|
---|
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. ML19338E8641980-10-0303 October 1980 Eia Data for AFRRI-TRIGA Reactor. ML19338E8531980-10-0303 October 1980 Reactor Operator Requalification Program. ML19345C8661980-09-18018 September 1980 Section VI Safety Analysis of Fsar. ML19338E8501980-09-18018 September 1980 Safety Analysis of Hazard Summary Rept,Chapter 6 to 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
. __ . _ __ . _ ._ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _
, j
.q ' y ,
~'
[ '
~
DEFENSE NUCLEAR AGENCY ]
^ l f -
ARMoo PoRCes RAoloeloLoGY RossARcM WsrlTUTs l
- esrMesca,MARYLANo 20s14 s41s G,
Memorandum 23 March 1988 ,
LICENSEE' EVENT REPORT (LER)
Abstract: The- Reactor room primary Continuous Air Monitor (CAM) was accidently left in TEST mode during the reactor operations on 29 February 1988. Two sets of corrective action were taken to p prevent reoccurance. One was to instruct the Safety and Health p Department staff to be more attentive to their routine mr.intenance -
on the Reactor CAMS. The second was the installation of a l flashing visual light on the reactor auxiliary instrumentation console in the control room. This flashing light is illuminated by a signal from the Primary Reactor Room CAM when the TEST circuit is -
activated. This will alert the operator when the CAM is in TEST mode. >
l, Cire==tances surroundina the event - 29 February 1988:
0640 Startup checklist ' completed, all required systems are operable.
0434 Console locked by reactor operator after two experimental runs; reactor i operator proceeded downstairs for an Exposure Room opening.
0845 Routine maintenance of reactor CAM's in-progress by a member of the -
Safety Reactorand RoomHealth.
Primary Department CAM was place (SHD)d into TEST mode by a memberDurin of SHD, a non-licensed individual, and was accidently left in TEST mode upon completion of the routine maintenance (SHD routinely performs the maintenance of all CAM's in the Reactor Facility).
0921 Reactor operator returned to the control room to continue with the experimental runs; the reactor operator did not know that the SHD member had performed a daily check on the CAM, and that the CAM had been accidently left in TEST mode.
The reactor operations for the day, after 0921, included a series of one minute-runs at low power of 1 Kw (five runs total), and a series of medium power pulses between 82.05 and 82.15 step reactivity insertions. During the pulse mode operations in the afternoon, the reactor operator on console first noticed above normal CAM readings on the readout meter in the control room, but attributed y these above normal readings to those levels which are expected for medium power pulse operations.
At 1521, while doing the Shutdown chxklist, the reactor operator printed out an hourly report from the Stack Gas Monitor, which is adjacent to the CAM on the Reactor deck. The Reactor Operatoc then noticed that the tracing on the strip chart on the CAM was not commensurate with the operations conducted 9003060216 900222 PDR ADOCK 05000170 S PDR 75
. , 7.. y ,
4 a
j Memorandum 23 March 1988 Page 2 I during the day; the CAM trace on the CAM chart recorder was a straight line trace as would be expected from a test ' input signal, instead of a fluctuating trace
- as would be expected from a series of medium power pulse operations. Upon further inspection, it was discovered that the CAM was in TEST mode and had been accidently left in TEST mode by the SHD member upon completion of routine maintenance that morning. l This event was due to a Safety and Health Department staff member not following the proper procedures to turn the CAM back to the OPERATE mode after completion of routine maintenance on the CAM. In. addition, due to the type of l cperations performed that day, the reactor control room CAM Readout Monitor l
levels appeared approximately correct when observed by the Reactor Operator.
This was particularly significant as the. Startup Checklist was completed earlier that morning, ensuring that all required instruments were operable.
The event was reported to the Reactor Facility Director, who notified the USNRC telephonically, the following morning. .
Probable consecuences:
f I- Leaving the CAM in the TEST mode during reactor operations would not ensbie the reactor ventilation system to be automatically secured via closure dampers by a signal from the CAM If the high alarm setpoint had ben reached. However, ,
manual closure of the dampers would occur if initiated by operator action. The ,
reactor operations during the day of the incident consisted of a series of short, low power experimental runs and a series of medium power pulses, and thus any L release of airborne radioactivity would have' been unlikely. In addition, none of L the Reactor Room Radiation Area Monitors (R1, R2, RS, R5) nor the Reactor Stack Gas Monitor registered any above normal ~ readings, consistent with the l reactor operations throughout the day. The Reactor Stack roughing and HEP A filter systems were functional throughout the day and were capable of performing mitigation had a release occurred. Based on the above, there w :o radiation releases due to the incident and no adverse effects on the faciuy.
Hatus of corrective action - 1 March 1988:
L L The' event was reported by the Reactor Facility Director to the USNRC, Region 1 (Curtis Cowsill) by telephone at 1130.
(- Two sets of corrective actions were taken to prevent recurrence. The first was to
) instruct the SHD staff to be more attenti e to their routine maintenance on the f Reactor CAMS. The second was the installation of a flashing visual light on the
! reactor auxiliary instrumentation console in the control room. This flashing light is illuminated by a signal from the primary Reactor Room CAM when the TEST circuit -is activated. This alerts the reactor operator when the CAM is in TEST mode.
l u
j i
- 1 .
4 Memorandum 23 March 1988 Page 3 "
I s
Reference:
There have been no previous similar events at this' Facility.
' Point of
Contact:
Reactor Facility- Director, M. L. Moore (202) 295-1290.
t '
George' ing,III '
( Colone , AF, BSC Directo
l-l l
l l
_.__.: _1..._._..____ ._ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __