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Category:ANNUAL OPERATING REPORT
MONTHYEARML20207A6541999-02-26026 February 1999
1998 Annual Rept for Ga Institute of Technology Research Reactor. New TS No Longer Require Annual Operating Rept to Be Submitted to Nrc.Rept Submitted Since Facility Under Previous TS for Portion of CY98
ML20203H0571998-02-24024 February 1998
1997 Annual Rept for Ga Institute of Technology Research Reactor
ML20135D2821996-12-31031 December 1996
1996 Annual Rept for Ga Institute of Technology Research Reactor
ML20106G4281996-02-27027 February 1996
Annual Rept for Ga Inst of Technology Research Reactor for CY95
ML20063L4971994-02-25025 February 1994
Annual Rept for Ga Inst of Technology Research Reactor
ML20090B3821992-02-24024 February 1992
Annual Rept for 1991 (CY91) for Ga Institute of Technology Research Reactor
ML20235W8571989-02-21021 February 1989
Annual Rept for 1988
ML20148F3191988-02-26026 February 1988
Annual Rept for 1987.Related Info,Including Revised Procedure 3800, Liquid Waste Disposal Sys, from Chapter 15 of Auxiliary Sys Encl
ML20207T4171987-02-16016 February 1987
Annual Rept for 1986,including Operations Summary,Power Generation,Shutdowns,Unscheduled Maint on safety-related Sys & Components & Changes,Test & Experiments W/O Prior NRC Approval
ML20235X1721986-12-31031 December 1986
Rev 1 to 1986 Annual Rept, Correcting Several Errors in Section 7, Environ Monitoring
ML20009A1861981-03-13013 March 1981
Annual Operating Rept for 1980
ML20009A1891980-02-28028 February 1980
Annual Operating Rept for 1979
ML20009A1901979-03-0707 March 1979
Annual Operating Rept for 1978
1999-02-26
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20210E9411999-07-22022 July 1999
Safety Evaluation Supporting Amend 14 to License R-97
ML20207A6541999-02-26026 February 1999
1998 Annual Rept for Ga Institute of Technology Research Reactor. New TS No Longer Require Annual Operating Rept to Be Submitted to Nrc.Rept Submitted Since Facility Under Previous TS for Portion of CY98
ML20155G9901998-11-0404 November 1998
Safety Evaluation Supporting Amend 13 to License R-97
ML20236Q0781998-06-0404 June 1998
Rev 3 to 82A9083, Ga Inst of Technology Research Reactor Decommissioning Plan
ML20217K7981998-04-0202 April 1998
Safety Evaluation Supporting Amend 12 to License R-97
ML20203H0571998-02-24024 February 1998
1997 Annual Rept for Ga Institute of Technology Research Reactor
ML20135D2821996-12-31031 December 1996
1996 Annual Rept for Ga Institute of Technology Research Reactor
ML20106G4281996-02-27027 February 1996
Annual Rept for Ga Inst of Technology Research Reactor for CY95
ML20078A0001995-01-10010 January 1995
SAR for 5 MW Ga Tech Research Reactor, Revised from First Submittal,Apr 1994
ML20149G8581994-10-31031 October 1994
Provides NRC W/Error Notice Received from Former Software Supplier
ML20072D5071994-07-27027 July 1994
Ro:On 940722,drift of Temp Trip Setting of Primary Coolant Occurred.Suspect Drift Occurred Since 940522 Due to Failure of Compressor That Provides Bldg Compressed Air.New Equipment Ordered to Replace Current Unit
ML20070M9701994-04-30030 April 1994
SAR for 5 MW Georgia Tech Research Reactor. W/Financial Qualifications of Georgia Institute of Technology to Operate Georgia Tech Research Reactor
ML20064N3581994-03-31031 March 1994
Nucleate Boiling Characteristics & Critical Heat Flux Occurrence in Subcooled Axial-Flow Water Sys
ML20063L4971994-02-25025 February 1994
Annual Rept for Ga Inst of Technology Research Reactor
ML20058L9001993-05-0404 May 1993
Part 21 Rept Consisting of Gtices Program Error Notice 93.14 Re Ibm RS6000 Computers Gt Modeler Recovery File.Resized Graphics Screen Can Not Be Completely Recovered.Lists Customers Not Notified Because of Unknown Current Addresses
ML20128A1481992-09-30030 September 1992
Analyses for Conversion of Ga Tech Research Reactor from HEU to LEU Fuel
ML20090B3821992-02-24024 February 1992
Annual Rept for 1991 (CY91) for Ga Institute of Technology Research Reactor
ML20096H5461991-12-31031 December 1991
