ML20155E812: Difference between revisions
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I LIST OF FIGURES g | |||
5 Figure Title Page I.D.1 Floor Plan of the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-11 l III.A.1 Cutaway View of Standard TRIGA Mark II Core Arrangement . . . . . . . III-19 III.A.2 Horizontal Section of TRIGA Mark II Reactor . . . . . . . . . . . . . . . . . . . . III-20 III.A.3 Vertical Section of TRIGA Mark II Reactor . . . . . . . . . . . . . . . . . . . . . . . III-21 J | |||
III.C.1 Gammacell 220 "Co Irradiator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-22 IV.A.1 OSTR Annual Energy Production vs. Time (Annual Reporting Period) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-26 IV.E.1 Monthly Surveillance and Maintenance (Sample Form) . . . . . . . . . . . . . IV-30 IV.E.2 Quarterly Surveillance and Maintenance (Sample Form) . . . . . . . . . . . . . IV-31 IV.E.3 Semi-Annual Surveillance and Maintenance (Sample Form) . . . . . . . . . . IV-33 IV.E.4 Annual Surveillance and Maintenance (Sample Form) . . . . . . . . . . . . . . IV-35 V.D.1 TRIGA Facility and Radiation Center Area Dosimeter Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-2 7 I V.E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence . . . . . . . . . . . . . . . . . . . . . . . . . . V-28 V.E.2 Monitoring Stations for the OSU TRIGA Reactor . . . . . . . . . . . . . . . . . . V-29 I | |||
I l | |||
i Anturl Report cf the l Oreg:n St:te University Radiation Center and TRIGA Reactor l July 1,1997 -June 30,1998 l 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-AC07-76ERO1953) for University Reactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc. | |||
4 C. Oregon Office of Energy, OOE Rule No. 345-030-010. | |||
Edited by: | |||
S. E. Binney, Director With contributions from: | |||
K. M. Brock, Health Physicist D. R. Carver, Radiation Protection Technologist M. R. Conrady, Analytical Support Manager D.K. Dalton, Administrative Assistant B. Dodd, Director A. D. Hall, Reactor Supervisor J. F. Higginbotham, Reactor Administrator L. M. James, Office Specialist ' | |||
R. A. Keen, Office Coordinator D. S. Pratt, Senior Health Physicist L. J. Robinson, Word Processor S. P. Smith, Scientific Instrument Technician E. G. Schotfort, Project Manager D. C. West, Office Specialist 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 1998 | |||
_--_ __ _ J | |||
I I | |||
.g Annual Report of the l | |||
.E Oregon State University Radiation Center and TRIGA Reactor l Table of Contents b | |||
PART I- OVERVIEW I A. | |||
B. | |||
Acknowledgements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-l Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 1 l | |||
C. In trod ucti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-2 D. | |||
-l E. | |||
Overview of the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-3 Summary of OSTR Environmental and Radiation Protection Data . . . . . . . . . . . . . . . . . I-5 | |||
: 1. Liquid Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 5 | |||
; 2. Liquid Waste Generated and Transferred . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-5 | |||
: 3. Airborne Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 ig 4. Solid Waste Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-6 E 5. Radiation Exposure Received by Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-7 | |||
: 6. Number of Routine Onsite and Offsite Monitoring Measurements and Samp l es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I- 8 F. Hi sto ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-9 I PART II- PEOPLE A. Fac ul ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II - l B. Visiting Scientists and Special Trainees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-6 C. OSU Graduate S tudents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-7 D. Business, Administrative and Clerical Staff. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-8 E. Reactor Operations Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-8 F. Radiation Protection Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-8 G. Scientific Support Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-9 H. OSU Radiation Safety Office Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-9 lI I. Co mmittees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-9 | |||
: 1. Reactor Operations Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | |||
l . . . . . . . II-9 l 2. Radiation Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-10 | |||
: 3. Radiation Center Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-10 I | |||
PART III- FACILITIES | |||
= I A. Research Reactor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- l | |||
: 1. Descriptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- l | |||
: 2. Utilization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-2 | |||
: a. Instructio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-2 l | |||
: b. Research . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-3 g B. Analytical Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-3 g | |||
: 1. Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-3 | |||
: 2. U tilization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 C. Radioisotope Irradiation Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 | |||
: 1. Descriptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 D. | |||
: 2. Utilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 Laboratories and Classrooms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 l | |||
: 1. Desc ription . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 | |||
: 2. Utilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-5 E. Instrument Repair and Calibration Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6 | |||
: 1. D escripti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6 E | |||
: 2. U tilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6 m G. Li braries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6 | |||
: 1. Desc riptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6 | |||
: 2. Utilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H I-7 PART IV - REACTOR A. Operating S tatistics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-1 B. Experiments Performed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV- 1 | |||
: 1. Approved Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV- 1 | |||
: 2. Inactive Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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-4 | |||
: 2. 10 CFR 50.59 Changes to Reactor Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . IV-9 | |||
: 3. 10 CFR 50.59 Changes to Reactor Experiments . . . . . . . . . . . . . . . . . . . . . . . . IV-16 i E. Surveillance and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-17 | |||
: 1. Non-Routine Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-17 | |||
: 2. Routine Surveillance and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-18 F. Reportable Occurrences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-18 , | |||
1 1 | |||
1 P.m PART V- PROTECTION A. Introd ucti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V- 1 B. | |||
i Environmental Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-1 | |||
: 1. Liquid Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-2 2. | |||
Airborne Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-2 3. | |||
l C. | |||
Solid Waste Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-3 Personnel Doses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-3 D. Facility S urvey Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-4 1. | |||
Area Radiation Dosimeters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-5 | |||
: 2. Routine Radiation and Contamination Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . V-5 E. Environmental Survey Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-6 I 1. Gamma Radiation Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-6 | |||
: 2. Soil, Water, and Vegetation Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-7 F. Radioactive Material Shipments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-9 G. | |||
References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-9 I | |||
PART VI- WORK A. S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI- l B. Teachi ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI- 1 C. | |||
l Research and Service . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-l | |||
: 1. Neutron Activation Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-2 2. | |||
Forensic S tudies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-2 3. | |||
Irradiations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-3 | |||
: 4. Radiological Emergency Response Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-3 | |||
: 5. Training and Instruction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-4 1 6. | |||
Radiation Protection Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-4 | |||
: 7. Radiological Instrument Repair and Calibration . . . . . . . . . . . . . . . . . . . . . . . . . VI-5 8. | |||
Co nsultation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-6 l | |||
l PA.RT VII- WORDS L A. Publications in Print . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII- l B. Th e se s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII -7 C. Reports Submitted for Publication . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-8 D. Documents in Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-9 1. | |||
P ublications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-9 | |||
[ 2. Theses...................................................... . VII-10 E. | |||
Presentations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII- 10 F. | |||
Public Relations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-14 | |||
l i | |||
j LIST OF TABLES Table Title P. age I, | |||
III.A.1 OSU Courses Using the OSTR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-8 III.A.2 OSTR Teaching Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-9 III.A.3 OSTR Research Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- 10 III.B.1 Radiation Center Spectrometry Systems: Ganuna, Low Energy Photon, Alpha . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- 1 1 III.B.2 Radiation Center Liquid Scintillation Counting Systems . . . . . . . . . . . . . III-12 I | |||
III.B.3 Radiation Center Proportional Counting Systems . . . . . . . . . . . . . . . . . . III-13 III.B.4 Thermoluminescent Dosimeter Systems . . . . . . . . . . . . . . . . . . . . . . . . . . III-14 III.C.1 Oammacell 220 *Co Irradiator Use . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-15 III.D.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-16 IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) . . . . . . . . . . . . . . IV-19 IV.A.2 OSTR Operating Statistics with the Original (20% Enriched) | |||
Standard TRIGA Fuel Core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-22 IV.A.3 Present OSTR Operating Statistics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-23 IV.A.4 OSTR Use Time in Terms of Specific Use Categories . . . . . . . . . . . . . . . IV-24 IV.A.5 OSTR Multiple Use Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-25 IV.B.1 Use of OSTR Reactor Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-27 IV.C.1 Unplanned Reactor Shutdowns and Scrams . . . . . . . . . . . . . . . . . . . IV-2 8 V.A.1 Radiation Protection Program Requirements and Frequencies . . . . . . . . . V-10 I | |||
I | |||
i 4 i | |||
1 l | |||
\ | |||
LIST OF TABLES (Continued) | |||
Table Title | |||
! Page l | |||
V.B. I .a Monthly Summary of Liquid Effluent Releases to the Sanitary I S ewer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V- 1 1 V.B. I .b Annual Summary of Liquid Waste Generated and Transferred . . . . . . . . . V-12 i V.B.2 Monthly Summary of Gaseous Effluent Releases . . . . . . . . . . . . . . . . . . . V-13 V.B.3 Annual Summary of Solid Waste Generated and l | |||
Transferred . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V- 14 I V.C.1 Annual Summary of Personnel Radiation Doses Received . . . . . . . . . . . . V-15 I V.D.1 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-16 ' | |||
V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-17 | |||
, V.D.3 Annual Summary of Radiation Levels and Contamination Levels j Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-19 V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence . . . . . . . . . . . V-20 j V.E.2 Total Dose Equivalent at the Off-Site Gamma Radiation | |||
;E Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-21 V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity 3 | |||
(Minus H) for Environmental Soil, Water, and Vegetation S ampl es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-22 V.E.4 Average LLD Concentration and Range of LLD Values for Soil, Water and Vegetation Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-23 l V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 . . . . . . . . . . . . . V-24 | |||
I LIST OF TABLES (Continued) | |||
