ML20127C897
| ML20127C897 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 07/31/1992 |
| From: | Hang D, Holm R, Bradley Jones ILLINOIS, UNIV. OF, URBANA, IL |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9209100275 | |
| Download: ML20127C897 (4) | |
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, Unisersity of Illinois Deruiment or couese of Enginecing
'
- Nucim Enginm!ng at Urbana-Champaign
- a 214 Nudear 'ingineering 217 333 2295 Y t.aboratory 217 333-29'16 fat 103 Ssuth Goodwin Avenue l'rbana 11. 61801 0 984 August 28, 1992 Docket Ho. 50-356 Director cf Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission ATTN: Document Control Desk Mail Station P1-137 Washingtoli, DC 20555
Dear Sir,
Subject:
Annual Report, LOPRA Reactor License No. R-117 Docket No. 50-356 The following is written to comply with the requirements of Section 6.7.f of the Technical Specifications and conditions of 50.59 of 10CFR50. The outline follows the numbered sequence of Section 6.7.f of the Technical Specifications.
Respectfully, 6 ' +1
- Richard L. Holm Rr +or Supervisor
/ ubl Dlba9 Daniel F. Hang ' ' (/
Director Nuclear Rear',or Laboratory
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Head I Department of Nuclear Enginneering cc: Region III, USNRC i 9209100275 920731 6 p{
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o STATE OF ILLIr401S i COUNTY OF CHAMPAIGN Richard L. Holm, being.first dulf sworn on oath, deposes and says that he has affixed his signature to the letter abo're in nis official capacity-as Reactor Supervisrec, University of Illinois Nuclear Reactor Laboratory; that in i accordance with the provisions of Part 50 Chanter 1, Title 10 of the Code of .!
Federal Regulations, he is attaching this affidavit;-that the facts set forth -l in the within letter are true to his best information ano boliaf. l l
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t' Ri6hard L. Holm l Reactor Supervisor j i Subscribed and sworn to before me, a Notary F.,blic, in and for the County of l Champaign, State of Illinois, this l day of .d e f , A.D., 1992.
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- 1. ANNUAL REPORT August 1, 1991 - July 31, 1992 ILLINOIS LOPRA REACTOR i- Facility License R-117 j I. _StLMMARLOF OP_f!MLIjLG_fXPERIEN_Qf 1
) The reactor was in operation a total of 24.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the period. This
! includes time when the reactor was used for an " Approach to Critical" fuel
- loading experiment and the reactor was not actually critical. The remainder of operating time was due to fulfilling surveillance requirements.
Student experiments / demonstrations 11.5 hrs 47.7 %
i Surveillance regairements 12t s br3 Etta_%
24.1 hrs -100 %
i II. _TABJJLA1IDh_of_QPERATIONS 4
Bqsti_qritical' and Energy 24.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0.00515 Hw-brs
' This time in:1udes that used for loading fuel elements during the Approach a to Critical experiment and sub-critical time during '5e control rod calibration. Tb9 actual critical time was approximately 6.5 hrs. Virtually all of the energy generated was due to the power calibration surveillance.
! III. EHMGMOY SHUT 00WNS AND INAQVERJfNT SCRAMS There was one unplanned scram during the reporting period due to operator i error. This scram occurred due to the operator not resetting the gamma monitor scram to a higher value prior to commencing.the power calibration.
- The gamma monitor scram is normally set at 20 mr/hr and limits reactor power to about 300 watts. This scram is normally set to 500 mr/hr or so in order to
- perform the power calibration.
IV. HAINT ENAdCE There was no significant maintenance performed other than that described in Section V duririg this reporting period.
V. QQt4QLTLOES UNQSR_SECTION 50.59,_QF 10CfB59 l
There were no changes to procedures or new experiments during this per.iod. A 50.59 review was performed in December.of 1991 in order to repair the source range channel. The source range channel is described in block form in the-LOPRA Safety Analysis Report and does~not perforta any automatic cafety_
function. The tube-driven source range channel scaler became inoperative .in November with the necessary tubes unavailable for replacement.- The. system was replaced with the' transistorized equivalent of the previous tube drivan components.
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2 I VI., VII., VII1. RAQ19ACllVf_ RELEASE /BADIAHON_EA?QSLEE
- Because of the low power and infrequer.t use of the LOPRA,-its operation does
- i. not contribute to the release of effluents. Personnel radiation exposures for the laboratory are givon in-the Annual Report for the Advanced TRIGA Reactor, 4
cicense No. R-115, Docket No. 50-151, dated January 17, 1992. ,
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