ML20092K276

Annual Operating Rept for 1983

ML20092K276
Person / Time
Site:	Idaho State University
Issue date:	12/31/1983
From:	Tanya Smith IDAHO STATE UNIV., POCATELLO, ID
To:	Thomas C Office of Nuclear Reactor Regulation
References
NUDOCS 8406280193
Download: ML20092K276 (4)

Text

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ANNUAL OPERATING REPORT 1983 Idaho State University AGN-201 Nuclear Reactor Pocatello, ID 83209

1) Brief Narrative of Changes There have been no changes in facility design, performance characteristics or operating procedures relating to reactor safety during calendar year, 1983 Major surveillance was performed during the period in accordance with the-Technical Specifications; the following is a summary of the results:

a) A visual inspection of the control rod drive mechanisms was satisfactory.

b) Scram drop times of all control rods were less than <

100 milliseconds.

c) Rod run-up times were measured and average reactivity insertion rates calculated. The maximum average reactivity insertion rate was. 034% per second for the course control rod.

d) Channel tests of all safety channels and interlocks have been satisfactory.

e) Power and period calibrations were performed and no significant changes from the previous calibration were found, f). The shield tank was inspected and no excessive corrosion or water leakage was apparent.

g) Shutdown margin was measured and found to be 1.92%

reactivity.

2) Monthly Tabulation of Reactor Operating Hours for 1983:

Month Hours Month Hours January 11.13 July 1.32 February 7.39 August 1.67

. March 8.58 September 8.99 April 10.54 October 6.62 May 0 November 7.38 June O December 1.20

-3) List of Unscheduled Shutdowns: None j 8406280193 831231 i PDR ADOCK 05000284 PDR \

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. '  ?

.. I 1 Annual Operating' Report f

.AGN-201-Nuclear Reactor l Page Two' ,

i 4); -Discussion of Major Safety Related Corrective Maintenance j On-March 28,'1983, instrument number 2 experienced the same  !

problem as instrument number-3 had (as was discussed in the last ,

' operating report). Instrument number 2 developed pin hole leaks in ,

'the aluminum housing containing the ion chamber, The housing '

was removed, repaired and re-installed.

, +

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 the facility Technical Specifications.

i .c) A'new experiment was performed with the AGN-201 reactor -

during the calendar. year, 1983 (See number 6 below.)  ;

6) Summary of Safety Evaluations

A computer controlled graphite rod was temporarily installed

-in instrument port' number 3. The experiment had been approved October 21,1983 by the Reactor Safety Committee when it was

-demonstrated thatt:

a) . Excess reactivity'of the deactor with the experiment installed would decrease 0.065.

b) The minimum period due to full rod insertion from critical was 48 seconds.

c) The control rod worth was 0.205.

d). The' average rate of_ reactivity insertion-for the control F rod was 0.0135 per second.

~

These all were well within the limits of operation as stated in the Technical Specifications. Thus, the Committee found that no unreviewed safety questions existed.

7) . Summary of Safety Evaluations Liquid Airborne Solid Curies Volume Curies Volume Curies Volume

0 0 0 0 0 0

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Annual Operating Report AGN-201 Nuclear Reactor Page Three

8) Summary of Radiological Surveys Outside the. Facility No environmental surveys have been performed outside the facility.

9) No person received greater than 100 millirem during this reporting period, and no person under 18 years of age received greater than 50 millirem.

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Idaho State University Pocatello, Idaho 83209 -0009 June 20, 1984 Cecil 0. Thomas, Chief Division of Licensing Standardization and Special Projects Branch Mail Stop 34D U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Thomas:

Attached is the Annual Operating Report for the Idaho State University AGN-201 Nuclear Reactor, License R-110, Docket No. 50-284, for the calendar year, 1983.

Respectfully submitted, s d& f fN. d Terry W. Smith Reactor Supervisor TWS:bgs CC: V. Charyulu, Dean, School of Engineering U.S. Nuclear Regulatory Commission C/0 Document Management Branch Washington,_DC 20555 I

ISU is An Equal Opportunity Employer l I