Table Title Page V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License O RE 9 000 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-25 V.F.3 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 . . . . . . . . . . . . . . . . . . . . . . . V-26 VI.C.1 Institutions and Agencies Which Utilized the Radiation C e n t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V I -7 VI.C.2 Graduate Student Research Which Utilized the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-12 VI.C.3 Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies . . , . . . . . . VI-26 VI.C.4 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and the l Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-61 l VI.C.5 Summary of Radiological Instrumentation Calibrated to Support Other OSU Departments and Other Agencies . . . . . . . . . . . . . . . . . . . . . . . VI-62 l VI.C.6 Summary of Radiological Instrument Repair Activities for Non-Radiation Center Departments and Agencies . . . . . . . . . . . . . . . . . . . VI-63 VII.F.1 Summary of Visitors to the Radiation Center . . . . . . . . . . . . . . . . . . . . . VII-15 1 | |||
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1 Overview Part1 Part I OVERVIEW A. Acknowledgments Many individuals and organizations help the Radiation Center succeed, and in recognition ofthis, the staffof the OSU Radiation Center and TRIGA Reactor would like to extend its appreciation to all of those who contributed to the information and events contained in this report: to the University administration; to those to provided our funding, particularly the state ofOregon and the U. S. Department ofEnergy (USDOE); to our regulators; to the researchers, the students, and others who used the Radiation Center; to OSU Facilities Services; to OSU Security Ser ices and the Oregon State Police; and to the OSU Department ofPrinting and Mailing, who provide a consistent and quality service in this report. We most camestly say,"thank you." | |||
The Center would not be able to accomplish all that is shown in this report without the diligent efforts ofall ofits staff. These times ofbudget cuts have meant that each person has had to work harder with less help. It is to their credit that we have managed to maintain our level and quality of service. To each one..."thank you." | |||
Putting this report together each year is a major effort for several people. Only those who have been involved can fully understand what a greatjob Linda James has done at the data-gathering, organization and keyboarding of this annual report. Thanks, Linda! | |||
B. Executive Summary The data from this reporting year show that the use of the Radiation Center and OSTR has still increased, despite being "maxed" out in many areas. This increase has been achieved by greater efficiencies. A good illustration of this is in reactor use hours. The reactor was busy an average of40hoursperweek. Additionaluserswereaccommodatedbyincreasingthenumberofpeople who were simultaneously using the different reactor facilities. This year there were two or more users on the reactor for a total of 441 hours. | |||
The OSTR supported 29 different OSU classes this year, mostly in the Department ofNuclear Engineering. The number ofhours for courses (up 29% from last year) roughly equaled the number ofhotr spent supporting research projects (about 1490 hours each). Eighty-five percent of the OSTR research hours were in support ofoff-campus research projects. The number ofsamples irradiated in the reactor during this reporting period was 4,707, which is over 1,000 more than the average. The percent ofunfunded OSTR use hours (3 %) decreased by a factor oftwo from last | |||
2 Overview Parti I | |||
year. This is the result of an initial attempt to move to a more full cost recovery basis for services provided by the Center. | |||
The OSTR continues to be the facility of choice for many of the "Ar/*Ar geochronology laboratories around the world. | |||
Personnel at the Radiation Center conducted 101 tours of the facility, accommodating 1,081 visitors. The visitors included elementary, middle school, high school, and college students; relatives and friends; faculty; current and prospective clients; national laboratory and industrial g scientists and engineers; and state, federal and in. ernatical officials. The Radiation Center is a g significant positive attraction on campus because visitors almost always go away with a good impression of the facility and of Oregon State University. | |||
Research proj ects ofpersonnel housed in the Radiation Center totaled approximately $ 1.2 million for this year. | |||
l The Radiation Center projects database initiated a fewyears ago continues to provide a useful way oftracking the many different aspects of work at the facility. The number ofproj ects supported this year was 134. Reactor projects comprised about 93% of all projects. The contracts supporting these research proj ects totaled approximately $3,000,000. This year the Radiation E Center serviced 81 research faculty and 133 students (for a total of 586 uses of Center facihties) E from 63 different institutions,65% ofwhich were from other states and 16% ofwhich were from outside the U. S. and Canada. So while the Center's primary mission is local, it is also a facility with a national and international clientele. | |||
With the closing ofthe State of Oregon's environmental radiological monitoring laboratory in Portland, the Radiation Center is essentially now the only place in the state where radiological monitoring can be performed. | |||
The Radiation Center web site provides an easy way for potential users to evaluate the Center's facilities and capabilities as well as to apply for a project and check use charges. The address is: | |||
http://www.ne..orst.edu/ facilities / radiation _ center. (check it out!) | |||
C. Introduction The current annual report ofthe Oregon State University Radiation Center and TRIGA Reactor follows the usual format by including information relating to the entire Radiation Center rather than just the reactor. However, the information is still presented in such a manner that data on the g reactor may be examined separately,ifdesired. It should be noted that all annual data given in this E report cover the period from July 1,1997 through June 30,1998. Cumulative reactor operating I | |||
I' | |||
1 3 | |||
Overview Parti data in this report relate only to the FLIP-fueled core. This covers the period from August 1,1976 through June 30,1998. For a summary ofdata on the reactor's original 20% enriched core, the reader is referred to Table IV.A.2 in Part IV of this report or to the 1976-77 annual report if a more comprehensive review is needed. | |||
In addition to providing general information about the activities ofthe Radiation Center, this report is designed to meet the reporting requirements ofthe U. S. Nuclear Regulatory Commission, the U. S. Department of Energy, and the Oregon Office of Energy. Because of this, the report is divided into several distinct parts so that the reader may easily find the sections ofinterest. | |||
D. Overview of the Radiation Center The Radiation Center is a unique facility which serves the entire OSU campus, all other institutions within the Oregon University System, and many other colleges and universities throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforcement, energy, health, and environmental quality, and renders assistance to Oregon industry. In addition, the Radiation Center provides permanent office and laboratory space for the OSU Department ofNuclear Engineering, the OSU Radiation Safety Office, the Institute ofNuclear Science and Engineering, and for the OS U nuclear chemistry, radiation chemistry, and geo- and cosmochemistry programs. There is no other universityfacility with the combinedcapabilities ofthe OSURadiation Center in the western halfofIhe UnitedStates. | |||
Located in the Radiation Center are major items ofspecialized equipment and unique teaching and research facilities. Figurel.D.1 shows the layout ofthese facilities at the Radiation Center. They include a TRIGA Mark Il research nuclear reactor; a "Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associated germanium detectors; a neutron radiography facility capable oftaking still or very high speed radiographs; and a variety ofinstruments for radiation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with up-to-date instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laboratories for animal and plant experiments involving radioactivity; a facility for repair and calibration of mchation protection instrumentation; and facilities for pachging radioxtive materials for shipment to national and international destinations. | |||
A major non-nuclear facility housed in the Radiation Center is the one-quarter scale thermal hydraulic advanced plant expenmental (APEX) test facility for the Westinghouse AP600 reactor design. The AP600 is a next-generation nuclear reactor design which incorporates many passive safetyfeaturesaswellasconsiderablysimplifiedplantsysternsandequipment. APEXoperates at pressures up to 400 psia and temperatures up to 450 F using electrical heaters instead of | |||
4 Overview Parti nuclear fuel. All major components of the AP600 are included in APEX and all systems are appropriately scaled to enable the experimental measurements to be used for safety evaluations and licensing ofthe full scale plant. This world-class facility meets exacting quality assurance criteria to provide assurance of safety as well as validity of the test results. | |||
Also added to the Radiation Center this past year is the Advanced Thermal Hydraulics Research Laboratory, which will be used for state-of-the-art two-phase flow experiments. The Radiation Center staff regularly provides direct support and assistance to OSU teaching and research programs. Areasofexpertisecommonlyinvolvedinsucheffortsincludenuclearengineering, nuclear and radiation chenustry, neutron activation analysis, radiation effects on biological systems, radiation dosimetry, environmental radioactivity, production ofshort-lived radioisotopes, radiation shielding, nuclear instrumentation, emergency response, transportation ofradioactive materials, instrument calibration, radiation health physics, mdioactive waste disposal, end other related areas. | |||
In addition to formal academic and research support, the Center's staffprovides a wide variety of other services including public tours and instructional programs, and professional consultation associated with the feasibility, design, safety, and execution ofexperiments using radiation and radioactive materials. | |||
I I | |||
I I | |||
I | |||
5 Overview Parti | |||
[I E. Summary of Environmental and Radiation Protection Data | |||
: 1. Liquid Effluents Released (See Table V.B.I.a) | |||
: a. Total estimated quantity of radioactivity sLLD (95%) of released (to the sanitary sewer)<o(2) 1.79 x 10-5 Ci | |||
: b. Detectable radionuclides in the liquid waste N/A I c. Estimated average concentration of released radioactive material at the point of release sLLD (95%) of 4.08 x 104 Ci/ml l | |||
1 | |||
: d. Percent of applicable monthly average concentration for released liquid radioactive material at the point of release N/A I | |||
: e. Total volume ofliquid effluent released, including diluent (3) 1,158 gallons | |||
: 2. Liquid Waste Generated and Transferred (See Table V.B.I.b) | |||
: a. Volume ofliquid waste packagedW 52 gallons | |||
: b. Detectable radionuclides in the waste 32p, wCo, "Rb | |||
: c. Total quantity of radioactivity in the waste 4.0 x 10-2 Ci I 1 I (1) OSU has implemented a policy to reduce radioactive wastes disposed to the sanitary sewer to l | |||
the absolute minimum. | |||
(2) The OSU operational policy is to subtract only detector background from our water analysis data and not background radioactivity in the Corvallis city water. 1 (3) Total volume ofeffluent plus diluent does not take into consideradon the additional nuxmg with the over 250,000 gallons per year ofliquids and sewage normally discharged by the Radiation Center I complex into the same sanitary sewer system. | |||
(4) TRIG A and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer l l to its waste processing facility for solidification and final packaging. | |||
1 l | |||
6 Overview Part1 | |||
: 3. Airbome Effluents Released (See Table V.B.2) | |||
: a. Total estimated quantity ofradioactivity I | |||
released 5.42 Ci | |||
: b. Detectable radionuclides in the gaseous waste") d"Ar (ti,f = 1.83 hr) | |||
: c. Estimated average atmospheric diluted concentration of d!Ar at the point ofrelease 3.5 x 10-8 Ci/ml | |||
: d. Percent of applicable monthly average concentration for diluted concentration l | |||
of 4'Ar at the point of release 0.9% | |||
: e. Total estimated release of radioactivity in particulate form with half-lives greater than 8 daysG) None | |||
: 4. Solid Waste Released (See Table V.B.3) | |||
: a. Total amount of solid waste packaged and disposed of 66 f1 3 3 | |||
: b. Detectable radionuclides in the solid waste H,22Na, 24Na, 46Sc, 47 Sc, 5'Cr, 58Co, 59e, 6 Co, s6Rb, "Sr, "3Cd,i22Sb, i24Sb, g 204 T1,2"Bi, 226Ra, E 238U, 24 Am | |||
: c. Total radioactivity in the solid waste 6.6 x 10-5 Ci (1) Routine gamma spectmscopy analysis ofthe gaseous radioactivity in the stack discharge indicated that it was virtually all d'Ar. | |||
