RA)DIATION CEN TER October 24, 2000 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 Reference: Oregon State University TRIGA Reactor (OSTR), Docket No. 50-243, License No. R-106 In accordance with section 6.7.e of the OSTR Technical Specifications, we are hereby submitting the Oregon State University Radiation Center and TRIGA Reactor Annual OREGON Report for the period July 1, 1999 through June 30, 2000 Please note that we are also STATE using this letter of transmittal to send copies of the current report to Mr. Al Adams, UNIVERSITY OSTR Senior Project Manager, USNRC, Washington, DC. The 1999-2000 Annual Report continues the pattern established over the past few 100 Radiation Ccntcr years by including information about the entire Radiation Center rather than concentrat Corvallis, Oregon ing primarily on the reactor. Because the report addresses a number of different 97331-5903 interests, it is rather lengthy, but we have incorporated a short executive summary which highlights the Center's activities and accomplishments over the past year. The executive summary indicates that the Radiation Center has maintained its high degree of productivity this past year. We hope that you will find the current report to be informative and interesting. Should there be any questions, please let me know. Sincerely, Stephen E. Binney Director SEB :jms-J:AA Phetters N00\Rcletter Teleph otl C Enclosure 541.737.2341 Fax 541.737.0480 ý 09-0 USNRC -2- October 24, 2000 cc w/enclosure: Mr. Al Adams, Jr., Senior Project Manager, USNRC, MS 011 B20, Washington, DC 20555-0001 (1 copy) Mr. Craig Bassett, USNRC, 61 Forsyth St. SW, Ste. 23T85, Atlanta, GA 30303 (1 copy) Mr. Ledyard Marsh, USNRC, MS 012, Washington, DC 20555-0001 (1 copy) cc w/out enclosure: D. Stewart-Smith, Oregon Department of Energy J. F. Higginbotham, Chairman, OSTR Reactor Operations Committee A. D. Hall, OSTR Reactor Supervisor, OSU S. R. Reese, OSTR Reactor Administrator, OSU D. S. Pratt, Senior Health Physicist, OSU Oregon State University Radiation Center and TRIGA Reactor Annual Report July 1, 1999 - June 30, 2000 Annual Report of the Oregon State University Radiation Center and TRIGA Reactor July 1, 1999 - June 30, 2000 To satisfy the requirements of: A. U.S. Nuclear Regulatory Commission, License No. R-106 (Docket No. 50-243), Technical Specification 6.7(e). B. Task Order No. 3, under Subcontract No. C84-110499 (DE-AC07-76ER01953) for University Reactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc. C. Oregon Office of Energy, OOE Rule No. 345-030-010. Edited by: S. E. Binney, Director With contributions from: S. E. Binney, Director K. M. Brock, Health Physicist S. C. Campbell, Business Manager M. R. Conrady, Analytical Support Manager A. D. Hall, Reactor Supervisor R. A. Keen, Office Coordinator S. A. Menn, Assistant Health Physicist D. S. Pratt, Senior Health Physicist S. R_ Reese, Reactor Administrator L. J. Robinson, Word Processor E. G. Schiiftfort, Project Manager S. P. Smith, Scientific Instrument Technician J. M. Stueve, Office Coordinator G. M. Wachs, Senior Reactor Operator Submitted by: S. E. Binney Director, Radiation Center Radiation Center Oregon State University Corvallis, Oregon 97331-5903 Telephone: (541) 737-2341 Fax: (541) 737-0480 October 2000 Annual Report of the Oregon State University Radiation Center and TRIGA Reactor Table of Contents PART I - OVERVIEW A . A cknow ledgem ents ................................................... I-1 B . Executive Sum m ary ................................................... I-1 C . Introduction ......................................................... 1-2 D. Overview of the Radiation Center ........................................ 1-3 E. Summary of Environmental and Radiation Protection Data ..................... 1-5 1. Liquid Effluents Released .......................................... 1-5 2. Liquid Waste Generated and Transferred .............................. 1-5 3. Airborne Effluents Released ........................................ 1-6 4. Solid W aste Released ............................................. 1-6 5. Radiation Exposure Received by Personnel ............................ 1-7 6. Number of Routine Onsite and Offsite Monitoring Measurements and Sam ples .................................................... 1-8 F . History ............................................................. 1-9 PART H - PEOPLE A. Professional and Research Faculty ........................................ II-1 B. Visiting Scientists and Special Trainees .................................... 1-6 C. OSU Graduate Students ................................................ 11-6 D. Business, Administrative and Clerical Staff ................................. 