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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
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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
IA-85-826, Partially Released Commission Paper Recommending NRC Response to co-owner Petition for Exemption from License Fee for Withdrawn CP Be in Form of Order.Draft Order Encl1985-11-25025 November 1985
Partially Released Commission Paper Recommending NRC Response to co-owner Petition for Exemption from License Fee for Withdrawn CP Be in Form of Order.Draft Order Encl
ML20199E8641985-11-25025 November 1985
Partially Released Commission Paper Recommending NRC Response to co-owner Petition for Exemption from License Fee for Withdrawn CP Be in Form of Order.Draft Order Encl
ML20137F3101985-07-31031 July 1985
Annual Rept,Aug 1984 - Jul 1985
ML20098C7561984-07-31031 July 1984
Annual Rept,Aug 1983 - Jul 1984
ML20076B4471983-08-10010 August 1983
Followup Part 21 Rept Re Emergency Diesel Generator 2B-B in Parsons-Peebles Electric Products Synchronous Generator S/N 14701228,supplied by Ge.Plants Supplied W/Generators Identified.Notification Ltr to GE Encl
ML20080L1801983-07-31031 July 1983
Annual Rept,Illinois Lopra Reactor,Aug 1982 - Jul 1983
ML20062N6071982-08-23023 August 1982
Annual Operating Rept,810801-820801
ML20054K1531982-06-23023 June 1982
Informs That Final Deficiency Repts for Listed Nonconformances Will Not Be Submitted Until Final Decision Is Made Re Const of Projects
ML20050B0221982-03-19019 March 1982
Final Deficiency Rept 2 Re Failure of Transamerica Delaval to Correct Violations Identified During Audits 79V-38 & 80V-39 Promptly,Due to Improper QA Program Implementation, Initially Reported on 820114.Also Reported Per Part 21
ML20010H8561981-09-25025 September 1981
Annual Rept,Il Lopra Reactor,800801-810801.
ML20140B2911981-09-0101 September 1981
Amend 16 to PSAR, Emergency Response Rept. Amend Constitutes Addendum I of Psar.Affidavit Encl
ML20010H4081981-08-31031 August 1981
Ok Corp Commission Black Fox Station Economic Viability Study.
ML20008F9841981-05-0404 May 1981
First Interim Deficiency Rept,Initially Reported 810402,re Tornado Depressurization Design Deficiencies.Ventilation Analysis for Intake & Essential Raw Cooling Water Pumping Stations Performed.Next Rept Will Be Submitted by 810909
ML19343B5011980-12-0808 December 1980
Part 21 Rept Re Reactor Protection Sys Flexible Conduit Defect Causing Hot Shorts If Improperly Grounded.Caused by Paint on Panel Surfaces or High Resistance Connection to Panel Survaces Where Termination Modules Are Mounted
ML19344F5771980-09-0505 September 1980
Annual Rept,Aug 1979-Aug 1980,IL Lopra Reactor.
ML20039E8991980-01-31031 January 1980
Containment Loads Rept,Mark III Containment, Revision 4
ML19256F2001979-11-26026 November 1979
First Interim Deficiency Rept Re Nonconformance in Metal Conduits.Damaged Threads,Burrs & Flaked Galvanized Coating Detected.Defective Parts Will Be Returned to Triangle Pwc & All Conduits Inspected
ML20039E8921979-09-30030 September 1979
Interim Containment Loads Rept,Mark III Containment, Revision 3
ML19207C4431979-08-0101 August 1979
Annual Operating Rept for Aug 1978-Jul 1979
ML19208D6751979-07-27027 July 1979
Supplemental Rept, Response to NUREG-0578,App A,TMI-2 Lessons Learned Task Force Short Term Recommendations
ML19209A6431979-07-0202 July 1979
Revised BVTR-1-0, QA Program Description.
ML19282A0381979-05-0909 May 1979
Annual Financial Rept 1978.
ML19282A0371979-05-0909 May 1979
Annual Financial Rept 1978.
ML19269C6131979-01-29029 January 1979
Amend 14 to PSAR Updating Following Areas:Eccs Performance, Qualification of Preoperational & Startup Testing Personnel, Expansive Structures & Interim Rept Mark III Containment, Revision 2.
ML20148J1131978-11-0202 November 1978
Interim Rept Re Geologic Inves of Subj Facil Excavation. Identifies Anomalies:Depression in Coal,Offset Along West Flank Anomaly,Offset in Northwestern Excavation.No Tectonic Indication W/Oversize Drawings Available in Central Files
1997-07-16
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ANNUAL REPORT August 1, 1980 - August 1, 1981 ILLIN0IS LOPRA REACTOR Facility License R-117 f- I.
SUMMARY
OF OPERATING EXPERIENCE The LOPRA was scheduled for operation a total of 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> and was in actual operation a total of 18.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Scheduled operations averaged 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> / month and actual operation 1.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> / month. Use of the LOPRA was for an ' Approach to Critical' experiment for students and operator training in which this experiment was completed. The types and percentages of usage for this time were:
Approach to Critical Experiments 28%
Operator Training 55%
Measurements for Surveillance Requirements 17%
There were no new experiments or changes in facility design, performance characteristics, and operating procedures during this period. The LOPRA was placed in an Inoperative condition, as defined by the Technical Specifications, from October 10, 1981 througia May 8,1981. During this time, the BF tube 3
that is used for start-up was removed and was utilized as a temporary source range detector for the Illinois Advanced TRIGA Reactor, License No. R-115. ,
This was described in the Annual Report for this reactor, dated February 28, 1980.
II. TABULATION OF OPERATION llours Critical
- and Energy Steady State Operation 18.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.0014 MW-hrs
- This includes time for loading fuel elements during the approach to critical experiments. Actual critical time would be about 30% of this value.
III. EMERGENCY S!!UTDOWNS - None.
IV. MAINTENANCE The only maintenance was a change in the power supply for the BF 3 tube that is used as the source range monitor. After repeated difficulties and the final failure of a 23 year old tube-type high voltage power supply, a new solid-state system was substituted _to obtain the 1700 volts necessary for this operation.
V. CONDITIONS UNDER SECTION 50.59 g 10 CFR 50 As indicated above, there were no changes to the system, procedures, or new experiments during this period.
81092903598109253 PDR ADOCK 050003567 R PDR9
.e 8 VI., VII., VIII. RADIOACTIVITY Because of the low power and infrequent use of the LOPRA, its operation does not contribute to the release of effluents. Personnel records for the laboratory are given in the Annual Report for the Advanced TRIGA Reactor, License No. R 115, dated February 28, 1981 (Docket No. 50-151).
- LICENSE RENEWAL Amendment No. 3 to Facility License No. R-117 was received on April 6,-1981.
This amendment renews the operating license until November 1, 1989. The only.
j change in the amendment is a section that requires limiting conditions of operation for the water quality and surveillance requirements to assure that the con dition is met.
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