|
|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20012E9841990-03-29029 March 1990
Ro:On 900228,chamber Door of Primary Reactor Continous Air Monitors (CAM) Left Partially Open,Causing Filter to Be Several Centimeters Further from Detector than Normal. Backup CAM Will Be Wired Into Damper Isolation Sys
ML20006G2261990-02-22022 February 1990
Ro:On 900126,reactor Room Sealing Dampers Did Not Fully Seal When in Closed Position During Triga Ventilation Sys Insp. Air Monitoring Sys Showed No Release of Fission Products or Release of Contaminants in Reactor Room.Dampers Repaired
ML20006F1561990-02-0707 February 1990
Ro:On 900126,discovered That Reactor Room Sealing Dampers Did Not Fully Seal When in Closed Position During Insp of Ventilation Sys.Dampers Repaired & Returned to Svc on 900126
ML20006G2281988-11-0808 November 1988
Ro:On 881011,reactor Operator Left Console Unlocked While Tracing Electrical Circuit.Discovered by Another Operator Who Locked Console & Removed Key.Two Corrective Actions Were Taken to Prevent Recurrence.Operator Counseled
ML20006G2311988-03-23023 March 1988
Ro:On 880229,reactor Room Primary Continuous Air Monitor Accidently Left in Test Mode During Operations.Two Sets of Corrective Actions Taken to Prevent Recurrence Including Flashing Visual Light Installed on Console in Control Room
ML20040A9341981-12-29029 December 1981
Ro:On 811222 & 23,intermittently Changing But Fixed Vertical Position of Transient Control Rod Noted.Caused by Failure of Bolt That Secures Telescoping Section of Transient Connecting Rod.Section Removed & Secured W/Bolt
ML20010B4051981-07-31031 July 1981
Ro:On 810730,operator Failed to Measure k-excess Prior to First Reactor Power Operation.Excess Reactivity,Measured on Daily Basis,Has Not Varied Outside Normal Operational Conditions.Internal Administrative Procedure Instituted
ML19322E5831980-03-25025 March 1980
Ro:On 800315,scram Indicators on Reactor Control Console Were Illuminated,Indicating Power Failure or Outage of Console.Caused by Damaged Operational Amplifier.Circuit Board Replaced.Relay,Requiring Manual Reset,Installed
1990-03-29
[Table view]
Category:LER)
MONTHYEARML20012E9841990-03-29029 March 1990
Ro:On 900228,chamber Door of Primary Reactor Continous Air Monitors (CAM) Left Partially Open,Causing Filter to Be Several Centimeters Further from Detector than Normal. Backup CAM Will Be Wired Into Damper Isolation Sys
ML20006G2261990-02-22022 February 1990
Ro:On 900126,reactor Room Sealing Dampers Did Not Fully Seal When in Closed Position During Triga Ventilation Sys Insp. Air Monitoring Sys Showed No Release of Fission Products or Release of Contaminants in Reactor Room.Dampers Repaired
ML20006F1561990-02-0707 February 1990
Ro:On 900126,discovered That Reactor Room Sealing Dampers Did Not Fully Seal When in Closed Position During Insp of Ventilation Sys.Dampers Repaired & Returned to Svc on 900126
ML20006G2281988-11-0808 November 1988
Ro:On 881011,reactor Operator Left Console Unlocked While Tracing Electrical Circuit.Discovered by Another Operator Who Locked Console & Removed Key.Two Corrective Actions Were Taken to Prevent Recurrence.Operator Counseled
ML20006G2311988-03-23023 March 1988
Ro:On 880229,reactor Room Primary Continuous Air Monitor Accidently Left in Test Mode During Operations.Two Sets of Corrective Actions Taken to Prevent Recurrence Including Flashing Visual Light Installed on Console in Control Room
ML20040A9341981-12-29029 December 1981
Ro:On 811222 & 23,intermittently Changing But Fixed Vertical Position of Transient Control Rod Noted.Caused by Failure of Bolt That Secures Telescoping Section of Transient Connecting Rod.Section Removed & Secured W/Bolt
ML20010B4051981-07-31031 July 1981
Ro:On 810730,operator Failed to Measure k-excess Prior to First Reactor Power Operation.Excess Reactivity,Measured on Daily Basis,Has Not Varied Outside Normal Operational Conditions.Internal Administrative Procedure Instituted
ML19322E5831980-03-25025 March 1980
Ro:On 800315,scram Indicators on Reactor Control Console Were Illuminated,Indicating Power Failure or Outage of Console.Caused by Damaged Operational Amplifier.Circuit Board Replaced.Relay,Requiring Manual Reset,Installed
1990-03-29
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20205B1161998-12-31031 December 1998
1998 Annual Rept of Afrri Triga Reactor. with
ML20216H7451998-03-12012 March 1998
