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Category:ANNUAL OPERATING REPORT
MONTHYEARML20091L7731995-07-31031 July 1995 Illinois Lopra Reactor-Annual Rept for Aug 1994 - Jul 1995 ML20072L5001994-07-31031 July 1994 Illinois Lopra Reactor Annual Rept for Aug 1993 - Jul 1994 ML20056H3241993-08-31031 August 1993 Forwards Annual 10CFR50.59 Rept Per Section 6.7.f of TSs ML20127C8971992-07-31031 July 1992 Annual Rept Aug 1991 - Jul 1992 Illinois Lopra Reactor ML20085E0011991-07-31031 July 1991 Illinois Lopra Reactor Annual Rept for Aug 1990 - Jul 1991 ML20059M1401990-07-31031 July 1990 Annual Rept Aug 1989 - Jul 1990,Illinois Lopra Reactor ML20248E1331989-07-31031 July 1989 Annual Rept for 880801-890731 ML20245D6931988-07-31031 July 1988 Annual Rept Illinois Lopra Reactor Aug 1987 - Jul 1988 ML20235K0581987-07-31031 July 1987 Annual Rept,Aug 1986-Jul 1987 ML20210Q5431986-07-31031 July 1986 Annual Rept,Low Power Reactor Assembly Reactor ML20137F3101985-07-31031 July 1985 Annual Rept,Aug 1984 - Jul 1985 ML20098C7561984-07-31031 July 1984 Annual Rept,Aug 1983 - Jul 1984 ML20080L1801983-07-31031 July 1983 Annual Rept,Illinois Lopra Reactor,Aug 1982 - Jul 1983 ML20062N6071982-08-23023 August 1982 Annual Operating Rept,810801-820801 ML20010H8561981-09-25025 September 1981 Annual Rept,Il Lopra Reactor,800801-810801. ML19344F5771980-09-0505 September 1980 Annual Rept,Aug 1979-Aug 1980,IL Lopra Reactor. ML19207C4431979-08-0101 August 1979 Annual Operating Rept for Aug 1978-Jul 1979 1995-07-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20149G2091997-07-16016 July 1997 Safety Evaluation Granting Order Terminating Facility License R-117 for Univ of Il at Urbana-Champaign Lopra ML20133N7511997-01-21021 January 1997 Safety Evaluation Supporting Amend 6 to License R-117 ML20091L7731995-07-31031 July 1995 Illinois Lopra Reactor-Annual Rept for Aug 1994 - Jul 1995 ML20080K8671995-02-28028 February 1995 Decommissioning Plan for Univ of Il Lopra ML20072C6831994-08-12012 August 1994 Ro:Damage Noted on Aluminum Clad Fuel Element in Lopra Reactor.Suspect Damage Occurred in Nov 1993 When Burr Removed from Lopra Upper Grid Plate.Fuel Element Removed from Lopra Core & Wrapped in Polyethylene ML20072L5001994-07-31031 July 1994 Illinois Lopra Reactor Annual Rept for Aug 1993 - Jul 1994 ML20056H3241993-08-31031 August 1993 Forwards Annual 10CFR50.59 Rept Per Section 6.7.f of TSs ML20127C8971992-07-31031 July 1992 Annual Rept Aug 1991 - Jul 1992 Illinois Lopra Reactor ML20085E0011991-07-31031 July 1991 Illinois Lopra Reactor Annual Rept for Aug 1990 - Jul 1991 ML20059M1401990-07-31031 July 1990 Annual Rept Aug 1989 - Jul 1990,Illinois Lopra Reactor ML20058L0761990-07-26026 July 1990 Univ of Illinois Nuclear Reactor Lab Operator Requalification Program ML20055J3941990-07-11011 July 1990 Revised Univ of Illinois Nuclear Reactor Lab Operator Requalification Program ML20042D8221990-01-31031 January 1990 Site Description Nuclear Reactor Lab,Univ of Illinois. ML20248E1081989-09-30030 September 1989 SAR for Low Power Reactor Assembly ML20248E1331989-07-31031 July 1989 Annual Rept for 880801-890731 ML20245D6931988-07-31031 July 1988 Annual Rept Illinois Lopra Reactor Aug 1987 - Jul 1988 ML20236N1511987-08-0404 August 1987 Safety Evaluation Supporting Amend 4 to License R-117 ML20235K0581987-07-31031 July 1987 Annual Rept,Aug 1986-Jul 1987 ML20214Q2701986-09-18018 September 1986 Part 21 Rept Re Defective Interlock in Control Rods During Movement to Full Up Position.Initially Reported on 860915. Corrective Action Will Be Taken by Univ of Illinois & Univ of California at Irvine ML20210Q5431986-07-31031 July 1986 Annual Rept,Low Power Reactor Assembly Reactor ML20137F3101985-07-31031 July 1985 Annual Rept,Aug 1984 - Jul 1985 ML20098C7561984-07-31031 July 1984 Annual Rept,Aug 1983 - Jul 1984 ML20080L1801983-07-31031 July 1983 Annual Rept,Illinois Lopra Reactor,Aug 1982 - Jul 1983 ML20062N6071982-08-23023 August 1982 Annual Operating Rept,810801-820801 ML20010H8561981-09-25025 September 1981 Annual Rept,Il Lopra Reactor,800801-810801. ML19344F5771980-09-0505 September 1980 Annual Rept,Aug 1979-Aug 1980,IL Lopra Reactor. ML19207C4431979-08-0101 August 1979 Annual Operating Rept for Aug 1978-Jul 1979 1997-07-16
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ANNUAL REPORT August 1. 1988 - July 31,-1989 ILLINOIS LOPRA REACTOR Facility License R-117
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SUMMARY
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 11-was generated during the two power calibrations performed during this reporting period. No maintenance 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.
Ma'intenance 0% 1
' Student Experiments 44 %
Surveillance' Requirements 56 %
Laboratory Measurements 0%
Total 100 %
li. TABULATION OF OPERATIONS Hours Criticalm and Enerov 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 Critical experiment and sub-critical time during the control rod calibration. The control rods are calibrated using sub-critical multiplication so that a large portion of the experiment is done wi t ti t h e 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.
111. EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS There were no unplanned scrams or emergency shutdowns during this reporting period.
IV. MAINTENANCE There were no significant items of maintenance performed during this reporting period.
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V. CONDITIONS UNDER SECTION 50.59 OF 10 CFR 50-fi There were no changes to procedures or new experiments during this pertoo. 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 reactivsty. .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., Viti., RADIOACTIVITY Because of the lower 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 29, 1988, r
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