ML20054F156
| ML20054F156 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 05/24/1982 |
| From: | IOWA STATE UNIV., AMES, IA |
| To: | |
| Shared Package | |
| ML20054F155 | List: |
| References | |
| NUDOCS 8206150265 | |
| Download: ML20054F156 (3) | |
Text
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ANNUAL OPERATING REPORT 1981 Idaho State University AGN-201 Nuclear Reactor Pocatello, Idaho 83209
- 1) Brief Narrative Summary of Changes -
There have been no changes in facility design, performance characteristics or operating procedures relating to reactor safety during calendar year 1981.
Major surveillance was performed during the period in accordance with the. Technical Specifications; the following is a summary of the results:
- a. Visual inspection of the control rod drive mechanisms satisfactory,
- b. Scram drop times of all control rods less than 95 milliseconds.
- c. Rod run up times were measured and average reactivity insertion rates calculated and were less than .035% 4K/K per second.
- d. Channel tests of all safety channels and interlocks have been satisfactory.
- e. Power and period calibrations were performed on the instruments and no significant change from the previous calibration was found.
- f. The shield tank was visually inspected and no excessive corrosion or water leakage was apparent.
- 2) Monthly Tabulation of Reactor Operating Hours for 1981.
Month Hours Month Hours January 6.25 July 0 February 7.66 August 0 March 5.84 September 3.79 April 7.51 October 3.25 May 4.19 November 1.65 June 1.35 December 2.97
- 3) List of Unscheduled Shutdowns:
11/3/81 due to Channel #2 malfunction (see item 4).
1 8206150265 820524 PDR ADOCK 05000284 R PDR
Annual Operating Report ISU AGN-201 Nuclear React'or Page 2
- 4) Discussion of Major Safety Related Corrective Maintenance On November 3, 1981 power instrument No. 2, period trip, No. 2, ca 1.5 x 10-gsed ampsa and scram the' hen power period instrument meter indicated#3greater indicated than 30 seconds. At this point Channel #2 power instrument lagged approximately 1 decade behind Channel #3.
Upon investigation of Channel #2 instrument it was found that the period meter indicated 4 seconds when Channel #2 instrument was in the 10-7 amp calibrate position. This was caused by a 25 volt peak to peak AC signal, 120 hz, at the sensing capacitor. The full wave bridge rectifier which' feeds the sensing diode filament was found faulty. The full wave bridge rectifier, zoner diode, capacitor and transistor in the circuit were replaced. The instrument was then checked out and calibrated satisfactorily.
- 5) Changes to the Facility a) There have been no changes to the facility as described in the application for license.
b) There have been no changes to the procedures as described in facility technical specifications.
c) Two new experiments were successfully conducted. The first was a sample transfer by pneumatic tube for irradiation. The second was a micro. computer controlled data acquisition system for the AGN-201 reactor.
- 6) The sample transfer by pneumatic tube experiment was approved February 19, 1981 by the Reactor Safety Committee. The reactivity addition of the tube and sample holder was measured and the reactivity of the sample is calculated or measured before insertion. This determines the maximum power level of l the reactor for sample insertion. It was concluded that no unreviewed safety question exists.
The installation of a data logger system on the AGN-201 reactor was considered and approved September 3, 1981. It was noted that there are presently no standards that apply to the control and instrumentation systems of small training
- reactors. It was found however that the data logger system
( did conform to the IEEE standards for power reactors. It was concluded that no unreviewed safety question existed, l
l l
1
Annual Operating Report ISU AGN-201 Nuclear Reactor Page 3
- 7) Summary of Radioactivo Effluents Released or Discharged to the Environment:
Liquid Airborne Solid Curies Volume Curios Volume Curies Volume 0 0 0 0 0 0
- 8) Summary of Radiological Surveys Outside the Facility None (9 Radiation Exposure No person roccived greater than 50 millirem during this reporting period.