(2) Evaluation ofthe detectable particulate radioactivity in the stack discharge confumed its origin as naturally occurring radon daughter products, predominantly2 "Pb and 2"Bi, which are not associated with reactor operations. | |||
7 Overview Part1 | |||
[' 5. Radiation Exposure Received by Personnel (See Table V.C.1)W | |||
: a. Facility Operating Personnel | |||
{: (mrem) | |||
(1) Average whole body 11 | |||
[ (2) Average extremities 80 (3) Maximum whole body 35 (4) Maximum extremities 100 | |||
: b. Key Facility Research Personnel i | |||
[ Average whole body (1) <1 (2) Average extremities 2 | |||
[ (3) Maximum whole body ND (4) Maximum extremities 30 | |||
[ c. Facilities Services Maintenance Personnel r (1) Average whole body <1 L | |||
(2) Maximum whole body 1 | |||
: d. Laboratory Class Students | |||
{ | |||
(1) Average whole body <1 | |||
( (2) Average extremities 1 (3) Maximum whole body 10 (4) Maximum extremities 80 | |||
[. | |||
: e. Campus Police and Security Personnel | |||
[' | |||
(1) Average whole body ND (2) Maximum whole body ND | |||
: f. Visitors | |||
[. (1) Average whole body <1 (2) Maximum whole body 20 | |||
[ | |||
{ | |||
(1) "ND"indime that each ofthe beta-gamma dosimeters during the reporting period was less than | |||
, the vendor's gamma dose reporting threshold of10 mrem or that each ofthe neutron dosimeters L was less than the vendor's threshold of 30 mrem, as applicable. | |||
c | |||
-___-___-______f | |||
8 Overview Part i | |||
: 6. Number of Routine Onsite and Offsite Monitoring Measurements and Samples I | |||
: a. Facility Survey Data (1) Area Radiation Dosimeters (See Table V.D.1) | |||
(a) Beta-gamma dosimeter measurements 148 (b) Neutron dosimeter measurements 48 (2) Radiation and Contamination Survey Measurements (See Table V.D.3) ~6000 | |||
: b. Environmental Survey Data (1) Gamma Radiation Monitoring (See Tables I' | |||
V.E.1 and V.E.2) | |||
(a) Onsite monitoring | |||
- OSU TLD monitors 108 E | |||
-- Radiation Detection Co. TLD monitors 72 E | |||
- Monthly rem /h measurements 108 (b) Offsite monitoring | |||
-- OSU TLD monitors 264 | |||
-- Radiation Detection Co. TLD monitors 104 | |||
- Monthly rem /h measurements 252 (2) Soil, Water and Vegetation Surveys (See Table V.E.3) | |||
(a) Soil samples 16 (b) Water samples 14 (c) Vegetation samples 56 I | |||
l l | |||
l i | |||
9 m.wiew I F. History A brief chronology of the key dates and events in the history of the OSU Radiation Center and the TRIGA reactor is given below: | |||
l June 1964 Completion of the first phase of the Radiation Center, consisting of 32,397 square feet of office and laboratory space, under the direction of founding Director, C. H. Wang. | |||
July 1964 Transfer of the 0.1 W AGN 201 reactor to the Radiation Center. | |||
I This reactor was initially housed in the Mechanical Engineering Department and first went critical in January,1959. | |||
October 1966 Completion of the second phase of the Radiation Center, consisting of 9,956 square feet of space for the TRIGA reactor and associated laboratories and offices. | |||
March 1967 Initial criticality of the Oregon State TRIGA Reactor (OSTR). | |||
I The reactor was licensed to operate at a maximum steady state power level of 250 kW and was fueled with 20% enriched fuel. | |||
October 1967 Formal dedication of the Radiation Center. | |||
August 1969 OSTR licensed to operate at a maximum steady state power of 1 I MW, but could do so only for short periods of time due to lack of cooling capacity. | |||
I June 1971 OSTR cooling capacity upgraded to allow continuous operation at 1 MW. | |||
April 1972 OSTR Site Certificate issued by the Oregon Energy Facility Siting Council. | |||
September 1972 OSTR area fence installed. | |||
December 1974 AGN-201 reactor permanently shut down. | |||
March 1976 Completion of 1600 square feet of additional space to accommodate the rapidly expanding nuclear engineering program. | |||
l July 1976 OSTR refueled with 70% enriched FLIP fuel. | |||
July 1977 Completion of a second 1600 square feet of space to bring the Radiation Center complex to its current total of 45,553 square feet. | |||
January 1980 Major upgrade of the electronics in the OSTR control console. | |||
10 Overview Part1 January 1980 Major upgrade of the electronics in the OSTR control console. | |||
July 1980 AGN-201 reactor decommissioned and space released for unrestricted use. | |||
June 1982 Shipment of the original 20% enriched OSTR fuel to Westinghouse Hanford Corporation. | |||
December 1984 C. H. Wang retired as director. C. V. Smith became new director. | |||
I August 1986 Director C. V. Smith left to become Chancellor of the University of Wisconsin-Madison. A. G. Johnson became new Director. | |||
December 1988 AGN-201 components transferred to Idaho State University for use in their AGN-201 reactor program. | |||
December 1989 OSTR licensed power increased to 1.1 MW. | |||
l June 1990 Installation of a 7000 Ci 6 Co Gammacell irradiator. | |||
l March 1992 25th anniversary of the OSTR initial criticality. | |||
l November 1992 Start of APEX plant construction. | |||
June 1994 Retirement of Director A. G. Johnson. B. Dodd became new I Director. | |||
l August 1994 APEX inauguration ceremony. | |||
August 1995 Major extemal refurbishment: new roof; complete repaint; rebuilt parking lot; addition of landscaping and lightine, i | |||
l March 1998 Start of ATHRL construction. | |||
l l | |||
I I | |||
I | |||
I overview pm i1 Figure I.D.1 Floor Plan of the Radiation Center I | |||
, . . . . THNLO FLOOR c, N sEcoNO FtooR 1 ; _ | |||
c / R - ,tooR _ J. O7j | |||
- \ | |||
!l A'9 | |||
~ y s l O N /.>-s. | |||
$N / | |||
* =d b= 0104 j 0104A 0104 0104 REACTOR BAY | |||
* REACTOR BAY g 0300 I Il, | |||
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1 People pa,, y Part II I PEOPLE l This part contains a listing of all people who were residents of the Radiation Center or who worked a I significant amount oftime at the Center during this reporting period. Sections A, B and C list the academic staff, trainees, and students, while sections D through G give the Radiation Center's operating staff. Section H shows the OSU Radiation Safety Oflice staff, and section I provides the composition ofcommittees involving Ceriter personnel. | |||
It should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are listed in this part. Summary information on the number ofpeople involved is given in Table VI.C.1, while individual names and projects are listed in Tables VI.C.2 and VI.C.3. | |||
A. Professional and Research Faculty Attfield, Martin P. | |||
Faculty Research Associate Chemistry l | |||
I *Binney, Stephen E. | |||
I Professor Nuclear Engineering Chairman, OSTR Reactor Operations Committee | |||
* Brock, Kathryn M. | |||
Faculty Research Assistant l Health Physicist | |||
*Conard, Bobb! L. | |||
Senior Faculty Research Assistant College of Oceanic md Atmospheric Sciences | |||
*Conrady, Michael R. | |||
L Faculty Research Assistant i Analytical Support Manager | |||
+ | |||
l L Craig, A. Morrie Professor | |||
{ College of Veterinary. Medicine m | |||
L | |||
* OSTR users for research and/or teaching. | |||
m | |||
2 People Part11 Daniels, Malcohn g Professor Emeritus E Chemistry | |||
*Dodd, Brian Director, Radiation Center Director, Institute of Nuclear Science and Engineering Professor Nuclear Engineering and Radiation Health Physics Fekou-Youmbi, Valentin I | |||
Faculty Research Associate Chemistry Groome, John T. | |||
Faculty Research Assistant APEX Facility Operations Manager Nuclear Engineering l | |||
Guncerson, Chris E. | |||
Faculty Research Assistant APEX Facility Operator / Test Engineer Nuclear Engineering Hart, Lucas P. | |||
Faculty Research Associate Chemistry | |||
'Higginbotham, Jack F. | |||
Reactor Administrator Associate Professor g Nuclear Engineering and Radiation Health Physics s | |||
*Higley, Kathryn A. | |||
Assistant Professor Nuclear Engineering and Radiation Health Physics Hovermale, Jeannette T. | |||
Faculty Research Assistant College of Veterinary Medicine I | |||
* OSTR users for research and/or teaching. | |||
L 3 | |||
People | |||
{ Part11 Johnson, Arthur G. | |||
{- Director Emeritus, Radiation Center Professor Emeritus | |||
[ Nuclear Engineering and Radiation Health Physics Johnson, Richard A. | |||
[ Adjunct Faculty Nuclear Engineering Klein, Andrew C. | |||
Acting Department Head | |||
[. Department ofNuclear Engineering Director, Oregon Space Grant Program Professor | |||
[ Nuclear Engineering | |||
*Krane, Kenneth S. | |||
[ | |||
t Chair, Physics Department Professor Physics | |||
[ | |||
Krebs, Rolf | |||
(. Faculty Research Associate Crop and Soil Science Lafi, Abd Y. | |||
Faculty Research Associate APEX Research Analyst | |||
[ | |||
Nuclear Engineering | |||
[ *Loveland, Walter D. | |||
1:afessor Chemistry MacVicar, Robert President Emeritus | |||
{ | |||
*Meredith, Charlotte C. | |||
Faculty Research Assistant | |||
{ | |||
College of Oceanic and Atmospheric Sciences f~ | |||
f r | |||
* OSTR users for research and/or teaching. | |||
r J | |||
People Part11 l | |||
Mommer, Niels K. | |||
Faculty Research Associate g Physics a Palmer, Todd S. E E | |||
Assistant Professor Nuclear Engineering | |||
*Pastorek, Christine SeniorInstructor Chemistry Popovich, Milosh I' Vice President Emeritus 5 | |||
*Prahl, Frederick G. g a | |||
Professor College of Oceanic and Atmospheric Sciences | |||
*Pratt, David S. | |||
Faculty Research Assistant Senior Health Physicist . | |||
Reyes, Jr., Jos6 N. | |||
APEX PrincipalInvestigator Professor Nuclear Engineering El 3 | |||
Ringle, John C. l Professor l Nuclear Engmeenng j Associate Dean of the Graduate School i Robinson, Alan H. | |||
Department Head Emeritus Nuclear Engineering l | |||
*Schmitt, Roman A. | |||
Professor Emeritus Chemistry I | |||
* OSTR users for research and/or teaching. | |||
l | |||
5 People Part11 | |||
*Schutfort, Erwin G. | |||
Faculty Research Assistant Radiation Center Project Manager | |||
* Sparrow, Margaret Senior Research Assistant College of Oceanic and Atmospheric Sciences | |||
*Sullivan, Barbara E. | |||
Faculty Research Assistant I College ofOceanic and Atmospheric Sciences Wang, Chih H. | |||
I Director Emeritus, Radiation Center Professor Emeritus Nuclear Engineering Young, Roy A. | |||
I Professor Emeritus Botany and Plant Pathology Yundt, Michael S. | |||
Faculty Research Assistant I APEX Instrument Specialist / rest Engineer Nuclear Engineering I | |||
I . | |||
I I | |||
b | |||
[ | |||
r L | |||
* OSTR users for research and/or teaching. | |||
l | |||
1 6 | |||
P:ople Part11 I | |||
l l | |||
B. Visiting Scientists and Special Trainees Advisor or Research Name Field (Afiliation) Program Director Foreman, Katherine Saturday Academy Mentorship Program W. D. Loveland Crescent Valley High School l Corvallis, Oregon Jovanovic, Ana G. Visiting Undergraduate Student E. G. Schtitfort l | |||
Chemical Engineering Baylor University Lekas, David Visiting Undergraduate Student W. D. Loveland l | |||
l Chemistry Uppsala Universitet, Sweden l Less, Greg Undergraduate Student W. D. Loveland Chemistry i Oregon State University l | |||
l Menge, Duncan Saturday Academy Mentorship Program W. D. Loveland l Crescent Valley High School Corvallis, Oregon . | |||
*Nakazawa, Yuko NSF Research Experience for K. S. Krane l | |||
Undergraduates Program State University of New York l at Stonybrook l | |||
E l Ngemvijit, Narippawaj Visiting Faculty J. F. Higginbotham l Thailand | |||
* Reel, Justin NSF Research Experience for K. S. Krane Undergraduates Program Camegie-Mellon University | |||
* Shivers, Robert J. Student Research Assistant W. D. Loveland Environmental Science Oregon State University Wallin, Petra Visiting Undergraduate Student W. D. Loveland Chemistry Royal Institute of Technology, Sweden Xiao, Zejun Project Manager J. N. Reyes Reactor Thermalhydraulic Lab Nuclear Power Institute of China Chengdu, China l | |||
* OSTR users for research and/or teaching. | |||
7 People party C. OSU Graduate Students Degree Name Program Field Advisor Al-Hussan, Khalid A. PhD Nuclear Engineering A. C. Klein Alves, Mauro A. PhD Physics J. A. Gardner Asghar, Sabooh MS Nuclear Engineering T. S. Palmer Baik, Seung-Hyuk PhD Nuclear Engineering J. F. Higginbotham Boone, Darren M. MS Radiation Health Physics J. F. Higginbotham Brice, Derek J. MS Nuclear Engineering T. S. Palmer Cantaloub, Michael G. MS Radiation Health Physics J. F. Higginbotham Chinudomsub, Kittisak MS Radiation Health Physics J. F. Higginbotham Colpo, Sarah E. MS Nuclear Engineering J. N. Reyes | |||
*Crail, Scott A. MS Radiation Health Physics J. F. Higginbotham Crowley, Paul R. MS Radiation Health Physics J. F. Higginbotham Day, Travis D. MS Chemistry W. D. Loveland Dunn, John R. MS Chemistry W. D. Loveland Ellis, Christopher P. MS Nuclear Engineering J. N. Reyes Jue, Tracy M. MS Radiation Health Physics S. E. Binney Keillor, Martin E. PhD Nuclear Engineering S. E. Binney Kellar, Marvin G. MS Radiation Health Physics B. Dodd Kim, Kang Seog PhD Nuclear Engineering T. S. Palmer Kropp, Edward K. MS Radiation Health Physics S. E. Binney Lee, Hsing Hui PhD Nuclear Engineering A. C. Klein ' | |||
Leon, Laura M. MS Radiation Health Physics J. F. Higginbotham Marianno, Craig M. PhD Radiation Health Physics K. A. Higley Menn, Scott A. MS Radiation Health Physics K. A. Higley Miller, Robert E. MS Radiation Health Physics K. A. Higley l | |||
