ML062790084

2006 Annual Report for the AGN-201M Reactor, University of New Mexico

ML062790084
Person / Time
Site:	University of New Mexico
Issue date:	09/29/2006
From:	Busch R, Prinja A Univ of New Mexico
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML062790084 (4)

Text

The University of New Mexico Chemical & Nuclear Engineering MSCOI 1120 1 University of New Mexico Albuquerque, NM 87131-0001 September 29, 2006 Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Enclosed is the 2006 Annual Report for the AGN-201M reactor located at the University of New Mexico - Docket 50-252.

Sincerely, 2,YS Robert D. Busch, Ph.D, P.E. Anil K. Ptn, h.

Chief Reactor Supervisor Reactor Administrator cc: Document Control Desk, USARC AD 2,c) 209 Farris Engineering Bldg.

• 505-277-5431 0 FAX 505-277-5433

REPORT ON FACILITY LICENSE NO. R-102 THE UNIVERSITY OF NEW MEXICO JULY 1, 2005 - JUNE 30,2006 The University of New Mexico's AGN-201 M reactor was not used for some research during 2005-2006. There were no changes in facility design, performance characteristics, or operating pr6cedures related to reactor safety during the reporting period. The NRC did an on-site review of the facility in April 2006 and found no safety concerns or noncompliance issues.

The AGN-201M Reactor Facility is an essential part of our educational program, including public education, and continues to serve us well. The use of the reactor from July of 2005 through June of 2006 was as follows:

Type of Use July 05 - June 06 July 05 - June 06 Hours Watt-hours Class Demonstrations 0.0 0.0 Faculty Research 0.0 0.0 Graduate Student Research 0.0 0.0 Maintenance and Equipment Check 38.75 0.0 Operator Training and Requalification 11.95 32.5 Teaching . . 64.9 164.7 Totals for the Year 115. 6 197.2 During the annual maintenance in August 2005, we checked the detector cans and found all to be in good condition including the interim PVC container for Channel 1. We are working on a new can design that will allow replacement of all containers as needed. In December 2005, we installed a new polyethylene detector can for channel 1. The replacement of a PVC can with a poly can doubled the channel one count rate as expected (elimination of Cl absorption). All detector cans will be inspected again as part of the 2006 annual maintenance, and if the poly can holds up, the cans for Channels 2 and 3 will be replaced (A 50.59 review will be done at that time as these are safety channels).

AGN-201 05-06 Report, Page 3 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 Specifications. No new experiments were performed during the reporting period.

There were no 10 CFR 50.59 issues during the reporting period. During the reporting period, there was no liquid radioactive waste released from the facility nor was there any solid waste released. There were no environmental radiation surveys performed outside the facility. All personnel exposures received during the reporting period were below 50 mrem per person with the majority of personnel receiving below 5 mrem. No facility visitors received measurable exposures.

The current personnel assignments are:

Dean, College of Engineering Joseph Cecchi Chair, Department of Chemical and Nuclear Engineering Julia Fulghum Reactor Administrator Anil K. Prinja Chief Reactor Supervisor Robert D. Busch USNRC-licensed Senior Reactor Operators Robert D. Busch Ken Carpenter Gary Cooper USNRC-licensed Reactor Operators (inactive) David Hindera Eduardo Padilla The current makeup of the Reactor Safety Advisory Committee is:

James Bryson Ron Knief Robert Long Ted Schmidt Joseph Sholtis David Summers with no vacant position although Ted Schmidt has retired from Sandia and may soon be retiring from the committee. = I

4 AGN-201 05-06 Report, Page 4 The University of New Mexico's AGN-201M 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 Safety Advisory Committee.

Anil K. Pnja Reactor Administrator F Iii