ML20153C295

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Rept on Facility License R-102,Univ of Nm for Period 970701-980630. with
ML20153C295
Person / Time
Site: University of New Mexico
Issue date: 06/30/1998
From: Busch R, Roderick N
NEW MEXICO, UNIV. OF, ALBUQUERQUE, NM
To: Mendoca M
NRC (Affiliation Not Assigned)
References
NUDOCS 9809240050
Download: ML20153C295 (4)


Text

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The University of New Mexico

, Chemical & Nuclear Engineering 209 Farris Engineering Center Albuquerque, NM 87131-1341 September 17,1998 Telephone (505) 277-5431 FAX (505) 277-5433 Marvin M. Mendoca Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington D.C. 20555-0001 Dear Mr. Mendoca; Enclosed is the 1998 Annual Report for the AGN-20lM .eactor located at the University of New Mexico - Docket 50-252.

Sincerely, -

./ b Robert D. Busch, Ph.D, P.E. Norman F. Roderick, Ph.D.

Chief Reactor Supervisor Reactor Administrator cc: Document ControlDesk, USNRC l

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9009240050 900630 l PDR ADOCK 05000252 l

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REPORT ON FACILITY LICENSE NO. R-102

, THE UNIVERSITY OF NEW MEXICO

! JULY 1,1997 - JUNE 30,1998 l The University ofNew Mexico's AGN-20lM reactor was used for some research during the 1997-1998. This was a continuation of the research from the previous year and involved subcritical i

multiplication and die-away measurements at power level below I microWatt. There were no changes in facility design, performance characteristics, or operating procedures related to reactor safety during the reporting period. The NRC did an on-site review of the facility in September 1997 and found no major violations. There were some problems with documentation and the reactor operator re-qualification program. These have been corrected.

The AGN-20lM Reactor Facility is an essential part of our educational program, including j public education, and continues to serve us well. The use of the reactor from July of 1997 through June of 1998 was as follows:

Type of Use July 97 - June 98 July 97 - June 98 Hours Watt-hours Class Demonstrations 1.0 0.100 Faculty Research 18.5 8.577 Graduate Student Research 0.0 0.000 l

Maintenance and Equipment Check 20.2 0.000 Operator Training and Requalification 14.6 33.125 Teaching l 18.3 41.568 Totals for the Year 72.6 83.370 There were no unscheduled shutdowns during the reporting period. During checkout on March 25,1998, it was discovered that Channel 2, one of the 2 safety channels, was not operating properly. It was determined that the power supply had failed. A new power supply was ordered from the manufacturer and placed in the unit. The unit was checked for proper operation and the reactor was returned to operation on March 30,1998. During the five-day period from 3/25 through 3/30, the reactor was not operated and there was no impact on its safety during this time.

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1 AGN-20197-98 Report, Page 2 1

I There were no changes to the facility as it is described in the application for license and

amendments thereto, nor were there any changes to the procedures as described in Facility Technical i Specifications. No new experiments were performed during the reporting period. A new method of I testing the control rod scram times was used in November 1997. This technique used an infrared j sensing circuit on bench tests of rod scram times. The measured scram times ranged from 170 '

) milliseconds to 332 milliseconds which is well below the technical specification limit of I second. This method will be used in the future for continued verification of control rod scram times. I

There were no 10 CFR 50.59 issues during the reporting period. During the reporting period,  !

j there was no liquid radioactive waste released from the facility nor was there any solid waste released.  !

l There were no environmental radiation surveys performed outside the facility. All personnel 1

, exposures received during the reporting period were below 50 mrem per person with the majority of )

l personnel receiving below 5 mrem. No facility visitors received measurable exposures. I i

! The following personnel assignments for the reporting period are summarized below:

l Dean, College of Engineering Paul Fleury i

Chairman, Department of Chemical j and Nuclear Engineering Joseph Cecchi I

Reactor Administrator Norman F. Roderick -

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Chief Reactor Supervisor Robert D. Busch {

USNRC-licensed Senior )

Reactor Operators Robert D. Busch Ken Carpenter -

Gary Cooper

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AGN-20197-98 Report, Page 3 For the Reactor Safety Advisory Committee, Robert Long was added to the committee in August 1997 and R. Douglas O' Dell resigned his position in April 1998. There current makeup of the Reactor Safety Advisory Committee is:

Robert Jefferson Ron Knief Robert Long Ted Schmidt David Summers with one vacant position.

The University of New Mexico's AGN-20lM reactor continues to be used extensively for teaching experiments as a part of our undergraduate and graduate programs. These experiments include approach-to-critical, reactor period and reactivity measurements, importance functions measurements, sample activation, control rod calibrations, and reactor power and neutron fluence measurements. The reactor is also used throughout the Fall, Spring and Summer sessions of the University. All experiments have received prior approval from our Reactor Safeguards Advis ry Committee. ..

J Norman F. Roderick Reactor Administrator i

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