Pagh, Richard T. PhD Nuclear Engineering A. C. Klein l Potter, Nathan K. MS Radiation Health Physics K. A. Higley | |||
*Povetko, Oleg G. PhD | |||
{ | |||
Radiation Health Physics K. A. Higley Richardson, Eric L. MS Nuclear Engineering T. S. Palmer Rios, Maribel G. MS Physics K. S. Krane Rusher, Christopher D. MS Nuclear Engineering J. N. Reyes Saiyut, Kittiphong PhD Nuclear Engineering J. F. Higginbotham | |||
*Schntfort, Erwin G. MS Geosciences C. Field Schwab, Kristen E. MS Radiation Health Physics K. A. Higley Strohecker, Mark F. MS Nuclear Engineering T. S. Palmer Tiyapun, Kanokrat PhD Radiation Health Physics S. E. Binney Uyeda Jr., Graydon S. MS Nuclear Engineering J. N. Reyes l Wachs, Daniel M. MS Nuclear Engineer'ng J. N. Reyes Walker, Matthew J. MS Radiation Health Physics J. F. Higginbotham Welter, Kent B. PhD Nuckar Engineering T. S. Palmer l Zyromski, Kristiana E. PhD Chemistry W. D. Loveland | |||
* OSTR users for research and/or teaching. | |||
8 People Part11 D. Business, Administrative and Clerical Staff Director, Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B. Dodd Business Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. C. Campbell Office Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. K. Dalton | |||
( | |||
Office Specialists . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. C. West L. M. James l | |||
Custodian . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E. Cimbri Office Coordinator (Nuclear Engineering) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . R. A. Keen | |||
; Word. Processing Technician (Nuclear Engineering) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L. J. Robinson Word Processing Tecimician (APEX - Nuclear Engineering) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . T. L. Culver l | |||
E. Reactor Operations Ssaff I | |||
Princij ,al Security Officer, Senior Reactor Operator . . . . . . . . . . . . . . . . . . . . . . . B. Dodd Reactor Administrator, Senior Reactor Operator . . . . . . . . . . . . . . . . . J. F. Higginbotham Reacto Supervisor, Senior Reactor Operator . . . . . . . . . . . . . . . . . . . . . . . . . . A. D. Hall Senior i'eactor Operator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. P. Smith l (from 3/12/98) G. M. Wachs Reactor oprator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. A. Crail (from 3/12/98) N. A. Carstens l | |||
Reactor Operator Trainec . . . . . . . . . . . . . (from 9/30/97 through 3/11/98) N. A. Carstens (from 9/30/97 through 3/11/98) G. M. Wachs i | |||
l l | |||
F. Radiation Protection Staff l Serior Health Physicist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D . S . Pratt | |||
[ Health Physicist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . K. M. Brock | |||
: l. Radiation Protection Technologist ......................... . . . . D. R. Carver Health Physics Monitors (Students) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J. Bergman J. Davidson J. Lewis M. Sellers K. Hulse l | |||
People Part11 G. Scientific Support Staff I Analytical Support Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M. R. Conrady Projects Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E. G. Schtitfort Geochemist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S . G ei g er I Neutron Activation Analysis Technicians (Students) . . . . . . . . . . . . . . . . . . . . . . I. Davis A. Ham M. Kelman P. Richards R. Shivers I Scientific Instrument Technician . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. P. Smith Nuclear Instrumentation Support . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. Menn t | |||
I IL OSU Radiation Safety Office Staff Radiation Safety Officer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . R. H. Farmer I Radiation Specialists . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. L. Harlan (through 721/97) E. F. Forter (from 9/29/97) S. R. Reese I Office Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . K. L. Miller Lab Technician . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L. C. Meeks Student Technicians . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. Menn l B. Kowash I. Committees | |||
: 1. Reactor Operations Committee Name Affiliation l S. E. Binney, Chair . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Nuclear Engineering j D. L. Amort . . . . . . . . (through 12B1/97) Electrical and Computer Engineering B. Dodd . . . . . . . . . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering il A. D. Hall . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center l J. F. Higginbotham . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering A.C.Klein . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Nuclear Engineering M. E. Magana . . . . . . . . . . . . . . . . . . . . . . . Electrical and Computer Engineering l D. S. Pratt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center W. J. Richards . . . . . . . . . . . . . . . . . . . . . . McClellan Nuclear Radiation Center J. C. Ringle . . . . . . . . . . . . . . . . . . . . . . Nuclear Engineering and Graduate School W. H. Warnes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Mechanical Engineering Q | |||
10 People Part11 | |||
: 2. Radiation Safety Committee (OSU) | |||
Name Affiliation T. Wolpert, Chair . . . . . . . . . . . . . . . . . . . . . . . . . . Botany and Plant Pathology J. Higginbotham, Vice Chair . . . . . . . Radiation Center and Nuclear Engineering R. Collier . . . . . . . . . . . . . . . . . . . . . . . . . . . Oceanic and Atmospheric Sciences T. Dreher . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Agricultural Chemistry R. Farmer, Secretary and RSO . . . . . . . . . . . . . . . . . . . . . . Radiation Safety Office B. Francis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Environmental Health and Safety M. McCambridge (ex officio) . . . Vice President for Finance and Administration D. ' Nelson . . . . . . . . . . . . . . . . . . . . . . . . . . . . Oceanic and Atmospheric Sciences C. Rivin . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Botany and Plant Pathology C. S now . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Exercise and Sport Science J. S teiner . . . . . . . . . . . . . . . . . . . . . . . . . . . . USDA-ARS/ Crop and Soil Science l | |||
I. Wong . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Biochemistry / Biophysics | |||
: 3. Radiation Center Safety Committee | |||
[ Name 4ffiliation l | |||
; W. D. Loveland, Chair . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Chemistry S. C. Campbell . . . . . . . . . . . . . . . . . . . . . . . (through 5/28/98) Radiation Center M. R. Conrady . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center B. Dodd . . . . . . . . . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering A. D. Hall . . . . . . . . . . . . . . . . . . . . . . . . . . . . (through 5/28/98) Radiation Center J. F. Higginbotham . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering D. S. Pratt . . . . . . . . . . . . . ............... . . . . . . . . . . . . Radiation Center S. P. Smith . . . . . . . . . . . . . . . . . . . . . . . . . . . (through 5/28/98) Radiation Center D. R. Carver . . . . . . . . . . . . . . . . . . . . . . . . (from 5/19/98) Radiation Center J. T. Groome . . . . . . . . . . . . . . . . . . . . . . . . . (from 5/29/98) Radiation Center K. L. Miller . . . . . . . . . . . . . . . . . . . . . . . . . . . (from 5/29/98) Radiation Safety | |||
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1 | |||
- 1. - | |||
Facilities Part til Part III FACILITIES I A. Research Reactor | |||
.g E 1. Description The Oregon S tate University TRIGA Reactor (OSTR) is a water-cooled, swinnung pool type ofresearch reactor which uses uranium / zirconium hydride fuel elements in a circular ' | |||
grid array. The reactor core is surrounded by a ring ofgraphite which serves to reflect neutrons back into the core. The core is situated near the bottom of a 22-foot deep water-filled tank, and the tank is surrounded by a concrete bioshield which acts as a radiation shield and structural support. See Figures III.A.1, III.A.2 and III.A.3. | |||
The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at a I maximum steady state power of1.1 MW and can also be pulsed up to a peak power of about 2500 MW. | |||
The OSTR has a number ofdifferentirradiation facilities including a pneumatic transfer tube, a rotating rack, a thermal column, four beam ports, five sampleholding (dummy) fuel I elements for special in-core irradiations, and a cadmium-lined in-core irradiation tube for experiments requiring a high energy neutron flux. | |||
The pneu m atic trans fer facility enables samples to be inserted and removed from the core in a few seconds. Consequently, this facility is normally used for neutron activation analysis involving short lived radionuclides. On the other hand,the rotating rackis used l for much longer irradiation ofsamples (e.g., hours). The rack consists ofa circular array of40 tubular positions, each ofwhich can hold two sample tubes. The rotation ofthe rack ensures that each sample will receive an identical irradiation. | |||
The reactor's thermal columa consists of a large stack ofgraphite blocks which slows I down neutrons from the reactor core in order to increase thermal neutron activation of samples. Graphite blocks are removed from the thermal column to enable samples to be positioned inside for irradiation. | |||
The beam ports are tubular pendu udons in the reactor's main concrete shield which enable neutron and gamma radiation to stream from the core when a beam port's shield plugs are l removed. Two of the OSTR's beam ports are permanently configured for neutron radiography while the other two may be used for a variety of experiments. | |||
I 1 | |||
1 1 | |||
2 l Pan 111 l Facilities Ifsamples which are to be irradiated require a large neutron fluence, especially from higher i energy neutrons, then such samples may be inserted into a d ummy fuel element. This device will then be placed into one of the core's inner grid positions which would normally be occupied by a fuel element. ' | |||
The cadmium-lined in-core irradiation tube enables samples to be irradiated in a high flux region near the center ofthe core. The cadmium lining in the facility elimimtm thermal neutrons and thus permits sample exposure to higher energy neutrons only. The cadmium-lined end of this air-filled aluminum irmdiation tube is inserted into an inner grid position of the reactor core which would normally be occupied by a fuel element. | |||
: 2. Utilization The two main uses of the OSTR are instruction and research. During this reporting period, the reactor was in use an average of40 hours during a typical work week. Since the normal reactor operations week of45 hours included several longer, after-hours mns this year. | |||
: a. Instruction Instructional use ofthe reactor is twofold. First, it is used significantly for classes in nuclear engineenng, radiation health physics, and chemistry at both the graduate and undergraduate levels to demonstrate numerous principles which have been presented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many demonstrations and instructional experiments an be performed using the OSTR which cannot be carried out with a commercial power reactor. Shorter-term demonstration experiments are also performed for many undergraduate students in physics, chemistry, and biology classes, as well as for visitors from other universities and colleges, from high schools, and from public groups. | |||
The second instructional application of the OSTR involves education ofreactor operators, operations managers, and radiation health physicists. The OSTR is in a unique position to provide such education since curricula must include hands-on experience at an operating reactorand la associated laboratories. The many types of educational programs that the Miation Center provides are more fully l described in Part VI(section VI.s 'i) of this report. | |||
During this reporting period the OSTR accommodated 29 different OSU academic classes. In addition, portions ofclasses from other Oregon universities El E | |||
were also supported by the OSTR. The OSU teaching programs utilized 1488 l l | |||
I | |||
l 3 l Facilities l Part til hours of reactor time. Tables III.A.1 and III.A.2, as well as Table III.D.1, provide detailed information on the use of the OSTR for instruction and training. | |||
: b. Research The OSTRis a unique and valuable tool for a wide variety ofresearch applications and serves as an excellent source ofneutrons and/or gamma radiation. The most popular experimental technique requiring reactor use is neutron activation analysis I | |||
(NAA). This is a particularly sensitive method of elemental analysis which is h | |||
* described in more detail in Part VI (section VI.C.1). Part III.B provides a listing of equipment used in NAA at the Radiation Center. | |||
l The OSTR's irradiation facilities provide a wide range ofneutron flux levels and neutron flux qualities, which are sufficient to meet the needs ofmost researchers. | |||
