ML20128P862
| ML20128P862 | |
| Person / Time | |
|---|---|
| Site: | University of Illinois |
| Issue date: | 02/16/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128P857 | List: |
| References | |
| R-115-A-006, R-115-A-6, NUDOCS 9302250144 | |
| Download: ML20128P862 (5) | |
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[ o f n UNITED STATES P NUCLEAR REGULATORY COMMISSION
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WASHING T ON, D. C. 20%5 NE )l ....
l THE UNIVERSITY OF llLIN015 QQCKET NO. 59-]11 1
6MENDMENT TO FACILITY LICENSE Amendment No. 6 License No. R-ll5
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to facility License No. R-ll5 filed by the University of Illinois (the licensee), dated June 9, 1992, as-supplemented on October 8,1992, December 1,1992, January 5,1993, l and January 11, 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 provisions of the Act, and the rules and regulations of the Commission; 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 i in compliance with the Commission's regulations; 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 Commission's satisfied; and regulations and all applicable requirements have been F.
Prior notice 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(4)(2).
9302250144 930216 PDR ADOCK'05000151 P- PDR u
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- 2. Accordingly, the license is amended by changes to:the Technical- Specifi-cations as indicated in the enclosure to this license amendment, and h paragraph 2.B. of Facility License No. R-115 is hereby amended to read as .n l follows:
B. Iqnhnicill_Soecifieatjjan The Technical Specifications contained in Appendix A, as revised through Amendment No. 6, are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license an:endment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION !
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u 4 Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support ,
Office of Nuclear Reactor Regulation.
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closure:
.ppendix A Technical Specifications Changes Date of Issuance: February 16, 1993 w
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.. LRCLqsun 10 LLqmig13EEDMENT NO. 2f.
FACILITY t.lCENSE NO. R-Lll ,
. DOCKET NO. 50,15] l Replace the following oages of the Appendix A Technical' Specifications-with the ericlosed pages. The revised pages are identified by Amendment number.and contain vertical lines indicating the areas of change.
Pemove Paues -Insert Pace).-
14 14 15 15 v
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3.5 Rggstor Saf_gtv Systqm Anplicability This specification applies to the reactor safety system channels.
QDjective The objective is to require t;.9 minimum number of reactor safety system channels that must be operable in order to assure that the fuel temperature safety limit is not exceeded.
Specification The reactor shall not be operated unless the safety system channels described in the following table are operable.
Minimum Operating Hoce Number in which H asurina Channel J Qperable Euns.tiqa Reauired Fuel Element Temperature 2* Scram All Modes Reactor Power Level i Scram Steady-State Mode and Square-Wave Mode Reactor Power Lovel 1 Prevent transient All Hodes rod withdrawal when power is
$250 kw Peak Reactor Power 1 Scram Pulse Hode Reactor Tank Water Level 2 Scram All Modes (When water level less than 14 feet above the and top grid plate) .
Initiate core Steady-state Spray Above 1 MW Hanual Button 1 Scram All Modes Watchdog (DAC to CSC) 1 Scram All Modes
- While operating in a steady-state mode, the bypass of one (1) of not less than two (2) temperature scram circuits for a ptriod of up to 30 minutes for a crannel check is permissible.
Amendment No. 6
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' l Minimum Operating Mode:
Numbe r- - -in.which Heasurina Channel Qperable- Functiont (B.eouired Startup Count Rate 1 PreventEcontrol
-Rod:withdrawaii Reactor Startup=
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when. neutron count rateLis less than
-1 per second 3
Standard Control Rod 1 Prevent withdrawal ,of_a Steady-state-Position transientfrod whan the' - Mode
- standard control-rods are.
not fully _-inserted. -(This:
does not apply to-the-adjustable' transient rod if the movable cylinder:is fu11y1 -
inserted'when the air pressure- >
1s applied.) .
AA19.A The interlocks which prevent the withdrawal of:the transientirods:in the-steady; state mode or -if the power level is. greater than 250 kw preventcinadvertent? -
pulses which might cause the fuel temperature;to exceed theisafety::-11mit'.1 Thes interlock to prevent startup of the' reactor with-less than one neutron per -
second inuicated on the startup. channel assures that sufficient = neutrons arei available to assure' proper operation ~of the:startup channel. .
2 The fuel temperature scrams provide the protection to assure that' ifta condition?
- results in which-the limiting safety system setting is: exceeded,Lan immediatel shutdown will occur to keep the, fuel temperature;belowLthe safety 711mit. -_ 'The - ..
power level scrams'are provided>1n all.modesnof operation as:added protection 't against abnormally high fuel temperatures such that the: reactor wil1~ scram before a safety limit.is exceeded as discussed:in?the?SafetyfAnalysis~Reporti.
The manual' scram allows the operator to shutdown ~ the' system lif an unsafe or > ,
abnormal condition occurs.
The specifications on the reactor tank water.leve15are= included as safetyt measures in the' event of a serious loss of: primary _ system _ water.J The tank water; 1evel criterion assures:that reactor. operations ~are' terminated when:a.majoreleakt
- occurs in the' primary' system. The spray system assures removal of the: decay:
heat.from the fuel elements if-the. water level in the tank-drops below:the1 top grid plate. The analysis in'Section VI of the SAR shows'that no fueidamagei
- would occur under these conditions.
I the watchdog scram ensures that adequate communications between the Data Acquisition Computer (DAC) and the Control System Computer (CSC)' unitsh '
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Amendment No. 6) w t4 ~
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