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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20077B4731991-05-10010 May 1991
Ro:On 910507,operator Failed to Perform Surveillances & Channel Tests for All 6 Scram Channels & 2 Interlocks Prior to Reactor Operation.Caused by Personnel Error. Tailgate Meeting Held & Mods to Hardware Initiated
ML20212Q6971986-08-26026 August 1986
Ro:On 860821,during Prestartup,Source Interlock Operated But Failed to Prevent Movement of Control Rods.Caused by Temporary Loss of Electrical Contact in Logic Circuits. Movement Restored Proper Electrical Contact
ML20136H3291985-11-13013 November 1985
Ro:On 851112,wide-range Log Channel Malfunctioned During Operation of Reactor.Caused by Faulty Calibr Switch in Log Channel.Switch Adjusted & Reactor Operated at Several Power Levels Up to 95 Kw
ML20114B3221985-01-14014 January 1985
Ro:On 850107,while Taking Unit to 95 Kw Power,Period Meter Indicated Period Decreasing W/Log Power Trace Levelling & Linear Power Trace Rising.Caused by wide-range Log Channel Malfunction.Manual Scram Initiated & Reactor Secured
ML20101M8491984-12-10010 December 1984
Ro:On 841203,wide-range Log Channel Malfunctioned,Resulting in Manual Scram.Cause Traced to Resistor in Filter on Detector High Voltage Supply.Repairs & Testing in Progress
ML20065R4001982-10-20020 October 1982
Ro:On 821006,malfunction of Eberline AMS-3 Continuous Air Monitor Pump Caused Pump to Be Inoperable for Approx 1-h.No Loss of Significant Signals Indicated.Pump Repaired.Changes to Procedures or Equipment Under Review
ML20137G4501981-03-24024 March 1981
Ro:During walk-through of Operator Training Program, O-ring Seal of Filter Holder Found Not Seated Properly Causing Partial Bypass of Filter for Air Sucked Into instrument.Filter-in Lock Adjusted
ML20137G4461977-06-23023 June 1977
Ro:On 770621,radioactive Source Containing 200 Mci Cs-137 Recovered from Brine Well 33.Incident Described in
ML20137H3841976-01-12012 January 1976
Ro:On 760106,operator Left Console Key in Switch So That Reactor Not Secured Per Tech Specs.Key Withdrawn from Console.Incident Discussed W/Operators & Large Red Plastic Tag Attached to Key to Make It More Visible
ML20137G8161973-02-16016 February 1973
Ro:On 730125,available Excess Reactivity of Core Exceeded Tech Specs Limit.Caused by Change in Worth of Control Rods. Rearrangement of Core Configuration Initiated to Reduce Available Excess Reactivity
ML20137G7931971-11-22022 November 1971
Ro:On 711022,during Startup of Reactor,Period Limiting Signal Unavailable for Servo Sys Which Continued to Raise Rod Causing Rapid Rise of Power.While Reactor Manually Scrammed,Reactor Period Less than Min Allowed in Tech Specs
1991-05-10
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Category:TEXT-SAFETY REPORT
MONTHYEARML20205K3851998-12-31031 December 1998
Dow Triga Research Reactor Annual Rept for 1998. with
ML20203A1031998-02-11011 February 1998
Safety Evaluation Supporting Amend 8 to License R-108
ML20217P6341997-12-31031 December 1997
Dow Triga Research Reactor Annual Rept - 1997
ML20210R1221997-08-19019 August 1997
Safety Evaluation Supporting Amend 7 to License R-108
ML20137C5401996-12-31031 December 1996
Dow Triga Research Reactor Annual Rept - 1996
ML20101F2761995-12-31031 December 1995
Dow Triga Research Reactor Annual Rept - 1995
ML20081F1491994-12-31031 December 1994
Dow Triga Research Reactor Annual Rept-1994
ML20063G7291993-12-31031 December 1993
Dow Triga Research Reactor Annual Rept for 1993
ML20127B4661992-12-31031 December 1992
Dow Triga Research Reactor Annual Rept 1992
ML20141M0461991-12-31031 December 1991
Dow Triga Research Reactor Annual Rept - 1991
ML20077B4731991-05-10010 May 1991
Ro:On 910507,operator Failed to Perform Surveillances & Channel Tests for All 6 Scram Channels & 2 Interlocks Prior to Reactor Operation.Caused by Personnel Error. Tailgate Meeting Held & Mods to Hardware Initiated
ML20081M7561991-03-26026 March 1991
Dow Triga Research Reactor Annual Rept - 1991, Covering May - Dec 1990 Period
ML20062F7491990-11-19019 November 1990
Microprocessor-Based I&C Sys for Dow Triga Research Reactor
ML20081E0901990-06-30030 June 1990
Dow Triga Research Reactor Annual Rept - 1990
ML20006B6581990-01-19019 January 1990
Ro:On 900116,wide Range Log Channel Failed While Reactor Taken to Power.Caused by Poor Connection in Rotary Switch in Wide Range Log Channel.Authorization to Replace Entire Control Console Initiated in Early Jan 1990
ML19354D5871989-12-21021 December 1989
Ro:On 891220,wide Range Log Channel Failed While Reactor Was Being Taken to Power.Caused by Poor Connection in Rotary Switch in Log Channel.Switch Repaired & Reactor Returned to Operation
ML20246J5981989-04-30030 April 1989
Safety Evaluation Report Related to the Renewal of the Facility License for the Research Reactor at the Dow Chemical Company
ML20237L4561987-08-14014 August 1987
Dow Triga Research Reactor Requalification Program
ML20210S6051987-02-0909 February 1987
Revised Licensed Operator Requalification Program for Facility
