ML20248F253
| ML20248F253 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 09/26/1989 |
| 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 8910060310 | |
| Download: ML20248F253 (1) | |
Text
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,.,.. W3 M.:,. '-MUniversity of Illinois-DePminent tf 5.
.CoHege of Engineering.
Nuclrar Engineering a C -.t
'at. Urbana,-Champaign A -
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. 22d Nuclear Engineering 217 333-2295-i Q'
- Laboratory
.103 South Goodwin Avenate
' Urbana, IL (1801-2984 h.
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Dir ec t ot-Office of-Nuclear Reactor Regulation
. U.S.j Nuc 4 eat ' Regu l a t or y Cornmi sa ion
' - l' W'a l t e.S l i n t - No r t h 11555 Rockville Rockville MD, 20852 Attention: Document Control Desk D'ea r. S i rit
Subject:
Annual. Report, LOPRA Ructor
. License No.~R-117 Docket No. 50-356.
The-following is.wrliten tr> comply with ihe requirement of Sociton 6,7.f-of:the. Technical Specifications: and conditions ~of SD.E9 of 10 CFR
- 50. The
.. outline,follows the numbered sequepr3 of Section 6.7.f 'of the Technical
. Specif~ications Yours truly.
%%)Pasa Crair; S. Pohlod:
Reactor, Supervisor fkY
- d. John G. Wi i l's ams,
Reactor Director k
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Dr. Geo/geH. Mile /,
Chairman, Nuclear Reactor Commiitce
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o Nuclear Engineering
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l ANNUAL REPORT August 1,
1988 - July 31, 1989 ILLINDIS LOPRA REACTOR Facility License R-117 I
EMMMARY OF OPERATING EXPERIENCE The reactor was scheduled for operations a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and was in actual operation a total of 16.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
Scheduled time is less this year because no maintenance and no laboratory measurements were performed other than those which are a part of the Student Experiments.
Student Experiments include an " Approach to Critical fuel loading experiment in the LOPRA and the determination of Control Rod Worth by sub critical multiplication.
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 LOPRA. Over 99.9 % of the energy listed in Section it was generated during the two power calibrations performed during this reporting period.
No maintenarme was required during this time reporting period. A large amount of maintenance was performed in the last two reporting periods.
This was performed in anticipation of re-licensing the LOPRA in November of 1989.
Maintenance 0%
Student Experiments 44 %
Surveillance Requirements 50 %
Laboratory Measurements 0%
Total 100 %
11.
TABULATION OF OPERATIONS Hours Critical
- and Enerav 16.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 6.19 kW-hrs
- This time includes that for loading fuel elements during the Approach to Crstical experiment and sub-critical timo during the control rod calibration. The control rods are catebrated using sub-critical multiplication so that a large portion of the experiment is done with the reactor sub-critical. The actual critical time was about 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> or 28% of the above time.
Ill. EMEAGENLY_1HUTDOWNS AND INADVERTENT SCRAMS There were no unplanned scrams or emergency shutdowns during this r epor t ing per iod.
IV.
MAINTENANCE j
There were no significant items of me:ntenance performed during this reporting period.
j ~
e l V.
C_ONDITIONS UNDER SECTION 50.59 OF 10 CFR 50 There were no changes to procedures or new experiments during this period,'The excess reactivity of the LOPRA core was increased from 22 cents to 26 cents during this reporting period. It is felt that this increase in excess reactivity is due to the change in orientation which occurs in the core when fuel is loaded back into the core during the Approach to Critical Experiment.This increase leaves the excess reactivity well below the maximum Technical Specification limit of 60 cents.
VI., Vll., Vill.,
RADIOACTIVITY Because of the lower power and infrequent use of the LOPRA, its operation does not coniribute to the release of effluents. Personnel radiation exposures for the labo,atory are Olven in the Annual Report for the Advanced TRIGA Reactor, License No. R-115. Docket No. 50-151, dated February 29, 1988.
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