ML20098C756
| ML20098C756 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 07/31/1984 |
| From: | Bech G, Miley G, Stubbins J ILLINOIS, UNIV. OF, URBANA, IL |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 8409270182 | |
| Download: ML20098C756 (3) | |
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1 ANNUAL REPORT
. August 1,1983 - Jult 31,1984 ILLIN0IS LOPRA REACTOR l
Facility License R-117
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SUMMARY
g OPERATING EXPERIENCE The LOPRA was scheduled for operation a total of 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> and was in actual operation.a total of 34.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Usage was slightly less than for the previous year. The present use includes an ' Approach to Critical' experiment in which the TRIGA is used as the external source of neutrons, measurements of the reactivity worth of the control rods using 1/M relationships, and power calibrations in which the loss of reactivity is related to the power level because of the negative temperature reactivity coefficient.
The ' Approach to Critical' experiment is conducted as part of a one-week' training program for nuclear power plant operators. The types and percentage of usage for the above period was:
Operator Training (power plant personnel) 67%
Student Experiments 24%
Surveillance Requirements 9%
II._
TABULATIm g _0PERATIm Hours Critical
- and Energy 34.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.00005 MW-hrs
- This includes times for loading fuel elements during the approach to critical experiments. The actual critical time was about 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> or
' 16% of the above time.
III.
ENERGENCY SHUTDOWS #4D IN ADVERTENT SCRAMS There were no. inadvertent scrams or emergency shutdowns during the period.
IV.
MAIN TEN #1CE The only significant maintenance was the re-wiring of the electromagnets of the two safety rods on June 29,l1984. These wires are stressed when the
. safety rods; are manually removed from the core and the positioned. On the
. above date,'it was noted that one of the wires was broken since the electro-
. magnet could.not be energized.
- Since it was surmised that the same thing could happen-at the other magnet, both of the magnets were re-wired.
V. - CONDITIGS tNDER SECTIm 50.59 of 10 CFR 50 There were no changes to procedures or experiments during this period.
With the present position of the assembly, the excess reactivity is only 1
5-64.
Thus the maximum power that could be attained is 3-4 kilowatts.
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PDR ADOCK 05000356 R
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-VI.. VII.,'-VIII.
RADI0 ACTIVITY Because of the low' power and infrequent use of the LOPRA, its operation
' does not contribute to the release of effluents. Personnel radiation exposures for the laooratory are given in the Annual Report for the Advanced TRIGA Reactor, License No. R-ll5, Docket No. 50-151, dated February 8,1984.
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. University of Illinois Nucl:ar Engineering Program at Urbana-ChamPai n 214 Nuctrar Engineering laboritory 217 333-2295 8
103 South Goodwin Avenue Urbana
. Illinois 61801 September 21, 1984 U.' S. Nuclear. Regulatory Commission
. Documents Control Room-
. Washington, D. C.
20555
Dear Sir:
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SUBJECT:
Annual Report, LOPRA Reactor License No. R-ll7 Docket No. 50-356 The fo'llowing is. written to comply with the requirements of Section' 6.7.f. of the Technical. Specifications and the conditions of 50.59 of 10 CFR 50. The. outline follows the numbered sequence of Section '6.7.f. 'of the Technical Specifications.
Yours truly', -
Qt shf f
Gerald P. Beck, Reactor Supe svisor bus--
4%t44 3-2 James F. Stubbins, Chairman-Nuclear Reactor Committee drM 7/L fdorge y Miley, Chair on Nuclear Engineering P am Attachment Copy: Region III USNRC.
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