ML20085E001
| ML20085E001 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 07/31/1991 |
| 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 9110170322 | |
| Download: ML20085E001 (3) | |
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', t,abora tor, 217 333 2906 f.n 103 South Gomhvin henue Urbana,11. 61h01 2981 9-25-91 Director ,
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission '
1 White Flint North 11555 Rockville Piko Rockville HD, 20852 Attention: Document Control Desh Dear Sir
Subject:
Annusi Report, LOPRA Reactor License No. R-117 Dociet No. 50-356 The following is written to comply with the requirement of Section 6.7.f of the TechMcal Specifications and condit ic>ns of 50.59 of 10 CFR 50. lhe outline foilews the numbered sequence of Section 0. 7.f of the Technical Specif ications.
Yours truly, a !~ f Craig S. Pohlod, Reactor Supervisor f(y $ L))k-
- r. John G. Williams, Reactor Director 5,0 49 -/
$'ll)?
Dr. Georfje H. Miley, Chairman, Nuclear React 5r
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7 Committee . , ,
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ds$ ktheXW% f~k' Dr.Barc[hG.,dk$nes, Head, Dehartmerft of l Nuclear Engineering l
l copy: Region III, USNRC P\
o110170322 910'/31 PCR ADOCK 05000356 k(I l R PDR 1 l
f ANNUAL REPORI August 1, 1990 - July 31, 1991 ILLINOIS LOPRA PEACTOR Facility License R-117
- 1. SUMMARLOF OPERATING EXPERJENCE The reactor was scheduled for operations a total of 44 hour5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> s and was in act uai operation a total of 18.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Scheduled time and operational time are greater this reporting period because of the scheduling of an Operator T raining Course for Shif t Technical Advisor Trainees f r om the Keuwenee Nuclear Power Station and the scheduling of a SRO licensing examination for Mr. Richard L.
Holm. Student Experiments /Demonstr ations scheduled in this reporting year include an " Appr oach to Critical' (ATC) fuel loading e mer1 ment in the LOPRA and the determination of Control Rod Worth by sub-critical multiplication.
The time scheduled for Surveillance Requ i r ement s includes power calibrations, cont rol rod worth determinations and fuel inspections. Scneduled time includes tirne for activities such as fuel inspections which don't require actual operation of the LOPRA. Over 99.9 % of the energy listed in Section 11 was generated during the two power calibrations performed during this reporting period. No maintenance was required during this reporting period. No labo atory measurements were performed other than those which are part of the Student Experiments / Demonstrations.
Timely application for re-licensing the LOPRA was filed with the USNRC on Sectember ?9, 1989. The LOPRA license expired 1 November 1989.
Maintenance 0%
Student Experiments / Demonstrations 45 %
Surveillance Requirements 46 %
SRO Licensing 9%
Lt'> orator y Measurements 0%
Total 100 %
II. TABULATION 0F_, OPERATIONS Hours Criti.. cal
- and_ Energy 18.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 5.69 FW-brs
- This time includes time 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 multiplication so that a large riortion of the experiment is done with the reactor sub-critical. The actual critical time during thcse experiments was about 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> or in of the above time.
III. EMERGENCY SHUTDOWNS AND INADVERTENT.SCPAMS There were no unplanned screms or emergency shutdownr during this reoarting period.
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3 IV. MAJNIENANCE [
-There were no significant items of maintenance performed - during this reporting period.
V. QQNQII1QNS UNDER__SECTIONJ0._59_QE10__CfR_50 There were- no changes to procedures or new experiments dur1ng this ' period. :
- The excess reactivity of the LOPRA core was increased from 27 cents to 27.5 cents !
- during this' reporting period. It is . felt that this increase in excess reactivity ?
is riue 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., VII., VIII., BAQ10AQlIXLT,1 Because of the low power and' infrequent use of the LOPRd,- its operation does
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not contribute to the release of effluents. Personnel radiation exposures for the laboratory are given in the P.nual Report' for the - Advanced TRIGA Reactor, License No. R-115, Docket No. 50-151, dated February- 28, 1991.
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