|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20211C7951997-09-18018 September 1997 Ro:On 970916,reactor Staff Discovered That Intrusion Alarm Sys Was Not Tested for Operability During First Calendar Wk of Sept.Caused by Other Members Being on Leave or Alternate Duty.All Sys Tests Were Properly Documented ML20096C5351996-01-11011 January 1996 Ro:On 960104,Shim-2 Control Rod Stopped at 917 Units. Operator Went Out on Reactor Bridge to Check Rod.After Examining Rod,Operator Shook Barrel & Rod Fell Into Core. Reactor Remains in Shutdown Condition ML20082P0161991-09-0303 September 1991 Ro:On 910830 Analog scram-capable Safety Channel of Dow Triga Research Reactor Found to Be Not Operating During power-up Operation of Reactor.Caused by Broken Connection in high-voltage Cable for Neutron Detector.Broken Cable Fixed ML20082N6131991-08-30030 August 1991 RO:analog-capable Safety Channel of Reactor Inoperable During Reactor Operation.Caused by Broken Connection in High Voltage Cable for Neutron Detector.Reactor Shutdown & Secured ML20210B2751987-03-18018 March 1987 Ro:Holes Found in Aluminum Reactor Tank Line.Cause Unknown. Operations Suspended Until Extent of Problem & Solution Determined.Proposed Actions to Correct Problem Will Be Submitted Prior to Resuming Operations 1997-09-18
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20202E9081998-12-31031 December 1998 Geological Survey Triga Reactor Annual Rept for Period Jan- Dec 1998. with ML20206K7031998-12-31031 December 1998 Revised Us Geological Survey Triga Reactor Annual Rept,Jan- Dec 1998 ML20217A2151998-04-15015 April 1998 Safety Evaluation Supporting Amend 9 to License R-113 ML20216H7811998-03-16016 March 1998 Safety Evaluation Supporting Amend 8 to License R-113 ML20202H1471997-12-31031 December 1997 USGS Triga Reactor Annual Rept for Jan-Dec 1997 ML20247F8221997-12-31031 December 1997 Corrected Pages for 1997 Annual Rept of USGS Survey Triga Reactor Facility, Originally Submitted on 980202,IAW License Conditions ML20211C7951997-09-18018 September 1997 Ro:On 970916,reactor Staff Discovered That Intrusion Alarm Sys Was Not Tested for Operability During First Calendar Wk of Sept.Caused by Other Members Being on Leave or Alternate Duty.All Sys Tests Were Properly Documented ML20096C5351996-01-11011 January 1996 Ro:On 960104,Shim-2 Control Rod Stopped at 917 Units. Operator Went Out on Reactor Bridge to Check Rod.After Examining Rod,Operator Shook Barrel & Rod Fell Into Core. Reactor Remains in Shutdown Condition ML20096G1881995-12-31031 December 1995 USGS Triga Reactor Annual Rept for Jan-Dec 1995 ML20078A6451994-12-31031 December 1994 USGS Triga Reactor Annual Rept for 1994 ML20063C6501993-12-31031 December 1993 USGS Survey Triga Reactor Annual Rept for Jan-Dec 1993. W/ ML20127N4481992-12-31031 December 1992 USGS Triga Reactor Annual Rept for Jan-Dec 1992 ML20087F3971991-12-31031 December 1991 Us Geological Survey Triga Reactor Annual Rept 910101-1231 ML20082P0161991-09-0303 September 1991 Ro:On 910830 Analog scram-capable Safety Channel of Dow Triga Research Reactor Found to Be Not Operating During power-up Operation of Reactor.Caused by Broken Connection in high-voltage Cable for Neutron Detector.Broken Cable Fixed ML20082N6131991-08-30030 August 1991 RO:analog-capable Safety Channel of Reactor Inoperable During Reactor Operation.Caused by Broken Connection in High Voltage Cable for Neutron Detector.Reactor Shutdown & Secured ML20066K5821990-12-31031 December 1990 Corrected Annual Rept of USGS Triga Reactor Facility 1990 ML20066H8881990-12-31031 December 1990 Annual Rept of USGS Triga Reactor Facility 1990 ML20006A5611989-12-31031 December 1989 USGS Triga Reactor Annual Rept 1989. W/900118 Ltr ML20246F6621989-04-30030 April 1989 Reactor Operator Requalification Program,Usgs Triga Reactor ML20149E5581988-01-0404 January 1988 Safety Evaluation Supporting Amend 4 to License R-113 ML20150A7641987-12-31031 December 1987 USGS Triga Reactor Annual Rept,1987 ML20210B2751987-03-18018 March 1987 Ro:Holes Found in Aluminum Reactor Tank Line.Cause Unknown. Operations Suspended Until