ML052770542

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2005 Annual Report for the University of New Mexico AGN-201M Reactor
ML052770542
Person / Time
Site: University of New Mexico
Issue date: 09/29/2005
From: Busch R, Prinja A
Univ of New Mexico
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML052770542 (4)


Text

The University of New Mexico Chemical & Nuclear Engineering MSCOI 1120 I University of New Mexico Albuquerque, NM 87131-0001 September 29, 2005 Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Enclosed is the 2005 Annual Report for the AGN-201 M reactor located at the University of New Mexico - Docket 50-252.

Sincerely, Robert D. Busch, Ph.D, P.E. Anil K. Ph.D.

Chief Reactor Supervisor Reactor Admi nistrator cc: Document Control Desk, USNRC C)0o 209 Farris Engineering Bldg.

  • 505-277-5431
  • FAX 505-277-5433

REPORT ON FACILITY LICENSE NO. R-102 THE UNIVERSITY OF NEW MEXICO JULY 1. 2004 - JUNE 30,2005 The University of New Mexico's AGN-201 M reactor was used for some research during 2004-2005. This was a continuation of the research from the previous year and involved subcritical multiplication and die-away measurements at power levels 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 July 2004 and found no safety concerns or noncompliance issues.

The AGN-201 M 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 2004 through June of 2005 was as follows:

Type of Use July 04 - June 05 July 04 - June 05 Hours Watt-hours Class Demonstrations 2.4 6.7 1I Faculty Research 3.1 1.7 Graduate Student Research 0.0 0.0 Maintenance and Equipment Check 12.5 0.0 Operator Training and Requalification 18.2 50.6 Teaching 86.5 173.8 Totals for the Year 110.1 232.8 During the annual maintenance in August 2004. 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. All detector cans will be inspected again as part of the 2005 annual maintenance.

AGN-201 01-05 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 Smrem. No facility visitors received measurable exposures.

In April 2005. six undergraduate students took the NRC licensing exam and three passed, receiving their Reactor Operator licenses. 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 Daniel Casey 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.

AGN-201 01-05 Report, Page 4 The University of New Mexico's AGN-201 M 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. Prinja Reactor Administrator