I This is true not only for NAA, but also for other experimental purposes such as geochronology using the "Ar/* Ar ratio t,echnique or fission track methods. | |||
I During this reporting period, the OSTR accommodated 98 funded research projects which utilized 1,448 hourt. of reactor time, and 16 unfunded research projects which utilized 43 hours of reactor time. Details of the l reactor's use specifically for resemh are given in Table III.A.3. Additional information regarding reactor use forresearch, thesis, and service can be found in Tables VI.C.1 through VI.C.3. In these tables OSTR use is indicated with an I asterisk. | |||
I B. Analytical Equipment | |||
: 1. Description The Radiation Center has a great variety ofradiation detection instrumentation. Much of this equipment involves the latest in counting technology as represented by the state-of-the-art gamma ray spectrometers with their associated computers and germanium detectors. Tables III.B.1 through III.B.4 provide a brieflisting of typical laboratory I counting devices present at the Center. Much additional equipment for use in the classroom and an extensive inventory ofportable radiation detection instrumentation are also available. | |||
h I | |||
L F | |||
4 I Facilities Part111 I | |||
: 2. Utilization Radiation Center nuclear instnunentation receives intensive use in both teaching and research applications. In addition, service projects also use these systems and the g combined use often results in 24-hour per day schedules for many of the analytical E instruments. Use ofRadiation Center equipment extends beyond that '.xated at the Center and instrumentation is commonly made available on a loan basis to OSU researchers in g | |||
other departments. | |||
C. Radioisotope Irradiation Sources I:; | |||
: 1. Description i | |||
l The Radiation Center is equipped with a Gammacell 220 *Co irradiator (Fig. III.C.1), | |||
which is capable ofdelivering high doses ofgamma radiation over a range ofdose rates i to a variety of materials. | |||
Typically, the irradiator is used by researchers wishing to perform mutation and other biological effects studies; studies in the area ofradiation chemistry; dosimeter testing; l sterilization offood materials, soils, sediments and other media; gamma radiation damage studies; and other such applications. In addition to the "Co irradiator, the Center is also equipped with a variety ofsmaller "Co, "7Cs,226Ra, plutonium-beryllium,and other isotopic sealed sources of various radioactivity levels which are available for use as irradiation sources. | |||
: 2. Utilization During this reporting period there was a diverse group ofprojects using the "Co irradiator. | |||
These projects included the irradiation ofa variety ofbiological materials inchiding different types ofseeds. In addition, the irradiator was used for sterilization ofseveral media and g the evaluation of the radiation effects on different materials. Table III.C.1 provides use E data for the Gammacell 220 irradiator. | |||
D. | |||
I i Laboratories and Classrooms | |||
: 1. Description I | |||
The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate classes offered by various OSU academic departments or off-campus groups. | |||
I | |||
I Facilities s | |||
Part til I | |||
Instructional facilities available at the Center include a laboratory especially equipped for teaching radiochemistry and a nuclear instrumentation teaching laboratory equipped with modular sets ofcounting equipment which can be configured to accommodate a variety of experiments invclving se measurement ofmany types ofradiation. The Center also has three student computer rooms equipped with a large number ofpersonal computers and workstations. | |||
In addition to these dedicated instmetional facilities, many other research laboratories and pieces ofspecialized equipment are regularly used for teaching. In particular, classes are I routinely given access to appropriate state-of-the-art gamma spectrometry equipment located in Centerlaboratories. A numberofclasses also regularly use the reactcr and the reactor bay as an integral part of their instructional coursework. | |||
I There are two classrooms in the Radiation Center which are capable ofholding about 35 I and 18 students, respectively. In addition, there are two smaller conference rooms and a library that are suitable for graduate classes and thesis examinations. As a service to the student body, the Radiation Center also provides an office area for the student chapters of the American Nuclear Society and the Health Physics Society. | |||
This reporting period saw continued high utilization ofthe Radiation Center's thermal l hydraulics laboratory. This laboratory is being used by a member of the nuclear engineering faculty to accommodate a one-quarter scale model of the Westinghouse Electric Corporation AP600 reactor. The AP600 is a next generation reactor which I features simplicity, passive safety and standardization in its design. The multi-million dollar advanced plant experimental (APEX) facility was fully utilized by the U. S. Nuclear Regulatory Commission to provide licensing data and to test safety systems in "beyond design basis" accidents. The fully scaled, integral model APEX facility uses electrical heating elements to simulate the fuel elements, operates at 450 F and 400 psia and l responds at twice real time. It is the only facility ofits type in the world and is owned by the U. S. Department of Energy, designed by Westinghouse, and operated by OSU. | |||
In addition, during this year a new building, the Advanced Thermal Hydraulics Research Laboratory (ATHRL), was constructed next to the Reactor Building. Two-phase flow experiments will be conducted in the ATHRL. | |||
: 2. Utilization I All ofthe laboratories and classrooms are used extensively during the academic year. For example, a listing of 84 courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table III.D. l . Table III.A.1 gives a separate listing o f the 29 classes specifically accommodated by the reactor during the f reporting period. | |||
I | |||
Facilities Pert 111 I | |||
E. Instrument Repair and Calibration Facility | |||
: 1. Description I | |||
The Radiation Center has a facility for the repair and calibration ofessentially all types of I radiation monitoring instrumentation. This includes instruments for the detection and i measurement of alpha, beta, gamma, and neutron radiation. It encompasses both high g range instmments for measunng intense radiation fields and low range instruments used to E) measure environmental levels of radioactivity. The Center's instrument calibration 1 capability is described more completely in Section VI.C.7 of this report. | |||
l , | |||
: 2. Utilization 11 The Center'sm ' stmment repair and calibration facility is used regularly throughout each year j and is absolutely essential to the continued operation of the many different programs g carried out at the Center. In addition, the absence ofany comparable facility in the state Ei has led to a greatly expanded instrument calibration program for the Center, including calibration ofessentially all radiation detection instruments usedbystate andfederal agencies in the state ofOregon. This includes instruments used on the OSU campus and i l | |||
all other institutions in the Oregon University System, plus instruments from the Oregon Health Division's Radiation Protection Services, the Oregon Oflice of Energy, the Oregon Public Utilities Commission, the Oregon Health Sciences University, the Army Corps of l3 Engineers, and the U. S. Environmental Protection Agency. Additionalinformation g regarding instrument repair and calibration efforts, is given in Tables VI.C.4, VI.C.5, and B VI.C.6. | |||
F. Libraries | |||
: 1. Description . | |||
1 The Radiation Center has libraries containing significant collections of texts, research reports, and videotapes relating to nuclear science, nuclear engineering, and radiation protection. | |||
The Radiation Center is also a regular recipient ofa great variety ofpublications from l l | |||
l commercial publishers in the nuclear field, from many ofthe professional nuclear societies, from the U. S. Department of Energy, the U. S. Nuclear Regulatory Commission, and lI l other federal agencies. Therefore, Center libraries maintain a current collection ofleading l research and regulatory documentation in the nuclear area. In addition, the Center has a collection over 50 sets ofnuclear power reactor safety analysis and environmental reports specifically prepared by utilities for their facilities. l Il | |||
7 . | |||
Facilities Part111 The Center maintains an up-to-date set of reports from such organizations as the Intemational Commission on Radiological Protection, the National Council on Radiation Protection and Measurements, and the Intemational Commission on Radiological Units. | |||
Sets of the current U.S. Code ofFederal Regulations for the U.S. Nuclear Regulatory Commission, the U.S. Departmem of Transportation and other appropriate federal agencies, plus regulations ofvarious state regulatory agencies are also available at the Center. | |||
The R ndiation Center videotape library has over one hundmd tapes on nuclear engineering, radiationprotection and radiological emergency response topics. In addition, the Radiation Center uses videotapes for most of the technical orientations which are required for personnel working with radiation and radioactive materials. These tapes are produced, recorded, and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center. | |||
: 2. Utilization Radiation Center libraries are used mainly to provide referen. ~ wer al on an as-needed basis. They receive extensive use during the academic year. In addition, the orientation videotapes are used intensively during the beginning of each term and periodically thereafter. | |||
I I | |||
I I | |||
1 1 | |||
i L_ | |||
r~" | |||
8 Facilitias Part111 I | |||
Table III.A.1 OSU Courses Using the OSTR I | |||
Course Number ' | |||
NE 111 Course Name'- | |||
Introduction to Nuclear Engineering l | |||
NE 113 Introduction to Nuclear Engineering NE 233 Nuclear Radiation Detection and Instrumentation RHP 233 Nuclear Radiation Detection and Instrumentation l | |||
NE 429 Nuclear Reactor Laboratory l | |||
NE 457 Nuclear Reactor Laboratory , | |||
RHP 480 Field Practices in Radiation Protection NE 484 Applied Radiation Safety RHP 484 Applied Radiation Safety NE 486 Radiation Dosimetry RHP 486 Radiation Dosimetry RHP 488 Radioecology l NE 503 Thesis (Nuclear Engineering) | |||
RHP 503 Thesis (Radiation Health Physics) | |||
RHP 506 Projects NE 559 Nuclear Reactor Laboratory RHP 580 Advanced Field Practices in Radiation Protection RHP 584 Advanced Applied Radiation Safety RHP 586 Advanced Radiation Dosimetry RHP 588 Advanced Radioecology NE 603 Resis (Nuclear Engineering) | |||
General Chemistry for Science Majors CH 222 g CH 462 Experimental Chemistry II E CH 503 Desis (Chemistry) | |||
GEO 503 nesis (Geosciences) | |||
OC 503 Resis (Oceanography) | |||
Adventures in Learning Visiting Students SMILE Visitirig Students Earth Week Celebration Visiting Students I | |||
I m_____. _. | |||
I 9 Facilities partfjj Table III.A.2 OSTR Teaching Hours | |||
.. Cumulative Values Description Annual Values for FLIP Core (hours) | |||
(hours) | |||
Departmental 473 6,747 | |||
;E Nuclear Engineering 425 Chemistry 40 Adventures in Learning 4 | |||
4H 2 SMILE _, | |||
1 Earth Week 1 i Geosciences0) 0 Oceanic and Atmospheric Sciencesm 0 Special Classes and Projects (2) 1,015 3,652 TOTAL TEACHING HOURS (3A5) 1,488 10,399 (i) Some use hours by these departments are not shown under " Teaching Hours," but are reflected under Thesis Research, both funded and unfunded. | |||
(2) A variety ofeducational classes were conducted which involved on' e-time meetings for orientation or support purposes. These included: high school science classes, new student programs support, community college classes, and classes from other universities. In addition, this category includes 974 hours of reactor operator training. | |||
(3) See Table III.D.1 for classes and student enrollment. | |||
(4) See Table IV.A.5 for a summary of all reactor use categories. | |||
Total teaching hours reflect all time the reactor was in use for teaching, and because of this the total I (5) hours include time the reactor itself may not actually have been in operation. | |||
10 Facilities Part 111 I | |||
Table III.A.3 OSTR Research Hours Types of Research Annual Values Camulative Values for FLIP Core l | |||
(hours) (hours) | |||
OSU Research 217 7,974 Off-Campus Research 1,274 12,404 l | |||
1 l TOTAL RESEARCII IIOURSU) L491 20,378 I | |||
l I I | |||
I (1) Total research hours statistics: | |||
(a) 97% (1,448 hours) ofthe total research hours were user-funded by federal, state, or other organizations. | |||
(b) 3% (43 hours) of the total research hours were user-unfunded studies in support of graduate thesis research or other academic investigations. Reactor costs for this research were absorbed (funded) by the OSU Radiation Center. | |||
l | |||
I1 Facilities Part111 Table III.B.1 Radiation Center Spectrometry Systems: | |||
Gamma, Low Energy Photon, Alpha Rel. Efric. | |||
Room System (%) | |||
