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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20216H7451998-03-12012 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 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 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 1998-03-12
[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
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- ARMED FORCES RADIO"lOLOGY RECEARCH INSTITUTE 8901 WISCONSIN AVENUE BETHESDA, MARYLAND 20889-6603 5106.6 9 March 1998 U.S. Nuclear Regulatory Commission Document Control Desk Washington,i)C 20555 Gentlemen:
Attached is the Licensee Event Report (LER) for the reportable event that occurred on 24 February 1998 at the AFRRI Reactor Facility, Docket Number 50-170, License Number R84. The event was telephonically reported on that day to appropriate NRC 00 ices. The event was investigated and corrective action was completed by 27 February 1998.
The point of contact for further information is Stephen Miller, Reactor Facility Director, at 301-295-9245.
Sincerely, f .
I R. E C LTC(P), MS, USA Director
Attachment:
As stated Copy to:
USNRC Region 1 Attn: Mr. Thomas Dragoun 475 Allendale Road King of Prussia, PA 19406-1415 [.,),
J I USNRC Attn: Mr. Marvin Mendonca Mail Stop 11B20 Washington, DC 20555 b!$fblllfllf$f5!lllll 9803230161 9003120i DR ADOCK 0500
Licensee Event Report for the l AFRRI TRIGA Reactor Facility Docket 50-170 Prepared by:
Robert George Stephen Miller Apprm'ed:
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ST 'N fMILLER Date i R or Fa:ility Director l i
Approved for Release:
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UT ROIfERT s
R. ENG ' ] Date An ,
LTC(P), MS, USA j l Director, AFRRI t
l Abstract A Senior Reactor Operator (SRO) unlocked the console and moved the reactor core assembly across the pool. The SRO then left the control room leaving the key unattended in the console. A few minutes later, the fire alarm sounded, the control room was locked, and the entire AFRR1 complex was evacuated. When the reactor staff returned at the conclusion of the fire alarm, the key was discovered in the console and removed. The SRO was reprimanded for failing to follow procedures, and the operators participated in a special training class on control of the reactor key and the importance of following procedures.
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Narrative Descrintion of the Event On 24 Feb 1998, an operator moved the reactor core across the pool and closed the lead shield doors to allow for an entry into exposure room 2 (ER2). The operator, then distracted while locating opening information and arranging the opening with the safety and health department, left the control room without removing the key from the console. The operator was then called down to the exposure room to deal with a lighting problem in ER2. Before the operator returned to the control room, the AFRRI fire alarm sounded and the building was evacuated. The control room was locked when the remaining staff left the reactor office area for the fire alarm. Upon completion of the fire alarm, approximately 50 minutes after the console was left unattended, the key was discovered and removed by a member of the reactor staff. The RFD was notified upon his return from the fire alarm. The event was considerri to be a reportable occurrence under the Reactor Technical Specification 6.1.3.2[a.3].
Assessment of Safetv Conscauences Non-licensed members of the staff are trained that they are not to manipulate the controls of the console without an SRO/RO's supervision. A review of the console's historical record (a computer recording of events occurring on the console) and chart recorders, which continuously record reactor power when the key is in the console, verified that the console had not changed power during the time the key was left unattended. Magnet power had not been activated for the core movement or during the time the console was unlocked and unattended. Magnet power is not required for movement of the reactor core and therefore had never bxn activated by the operator. Magnet power is required to bring the reactor to power.
Security of the console was not an issue during the time the key was Icft unattended. Access to AFRRI is controlled by security guards and an electronic card key system. Access to the reactor facility is controlled by an additional, independent card key system. Visitors allowed l
in to the reactor area are escorted by reactor staff. When the fire alarm sounded, the door to the control room was locked with a key and all personnel were evacuated from within AFRRI. All doors to the facility were kept locked to control access to the facility. ,
Description of Corrective Actions J
Facility management investigated the circumstances of the event, and concluded that an operator error occurred. The following actions were taken and completed by 27 February 1998,
- 1. The operator was reprimanded and cautioned that future failure to follow procedures would result in enhanced disciplinary action.
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- 2. All operators and trainees were required to attend a training class on the importance of maintaining control of the reactor key and following procedures.
Reference to Any Previous Similar Events A review of records found a similar incident in March 1993. A different operator in that incident was distracted by a phone call for information which was in his office next to the control room.
Point of Contact for Any Ouestions Points of contact for further information are Stephen Miller, Reactor Facility Director, 301-295-9245, or Robert George, Reactor Operations Supervisor, 301-295-1221.
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