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 PersonnelML19310A345 |
Person / Time |
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Site: |
Neely Research Reactor |
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Issue date: |
05/23/1980 |
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From: |
Kirkland R Neely Research Reactor, ATLANTA, GA |
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To: |
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References |
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NUDOCS 8006110118 |
Download: ML19310A345 (2) |
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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
[Table view] |
Text
6
= .4 GEORGIA INSTITUTE OF TECHNOLOGY SCHOOt. OF NUCLEAR ENGINEERING ATLANTA, GEdRGI A 30332'. .* 3 (,
F R AN K H. N EELY NUCLE AR RESE ARCH CENTER TE LE P'10 N E: (404)894 3600 May 23, 1980 U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W., Suite 3100 Atlanta, Georgia 30303 Gentlemen:
Reference:
Docket 50-160; License R-97
Subject:
Licensee Event Report LER 80-3 During the preparation for reactor startup on April 10, 1980, a " Low D,30 Temperature" alarm was received from the D 0 temperature recorder TRA-D1 2
when the pen drive cable broke. A spare cable was installed and the re-corder TRA-D1 was calibrated. During reactor operation later in the day, it was observed that the indicated temperature was exhibiting an erratic behavior. At apparently random intervals, point No. 1 (Reactor outlet) would print about 10 0F high for one or two cycles then return to normal.
The reactor was shutdown to investigate the problem. As a result of the investigation, a Inir of sliding contacts on one of the two scanner select switches was replaced due to excessive wear. The recorder then appeared to be operating normally but, contrary to established procedures, it was not recalibrated.
The reactor was operated for two brief periods on April 10, 1980 and April 11, 1980. In both cases the power level was <500 KW. On April 14, 1980, the reactor was scheduled to operate at 1000 KW. The power was increased in several increments because a replacement neutron detector has been in-stalled and its performance was being closely monitored. The power was stabilized when the nuclear instrumentation indicated approximately 1000 KW.
A thermal balance at this time gave a value of 933 KW. On April 15, 1980, the recorder TRA-D1 was calibrated. -The results indicated that the two monitored temperatures (reactor inlet and outlet) differed by approximately 0.50 F and the indicated reactor outlet temperature was 0.60F low. The dif-ference error is equivalent to 145 KW so the operating power on April 14, 1980 was approximately 933 + 145 or 1078 KW. The trip point for the High D 20 Temp.
l scram is required to be,s 125 F. It is actually set at 124 F. The 0.6 F
, error noted above means that on April 14, 1980, the trip point was 124.6 F, Q
still below the 125oF limit.
s
^
A am 8006110 $
U.S. Nuclear Regulatory Commission, Region II Page 2 May 26, 1980 The following steps have been taken to prevent a recurrence of an incident of this kind in the future.
- 1. Re-instruct all operating and maintenance personnel in the need and importance of calibrating any safety-related instrument following any maintenance, repair etc. on the instrument.
Status: Completed ,
- 2. Strengthen our program that documents all special repairs, surveillance and checks of the reactor instruments by requiring a second review of the documentation. We would expect the overlooked calibration noted above to be recognized by such a review.
Status: ' Completed Should you require any additional information on this matter, please advise me.
Sincerely yours
'. I Robert S. Kirkland Associate Director RSK:lrm cc: Members, Nuclear Safeguards Committee L.E. Weaver L.D. McDowell M.E. Mercer J.M. Burke O