ML20081M756
| ML20081M756 | |
| Person / Time | |
|---|---|
| Site: | Dow Chemical Company |
| Issue date: | 03/26/1991 |
| From: | Kocher C DOW CHEMICAL CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9107100106 | |
| Download: ML20081M756 (4) | |
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- 5\\f, Director Offico of Nuclear Reactor Regulation ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 DOW TRIGA REACTOR FACILITY - DOCKET NO. 50-264 The 1991 annual report for the Dow TRIGA I<osearch Reactor Facility is attached.
- YOurS, C/w K L C. W.
Kocher Reactor Supervisor Analytical Sciences (517)636-0304 dmp Attachment 9107100106 910326 POR ADOCK O'5000264
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v DOW TRIG A RESEARCil ill'. ACTOR ANNUAL REl' ORT.1991 This annual regort covers the perkxl of May 1990 through December 1990, a perk >d of eight mor.ths,in accordance with amendment 6 of license R.108. Subsequent annual reports will cover 12-month periods.
A.
Staff, Licenses, and Training The staff consists of five persons:
C. W. Kocher Senior Reactor Operator Reactor Supervir.or W. L. Rigot Senior Reactor Operator Assistant Reactor Supervisor T. J. Quinn Senior Reactor Operator M. E. Buchmann J. D. Romick Ilochmann and Romick are taking NRC examinations this week, secking instant SRO licenses. J.
j J. Carni has this week relinquished his license as SRO.
J Licenses of the SROs are current, with renewals expected in 1993 (Rigot and Quinn) and 1995 (Kocher). Medical examinations are current, with examinations scheduled for October 1991 (Quinn and Rigot) and April 1993 (Kocher).
The current two-year requalification program was started in the second quarter of 1990 and four sessions have been held. The SROs are current with operating experience and participation in hypothetical emergency drills, Reactor Operations Committee meetings and the annual fuel inventory.
The Reactor Operations Committee continues with five members:
J.J. llavel Facility Director C. W. Kocher Reactor Supervisor and Senior Reactor Operator S.W. Matey Radiation Safety Of0cer W. L. Rigot Senior Reactor Operator T.D.Lickly D.
Reactor Operat ng Experience i
During the period 5-190 through 12-31-90 the reactor was operated for about 5.2 megawatt hours, mostly at the maximum power level of 95 kilowatts. During that time there were about 163 (prations for the irradiation of samples and atout 160 operations for checkouts and training.
C.
Major Changes The Technical Specifications were changed (amendment #6 to the R.108 Operating License, December 1990) to allow the installation and use of a new control console and to change the required date of the Annual Report.
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%c reactor was shut down i12190 for the installation of the new console. %e control rod diives were returned to General Atomics to be rebuilt and upgtmled. He new comote was installed during the week of December 17-21,1990, under the direction of enginects f rom General Atomics. The instMlation was stcpw ise, starting with the old comote controlling the scram circuits in 6eries with the new console and changing out the old safety circuits for new ones one at a tirne he systern was shown to be operable on December 21 1990 and the old console was removed.
D.
Unscheduled Shutdowm During the period 1 May 1990 and 31 Decemter 1990 there were five unintentional shutdowns, four associated with the startup of the new console.
NUMilER DATE SCRAM REASON 1.
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% Power Operator error inattention during operation at 95 kilowatts - making entries in the log without being in the automatic imxic 2.
12-21 90 Rate Operator error - inattention at very low power during startup 3.
12 21 90 Rate Adjustment of detector at 80 kilowatts for calibration 4.
12 21 90 Rate Adjustment of calibrat.an circuits at about 100 watti 5.
12 21 90 Rate Adjustment of calibration at nhout 500 watts The four rate scrams that occurred during the first day of operation of the new console during the startup procedure do not irxlicate any need for modification of procedures. Unintentional scrams are expected to occur during the startup process and are expected to be greatly reduced in number after a period of testing and familiaritation.
E, Major Preventive and Corrective Maintenance The installation of the new console is expected to reduce the need for corrective mamtenance for the near future. Were were no other items of major mainten:mcc.
F.
Radioactive Elliuents The only radioactive material released to the environment from this facility is argon-41, which is produced from activation of the natural argon dissolved in the pool water, and which subse<1uently escapes from the pool into the reactor room and from there to the outside of the building, and from the natural argon present in the air used to transport samples from a laboratory into a tenninus in the core of the reactor.
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1ho aserage release af ter dilution or ditfusion is estinmied to le less than 25';i, of the allowed or recommended concentration.
G.
Radiadon Eyesures Radiadon exposures received by facility personnel and 5 isitors are monitored using film tudges tnd thermolwninescent detectors. No persons have received calosures approaching 25% of those allowed or ecommended in 10CI1t20.
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w C. W. Kocher Reactor Supervisor 26 March 1991 26 Mmh 1991 3
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