.63 psi (Min)
ReGector 0 1 0 2.00 psi (Max)
Differential Pressure Across Core 1 0 0 3200* gpm (Min)
Differential Pressure Across Core 0 1 1<2, 1600* gpm (Min)
Pressurizer High Pressure 1 1 1(2> 95 psia (Nax)
Pressurizer Low Level 1 1 It2) 16 inches below centerline (Min)
Pool Level 0 0 1 23 feet (Min)
Primary Coolant Isolation Valves 507A/B Off Open Either valve Position 1 1 142) Off Open Position Pool Coolant Isolation !
Valve 509 Off Open Valve 509 Off Open Position 1 1 0 Position Power Level Interlock 1 1 1 Scram as a result ofincorrect selection of operating mode !
Facility Evacuation 1 1 1 Scram as a result of actuating facility evacuation system Reactor Isolation 1 1 1 Scram as a result of actuating reactor isolation system i
Amendment No. 27 I
9 TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY s t
- Nun @er 3.3 Page 3 of 5 Date November 4, 1994 SUBJECT. Reactor Safetv System (continued)
Manual Scram 1 1 1 Push 13utton at Control Console (1) Flow orifice or heat exchanger AP (psi)in each operating heat exchanger leg corresponding to the flow value in the table.
(2) Not required below 50 KW operation if natural convection flange and pressure vessel cover are removed or in operation with the reactor suberitical by a margin of at least 0.015 AK.
(3) Trip pressure is that which corresponds to the pressurizer pressure indicated in the table with normal primary coolant flow.
(4) Flow orifice AP (psi) corresponding to the flow value in the table.
(r0 Core AP (psi) corresponding to the core flow value in the table.
Bases
- a. The specifications on high power, primary coolant flow, primary coolant pressure, and reactor inlet temperature provide fbr the safety system settings outlined in specifications 2.2.a. 2.2.b, and 2.2.c. In Mode I and II operation the core differential temperature is approximately 17cF Amendment No. 27
TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI
@_ s RESEARCH REACTOR FACILITY Number t
- 4.4 Page 1 of 3 Dak November 4, 1994 SUIMECT: Reactor Coolant Svstem Applicabili.ty This specification shall apply to the reactor coolant systems.
Obiectiv.e It is the objective of this specification to assure proper coolant for safe operation.
Snecification
- a. The reactor coolant system shall consist of not less than a reactor pressure vessel, two primary system pumps, primary pressurizer, two primary heat exchangers, two pool system pumpa, one 1009F capacity or two 50r/c capacity pool system heat exchanger (s), and one pool system hold-up tank plus all l associated piping and valves. l
- b. The reactor coolant system shall have one secondary coolant system capable of l continuous discharge of heat generated at the operating power of the reactor. !
- c. The pumps and heat exchangers in the primary system shall constitute two parallel systems separately instrumented to permit safe operation at five l 1
megawatts on either system or ten megawatts with both systems operating i simultaneously.
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Amendment No. 27 l