Ro:On 980224,SRO Left CR Leaving Key Unattended in Console. Caused by Personnel Error.Rso Was Reprimanded for Failing to Follow Procedures & Operators Participated in Special Training Class
ML20217F0331997-12-31031 December 1997
1997 Annual Rept of Affri Triga Reactor
ML20137H5161996-12-31031 December 1996
1996 Annual Rept of Afrri Triga Reactor
ML20108A1291995-12-31031 December 1995
Corrected 1995 Annual Rept of Afrri Triga Reactor
ML20107K1921995-12-31031 December 1995
Corrected Copy of 1995 Annual Rept of Affri Triga Reactor Facility. W/Undated Ltr
ML20101D5791995-12-31031 December 1995
1995 Annual Rept of Afrri Triga Reactor. W/Undated Ltr
ML20081K3101994-12-31031 December 1994
1994 Annual Rept of Afrri Triga Reactor
ML20065A0221993-12-31031 December 1993
1993 Annual Rept of Afrri Triga Reactor
ML20058F6191993-11-30030 November 1993
Ro:On 931105,during Radiation Measurements in Exposure Room One,Core Support Shroud Came in Contact W/Lead Shield Doors When Interlock Failed,Causing Subj Doors to Close.Caused by Lack of Communication.Operators Involved Reprimanded
ML20056C0691992-12-31031 December 1992
1992 Annual Rept of Afrri Triga Reactor
ML20106B4991992-09-25025 September 1992
Ro:On 920904,discovered Operating Anomaly on Console Which Would Drive Out of Core in Pulse Mode If Square Wave Button Pressed While Pressing Rod Drive Up Button.Caused by Failure to Remove Transient Rod.Second Switch Installed
ML20091A8621991-12-31031 December 1991
Afrri Triga Reactor 1991 Annual Rept. W/Undated Ltr
ML20070Q1571990-12-31031 December 1990
1990 Annual Rept,Armed Forces Radiobiology Research Inst, Reactor Facility
ML20055J4821990-07-23023 July 1990
Safety Evaluation Supporting Amend 19 to License R-84
ML20042F0431990-05-0303 May 1990
Comparison & Correlation of Proposed & Current Emergency Plans.
ML20042F0291990-04-30030 April 1990
Fuel Follower Control Rod Safety Analysis for Armed Forces Radiobiology Research Inst Triga Reactor Facility.
ML20012E9841990-03-29029 March 1990
Ro:On 900228,chamber Door of Primary Reactor Continous Air Monitors (CAM) Left Partially Open,Causing Filter to Be Several Centimeters Further from Detector than Normal. Backup CAM Will Be Wired Into Damper Isolation Sys
ML20006G2261990-02-22022 February 1990
Ro:On 900126,reactor Room Sealing Dampers Did Not Fully Seal When in Closed Position During Triga Ventilation Sys Insp. Air Monitoring Sys Showed No Release of Fission Products or Release of Contaminants in Reactor Room.Dampers Repaired
ML20006F1561990-02-0707 February 1990
Ro:On 900126,discovered That Reactor Room Sealing Dampers Did Not Fully Seal When in Closed Position During Insp of Ventilation Sys.Dampers Repaired & Returned to Svc on 900126
ML20245G8781988-12-31031 December 1988
Reactor Facility Annual Rept 1988
ML20006G2281988-11-0808 November 1988
Ro:On 881011,reactor Operator Left Console Unlocked While Tracing Electrical Circuit.Discovered by Another Operator Who Locked Console & Removed Key.Two Corrective Actions Were Taken to Prevent Recurrence.Operator Counseled
ML20196D2731988-07-0505 July 1988
New Reactor Control Console QA Program
ML20196D2821988-05-11011 May 1988
Description of Old & New Reactor Instrumentation & Control Sys for Affri Mark F Reactor Facility
ML20196D2531988-05-11011 May 1988
10CFR50.59 SER of New Reactor Instrumentation & Control Sys at Armed Forces Radiobiology Research Inst
ML20006G2311988-03-23023 March 1988
Ro:On 880229,reactor Room Primary Continuous Air Monitor Accidently Left in Test Mode During Operations.Two Sets of Corrective Actions Taken to Prevent Recurrence Including Flashing Visual Light Installed on Console in Control Room
ML20150E6021987-12-31031 December 1987
Reactor Facility Annual Rept Jan-Dec 1987
ML20140B8901985-12-31031 December 1985
Reactor Facility Annual Rept 1985
ML20100D0301984-12-31031 December 1984
Annual Rept for Armed Forces Radiobiology Research Inst Triga Mark-F Reactor
ML20100D0521984-09-30030 September 1984
Revised SAR for Armed Forces Radiobiology Research Inst Triga Mark-F Reactor
ML20082B0791983-10-31031 October 1983
Annual Rept,Oct 1982 - Sept 1983
ML20066C1541982-09-30030 September 1982
Annual Operating Rept for Armed Forces Radiobiology Research Inst for Oct 1981 - Sept 1982
ML20040A9341981-12-29029 December 1981
Ro:On 811222 & 23,intermittently Changing But Fixed Vertical Position of Transient Control Rod Noted.Caused by Failure of Bolt That Secures Telescoping Section of Transient Connecting Rod.Section Removed & Secured W/Bolt
ML20038B2551981-08-26026 August 1981
General Atomic Triga Mark F (GA-TRIGA F).
