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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20203A1031998-02-11011 February 1998
Safety Evaluation Supporting Amend 8 to License R-108
ML20210R1221997-08-19019 August 1997
Safety Evaluation Supporting Amend 7 to License R-108
1998-02-11
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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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NUCLEAR REGULATORY COMMISSION WASHINoToN, D.C. 20665-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE NQJ 108 IliE.DOW CHEMICAL COMPANY DOCKET NO. 50-284 1.u INTAODUCTION By letter dated January 29,1998, as supplemented on February 2,1998, the Dow Chemical Company (Dow or licensee), submitted a request for amendment M the operating license for its TRIGA Mark i research reactor located in Midland, Michigan. The licensee requested that Appendix A of the license, Technical Specification; (TS) for the Dow TRIGA Research Reactor, be amended to increase the amount of time from 30 to 60 days that a temporane radiation monitor may be used in place of the area monitm 'AM).
2.0 EVALUATION TS 3.6, " Radiation Monitoring Systems," reads in part:
The Area Monitor IAM)(with readout meter and audible alarm) in the reactor room must be operating during operation of the reactor or when work is being done on or around the reactor core or experimental facilities. During short periods of repair to this monitor, not to exceed thirty days, reactor operations or work on or around the core or experimental facilit.'es ma/
continue while a portable gamma-sensitive ion chamber is utilized as a temporary substitute, provided that the substitute can be monitored by the reactor operator.
The licensee has requested that the period of time that the temporary monitor can be used be increased from 30 to 60 days. The licensee experienced a failure of the AM. Upon inspection, the instrument repair group suggested replacing the AM because it is more than 20 years old. On the basis of the estimated delivery date of the new AM, the licensee a
believes that the process c? evaluating the failed monitor, purchasing a replacement, and "
installing the replacement may exc3ed 30 days.
f The purpose of this TS is to provide flexibility to allow reactor operations to continue if ttw AM fails, but to limit the amount of time a portable instrument may be used as a replacement for the AM. This is to prevent the long-term or permanent substitution of portable instrumentation for hard-wired, fixed instrumentation. The licensee took I
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immadiate steps to replace the failed AM, but this experience has shown that 30 days is not a sufficient period for the purchase and installation of a replacement AM. The stafi concludes that allowing the use of a temporary instrument as s substitute for the AM for periods up to 60 days is not a long term or permanent use of the temporary instrumentation and that the licensee diligently pursued replacement of the AM. Therefore, the increase in the amount of time from 30 to CO days that a portable, gamma sensitive ion chamber can be used es a substitute for the AM is acceptable to the staff.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in th: insta9ation or use of a facility component lccated withir, the restricted area as defined in '.J CFR Part 20 or changes in inspection and surveillance requirements. The staff has determined that this amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents
' fiat may be relaased of f site, and no significant increase in individual or cumulative '
occupational radiation exposure. Accordiragly, this amendment meets the eligibility criteria for categorical exclusion stated in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.2?ib), no environmental impact statement or environmental assessment need be prepared in ennnection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, on the basis of the considerations diccussed above, that (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated, or create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangeied by the proposed activities; and (3) such activities will be conducted in corrpliance with the Commis aion's regulations, and the issuance of this amendment will not be inimical to the common defense and xecurity or the health and safety of the public.
Principal Contributor: A. Adams, Jr.
Date: February 11, 1998 9