ML20137F310
| ML20137F310 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 07/31/1985 |
| From: | Beck G, Miley G, Stubbins J ILLINOIS, UNIV. OF, URBANA, IL |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 8508260192 | |
| Download: ML20137F310 (3) | |
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ANNUAL REPORT August 1, 1984 - July 31, 1985
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ILLIN0IS LOPRA REACTOR Facility License R-ll7
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SUMMARY
OF OPERATING EXPERIENCE The reactor was scheduled for operation a total of 94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br /> and was in actual operation a total of 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Usage was almost 50% greater than in 1984. This was due to an increase 'in the usage by Nuclear Engineering students to perform an ' Approach to Cri tical' and ' Control Rod Calibration' experiments.
The ' Approach to Cri tical' experiment is also conducted as part of a one-week training program for nuclear power plant operators. The time involved in the Surveillance Requirements was for power calibration. It might be noted that over 99% of the energy in Section 11 occurred during two power calibrations.
The types and percentage of usage for the above period was:
Operator Training (power plant personnel) 43%
Student Experiments 53%
Surveillance Requi rements 4%
- 11. TABULATION E OPERATION Hours Cri tical*cand Energy 49 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 4.14 kW-hours
- This time includes that for loading fuel elements during the approach to critical experiments and subcri tical time during control rod calibrations.
The control rods are calibrated using 1/M values so that a good portion of the experiment is done wi th the reactor subcritical . The actual critical time was about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or 20% of the above time.
Ill. EMERGENCY _ SHUTDOWNS AND INADVERTENT SCRAMS There were no inadvertent scrams or emergency shutdowns during this period.
IV. MAINTENANCE The only maintenance occurred with the replacement of some parts in the poison control rod drive system. During an attempt to move the poison control rod, chattering in the position indicator occurred with no movement of the rod.
The problem was found in the potentiometer that allowed the operator to vary
- the speed of the control rod. In addition to the bad potentiometer, a number of gears involved in attaining the variable speed showed a great deal of wear.
I This system was replaced by a new speed control mechanism that allows for j only a fast or a slow speed. The slow speed can be adjusted by a potentiometer.
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The gears were eliminated 'through having separate controls for the rod direction and the rod speed. This system will be retained for future operations.
However, changes are planned when the controllers are mounted on the control panel. With 'the gears removed, this system should be more reliable.
V. CONDITIONS UNDER SEC140N 50.59 of 10 CFR 50.
There were no changes to procedures or new experiments during this period.
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The present excess reactivity is about 13 15 cents. This would allow a maximum l 1
power level of about 12 kilowatts.
VI., Vll., Vill. 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 laboratory are given in the Annual Report for the Advanced TRIGA Reactor, License No. R-115, Docket No. 50-151, dated February 24, 1985 t
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.. s University of Illinois at Urbana-Champaign Nuclear Engineering Program 214 Nclear Eogineering laborciary 103 South Goodwin Avenue 8-20-85 Urbana, Illinois 61801 r217) 333 2295 U. S. Nuclear Regulatory Commission Documents Control Room Washington, D. C. 20555
Dear Sir:
SUBJECT:
Annual Report, LOPRA Reactor License No. R-ll7 Docket No. 50-356 The following 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, MY /dk Gerald P. Beck, Reactor Supervisor Qtw2 b 1 h'if James F. Stubbins, Chai rman Nuclear Reactor Committee MN O'6orge H. 44i ley, Chai rperp Nuclear Engineering Program Attachment Copy: Region iII, USNRC o
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