ML20098C756

Annual Rept,Aug 1983 - Jul 1984

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.

1 With the present position of the assembly, the excess reactivity is only 5-64. Thus the maximum power that could be attained is 3-4 kilowatts. 0 7

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1. 8409270182 840731 l PDR ADOCK 05000356 R PDR

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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

1. M*~ 214 Nuctrar Engineering laboritory 217 333-2295

- at Urbana-ChamPai8 n 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 4%t44 bus--

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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