ML20027B618
| ML20027B618 | |
| Person / Time | |
|---|---|
| Site: | 05000112 |
| Issue date: | 09/10/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20027B614 | List: |
| References | |
| R-053-A-009, R-53-A-9, NUDOCS 8209290057 | |
| Download: ML20027B618 (4) | |
Text
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2 UNITED STATES (M[4 s
NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. c,0555
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ss UNIVERSITY OF OKLAHOMA DOCKET NO.
50-112 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. R-53 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by University of Oklahoma (the licensee), dated July 31, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with t.5c application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) tha15 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
8209290057 820910 PDR ADOCK 05000112 P
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Accordingly, paragraphs 2.B.(3) and 2.C.(2) of Facility Operating License No. R-53 are revised as follows:
(3) Pursuant to the Act and Title 10, CFR, Chapter 1, Part 70, "Special Nuclear Material", to use up to 1500 grams of contained uranium-235 for us: in connection with operation of the reactor; and (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Darrell G. E.isenhut, Director
- Division of Licensing
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I ATTACHMENT TO LICENSE AMENDMENT NO 9 FACILITY LICENSE NO. R-53 DOCKET NO.
50-112 Revise Appendix A Technical ~ Specifications as follows:
Remove Page Insert Page 2
2 Changes on the revised page are identified by marginal lines.
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yJ kWL Mir.'#1ts 1.7 Safety Chann'el Calibration Safety channel calibration shall mean adjustment of channel output such that it responds within an acceptable range and accuracy to independeni.ly known values of the parameter which the channel measures.
Calibration shall encompass the entire channel including actuation, trip devices, and those sensors for which calibration adjustments are provided.
"1.8 Reactor Shutdown
-9 The reactor shall be considered in a shutdown condition Oh
/d when all control and safety rods are fully inserted, the p
i console power is off, and the key removed from the key switch."
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2.0 Reactor Pool
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C 2.1 The minimum level of the pool water shall not be less than 12 inches below the reactor tank top during operation.
2.2 The minimum pool water temperature shall not be less than 15*C.
2.3 The pool water condactivity shall be sampled at least monthly and the conductivity shall not exceed 7.5 micronhos/cm.
2.4 The radioactivity centained in the pool water shall be such that it is less than twice the normal background.
3.0 Practor Core 3.1 The reactor core shall contain not more than twenty (20) fuel elements.
Each element shall be composed of 20 w/o U-235 0xide encapsulated in polyethylene. The exterior of all fuel shall be coated with epoxy resin.
'The tot'i excess reactivity, including the reactivity if '.L _
"3.2 a
C.,#1 d
0(f N,j d votth of all experiments per section 5.1, shall not exceed 0.65% delta k/k at 20*C with all control and 1
safety rods fully withdrawn."
4.0 Control and Instrumentation Systems 4.1 The fi'ne control rod, coarse control rod, and two safaty rods shall be operable and the carriage position of tha control rods shall be displayed at the console whenever any rod is above its lower limit.
"4.2 ' The reactivity worths of the control and safety rods FP i
shall be such that the reactor will be.subcritical when:
(a) both safety rods are fully withdratm and M)I -
Ql both control rods fully inserted, or (b) either of O
,,the saf ety rods or the coarse control rod is fully inserted."
N "4.31 Each of the safety channels in Tpble I shall be operating I whenever any control or safety rod is not in its fully
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channel may be bypassed during rod drop tests.
Each y,
of th'e operating safety channels shall sound an alarm
'K e and cause automatic reactor shutdown if the limiting saf ety system settin3 is reached."
AmendmentNh.9
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