ML20202F523
| ML20202F523 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 07/07/1986 |
| From: | Crawford K UTAH, UNIV. OF, SALT LAKE CITY, UT |
| To: | Rozier Carter Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8607150185 | |
| Download: ML20202F523 (2) | |
Text
-
THE
--.m m UNfs/EZlTY
=f fMA...,~e OF UTAH rah-Mr. Robert Carter Standardization and Special Projects Branch Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 July 7,1986
Dear Mr. Carter:
During your last visit to the University of Utah Nuclear Engineering Laboratory while our facility was under relicensing review, we discussed the development of computer control of our 100 kWatt TRIGA reactor (Facility Operating License ho. R-126, Docket No. 50-407). Your advice concerning console upgrades was to classify the changes as facility modifications and follow the requirements outlined in ANSI 15.15. All modifications are to be reviewed by our Reactor Safety Committee to insure that all safety aspects are not compromised. A summary of the modifications is to be included in the reactor's Annual Report as outlined in 10CFR50.59. (Our next annual report period ends June 30,1986.)
Since our initial discussion, we have acquired an IBM Series /1 process control computer for the purpose of upgrading our reactor control system. We have been slowly installing and testing hardware and software interfacing systems. The reactor is currently controlled by the original console. All control rod drives, scram and interlock functions required by our technical specifications remain on the original console.
In Fall,1985, our Reactor Safety Committee approved the computer monitoring and display of redundant and periferal signals from power detectors, thermocouples, area radiation monitors, conductivity and pH probes, and flowmeters. In Winter,1986, the regulator control rod was classified as an experiment as allowed under our technical specifications. The rod drive motor was removed from the original console and installed on the computer system. All movements of the regulator rod are considered as experiments and must be accompanied by the appropriate documentation. Under these circumstances, tests of the monitoring, control, scram, and interlock functions of the computer control system will be conducted under near realistic conditions (ie.during reactor operation) without interferring with the original control system.
Assuming the final system is approved by our Reactor Safety Committee, the next step will be to remove the original console and move the remaining rod drives, power monitoring channels, thermocouples, and etc. over to the computer control system. This procedure should occur during the reperting period 1986-87 and will be included in the annual report due Summer,1987.
860715018S 860707 a
PDR ADOCK 05000407
()
O p
PDR Ifb
We would like to request that your office provide us with a written response to our previous and planned pmcedun:s. Please inform us of any additional requireinents we may have overlooked.
Sincerely, Kevan Crawford Senior Reactor Engineer MEB 3008 University of Utah Salt Lake City, Utah 84112 l
l 4