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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Idaho State University ,
Pocatello, Idaho 83209-0009 College of Engineering t Box 8060 (2081 236 2902 June 5, 1990
-Ghar Snhou-L. g. uyss lJCk hY 11er-Division of Liter. sing Standardiention arnd-special=Ffo1Ects=Brw U.S.
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Nuclear Regulatory Commission
_m Washington -D.C. 20555 Dear Mr. "' _a 'I l
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 l
cc: V. Charyulu, Dean, College of, Engineering l U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C. 20555 4
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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.
l L 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.
l L 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.
1 proximately 110 watt-hours. The monthly breakdown of opera-
' tion time follows:
i-Month Hours Month Hours l January 13.7 July 0.8 February 14.9 August 5.0 l 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 i 3.. Unscheduled shutdowns Planned startups were delayed on three occasions (3/1, 4/12 1 1
& 6/27) due to weak and/or burned out tubes in channel 2.
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- 4. . 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 'I
.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 g The reactivity change associated with the fuel addition !
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. l i
The addition of 3 small fuel disks to the core was calcu-lated to produce a reactivity change of not greater than j L
+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.
l 7. - 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
l , 9. 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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