11-7 E. Reactor Operations Staff ............................................... 1 -7 F. Radiation Protection Staff .............................................. 11-7 G. Scientific Support Staff ................................................ 11-8 H. OSU Radiation Safety Office Staff ....................................... 11-8 I. Com m ittees ......................................................... 1 -8 1. Reactor Operations Committee ...................................... 11-8 2. Radiation Safety Committee ........................................ 11-9 3. Radiation Center Safety Committee .................................. 11-9 I - - PART II - FACILITIES Page A. Research Reactor.................................................111-1 . D escription .................................................... III-1 2. U tilization .. .................................................. 111-2 a. Instruction... ............................................. 111-2 b. R esearch .. .............................................. 11 I-3 B. Analytical Equipment.............................................. 111-3 1.. Description ... .............................................. 111-3 2. U tilization .. .................................................. 111-3 C. Radioisotope Irradiation Sources ........................................ M1-4 1. D escription .. ................................................. 111 4 2 . Utilization ..................................................... I -4 D. Laboratories and Classrooms ........................................... 111-4 1. D escription .................................................... 111-4 2. Utilization ................................................. 111-5 E. Instrument Repair and Calibration Facility ............................... -5 1. D escription .................................................... r I -5 2. U tilization ..................................................... 111-5 F . L ibraries .......................................................... 111-6 I1. D escription .................................................... I1 -6 2. U tilization ..................................................... 111-7 PART IV - REACTOR A . Operating Statistics .................................................. IV-1 B. Experim ents Perform ed ............................................... IV-1 1. Approved Experim ents ........................................... IV-1 2. Inactive Experim ents ............................................ IV-2 C. Unplanned Shutdowns ................................................ IV-3 D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59 .................... IV-3 1. 10 CFR 50.59 Changes to the Reactor Facility ......................... IV-3 2. 10 CFR 50.59 Changes to Reactor Procedures ........................ IV-10 3. 10 CFR 50.59 Changes to Reactor Experiments ....................... IV- 1I E. Surveillance and M aintenance ......................................... IV- 1I 1. Non-Routine M aintenance ....................................... IV-1 1 2. Routine Surveillance and Maintenance .............................. IV-13 F. Reportable Occurrences .............................................. IV-13 Peag PART V - PROTECTION A . Introduction ......................................................... V -1 B. Environm ental Releases ................................................ V-1 1. Liquid Effluents Released .......................................... V-2 2. Airborne Effluents Released ........................................ V-2 3. Solid W aste Released ............................................. V-3 C . Personnel D oses ...................................................... V-3 D . Facility Survey D ata .................................................. V-4 1. Area Radiation Dosim eters ......................................... V-5 2. Routine Radiation and Contamination Surveys .......................... V-5 E. Environmental Survey Data ............................................. V-6 1. Gamma Radiation Monitoring ....................................... V-6 2. Soil, W ater, and Vegetation Surveys .................................. V-7 F. Radioactive M aterial Shipments .......................................... V-8 G . References .......................................................... V -9 PART VI - WORK A . Summ ary .......................................................... V I-1 B. Teaching ...... ................................................. VI-1 C. Research and Service ................................................. VI-1 1. Neutron Activation Analysis ....................................... VI-2 2. Forensic Studies ................................................ V I-2 3. Irradiations ................................................