ML20214C5491986-12-31031 December 1986
Dow Triga Research Reactor Requalification Program
ML20214C5411986-12-31031 December 1986
Dow Triga Research Reactor Environ Rept
ML20214C5351986-12-31031 December 1986
SAR for Dow Triga Research Reactor 300 Kw
ML20212Q6971986-08-26026 August 1986
Ro:On 860821,during Prestartup,Source Interlock Operated But Failed to Prevent Movement of Control Rods.Caused by Temporary Loss of Electrical Contact in Logic Circuits. Movement Restored Proper Electrical Contact
ML20214C5121985-12-31031 December 1985
Dow Chemical Co,1985 Annual Rept
ML20136H3291985-11-13013 November 1985
Ro:On 851112,wide-range Log Channel Malfunctioned During Operation of Reactor.Caused by Faulty Calibr Switch in Log Channel.Switch Adjusted & Reactor Operated at Several Power Levels Up to 95 Kw
ML20114B3221985-01-14014 January 1985
Ro:On 850107,while Taking Unit to 95 Kw Power,Period Meter Indicated Period Decreasing W/Log Power Trace Levelling & Linear Power Trace Rising.Caused by wide-range Log Channel Malfunction.Manual Scram Initiated & Reactor Secured
ML20101M8491984-12-10010 December 1984
Ro:On 841203,wide-range Log Channel Malfunctioned,Resulting in Manual Scram.Cause Traced to Resistor in Filter on Detector High Voltage Supply.Repairs & Testing in Progress
ML20065R4001982-10-20020 October 1982
Ro:On 821006,malfunction of Eberline AMS-3 Continuous Air Monitor Pump Caused Pump to Be Inoperable for Approx 1-h.No Loss of Significant Signals Indicated.Pump Repaired.Changes to Procedures or Equipment Under Review
ML20052E2361982-04-28028 April 1982
RO: on 820421,instructions Given to Disconnect Power Supply & Single Lead to Compensated Ion Chamber.Incident in Violation of Tech Specs Requiring Two Linear Safety Channels Operating While Reactor Is Operating
ML20137G4501981-03-24024 March 1981
Ro:During walk-through of Operator Training Program, O-ring Seal of Filter Holder Found Not Seated Properly Causing Partial Bypass of Filter for Air Sucked Into instrument.Filter-in Lock Adjusted
ML20137G4461977-06-23023 June 1977
Ro:On 770621,radioactive Source Containing 200 Mci Cs-137 Recovered from Brine Well 33.Incident Described in
ML20137H3841976-01-12012 January 1976
Ro:On 760106,operator Left Console Key in Switch So That Reactor Not Secured Per Tech Specs.Key Withdrawn from Console.Incident Discussed W/Operators & Large Red Plastic Tag Attached to Key to Make It More Visible
ML20137G8161973-02-16016 February 1973
Ro:On 730125,available Excess Reactivity of Core Exceeded Tech Specs Limit.Caused by Change in Worth of Control Rods. Rearrangement of Core Configuration Initiated to Reduce Available Excess Reactivity
ML20137G7931971-11-22022 November 1971
Ro:On 711022,during Startup of Reactor,Period Limiting Signal Unavailable for Servo Sys Which Continued to Raise Rod Causing Rapid Rise of Power.While Reactor Manually Scrammed,Reactor Period Less than Min Allowed in Tech Specs
1998-02-11
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DOW CHEMICAL U.S.A. hM August 26, 1986 MICHIGAN DIVISION MIDLAND,. MICHIGAN 48640 Mr. James C. Keppler U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 DOW TRIGA RESEARCH REACTOR, LICENSE R-108, DOCKET 55-264
Dear Mr. Keppler:
This letter reports an event which is described in section D.(1) of the operating license of the Dow TRIGA Research Reactor.
NUCLEAR SYSTEM: Source Interlock SAFETY FUNCTION: Prevent withdrawal of control elements with less than two neutron induced counts per second on the startup channel. '
CONDITION: During pre-startup checkout on Augut 21, 1986 the source interlock operated, given the proper signal, but failed to prevent the movement of the control
- rods.
The pre-startup checkout was halted while the operation of the interlock was reviewed. The interlock was reset and a signal was again provided which operated the source interlock. At this time the interlock did prevent the movement of the control rods. The interlock system was examined, relays and connections were removed and inspected, the system was returned to working order and was tested three times. At each time the proper interlock was achieved.
The failure was ascribed to a temporary loss of electrical contact in the logic circuits, which use plug-in relays. Subsequent inspection and movement restored the proper electrics.1 contacts and the system, af ter testing, was returned to service, mY
/,!Y , 1 8609080001 860826 PDR ADOCK 05000264 S PDR %
AUG 2 91986 I AN OPERATING UNIT of' THE DOW C#4EMICAL COMPANY
~
, h-i Mr. James C. Keppler U.S. Nuclear Regulatory Commission August 26, 1986 Page 2 A telephone report was made to the duty officer at llegion III on the afternoon of August 21, 1986.
Yours,
- G&) /6L C. W. Kocher Reactor Supervisor Analytical Laboratories 1602 Building cc: L. W. Rampy Chairman, Radiation Safety Committee The Dow Chemical Company 1803 Building Midland, MI 48674 D. L. Berry Chairman, Reactor Operations Committee The Dow Chemical Company 1602 Building Midland, MI 48674 i
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