ML20059M140
| ML20059M140 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 07/31/1990 |
| From: | Miley G, Pohlod C, Williams J ILLINOIS, UNIV. OF, URBANA, IL |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9010030180 | |
| Download: ML20059M140 (3) | |
Text
{{#Wiki_filter:," University of Illinois ocrarement of . college of Engineering
, ,' Nudur Enginndng -
at Urbana-Champaign 214 Nudear Engineenng 217 333 1295 , laboratory - 217 333 2906 fax 103 South Goodwin Avenue Urbana,IL 61801 2964 9-26-90 , Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville MD, 20852 r Attention: Document Control Desk
Dear Sir:
Subject:
Annual Report, LOPRA Reactor License No. R-117 Docket No. 50-356 The following is written to comply with the requirement of Section 6.7.f of the Technical Specifications and conditions of 50.59 of 10 CFR 50. The r"tline follows the numbered sequence of Section 6.7.f of the Technical Specificauons. Yours truly 0 b Craig S. Pohloe, Reactor Supervisor h%$Y Df.JohnG. Williams, Reactor Director M % r.Ge[geH.Hiley,[_, l Chainnan, Nuclear Reactor Committee 7 l h$v r, w I Dr.Barcig[tmentofG.Johs, Head, Depar Nuclear Engineering copyQ ,Repfjn)'III, USNRC 9010030100 900731 .
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[.. . s ; ., : s I . 4 l 4 u ANNUAL REPORT. . i August.1, 1989;- July 31v 1990-ILLINOIS LOPRA REACTOR l Facility 11 cense R-117 , J I. .
SUMMARY
OF OPERATING EXPERIENCE : ). The ' reactor was schSduled for operations a total of 20 ' hours a+vt was in - ' actual operation a total of 7.t" hours. Scheduled time is less this year, because no maintenance and no'laborato.ry measurements were. performed other than those 3' which are a part of the - Student Experiments. Student : Experitnents--include . an -
" Approach to Critical" (ATC) fuel loading experiment in the . LOPRA.. and the 4 determination of - Control Rod Worth by sub critical multiplication. ' The ATC 'l experiment was used as a demonstration experiment early in the summer as part ,
of an IAEA/ANL Training Course on " Safety in the Operation of Nuclear Research
~ Reactors", a part of. which was hosted.'by the University of Illinois. Nuclear t Reactor Laboratory. -{
. .. t The time . involved with Surveillance Requirements _ includes . power ;
calibrations, control rod. worth determinations and- fuel inspections. Scheduled-time includes time for activities'such as fuel inspections which don't require' ; actual operation of the.t0PRA. Over 99.9 % of the energy listed in Section II was generated during the two power calibrations performed during this reporting ! period. No maintenance was required during this-time reporting period.. i Timely application for re-licensing the LOPRA was' file'd with the USNRC on September 29, 1989. .The LOPRA license expired 1 November 1989. Maintenance 0% Student Experiments / Demonstrations 20 % Surveillance Requirements. 80 % Laboratory Measurements _0.% Total 100 % II. TABULATION'0F OPERATIONS Hours Critical
- and Enerav: 7.6 hours- 4.0 kW-hrs
- This time Lincludes that' for loading fuel elements during the Approach to Critical experiment and sub-critical. time during the control rod calibration.
The control rods are calibrated using sub-critical multiplication so that a large portion' of' the experiment is done with the t reactor sub-critical. The actual critical time was about 2.0 hours or 20% of the above time. III. EMERGENCY SHUTDOWNS AND INADVEhrENT SCRAMS There were no unplanned scrams or emergency shutdowns during this reportingj period.
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jr - y s .j r- , : I-IV... MAINTENANCE l There ; were no) signif jeant fitems ofl maintenanca' performed - during;this
. j reporting period. 'j V. CONDITIONS UNDER SEQTION_$0;59 OF410 CFR $Q ,j
'J There were no changes tb procedures-or' neu e' x periments during thisl period.
, j The excess reactivity of the LOPRA_ coie was increased from 26 cents'to.27l cents-U during this reporting period. .It is . felt that this increase 1n:excessL reactivity
. .l is due to the change.in' orientation which occurs .in the core when fuel is loaded ~
1 back into the core during the Approach to. Critical ~' Experiment.This increase ' leaves the excess reactivity.well below the maximum Technical Specification <1imit ; of 60 cents.- ' j VI., VII., VIII., RADI0 ACTIVITY j( Because of the lower power and infrequent'use=of thefLOPRA', sits operation O does not contribute to the release of effluents. Personnel . radiation exposures-for the laboratory are given in the Annual Report for the Adyt.nced TRIG.'..".= tor, , License No. R-115, Docket No. 50-151, dated February 28. 1990. j t I! o 1 ' f.; 4 P 3}}