B100 Adcam 8k MCA, Ortec HP Ge 26.8 B100 Adcam 8k MCA, Ortec HP Ge 38.1 B100 Adcam 8k MCA, EG&G HPGe 30.0 B100 Adcam 8k MCA, Ortec HP Ge 28.8 D102 Adcam 8k MCA, Ortec Ge(Li) 27.0 C120 Ace 1,4k Ortec, Nal(TI) 3x3 N/A C123 Adcam 8K MCA, Canberra Ge(Li) 16.6 A138 H.P. Scaler, Nal(Tl) 2x2 N/A C134 Ace,4k Ortec, Ortec Si(Li) N/A C134 Adcam 8k MCA, PGT Ge(Li) 19.3 Cl34 Adcam 8k MCA, PGT LEP N/A I Cl34 Adcam 8k MCA, Ortec LEP N/A C120 Ace 3,4k Ortec,576A Alpha Spectrometer N/A I | |||
L | |||
[ | |||
E o | |||
m | |||
12 Fccilities Part 111 Table III.B.2 Radiation Center Liquid Scintillation Counting Systems 1 | |||
Room - | |||
System 1 I | |||
l C120 Beckman, Betamate I | |||
C120 Beckman, Betamate | |||
( | |||
C118 Beckman, Betamate C118 Beckman, Betamate i B136 Beckman, LS 6500 l | |||
l I | |||
I | |||
13 Facilities Partlli | |||
( Table III.B.3 | |||
{ Radiation Center Proportional Counting Systems | |||
[ Room > | |||
System ?: | |||
C120 NMC 1, PCS C120 NMC 2, Pt . | |||
( C120 NMC 3, PCS C120 NMC, PCC-1IT and DS 2 | |||
[ A124 NMC ACS 84 A138 Protean MPC 9400 A138 Tennelec LB 5100 Auto Counting System w/ IBM PC | |||
( | |||
{ | |||
( | |||
{ | |||
{ | |||
[ | |||
[ | |||
_.__a | |||
i i | |||
14 .. | |||
Facilities Part 111 Table III.B.4 Thermoluminescent Dosimeter Systems l | |||
Room System: ; | |||
C120 Harshaw Model 2000 A132 Harshaw Medel 2000 I' | |||
D I | |||
L 1 1 | |||
15 | |||
( Facilities Part M I Table III.C.1 Gammacell 220 6 Co Irradiator Use (2809 Ci: 7/1/97) | |||
Purpose of Dose Range. - Number of _ Use Time Irradiation: Samples -(rads) Irradiations (hours) | |||
Blood serum, 2.50 x 106 Sterilization wood, soil, to 34 584 plastic tubes 4.0 x 106 | |||
{ | |||
1.0 x 10 6 Material Memory chips, to 9 | |||
[ Evaluation gemstones 2.0 x 10 7 371 Com, bean 4.0 x 10' Botanical Studies seeds, nectarines, to 27 22 other food items 2.5 x 106 I Calfserum, 2.0 x 10 3 spleen cells, Biological Studie: to 45 79 blood, peptid 2.5 x 10 6 DNA bases l TOTALS 115 1,056 | |||
[ | |||
[ | |||
[ | |||
[ | |||
[ | |||
{ | |||
L | |||
I6 Facilities Part W Table III.D.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number of Students Course Credit . Course Title Fall Winter Spring Summer 1997 1998 1998 1998 Nuclear Engineering Department Courses NE 1Il' 3 Introduction to Nuclear Engineering 35 - - - | |||
NE 112 3 Introduction to Nuclear Engineering - 30 - - | |||
NE 113' 3 Introduction to Nuclear Engineering - - 26 - | |||
NE 231 3 Nuclear and Radiation Physics 14 - - - | |||
RHP 231 3 Nuclear and Radiation Physics 9 - - | |||
NE 232 3 Nuclear and Radiation Physics - | |||
14 - | |||
RHP 232 3 Nuclear and Radiation Physics 4 - - | |||
NE 233* 0 Nuclear Radiation Detection and instrumentation - - | |||
11 - - | |||
RHP 233* 0 Nuclear Radiation Detection and Instrumentation - - 7 - | |||
NE 319 3 Societal Aspects of Nuclear Technology 47 - - - | |||
NE 361 3 Nuclear Reactor Systems - | |||
6 - - | |||
NE 381 3 Principles of Radiation Safety 5 - - - | |||
RHP 381 3 Principles of Radiation Safety 11 - - - | |||
RHP 401 1 16 Research - 1 1 - | |||
RHP 405 1 16 Reading & Conference 1 - - | |||
NE 406 1 16 Projects 1 - - - | |||
g NE 407 1 Nuclear Engineering Seminar 13 11 10 - | |||
E RHP 410 1 12 Internship 1 - | |||
1 - | |||
NE 429" 3 ST: Nuclear Reactor Laboratory 6 5 5 - | |||
NE 444 3 Nuclear Fuel Cycle - | |||
12 - - | |||
RHP 444 3 Nuclear Fuel Cycle - 10 - -- | |||
RHP 450 3 Principles of Nuclear Medicine - - 6 - | |||
NE 454 3 Nuclear Reactor Analysis 6 - - - | |||
NE 455 3 Nuclear Reactor Analysis - | |||
5 - - | |||
NE 456 3 Nuclear Reactor Analysis 5 NE 467 4 Nuclear Reactor Thermal Hydraulics 7 - - - | |||
NE 417 3 Nuclear Power Systems Design - | |||
5 - - | |||
NE 472 3 Nuclear Power Systems Design - - | |||
5 -- | |||
RHP 480" 13 Field Practices in Radiation Protection 3 3 I NE 484" 3 Applied Radiation Safety 6 - - - | |||
= Special Topics ST | |||
* = | |||
OSTR used occasionally for demonstration and/or experiments. | |||
** = OSTR used heavily. | |||
17 Facilities Part111 Table III.D.1 (continued) | |||
Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number ofStudents - | |||
' Course Credit ' Course Title Fall Winter Spring Summer 1997 1998 1998 1998-RHP 484" 3 Applied Radiation Safety 9 - - - | |||
NE 486* 3 Radiation Dosimetry - - | |||
4 - | |||
RIIP 486* 3 Radiation Dosimetry - - | |||
7 - | |||
I RIIP 487 3 Radiation Biology - - | |||
9 - | |||
RilP 488* 3 Radioecology - | |||
1 - - | |||
RHP 501 1 16 Research - | |||
I NE 503' l 16 Thesis 4 3 1 | |||
3 1 - | |||
RIIP 503* l 16 Thesis 8 6 6 2 NE 50S l 16 Reading and Conference - | |||
I - - | |||
RHP 505 1-16 Reading and Conference 2 - | |||
3 I NE 506' l 16 Projects - - | |||
1 - | |||
I RHP 506 1-16 Projects 1 - | |||
1 NE 507 1 Seminar 2 1 2 - | |||
RHP 510 1-12 Internship - - | |||
1 - | |||
NE $35 3 Nuclear Radiation Shielding - - | |||
3 - | |||
RHP535 3 Nuclear Radiation Shielding - - | |||
9 - | |||
NE 543 3 Radioactive Waste Management - | |||
3 - - | |||
RHP $43 3 Radioactive Waste Management - | |||
7 - - | |||
NE $44 3 Nuclear Fuel Cycle - | |||
1 - | |||
I RHP 544 3 Nuclear Fuel Cycle - | |||
7 - - | |||
RH.P550 3 Principles of Nuclear hiedicine - - 5 - | |||
NE 554 3 Advanced Nuclear Reactor Analysis 1 - - - | |||
NE $55 3 Advanced Nuclear Reactor Analysis - | |||
2 - - | |||
NE 556 3 Advanced Nuclear Reactor Analysis - - | |||
2 - | |||
I NE 559" i ST/ Nuclear Reactor Lab I I I - | |||
NE 567 4 Advanced Nuclear Reactor Thermal Hydraulics 3 - - - | |||
NE 568 3 Nuclear Reactor Safety - - | |||
5 ~ | |||
I NE 571 3 Nuclear Power Systems Design - | |||
2 - | |||
NE 572 3 Nuclear Power Systems Design - - | |||
1 2 RHP 580" l-3 Field Practice Radiation Protection 2 - - - | |||
= | |||
ST Special Topics | |||
* = | |||
OSTR used occasioaally for demonstration and/or experiments. | |||
** = | |||
L OSTR used heavily, c | |||
18 Facilities Part111 I | |||
Table III.D.1 (continued) | |||
Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number of Students - | |||
Course : Credit Course Title Fall Winter Spring Summer 1997 1998 1998 1998 RHP 584* | |||
* 3 Applied Radiation Safety 4 - - - | |||
RHP $85 3 Environmental Aspects of Nuclear Systems 13 - - - | |||
RHP 586* 3 Advanced Radiation Dosimetry - - 1 - | |||
RHP 587 3 Radiation Biology - - 7 - | |||
RHP 588* 3 Radioecology - 5 - - | |||
RHP 589 i ST: Computer Modeling Lab - 4 - - | |||
l RHP 599 1 ST: Principles of Nuclear Medicine - - 1 - | |||
RHP 599 2 ST: Principles of Nuclear Medicine - - 1 - | |||
l NE 603* l-16 Thesis - - - 2 | |||
( RHP 603 1 16 Resis - | |||
3 3 - | |||
NE 607 I Nuclear Engineering Seminar 2 1 1 - | |||
( | |||
RHP 607 Nuclear Engineering Seminar l | |||
1 - - 2 - | |||
3 RHP 610 1 12 Internship - | |||
1 - - | |||
NE 654 3 Neutron Transport neorv 6 - - - | |||
Courses from Other Departments CH 222' 5 General Chemistry (Science Majors) - 456 - - | |||
CH 462* 3 Experimental Chemistry 11 Laboratory - 26 - - | |||
CH 503 1-16 Thesis (Chemistry) 2 1 1 - | |||
CHE 101 3 Chemical Engineering Orientation 40 - - - | |||
CE 356 3 Technoloev and Environmental Systems - - 45 .. | |||
Courses from Other Institutions CH 223 PCC Chemistry - - - 40 g | |||
RH 289 LBCC Alternate Enerev Sources 12 30 - - | |||
E GS 105 CCC General Science - - - - | |||
GS 105 LBCC General Science - 84 - - | |||
CH 223 LBCC l | |||
Nuclear Enerev _ | |||
- - 44 - M NOTE: | |||
This tsble does not include the thesis courses from other OSU departments (see Table VI.C.2). | |||
ST = Special Topics | |||
* = | |||
OSTR used occasionally for demonstration and/or experiments. | |||
** = | |||
OSTR used heavily. | |||
I | |||
[ | |||
19 Facilities Part til CENTRAL EX PE RIM E NTAL r | |||
THE RM ALIZlNG l T HIM B L E, COLUM N -, I- | |||
' ROTARY | |||
- CIMEN RACK | |||
. , ,, DR IVE SHAFT SPECIMEN . iJ _ | |||
. REMOVAL TUBE r a - ION CHAMBER | |||
- ,, SUPPORT TUBE | |||
**I , | |||
PN E UM ATIC | |||
~ | |||
tj.f \. _, ..- | |||
', T R AN S f" E R ROTARY **' = | |||
SPECIMEN R AC'K - d. - | |||
k' N I' 5A % ,,; | |||
-I | |||
, +4, Ng. FUE ' ELEMENTS PIERCING g y. | |||
* BEAM TUBE ,' | |||
, s. . f | |||
' .,y .$.. | |||
f BEAM TUBE'.' . 1 j | |||
PLUG - . - | |||
, GRAPHITE REFLECTOR e | |||
. :: }y \l 1 | |||
f , | |||
, j J THERMAL COLUMN | |||
..\.. | |||
i. | |||
fj x | |||
. . . . s | |||
-l :.: | |||
..# 4 4 | |||
; 5. :q | |||
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: ;: ..,z..., | |||
*~ | |||
6 * | |||
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,.- , . );r[g. , | |||
'N, | |||
' = + + | |||
+3 ' ,', * . | |||
[ | |||
[ (hill- 278) . _ _ . | |||
( | |||
l Fig. III.A.1 Cutaway View of Standard TRIGA Mark 11 Core Arrangement | |||
n . | |||
s | |||
= | |||
RADIAL BEAM PORT - | |||
O | |||
#1 . - * | |||
. RADIAL BEAM PORT | |||
# 2, | |||
" ;N | |||
.. , " 2 7 3 C-40* . | |||
N ~ | |||
" t.E A0 z | |||
- THERMAL | |||
- - 4 | |||
. THERMAL , l . / COLUMN | |||
- ~ " | |||
' SHIELD GRAPHITE | |||
^,'. . | |||
/ DOOR REFLECTOR ,- f-- ALUMINUM C ASING , | |||
f ALUMINUM '. ~ . .. | |||
w 09"_l_1. | |||
~ | |||
l GRAPHITE THERMAllZlNG I e | |||
/ , e f | |||
22 F T. tO tN. | |||
8FT COLUMN : | |||
/ [CO,RE I te40 , | |||
/, ,. ' , . ' i ' ' . '- | |||
[BORAL I | |||
POOL IRF.ADIATION FACILITY POLYETHYLENE | |||
.- I t * - ' l. U ' ' .' ."-' *. | |||
* j GRAPHt TE 6 . THERMAL THERMAL SHIELDING COLUMN COLUMN | |||
.- !.g, . . | |||
- - + DOOR PLUG 2.21N. | |||
.q. | |||
blREACTOR WATER | |||
- , TANK | |||
~ | |||
i STEEL SHADOW SHIELO | |||
/ | |||
.x 27 . 3 _ ,50 TANGENTIAL BEAM PORT RADIAL W5 PIERCING BEAM PCAT n | |||
d4 28FT 4 tN r | |||
= | |||
A Fig. III.A.2 Horizontal Section of TRIGA Mark II Reactor $ | |||
m m m m m m m m m M M M m m m m m m m | |||
R | |||
~. | |||
l / 11 il II I f/A . | |||
.i3 _ . . | |||
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ALUMsNUM TANG | |||
_ 3 py 6 n ssy f, l iryp, 28 FT. sgy, | |||
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12 FT. I.gn g | |||
~ V '- | |||
l - | |||
GRAPHITE PQQLgpRADtATDON .. INUM CAslNG FACILgry ' CORE BORAL l ' | |||
I ffffff - | |||
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[?i=?kb.%.:v. | |||
_.ty , - y sTAnoAno co ,c ,,,r .. :,, . | |||
28 FT. Ass. | |||
y Fig. Ill A.3 Vertical Secdon ofTRIGA Mark Il Reactor au | |||
__u | |||
22 Facilities Part111 I | |||
I COLLAR & SAMPLE CHAM 8ER INTERLOCKS 3 HlCROSWITCHES SAMPLE CHAMBER DOOR | |||
" LEAD SHIELDING COLLAR (Opened for loading) | |||
, :: s MICROSWITCH g...-i.l T | |||
jg/ ; | |||
(Door Interlock) | |||
SAMPLE CHAM 8ER C ' | |||
A/ ' | |||
~ | |||
%r DRAIN f , U | |||
' '- / | |||
SHIELOING PLUG C L , | |||
RADIOACTIVE SOURCE- 1 | |||
'N E h E RADIATION SHIELO . | |||
DRAWER, UP c : | |||
I g l , | |||
(Loading Position) I e I M t | |||
l[ l N r | |||
/ | |||
2 MICROSWITCHES N (Drawer Down) g | |||
\ | |||
/ I l | |||
BACK-UP MICROSWITCHES I | |||
I Fig. III.C.1 Gammacell 220 "Co Irradiator I | |||
$ -Q 04(4 fM.J.4 MM M8 M4f8P+ W M M N-"W"4 . SWM MM WM 3 N NNN '8M M1'M W-@d.W'M W.4EEas g- - - - . M W.ET NMp@4HM@ MN4 'ym MM 46 M 6%g W.*M NM NWMEMPWM-WNMe o-NM N% | |||
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1 Reactor Part IV lI I Part IV l REACTOR A. Operating Statistics For the current reporting period, some of the operating statistics for the OSTR showed a slight drop as shown in this section. Operating data by individual category are given in Table IV. A.1 and annual energy production is plotted in Figure IV.A. I . Table IV.A.2 is included mainly for reference and summarizes the operating statistics for the original 20% enriched fuel. | |||
The thermal energy generated in the reactor during this reporting period was 38.6 megant days (MWD). The cumulative thermal energy generated by the FLIP core now totals 828.4 MWD from August 1,1976 through June 30,1998. Reactor use time averaged approximately 89.3% | |||
of the normal nine-hour, five-day per week schedule. Tables IV.A.3 through IV.A.5 detail the operating statistics applicable to this reporting period. | |||
I No fuel elements were removed or added during the reporting period. The reactor core excess reactivity increased slightly (~5 c) over this reporting period. This slight increase is due to the erbium poison in the fuel elements burning at a faster rate than the fuel. | |||
B. Experiments Performed | |||
: 1. Approved Experiments During the current reporting period there were seven approved reactor experiments available for use in reactor-related programs. The following list ofreactor experiments l identifies the seven approved experiments. Missing numbers signify reactor experiments which are in the inactive file and are not currently being used. These are listed in the next section. | |||
, A-1 Normal TRIGA Operation (No Sample Irradiation). | |||
B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities. | |||
l B-11 Irradiation ofMaterials Involving Specific Quantities ofUranium and Thorium in the Standard OSTR Irradiation Facilities. | |||
I B-12 . Exploratory Experiments. | |||
I | |||
2 Reactor Part IV I | |||
B-23 Studies Using TRIGA Thermal Column. | |||
B-29 Reactivity Worth of Fuel. | |||
B-31 TRIGA Flux Mapping. | |||
Of the approved experiments on the active list, three were used during the reporting g period. A tabulation ofinformation relating to reactor experiment use is given in Table 5 IV.B.1, and includes a listing of the experiments which were used, how often each was used, and the general purpose of the use. | |||
