ML20056D929
| ML20056D929 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Rolla |
| Issue date: | 07/30/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056D927 | List: |
| References | |
| R-079-A-012, R-79-A-12, NUDOCS 9308190023 | |
| Download: ML20056D929 (4) | |
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UNITED STATES n
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NUCLEAR REGULATORY COMMISSION i
WASHINGTON, D.C. 20656 s
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i UNIVERSITY OF MISSOURI. ROLLA-DOCKET NO.-50-123 AMEN 0 MENT TO FACILITY OPERATING LICENSE i
1 Amendment No. 12 License No. R-79
'I.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
I A.
The application for amendment filed by the: University of Missouri, Rolla, (the licensee), dated June 4,1993, complies with.the standards and requirements of the Atomic Energy Act of 1954, as-amended (the Act), and the Commission's rules and' regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the-j provisions of the Act, and the rules and regulations of the Commission;-
j C.
There-is reasonable assurance:
(i) 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 Commission's regulations;-
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D.
ihe 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-i the Commission's regulations and all applicable requirements have been
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satisfied; and F.
Prior notice of this amendment was not required by 10 CFR 2.105(a)(4)
C and publication of notice for this amendment is not required by 1
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2.
Accordingly, the license is amended by change of the Technical 1
Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.2 of Facility Operating License No.-R-79'is hereby amended to read as follows:
2.C.2 Technical Specifications i
The. Technical Specifications contained in Appendix.A, as' revised
>j through Amendment No. 12 are hereby incorporated in this 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.
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.t FOR THE NUCLEAR REGULATORY COMMISSION 1
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s Seymour H. Weiss, Director Non-Power Reactors ~and Decommissioning Project Directorate 1
Division of Operating Reactor Support Office ~of Nuclear Reactor Regulation -
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Enclosure:
-Appendix A Technical
'l Specifications Change
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Date of Issuance-
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F.-
's ENCLOSURE TO LICENSE AMENDMENT NO. 12 FACILITY OPERATING LICENSE NO. R-79 l
DOCKET NO. 50-123 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pace Insert Pace 28 28 f
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28 (3)
Tho regulating rod worth shall bo coasurod chonover tho rod Is' Installed In'a new core configuration.
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(4)
The shutdown margin shall be determine'd after the excess reactivity of the core and the total worth of each control
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rod have been experimentally determined for a new core configuration.
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(5)
The shim / safety rods shall be visually Inspected annually j
l for pitting and cracking and whenever rod drop times exceed f
the limiting conditions for-operation (section 3.2.3 of 4
these specifications).
Beses:
The reactivity worth of the shim / safety rods is measured i
to assure that the required shutdown margin is available and to-i provide means for determining the reactivity worth of l
experiments inserted in the core.
The visual inspection of the shim / safety rods and measurement of their drop times are made to determine whether they are capable of performing properly.
The determination of the regulating rod worth is to make certain Its value does not exceed the delayed neutron fraction.
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i 4.2.2 Safety Channels i
AeoIIceb111tv:
This specification applies to the surveillance requirements for the reactor safety system channels for the reactor.
Objective:
To ensure that the reactor safety system channels are operable as required by Specification 3.2.2.
-Sneeffications:
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(1)
A channel. test of each of the reactor safety system channels shall be performed before each day's operation or.
before each operation expected to extend more than one day, except for the bridge motion monitor.which shall be done This. visual inspection shall be conducted before October 17, 1994, or within four. months.after an adequate number of High Enriched. Uranium fuel elements are removed from the facility so that the current low Enriched Uranium fuel can be offloaded from the core in accordance with-
- facility procedures to allow the inspection.
/Wendment No.l?
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