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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML19310A3451980-05-23023 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 1980-05-23
[Table view] Category:LER)
MONTHYEARML19310A3451980-05-23023 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 1980-05-23
[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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t, 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 have not been able to completely check this repair because the reactor is 5 l 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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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
- 2. Fill tank TD-2 with D 02 and thouroughly check the operation of valve 94 to assure ourselves of consistant, reliable operation.
Status: Not complete. Eis will be done as soon as additional D 20 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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