l | |||
: 2. Inactive Experiments Presently 30 experiments are in the inactive file. This consists ofexperiments which have been performed in the past and may be reactivated. Many of these experiments are now I | |||
performed under the more genemi expenments listed in the presious section. The following 5 l list identifies these 30 inactive experiments. | |||
l A-2 Measurement of Reactor Power Level via Mn Activation. | |||
j A-3 Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack. | |||
A-4 Neutron Flux Measurements in TRIGA. | |||
A-5 Copper Wire Irradiation. | |||
A-6 In-core Irradiation of LiF Crystals. | |||
A-7 Investigation ofTRIGA's Reactor Bath Water Temperature Coefficient and High Power Level Power Fluctuation. l B-1 Activation Analysis of Stone Meteorites, Other Meteorites, and Terrestria I | |||
Rocks. m B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column. | |||
B-4 Flux Mapping. | |||
B-5 In-core Irradiation of Foils for Neutron Spectral Measurements. | |||
B-6 Measurements of Neutron Spectra in Extemal Irradiation Facilities. | |||
B-7 Measurements of Gamma Doses in External Irradiation Facilities. | |||
B-8 Isotope Production. | |||
B-9 Neutron Radiography. | |||
B-10 Neutron Diffraction. | |||
B-13 This experiment number was changed to A-7. | |||
B-14 Detection of Chemically Bound Neutrons. | |||
l l I | |||
3 Reactor PartIV B-15 This experiment number was changed to C-1. | |||
B-16 Production and Preparation of"F. | |||
B-17 Fission Fragment Gamma Ray Angular Correlations. | |||
B-18 A Study of Delayed Status (n, y) Produced Nuclei. | |||
B-19 Instrument Timing via Light Triggering. | |||
I B-20 Sinusoidal Pile Oscillator. | |||
B-21 Beam Port #3 Neutron Radiography Facility. | |||
B-22 Water Flow Measurements Through TRIGA Core. | |||
B-24 General Neutron Radiography. | |||
B-25 Neutron Flux Monitors. | |||
B-26 Fast Neutron Spectrum Generator. | |||
B-27 Neutron Flux Determination Adjacent to the OSTR Core. | |||
B-28 Gamma Scan of Sodium (TED) Capsule. | |||
B-30 NAA of Jet, Diesel, and Furnace Fuels. | |||
C-1 PuO2 Transient Experiment. | |||
I C. Unplanned Shutdowns Therewerefifteenunplannedreactorscramsduringthecunentreportingperiod. Ascramoccurs when the control rods drop in as a result of an automatic trip or as a result ofthe operator pushing I the manual trip button. Table IV.C.1 contains a summary ofthe unplanned scrams, including a brief description of the cause ofeach. | |||
D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59 The information contained in this section of the report provides a summary of the changes I performed during the reporting period under the provisions of 10 CFR 50.59. For each item listed, there is a briefdescription ofthe action taken and a sununary ofthe applicable safety evaluation. | |||
m Although it may not be specifically stated in each of the following safety evaluations, all actions taken under 10 CFR 50.59 were implemented only after it was established by the | |||
{ OSTR Reactor Operations Committee (ROC) that the proposed activity did not require a change in the facility's Technical Specifications and did not introduce or create an | |||
- unreviewed safety question as defined in 10 CFR 50.59(a)(2). | |||
U | |||
___J | |||
Reactor Partly I | |||
: 1. 10 CFR 50.59 Changes to the Reactor Facility There were five changes to the reactor facility during the reporting period. | |||
: a. Installation ofa Separate Cleanup Systemfor the Bulk Shielding Tank (1) Description The cleanup system for the water in the bulk shielding tank (BST) was I | |||
replaced to allow for complete separation between the water in the B ST and that in the pnmary reactor tank. This separation prosided the capability for the operations staff to place a chemical tracer in the water of the BST tank in order to confinn whether that tank was the source of the water leakage from the thermal column and beam port No. 2. The cleanup system also serves the function ofensuring excellent water quality to prevent corrosion ofthe stainless steel liner installed in January and February of 1997. | |||
The new system is housed in the D106 Mecht.nical Room and has siphon breaks 1 inch below the low water level. This vill prevent accidental drainmg of the BST. | |||
l It was proposed that the operations staffte move the existing cleanup lines and valves (DVl9 and DV2) which are identified in Fig.1.60 of the OSTR training manual. The ends ofthe piping were capped offat the 12 foot level. | |||
The BST cleanup system was installed f.fter being satisfactorily tested by the Reactor Supervisor. | |||
(2) Safety Evaluation The proposed facility change did not increase the probability ofaccidentally draining water from the Bulk Shielding Tank or from the reactor tank nor did it cause any corrosion problems with the primary system, since it was constructed with PVC pipe. ; | |||
: b. Replacement ofthe Rack and Drive Gear on the Regulating Rod 1 | |||
(1) Description Inspection ofthe regulatory rod drive system on September 10,1997 revealed that the rack had experienced significant wear and was in need of replacement. Unfortunately, the manufacturer ofthe rod drive system was | |||
5 | |||
\ Reactor PartIV unable to provide replacement parts for the rack, drive gear, draw tube | |||
) bearing, or drive bearing. These parts were available at the Radiation Center in the form of the new stepper rod drive which had been aw aiting installation pending final work on the development ofinterfacing and installation procedures. These parts were exactly the same as those in the existing l regulatory rod with the single exception that the stepper motor rack was made of brass instead of steel. Telephone conversations with General Atomic confirmed that the stepper motor purchased by OSU was the same model which had been placed in service at other facilities as direct replacement for theolderroddrivedesigns. Sincethemanufacturerhadsuccessfullymoved to using brass as the rack material in rod drives, the OSTR stafIwas confident l | |||
that the brass rack would perform its intended function and that it satisfied the ! | |||
need for an equivalent replacement part. | |||
Therefore it was proposed that the parts be replaced with those from the new stepper motor. The control rod drive maintenance shall be performed in j accordance with OSTROP 12," Control Rod Maintenance, Removal and E Replacement Procedures." | |||
j (2) Safety Evaluation The control rod drive mechanism was designed to maintain positive control over the insertion or removal ofreactivity from the core. The parts described did not diminish the ability ofthe drive system to serve this function. There I was no identified failure mode which could lead to an inadvertent reactivity insertion, and hence there was no new unreviewed safety concem as a result of the use of the brass rack instead of the steel rack. An increased rate of wear will occur with the brass versus the steel; however, the maintenance and inspection prognun already in place will be sufficient to identify when the wear reaches the point that the rack would need replacement again. | |||
: c. AP600 Addition to the Radiation Center (1) Description Dr. Jose Reyes's AP600 project entered a new phase which required that t | |||
additional laboratory space (Advanced Thermal Hydraulic Research Laboratory) be constructed adjacent to the Radiation Center's Reactor Building. There were two issues which arose from the perspective of the reactor facility. | |||
i i | |||
l 6 | |||
Reactor PartIV I | |||
: 1) The installation of the electrical power for the new addition was accomplished by a tie-in to the existing subdistribution panel "A"in the D-106 Mechanical Room. | |||
: 2) Does a seismic concem exist because ofthe location of the new building adjacent to the reactor building? | |||
Electrical Power Tie-in he installation of the electrical power for the new addition was accomplished by a tie-in to the existing sub-distribution panel"A" in the D-106 Mechanical Room. He Project Manual required that conduit routing be verified with "the l | |||
owner" prior to installation. It also required that all conduit inside the reactor bay be rigid or intermediate metallic conduit and that all reactor bay penetrations be sealed. The sealing was required to be one of the following methods: (1) provide mechanical fire-stop fittings with UL-listed fire rating equal to wall or (2) seal opening around conduit with UL-listed foamed siliconeelastomercompound. Andfinally,expansionjointswererequiredto be installed where conduit crossed building expansion or seismic joints. | |||
l Seismic Concem The architect, gLAs Architectural Group, stated that the new addition was actually a free-standmg structure, decoupled from the existmg reactor building, and would in no way interact with the seismic integrity of the reactor facility. g, The new addition is being built to current seismic standards. m (2) Safety Evaluation The conduit runs were sufficiently sealed and routed so that the integrity of the reactor bay was maintained. Thus the current ability of the facility to contain a potential release ofradioactive material was unaffected, and there was no I increased safety concern. | |||
EI El The seismic concem was adequately addn'ssed by the new building complying with current building code. There was no safety concem with regards to the seismic interaction between the two buildings. | |||
: d. Modification to the Scram Circuit System (1) Description On February 17,1998 at 0855, the reactor failed to scram when the manual l | |||
l | |||
7 Reactor PartIV scram button was depressed. The reactor had been operating for 14 minutes at a power level of 15 W. Reactor shutdown was achieved within two seconds by the operator checking the key switch and finding that it clicked from the reset into the operate position. He then retried the manual scram button, and it operated properly. Subsequent investigation discovered that the TB2-3 to TBl-9 jumper was not present. At sometime in the past, a connection had been made between TB 1-9 and TB 10-10 which was further connected to the B deck of the console key switch. This in turn was connected to the AC (neutral) at TB10-4. The consequence was that an attemate path wns created to supply power to the control rod magnets. When the key switch was in the reset position, the scram bus was disabled, so | |||
' instead ofthe magnet power being disrupted, the alternate pow er source kept the magnets energized, resulting in the failure to scram. | |||
It was proposed that the facility be modified: | |||
: 1) to remove the connection between TB1-9 and TB10-10 and | |||
: 2) to reinstall thejumper between TB2-3 and TB1-9. | |||
I In addition, the Scientific Instrument Technician electronically checked the rest of the scram loop circuitry to provide assurance that the as-built condition matched the circuitry shown in the facility documentation. The semi-annual S&M 15.11, Console Checklist, was conducted prior to restart ofthe facility. | |||
It was furtherproposed that a modification be made to the startup procedure, OSTROP 2, to add a scram test which would confirm that the control rod l magnetic power was de-energized when the console key switch was in the reset position. | |||
(2) Safety Evaluation The proposed facility change returned the operate permissive circuitry to its original, as designed configuration and hence removed the possibility that the scram bus could be rendered inoperative by positioning the console key switch L | |||
in the reset position. The procedural change provided operational verification before each startup that indeed the magnetic power was de-energized when | |||
{ the. console key switch was in the rest position. | |||
n u | |||
8 Reactor PartIV I | |||
Additional testing ofthe remainder ofthe scrrr. cimuitry was completed and the results confumed that there were no further desiations from the as designed circuit. | |||
These proposed changes permitted compliance with the requirement in the Technical Specifications that scrams identified in Table I ofsection 3.5.3 be operable when the reactor is unsecured. These changes corrected an identified malfunction ofequipment which was evaluated in the safety analysis | |||
~ | |||
mport. They did not introduce a possibility for a different type ofmalfunction, and clearly the overall margin of safety was increased by ensuring that the l | |||
scrams are operable during all phases of operation. | |||
: e. Installation ofa Temperature Monitor on the Primary Water Return Line (1) Description As the staffof the reactor facility continued to investigate the source of the water leak fmm the thermal column and beam port No. 2, it became apparent that when the temperature of the reactor tank primary water dropped below 23 C, there was an increase in waterleakage from both facilities. In order to minimize leakage from these facilities, the reactor primary cooling system had been operated with the administrative goal of maintaining the primary temperature above 23 C. In order to aid the operator in monitoring the status of the primary water temperature, it was proposed that a facility modification be performed to install a thermocouple on the outside ofthe primary piping downstream of PV6. This thermocouple was connected to a control unit located in the control room. The unit provided the operator with both an g | |||