ML20010B4051981-07-31031 July 1981
Ro:On 810730,operator Failed to Measure k-excess Prior to First Reactor Power Operation.Excess Reactivity,Measured on Daily Basis,Has Not Varied Outside Normal Operational Conditions.Internal Administrative Procedure Instituted
ML20009B0231981-05-12012 May 1981
SAR for Armed Forces Radiobiological Research Inst Triga Reactor Facility,License R-84
ML19345C8651980-12-0303 December 1980
Armed Forces Radiobiology Research Inst R-84,Annual Rept Oct 1980.
ML19338E8531980-10-0303 October 1980
Reactor Operator Requalification Program.
ML19338E8641980-10-0303 October 1980
Eia Data for AFRRI-TRIGA Reactor.
ML19338E8501980-09-18018 September 1980
Safety Analysis of Hazard Summary Rept,Chapter 6 to Fsar.
ML19345C8661980-09-18018 September 1980
Section VI Safety Analysis of Fsar.
ML19338D0441980-09-17017 September 1980
Proposed Reactor Operator Requalification Program.
ML19322E5831980-03-25025 March 1980
Ro:On 800315,scram Indicators on Reactor Control Console Were Illuminated,Indicating Power Failure or Outage of Console.Caused by Damaged Operational Amplifier.Circuit Board Replaced.Relay,Requiring Manual Reset,Installed
ML19242C4621979-08-0101 August 1979
Deficiency Rept Re Malfunction of Fuel Element Temp Sensing Circuit.Grounding Strap Installed at Main Ground to Lock Signal & Sys Ground Together
ML19242C4971979-07-31031 July 1979
Amended Deficiency Rept Re Malfunction of Pool Water Level Sensing Switch,Submitted by Defense Nuclear Agency.Switch Unit Replaced & Addl Sleeving Placed at Wear Point
ML20062A4411978-10-0606 October 1978
Forwards AFRRI-TRIGA(R-084 Yae)Annual Rept
1998-03-12
[Table view] |
Text
O s
ELECTRONIC DAMAGE TO SAFETY CHANNEL ONE O ti dr . ,-.
I. History and Description of the Damage On Saturday,15 March 1980, the Physicist-in-Charge of the AFRRI Reactor Facility discovered that most scram indicators on the reactor control console were illuminated. Such a condition is consistent with a power failure or outage of the console. A query of the AFRRI Security Watch revealed that between approximately 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />,14 March, and 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />,15 March, a survey of the AFRRI electrical systems was in progress. The nature of the survey was such that power could have been inadvertently removed and reapplied to the console. All scram indicators were reset and all systems appeared to be functioning normally.
On Monday,17 March 1980, a Weekly Nuclear Instrumentation Checklist was performed expressly to verify console operability in light of the events of 14 and 15 March, and prior to any reactor operation. This inspection revealed that Safety Channel One would not initiate a scram in accordance with the Technical Specifications of Reactor Licence R-84. Safety Channel Two and all other instrumentation were fully operational.
The operational amplifier on a Safety Channel One circuit board had been damaged when electrical power had been reapplied to the console af ter the power
! outage. Normally that amplifier would have had an output of 10 volts with an input of 1 milliamp and a scram set point for the circuitry at 11 volts. The damaged amplifier had a maximum saturated output of approximately 8.4 vo!!s. Thus, at the maximum authorized steady state power of 1000 KW, Safety channel One would have indicated about 340 KW. Safety Channel Two and all other nuclear instrumentation would have performed properly.
II. Corrective Action The circuit board containing the damaged operational amplifier was replaced.
At that time, Safety Channel One was calibrated, fully operational, and capable of performing its intended function. Additionally, a relay requiring manual reset was installed in series with the console so that, in the event of a power outage, the console circuitry is more fully protected.
The electrical survey performed on 14 March, was repeated on 22 March 1980. This survey revealed that the electricians involved had inadvertently thrown a circuit breaker that provided power to the console. That circuit breaker has been more clearly marked to prevent the recurrence of that particular event.
III. Safety Review The damage done to Safety Channel One does not represent an unreviewed safety question and did not endanger the health and safety of AFRRI personnel or of the general public. The AFRRI Reactor and Radiation Facility Safety Committee will review this report at its next scheduled meeting.
8003280 6 3 .
_