ML082740267
| ML082740267 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 09/18/2008 |
| From: | Busch R, Prinja A Univ of New Mexico |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AGN-201M | |
| Download: ML082740267 (4) | |
Text
The University of New Mexico Chemical & Nuclear Engineering MSC0I 1120 1 University of New Mexico Albuquerque, NM 87131-0001 September 18, 2008 Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Enclosed is the 2008 Annual Report for the AGN-201M reactor located at the University of New Mexico - Docket 50-252.
Sincerely, Robert D. Busch, Ph.D, P.E.
Chief Reactor Supervisor cc:
Cindy Montgomery Anil K Prminja, Ph.
Reactor Administrator 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, 2007 - JUNE 30, 2008 The University of New Mexico's AGN-201M reactor was not used for research during 2007-2008. 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 March 2008 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 2007 through June of 2008 was as follows:
Type of Use July 07 - June 08 July 07 - June 08 Hours Watt-hours Class Demonstrations 1.6 2.7 Faculty Research 0.0 0.0 Graduate Student Research 0.0 0.0 Maintenance and Equipment Check 53.8 0.0 Operator Training and Requalification 4.7 15.4 Teaching 114.4 260.0 Totals for the Year 174.5 278.1 During the annual maintenance in August 2007, we checked the detector cans and found the poly containers for Channel 1 and Channel 2 to be in good condition. We installed the poly replacement can for Channel 3. A 50.59 review of the can replacement was done and no safety issues were identified. Little change in current was ýnoted with the new polyethylene detector can for channel 3. The detector location in the water already provided adequate moderation so the additional moderation provided by the Poly can had minimal impact. All detector cans will be inspected again as part of the 2008 annual maintenance.
AGN-201 07-08 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, School of Engineering Chair, Department of Chemical and Nuclear Engineering Reactor Administrator Chief Reactor Supervisor USNRC-licensed Senior Reactor Operators License terminated Joseph Cecchi Julia Fulghum Anil K. Prinja Robert D. Busch Robert D. Busch Ken Carpenter Gary Cooper David Hindera The current makeup of the Reactor Safety Advisory Committee is:
James Bryson Ron Knief Robert Long Ted Schmidt David Summers with one vacant position as Joseph Sholtis resigned due to health reasons.
AGN-201 07-08 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 a d Summer sessions of the University. All experiments have received prior approval frowno/r Reactor Safety Advisory Committee.
" IIA.I//i Reactor Administrator