Extent of Problem & Solution Determined.Proposed Actions to Correct Problem Will Be Submitted Prior to Resuming Operations ML20210E4261986-12-31031 December 1986 USGS Triga Reactor Annual Rept for 1986 ML20137P4431985-12-31031 December 1985 Us Geological Survey Triga Reactor Annual Rept,1985 ML20079P6951983-12-31031 December 1983 Annual Operating Rept for 1983 ML20028G0771982-12-31031 December 1982 Annual Rept 1982. ML20040F5761981-12-31031 December 1981 Annual Rept 1981. ML20003A4871980-12-31031 December 1980 Annual Rept,Jan-Dec 1980. ML19296B3521979-12-31031 December 1979 Annual Operating Rept 1979 ML19250A8001979-10-10010 October 1979 Ro:On 791009,power Signal Was Lost About 60-s After Reactor Reached 1 MW Power Level.Reactor Immediately Shut Down. Caused by Moisture Shorting Signal Line Whose Coaxial Connector Was Lying in Water Near Reactor Tank ML19256A8441978-12-31031 December 1978 1978 Annual Rept for Triga Reactor.Prime Function Was to Provide Neutrons for Various Research Programs.Irradiations Were Also Done for Other Govt Agencies 1998-04-15
[Table view] |
Text
. _ _ . - -- _ .- -- ._ . - - - -
-. .-. - - . _ , . - - - ~ - - - - --
D ow U.S. A.
k h( l }
, o ,_ 2 1602 Building 3 September 1991 US Nuclear Regulatory Commission A'I*IN: Document Control Desk Washington DC 20555 DOW TRIGA RESEARCil REACTOR . DOCKET 50-274 EVENT The analog scram capable safety channel of the Dow TRIGA Research Reack>r was found to be not operating during a power up operation of the reactor at 1132 on 30 August 1991. This is a violation of the Technical Specifications, w hich require There shall be a minimum of one scrarn-capable analog safety channel (operating when the reactor is operating); and There shallle a minimum of two scram-capable safety channels operating w hen the reactor is .
operating.
During this event one independent scram-capable safety channel (digital) was operating. The reactor was under control and operating within spctified limits at all times.
The reactor was shut down and secured as soon as the taalfunction was noticed.
ANALOG S AFETY CilANNEl, The analog safety channel is one of two scram-capable safety channels which are used to control vid protect the operation of the reactor. The analog channel uses an uncompensated ion chamter outside the l reflector, and is intended to monitor the top two decmics of operating range. %c single range exten 1s to 100% of full power (full power is 300 kilowatts) and the present scram setting is 90% (270 kilowatts).
. The display legins to respond at the low end at a few percent of full range (atout 5 kilowatts). His channel is tot equipped with a source-level interlock.
CAUSE The loss of the safety channel information was caused by a broken connection in the high voltage cable for the neutron detector his cable shares an unprotected run at poolside under the grids that cover the -
pool, f
L t
9109100154 910903 l
g POR ADOCK 0S000274 ,
I 3 PDR $
i
\
- t. ,
RESIONSE The troken cable was repaired. 'Ihe neutron detector was evaluated at source level, through rnovernent of the neutron source, without opera ing the reactor. Other cables and connectors in the same area associated with .e safety channels were checked for physical sturdiness and continuity; all were found to be satisfactory The scram capability of the analog ciennel was confirmed and the reactor was operated at a power level sulliciently high to show that calitrations of the two scrarn capable channels agreed. The reactor was returned to service.
RECURRENCE The cables at poolside have been confined to a smaller area, to allow access to the poolside without disturbance of the cables. A covering device has teen ordered which will further protect the cables from stress or movement which could damage them.
All tractor operators have been informed of tids event. The operators and the Reactor Operations Committee (ROC) will review this event at the Septemler (necting of the ROC and will consider changes of equipment and surveillance procedures which could help prevent similar occurrences.
{,) w-- --
C. W. Kocher Reactor Supervisor i
.