ML20236C230
| ML20236C230 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 06/30/1987 |
| From: | Hendrickson R IOWA STATE UNIV., AMES, IA |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8707290377 | |
| Download: ML20236C230 (4) | |
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ANNUAL OPERATIONS REPORT
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for the l
Iowa State University UTR-10 Docket No. 50-116 July 1,1986 -- June 30,1987 This is a routine operations report to the Nuclear Regulatory Commission in l
accordance with Operating License R-59, Appendix A, Technical Specibcations, Section 6.6.
1.
Summary of reactor coeratino excerfence includino the eneroy oroduced by the reactor:
As in previous years, the operation of the reactor continues to support the teaching and research programs of the Department of Nuclear Engineering. Three
. different courses, required for all sophomores and juniors, proviced hands-on laboratory experierice and sample irradiation services during during fall and spring semesters. A graduate-level course that used the reactor extensively was offered in the fall.
The reactor availability was 100% for scheduled class periocs during the fall and spring semesters.
During the reporting period, a total of 215 kilowatt-hours of energy preduction and 307 hours0.00355 days <br />0.0853 hours <br />5.076058e-4 weeks <br />1.168135e-4 months <br /> of operation were recorded. A percentage breakdown by operations categories is shown below:
Research Teaching Maintenance Operator Service Grad-U grad Training Energy (%)
1 4
72 8
15 0
Tirne (%)
1 10 44 9
36 0
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l 2.
Unscheduled Mutdowns includino, where acolicable, corrective action j
taken to preclude recurrence:
There were eight unscheduled shutdowns during the reporting period.
o Three automatic scrams occured (Aug 13,1986, Sep 11,1986, and Oct 23, 1986) when there were brief AC power losses to the building.
Annual Operations Report for R-59... Page 1
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Two automatic scrams occured (Aug 21,'1986 and Nov 25, 1986) when the operator selected the automatic power controller switch. All scram i
annunciators were illuminated; this was illogical. The cause(s) are l
unknown. The auto controller continues to be used routinely.
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o An automatic scram occured on Nov 20,1986, due to unknown cause(s)
I while the reactor was being brought to critical. The annunciator board showed three diHerent scram conditions which were all discounted as illogical.
o A high voltage loss (to the neutron detectors) scram on the left-hand wide range instrument drawer was initiated by a brief, inadvertent i
shorting across the auxiliary output connector of the power supply on Sep li,1986. Administrative controls have been applied to prevent recurrence.
o On Jun 3,1987, reactor operation was terminated by manual scram at about 50% power when the operator noted the linear power (safety 1
channel) signal on the right-hand instrument drawer was down-scale on the panelindicator. The cause was traced to dirty contacts in an Operate-Calibrate switch that was used during the precritical checkout to calibrate the log and linear _ power channels; the switch was not making good contact in the operate position.' A Special Report was submitted to NRC on Jun 17,1987, concerning this event.
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Major preventive and corrective maintenance operations havino safety
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significant _e1 There were no major preventive or corrective maintenance operations with safety significance.
4.
Major chanaes in the reactor facility and procedures, and new tests or l
experiments, or both, that are significantly different from those performed oreviously and are not described in the Safety Analysi,3, Reoort,includino conclusions that no unreviewed safety ouestions were involved:
There were no major changes in the facility, procedures, tests, or experiments.
5.
Summary of the nature and amount of radioactive effluents released or discharaed to the environs beyond the effective control of the University as determined at or before the coint of such release or discharce. (Included, to the extent practical, are estimates of individual radionuclides cresent in the effluenh If the estimated averaae release af ter dilution or diHusion if ess than 25 oercent of the concentration l
allowed or recommended, a statement to this effect is used):
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Argon-41: The technical specification limits on release of this radionuclides '
into the environs are based on weekly (up to 100 kWh) and annual (up to 4760 kWh) energy production of the reactor. The operating records show that less than 25%
of the concentration allowed was released to the environs.
Others: No measurable amounts of other radioactive effluents were released i
to the environs.
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6.
Summarized resulta of any environmental surveys cerformed outside the facility:
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No environmental surveys outside the facility were required to be performed since the trigger level, based on surveys inside the facility, was not exceeded.
7.
Summary of exoosures received by facility personnel and visitors where such exposures are areater than 25 percent of that allowed or recommended:
I No f acility personnel or visitors had exposures greater than 25 percent of
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that allowed or recommended.
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j Annuai Operations Report for R-59... Page 3
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-e-Department of Nuclear Engineering
. 261 Sweeney Hall
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Telephone 515-294-5NO :
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'Ref: 10 CFR 50.71(a)-
' July 24,1987 Doc'Ket N'o. 50-116 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk -
Washington, DC 20555
Dear Sir:
Enclosed with this letter is the Annual Operations Report for the Iowa State UTR-10 research reactor. The period covered is from July 1,1986' to June 30, 1987.
Sincerely, Richard A. Hendrickson Ll Reactor Manager j
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Enclosure
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C: Administrator, US.NRC, Region III.
L. E. Burkhart, Chm, Radiation Safety Comm.
R. A. Danofsky, Chm, Reactor Use Comm. =
E. E. Sobottka, Dir Environmental Health & Safety Department B. I. Spinrad, Chm,' Nuclear Engineering Department-1
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