Corrected Pages 13 & 14 to Annual Rept,Consisting of Item 7(e) Re Max Cumulative Radiation Dose Which Could Have Been Received by Individual Continuously Present in Unrestricted Area During Reactor Operation
ML20079B1551991-06-0707 June 1991
Amend to 1990 Annual Rept - Georgia Tech Research Reactor. Submittal Corrects Error in Item 1.f on Page 5 Re Changes in Plant Staff & Committee Membership
ML20065S7981991-01-0202 January 1991
Requalification Program for Reactor Operators/Senior Reactor Operators,Georgia Tech Research Reactor
ML20235W8571989-02-21021 February 1989
Annual Rept for 1988
ML20151C0681988-07-12012 July 1988
Safety Evaluation Supporting Amend 7 to License R-97
ML20154N0061988-04-19019 April 1988
Neely Nuclear Research Ctr Response to NRC Concerns
ML20151R1981988-03-29029 March 1988
Rept of Visit to Georgia Tech Research Reactor Facility to Inspect Facilities & to Interview Operational Staff
ML20148E3451988-03-14014 March 1988
Incident Rept of Cadmium Spill on 870818
ML20148F3191988-02-26026 February 1988
Annual Rept for 1987.Related Info,Including Revised Procedure 3800, Liquid Waste Disposal Sys, from Chapter 15 of Auxiliary Sys Encl
ML20207T4171987-02-16016 February 1987
Annual Rept for 1986,including Operations Summary,Power Generation,Shutdowns,Unscheduled Maint on safety-related Sys & Components & Changes,Test & Experiments W/O Prior NRC Approval
ML20235X1721986-12-31031 December 1986
Rev 1 to 1986 Annual Rept, Correcting Several Errors in Section 7, Environ Monitoring
ML20009A1861981-03-13013 March 1981
Annual Operating Rept for 1980
ML19310A3451980-05-23023 May 1980
Ro:On 800410,heavy-water Temp Recorder TRA-D1 Was Not Recalibr After Replacement of Worn Sliding Contacts on Scanner Select Switch.Cause Not Stated.Importance of Recalibr Emphasized to Personnel
ML19309F1241980-04-14014 April 1980
RO 80-02:on 800305,low Flow Scram of Flow Recorder FRA-D1 Resulted in Reactor Trip & Subsequent Shutdown.Caused by Broken Teflon Gasket Pieces Restricting Flow.Gasket Repaired & Sys Refilled
ML19309F0881980-04-11011 April 1980
RO 80-1:on 791009,during ECCS Tank TD-2 Monthly Flow Rate Verification,Flow Rate Observed to Be 8 Gpm.Caused by Loose Lock Nuts Which Fix handle-to-ball Operating Shaft. Surveillance Program Will Be Strengthened
ML20009A1891980-02-28028 February 1980
Annual Operating Rept for 1979
ML20009A1901979-03-0707 March 1979
Annual Operating Rept for 1978
1999-07-22
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ATTACHMENT 1 REVISION 1 TO 1986 ANNUAL REPORT Page 6 TECHNICAL SPECIFICATION 6.7(6) - ENVIRONMENTAL MONITORING Tech Spec 6.7(7)(a) & (b) - The environment around the GTRR is monitored by a series of 30 film badges around the perimeter fence. This system is capable of assessing exposure from direct radiation and from gaseous effluent.
Tech Spec 6.7(7)(c) - Of the 30 film badge stations, none showed activity above local background levels due to reactor operations. Station 9 did show measurable activity above background; however, the annual dose of 190 mrem measured at this station was due to radiation from sealed sources stored in a nearby building which are used for calibrating health physics instruments.
Tech Spec 6.7(7)(d) - Highest, lowest and annual average levels of radiation for sampling point with the highest average due to reactor operations and location of that point with respect to the site (excludes Station 9).
The results of film badge monitoring of reactor operations indicate that no exposure at any station was above background radiation levels. Therefore:
Highest - < 10 mrem Lowest - < 10 mrem Average - < 10 inrem Tech Spec 6.7(7)(e) - Maximum cumulative radiation dose which could have been received by an individual continuously present in an unrestricted area during reactor operation from:
- 1. direct radiation and gaseous effluent
< 10 mrem / year
- 2. liquid effluent
< 1% 10 CFR 20 limits Tech Spec 6.7(8)
Summary of occupational exposure greater than 500 mrem -
None Summary of exposure for persons under 18 years of age greater than 50 mrem - None h$$ $0bbb $0 R
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