ML20235K058

Annual Rept,Aug 1986-Jul 1987

ML20235K058
Person / Time
Site:	05000356
Issue date:	07/31/1987
From:	Micklich B, Pohlod C, Williams J ILLINOIS, UNIV. OF, URBANA, IL
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8710020221
Download: ML20235K058 (3)

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ANNUAL REPORT August 1 1986 - July 31, 1987 ILLINDIS LOPRA REACTOR l Facility Liconse R-117 I l

1.

SUMMARY

OF OPERATING EXPERIENCE The reactor was scheduled for operations a. total of 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> and was in actual operation a, total of 25.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Usage was.a little over double what it was in. the previous reporting period. but less than half what it has been in the recent past. This apparent decrease over the recent'past j is due to the fact that the local utilities who usually send. power plant trainees through our training program.are either involved in ascension-to l commercial operation or adjusting training to match projected fuel loading

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and did not send any trainees during this- reporting period. The training program includes an " Approach to Critical'" fuel loading experiment in the  !

LOPRA. The time involved with Surveillance Requirements includes power calibrations and control rod worth determinations, g9.7 % of the energy listed in Section ll was generated during the three power calibrations performed during this reporting period.

Operator Training (Facility - new RO's) 18 %

Student Experiments 26 %

Surveillance Requirements 43 %

Laboratory Measurements 13 %

Total 100 %

I ll. TABULATION OF OPERATIONS Hours Critical

• and Enerov 25.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 5.69 kW-hrs

• This time includes 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

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multiplication so that a large portion of the experiment is done with the reactor sub-critical. The actual critical time was about 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> or 24 %

of the above time.

Ill. EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS q

'l There was one unplanned scram and no emergency shutdowns during this i period. The unplanned scram was due to system noise believed to be caused by a bad connector in the Compensated lon Chamber (CIC) . channel.

IV. MAINTENANCE -

No maintenance on the LOPRA was required during this reporting period except for the replacement of the aforementioned bad connector in the CIC Channel. Considerable maintenance was performed on the LOPRA during the previous reporting period. This effori eliminated most difficulties with the LOPRA.

b B710020221 B70731 " \

PDR ADOCK 05000356-R PINT : l l

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v V. CONDITIONS UNDER SECTION 50.59 0F 10 CFR 50 There were ~ no changes to procedures or new experiments during this period. The excess reactivity of_the LOPRA core was about 12 cents during this reporting period. This would have allowed a maximum power of about 10 kilowatts.

The .LOPRA was made inoperative on the 23rd of July. 1987 in anticipation of removal of- the CIC for inspection of its connectors and determination of the insulation resistance of its leads. This action was also taken to allow for modification of the pulley and winch system which positions the LOPRA platform relative to the thermal column. One set of pulleys has pulled away from the Bulk Shielding Tank wall. The modified system will not concentrate so much stress'on the pulley anchoring.

The above modification of the LOPRA pulley system will=be reviewed by the Reactor Committee before it is carried out, i 11 is felt that these- two inets should be performed before re-licensing of the LOPRA is requested in 1989.

l VI., Vil., Vill., RADIOACTIVITY

, Because of the lower power and infrequent use of the LOPRA, its l operation does not contribute to the release of effluents. Personnel radiation exposures for the laboratory are given in the Annual Report for the Advanced TRIGA Reactor, License No. R-115 Docket No. 50-151, dated February 27, 1987.

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University of 111inois ' oerart- eni or- -

Nuclear Engineering cottese or Ensineerins .-

at Urbana-Champaign  : 214 Nuclear Engineering' '217 333 2295 Laboratory 103 South'Goodwin Avenue Urbana, IL 61801-2984 l

9-28-87  !

l Director.

Office of Nuclear Reactor. Regulation U.S. Nuclear Regulatory Commission Documsnta Controf Room ,

Washington D.C. 20555 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 outline follows the numbered sequence of Section 6.7.f of the Technical Specifications.

Yours truly,-

%)Pau Craig S. Pohlod, Reactor Supervisor I/b Dd John G. Williams, l Reactor Director Bas 1 %J&k Dr. Bradl'ey J. Micklich, Chairman, Nuclear Reactor Commitiee

/IY AL W^ 644tp D r '.' B a r c l a y[)il. J o ff ,

Head, DepaMment #f -  !

Nuclear Engineering I

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