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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20072D5071994-07-27027 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
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
1994-07-27
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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
ML20035H0401993-04-22022 April 1993
Part 21 Rept Re Problem in Gtstrudl Computer Code,Resulting in Incorrect Answers or Job Aborts.Initially Reported on 920831.Listed Customers Not Notified Due to Unknown Current Addresses.Curve Data May Be Lost After Save/Restore Process
ML20035H0671993-04-14014 April 1993
Part 21 Rept,Consisting of Error Notice Received from Former Software Supplier (Georgia Inst of Technology) Re Problem Results in Gtstrudl Computer Code.Listed,Former Customers Not Notified Due to Unknown Current Addresses
ML20035G8261993-04-0101 April 1993
Part 21 Rept,Consisting of Error Notice Received from Georgia Inst of Technology Re Incorrect Answers Which May Not Be Apparent or Job Aborts in Gtstrudl Computer Code. Listed Vendors Not Notified Due to Unknown Addresses
ML20034E6811993-02-22022 February 1993
Annual Rept for 1992
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
ML20101L3751972-12-19019 December 1972
SER Approving Mod to Georgia Tech Research Reactor to Permit Operation at Increased Power Levels Up to 5 Mwt
1999-07-22
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GEORGI A INSTITUTE OF TECHNOLOGY ' ~
SCHOOL OF NUCLEAR ENGINEERING ATLANTA. GEORGI A 30332
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FR AN G M. MEE LY NUCLE AR RESE ARCM CENTER TE LE P6* DM E s (404) 894-3600 April 11, 1980 U.S. Nuclear Regulatory Comission, Region Ii 101 Marietta Street, N.W. Suite 3100 Atlanta, Georgia 30303 Gentlemen:
Reference:
Docket 50-160 License R-97
Subject:
Licensee Event Report IER 80-1 One of the Technical Specification Surveillance requirements for the Georgia Tech Research Reactor (GTRR) is a monthly flow rate verification from the Energency Core Cooling System (tCCS) tank TD-2.
On October 9, 1979, during the performance of this test, the flow rate was observed to be 8.0 gallons per minute. 'Ihis is less tnan the operational lower limit of 8.3 gallons per minute.
'Ihe technique for measuring the flow rate is to initiate ECCS flew and note tank level readings versus time. 'Ihese data are then used with a tark cali-bration curve to determine the flow rate. On October 9, 1979, the test was performed and a flow rate of 8.0 gallons per minute (gpm) was noted by the reactor operator. 'Ihe test was repeated and the operator observed that the rate could apparently be varied from 8.0 to 8.5 gpm cepending on the manner in which ball-valve No. 94 was opened.
valve 94 is a 1 1/2 inch, handle operated ball valve of stainless steel, type.116 with Teflon seat material.
A mechanical stop is installed to restrict the open position of the valve so that the desired flow rate can be obtained from the tank. 'Ihe operator stated that he felt the flow variation was due to a looseness of the two 5
lock nuts fixing the handle to the ball operatire chaft. 'Ihe lock nuts were tightened. At this time a misunderstanding arose rt;sulting in the Reactor Supervisor believing that the problem had been corrected. She system was next checked on December 5, 1979 and subsequently on December 14, 1979, January 25, 1980 and February 11, 1980. In each case, the system flow rate was within the operational limit of 8.5 1 0.2 gpm.
During a reactor shutdown in March, valve 94 was closely re-exami ted. It was found that some looseness still existea between the handle and the ball operat-ing shaft because of clearance between the " flats" on the shaft and handle.
AOO1 Shim material was installed to improve the fit between the two pieces. We (T
5 have not been able to completely check this repair because the reactor is j
presently in a Mode 1 status and there is no water in the ECCS tank.
. //g Even though the test made on Dece::ter 5,1979 and those subsequent to it wemg%
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-. - - __ 8004280 Y... h 4
U.S. Nucitar R:gulator/ Comission, Region II Page 2 April 11,1900 satisfactory, we bel.ieve it may have been possible for the flow rate from the tank to be as low as 6.0 gpm at tires. he required miminum flow rate from the ECCS system is 8.0 gm as stated in our Safety Analysis Report (section 4.4.8.3, page 79). me operational limit of 8.510.2 gpa was chosen to provide some flexibility.
The following steps have been or will be taken to prevent a recurrence of an incident of this kind in the future.
1.
Re-instruct all operating personnel in the necessity and requirement for fullow-up invest.igation and/or action when any reactor associated system coes not appear to be functioning norrally.
Status: Corpleted Fill tank TD-2 with D 0 and thouroughly check the operation of valve 2.
2 94 to assure ourselves of consistant, reliable operation.
Status: Not complete. Eis will be done as soon as additional D 0 2
is available to charge the process water system.
3 Strengthen our surveillance prograrl by establishing a second review of the surveillance documentation to be performed by a person of at least the level of plant knowledge of a senior reactor operator.
Status: h e second review has been put into effect.
Until item 2 above has been conpletec, the GTPR will not be operated at power levels greater than 1 Md.
Should you require any additional info: ration on this matter, please advise me.
Sincerely
- urs, Robert S. Kirkland Associate Director RSK:lzm cc: Menbers, Nuclear Safeguards Cam:ittee L.E. Weaver L.D. McDowell
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