ML20043G587
| ML20043G587 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 12/31/1989 |
| From: | Leviskas D IDAHO STATE UNIV., POCATELLO, ID |
| To: | Weiss S NRC |
| References | |
| NUDOCS 9006200461 | |
| Download: ML20043G587 (3) | |
Text
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Box 8060 (2081 236 2902 June 5, 1990
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11er-Division of Liter. sing Standardiention arnd-special=Ffo1Ects=Brw U.S.
Nuclear Regulatory Commission
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_m Washington
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20555 Dear Mr. "'
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'I Attached is the Annual Operating Report for the Idaho State l
University AGN-201 Nuclear Reactor, License R-llo, Docket No. 50-284, for the calendar year 1989.
Respectfully submitted,
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1 David Levinskas Reactor Supervisor DL/ tar cc:
V. Charyulu, Dean, College of, Engineering U.S.
Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.
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.n ANNUAL OPERATING REPORT FOR 1989 1.
Brief Narrative of Changes a.
There were no'_ changes to the facility design, perfor-mance characteristics or operating procedures relating to reactor safety during this reporting period.
b.
Results of major. surveillance tests and inspections.
1)
Channel tests on all safety channels were per-formed and all scram interlocks-were tested and i
found to be satisfactory and within specification.
2)
Power and period calibrations were performed with satisfactory results, i
3)
The shield tank was inspected and no leaks or ex-cessive corrosion were noted.
4) a)
The control rod drive mechanisms were inspec-
,o ted and tested with. satisfactory results.
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b)
Scram times were measured and found to be less-than 130 milliseconds, c)
Control and safety rod worths and run up times were measured; from these values the reactivity-insertion rate was determined to i
be less than 0.045%'per second for any rod.
d)
The shutdown-margin was determined to be-greater than 2.1% with the most reactive rod fully inserted.
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2.-
The total operating time for the. reactor during 1989 was l
nearly 102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> with a total thermal energy output cf ap-1.
proximately 110 watt-hours.
The monthly breakdown of opera-1
' tion time follows:
i-Month Hours Month Hours l
January 13.7 July 0.8 February 14.9 August 5.0 March 11.9 September 11.8 1
April 11.4 October 12.9 L-May:
5.3 November 11.8 L'
June 0.5 December 1.6 3..
Unscheduled shutdowns Planned startups were delayed on three occasions (3/1, 4/12
& 6/27) due to weak and/or burned out tubes in channel 2.
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Safety.related maintenance-included the fol, lowing
- a.
Replacement of various tubes in channel 2 5.
Changes to the Facility a.-
There have been no changes to the facility as described in the application for license, b.
A novable' graphite plug was installed in an access port
- j replacing an existing stationary graphite plug. -Three
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.small fuel disks were added to the top polyethylene I
disk in the core.
The total amount of fuel material 1
added was 59.62-gm.
The fuel addition changed the j
amount of U-235 in the core from 670.24 gm to 672.93 j
gm.
j The reactivity change associated with the graphite plug i
installation was measured and found to be -0.09% A k/k.
l The reactivity change associated with the fuel addition g
was measured and found to be +0.10% ak/k.
The net change in the excess reactivity of the reactor was
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+0.01% Ak/k.
c.
No new or untried experiments or tests were performed j
during the reporting period.
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6.
-Summary of' Safety Evaluations.
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The addition of 3 small fuel disks to the core was calcu-lated to produce a reactivity change of not greater than j
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+0.12% Ak/k.
Thas, the expected-excess. reactivity of the j
reactor after the fuel addition was estimated to be less than 0.45% Ak/k, which would not exceed.the technical y
specification of +0.65% Ak/k.
l The installation of the movable graphite plug was expected i
to' result in a' reactivity change of -0.13% Ak/k.
The Reac-1 tor Safety Cemmittee found that no unresolved safety issues i
existed for either change and-authorized procedures to.in-stall the graphite plug rirst and'then perform the fuel i
addition.
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- No radioactive effluents were released.or discharged to the environment during 1989.
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8.
No person using the facility received'a whole body exposure f
of. greater than.50 millirem during 1989; f
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Neutron and beta / gamma radiation surveys performed on the i ',
exterior walls of the faci?'<y indicated that maximum com-bined contact radiation le, s were less than 2 mrem /hr.
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