audible and visual alarm when the primary water temperature drops below a E set point value. | |||
t Installation of the type K thermocouple used a non-invasive technique of strapping the thermocouple to the outside surface of the return leg of the primary cooling system. The location was on the 24 foot level, under the deck plating and adjacent to the current thermocouple used to monitor reactor inlet temperature. The thermocouple lead was routed to the control room using existing conduits and was connected to the alarm / monitor unit (Love Controls Temperature Control Unit) in the right side cabinet. AC power for the new unit comes from an existing 120V power strip in the right hand side cabinet. | |||
An audio and visual alann with acknowledge capability was also designed into the circuit. The circuit was installed in the right hand side cabinet adj acent to l | |||
l | |||
i 9 | |||
l Reactor partjy I | |||
the temperature control unit. | |||
l The advantage o f the new system is that it has alarm eapability to warn the operator when the temperature of the retum water is below the set point. The set point is specified and changed by the Reactor Supervisor based on the g leakage history and the demands of the operating schedule. It was initially set 3 to alarm when the water temperature dropped below 23*C. | |||
I This system serves to notify the reactor operator when the primary temperature drops below the set point. The operator's actions are to either secure the primary cooling system to prevent further cooling or to notify the Reactor Supervisor, who has the authority to continue cooling based on other considerations. For example, the Reactor Supervisor will authorize cooling the primary water below the set point during power calibration opemtion. The consequence ofcontinued cooling is the increased possibility ofwater leakage from the thermal column and beam port No. 2. | |||
(2) Safety Evaluation There was no unreviewed safety concem from the installation ofthis monitor, The thermocouple was mounted using a technique currently employed on the existing temperature channel. The mounting materials were stainless steel, and hence there was no corrosion concem. The mounting did not require drilling into the existing piping, so there was no concem regarding leakage of air or water through the thermocouple mount. | |||
l 2. 10 CFR 50.59 Changes to Reactor Procedures There was one change to reactor procedures which were reviewed, approved and performed under the provisions of 10 CFR 50.59 during the reporting period, | |||
: a. Revisions to the Radiation Center and OSTR Emergency Response Plan (1) Description As a result of the annual review of the Radiation Center and OSTR Emergency Response Plan, a number ofchanges to the plan were needed. | |||
The majority ofthe corrections were typograpideal and grammatical errors or were updates which reflected staffchanges. The emergency plan was also I | |||
I | |||
10 Reactor Part lY I | |||
updated to conform to the revised Appendix I of NUREG-0849. The detailed description of the evaluation and implementation of this revision to l1 Appendix I is given in Record #97-4 of Emergency Response Plan activities. | |||
One other change was to correct the plan to reflect the change from semi-l annual calibration ofportable instmments to an annual schedule. The details i of these changes are given below. , | |||
1 | |||
? l l Cover Pace , | |||
Changed the last revision date to " November 1997." ' | |||
All Chanced Paces Added or changed the revision date to "11/97." | |||
l Pace i. ii. iii. Table of Contents Retyped the table into the current word processing program. On pages ii and l iii, changed the current page number from 7-5 through 7-17 to 7-6 through 7-18. | |||
Pace 3-1. Orecon Office of Enercy (OOE) i Corrected the reference to OOE rules from "30-005 and 30-010" to "345-030-0005 and 345-030-0010". | |||
Pace 4-4. footnote (1) | |||
Changed the last sentence from "This value is 8.13 x 10-4 (0.0008) of the 15 mrem action level ..." to "This value is 1.63 x 10-4 (0.00016) ofthe 75 mrem l | |||
action level ...". | |||
1 Pace 5-4. footnote (1) l l Changed the last sentence from: | |||
4 This value is 8.13 x 10 (0.0008) ofthe 15 mrem action level specified, ........ | |||
To: | |||
1 | |||
( | |||
l1 | |||
{ Reactor PartIV | |||
{ | |||
4 This value is 1.63x10 (0.00016) ofthe 75 mrem action level specified ........ | |||
Pane 7-5. 7.1.4. Protective Actions for Personnel and Onerational Events | |||
[ Moved from page 7.5 to 7.6 Page 7-11. Part 7.2.4 Protective Actions for Notification ofUnusual Events f | |||
Changed from: | |||
h) A battery-operated public address device (bullhom)is available in the emergency equipment locker in the ESC to communicate protective | |||
[ actions and other information to personnel at the assembly area. | |||
( h) A battery-operated public address device (bullhom)is available in the emergency equipment locker in B134 to communicate protective actions and other information to personnel at the assembly area. | |||
Pane 8-2. Part 8.2.1 Portable and Fixed Radiological Monitors | |||
[ | |||
(1) Changedparta)numberiv)Neutronsurveymeters(BF3detectors and rem meters). | |||
[ | |||
To: number iv) Neutron survey meters. | |||
[ (2) Changed v) Alpha survey meters (gas flow and scintillation). | |||
To: v) Alpha survey meters. | |||
(3) Deleted - vi) Tritium survey meter (gas flow). | |||
[ | |||
(4) Changed - vii) to vi) | |||
( Pane 8-8. Part 8.3.5 Medical Treatment Changed: | |||
iv) The radiological emergency footlocker at the hospital, which contains | |||
[ all the equipment necessary for monitoring and decontamination, will . | |||
r | |||
12 Reactor PartIV have been set up near the restricted treatment area. The typical , | |||
contents of this box are detailed in Appendix B. | |||
l l | |||
l To: | |||
iv) The radiological emergency cabinet at the hospital, which contains all the equipment necessary for monitoring and decontamination, will have been set up near the restricted treatment area. The typical contents of this cabinet are detailed in Appendix B. | |||
Pace 10-3. Part 10.4.1 Reauired Maintenance and Minimum Calibration Freauency Changed: | |||
b) All portable survey instruments are repaired as necessary and calibrated at least semiannually. | |||
To: | |||
b) All portable survey instruments are repaired as necessary and l | |||
calibrated at least annually. | |||
Apnendix B. nace B-1. nart B.2 Semi-Annual Emercency and Safety Equipment Insnection checklist Changed: | |||
a) Good Samaritan Hospital Emergency Department footlocker. | |||
I To: | |||
a) Good Samaritan Hospital Emergency Department cabinet. | |||
Annendix B. nace B-2 Added: | |||
Under A 2 - Exchange Batteries and check for proper operation. | |||
Under A 4 - 100 moist towelettes. Replace if dried out. | |||
l Apnendix B. Pace B-3. Item B. B134 Small Emercency Ea cinment Cabinet | |||
#15 1 | |||
l | |||
13 Reactor PartIV Changed: | |||
Four rolls of masking tape (replace annually) | |||
To: | |||
Four rolls of masking tape. Replace if discolored, dry, or brittle. | |||
Annendix B. Pace B-4 Item A: Changed - Good Samaritan Hospital (Foot Locker). | |||
TO: Good Samaritan Hospital (Cabinet). | |||
l Item A-9: Changed 4 rolls of 1 1/2" masking tape. Note that the tape is usable, i.e., not dried out or shriveled up. | |||
TO: 3-4 rolls ofi l/2" masking tape. Replace ifdiscolored, dry, or brittle. | |||
Annendix B. nace B-5 Item B # 6: Changed - 2 rolls masking tape. | |||
TO: 2 rolls masking tape. Replace if discolored, dry, or brittle. | |||
Item B, Box 2 #9: Changed - Masking tape TO: Masking tape. Replace if discolored, dry, or brittle. | |||
Item B, Box 3 #f: Chantved - Masking tape TO: Masking tape. Replace if discolored, dry, or brittle. | |||
Appendix. nace B-6 Box #5, Item 3a: Changed - Replace the battery in the air sampler. | |||
TO: Note date on battery, replace the battery in the air sampler biannually Box #5, Item 5: Deleted item a. Check and replace batteries. Changed item b to a. | |||
Annendix B. nace B-7 Box #5, Item 10: Changed - 2 flashlights. | |||
TO: 2 flashlights. Replace batteries and check for proper operation. | |||
14 Reactor l'artIV I | |||
Item C, #2: Changed - 2 flashlights. | |||
TO: 2 flashlights. Replace batteries and check for proper operation. | |||
Annendix B. nace B-10. item _A Changed item 1 title from "A100 Cabinet" to "B134 Large Cabinet" Changed item b. from "...large decon kit..." to ' ...large decon kit #1. ." | |||
Added item "c. Check large decon kit #2 (see item C. on next page)." | |||
Deleted entire item 2, "B126B Cabinet," including items a and b. | |||
Renumbered remaining items 3 and 4 to be items 2 and 3 Accendix B. case B-10. item B Number 1 : Changed - Verify the quantity and quality ofthe following small kit items: (ReSil or mplace as necessary to meet the mmimum quantity indicated for each item). | |||
TO: Verify the quantity and quality ofthe following small kit items: (Refill or replace as necessary to meet the minimum quantity indicated for each item or g | |||
ifitems are unusable). g Deleted the column for "Cl22" from the table. | |||
Anoendix B. nace B-11 Item C, # 1 : Changed - Verify the quantity and quality of the following large decon items: (Refill or replace as necessary to meet the minimum quantity l | |||
indicated for each item). | |||
l TO: Verify the quantity and quality ofthe following small kit items: (Refill or E | |||
replace as necessary to meet the muumum quantity indicated for each item or 5 ifitems are unusable). | |||
Changed table for Large Decon Kit item rooms from A 100 to B 134# 1, and B126B to B134#2. | |||
Attachment B: Revisions to the OSU Radiation Center and g TRIGA Reactor Emergency Response Plan E Implementing Procedures (ERIPs) | |||
I I | |||
15 Reactor PartIV | |||
[ | |||
Pace E-2-1 footnote (1) | |||
{ | |||
4 Changed the last sentence from"This i ahie is 8.13 x 10 (0.0008) ofthe 15 mrem action level specified, .... to "This value is 1.63 x 104 (0.00016) ofthe | |||
[ 75 mrem action level specified, .... | |||
Pace E-5-6 Anoendix B | |||
{ | |||
Made consistent with initials D. R. Carver, added J. T. Groome under APEX | |||
[ Facility Operator and M. Yundt under APEX I & C Technician. | |||
[ Pace E-5-16. Checklist for the Initial Emereency Resnonse Action of the Radiation Protection Technolocist Changed S. P. Smith to D. R. Carver. | |||
~ | |||
Pace E-5-17. Checklist for the Initial Emercency Response Action of the Radiation Center Recentionist | |||
[ Changed C. L. Hall to D. C. West. | |||
NEW Pace E-5-18 Inserted new Page E-5-18 with the following text. | |||
Renumbered previous page E-5-18 to become E-5-19. | |||
{ | |||
CHECKLIST FOR THE INITIAL EMERGENCY RESPONSE ACTION OF THE BUILDING CHECKERS | |||
.NAME CORRIDOR E. G. Torne A K. M. Brock B M. R. Conrady C | |||
[ A.D. Hall D S. E. Binney E F | |||
L | |||
16 Reactor Partly ERIP 7. nace E-7-4 Inserted new version of Radiation Center Directory. | |||
l Pace E-7-6 For Radiological Assessment Team, deleted "E. F. Forrer" and "S. R. | |||
Smith," and added "D. R. Carver" in alphabetical order by last name. | |||
For Historian,1st Choice, changed "C. L. Hall" to "D. C. West". | |||
For Historian, 2nd Choice, changed "J. R. Smith" to "L. M. James". | |||
(2) Safety Evaluation l | |||
The only change in the plan which changed from the original intent was the definition ofaction level for the duration ofa fire which would require the l | |||
declaration ofan Unusual Event. In the previous plan it wm defined as 10 minutes and in Appendix I as 15 minutes. Since there wm no documented or institutional memory for the basis ofselecting the 10 minute period, the ROC Emergency Plan Review Subcommittee felt it wm not a decrease in the effectiveness of the plan if the NRC definition of15 minutes wm used instead. The annual calibration criterion for the portable survey i instruments is actually the industry standard of practice and does not increase the chance that a given instrument would be incapable of l | |||
performing its intended function. All of the other changes corrected g typographical and grammatical errors or updated personnel lists. Since E these changes made the plan easier to read, the plan's effectiveness actually improved. | |||
: 3. 10 CFR 50.59 Changes to Reactor Experiments There were no changes to reactor experiments during this reporting period. | |||
I I | |||
I I | |||
17 Reactor PartIV E. Surveillance and Maintenance | |||
[ 1. Non-Routine Maintenance September 3,1997 Completed the installation ofa new deionized water make up and | |||
( clean up system for the bulk shielding tank. | |||
September 15,1997 Refurbished the regulating rod drive assembly. Replaced the rack | |||
[ | |||
and pinion gears, the pinion shan and bearing, and the draw tube sleeve bearings. | |||
[ | |||
September 17,1997 Replaced the reactor building water heater. | |||
-[ December 4,1997 Inspected and performed maintenance on the chemical injection pump in the reactor secondary cooling system. | |||
December 5,1997 Replaced the bearings on the regulating rod motor. | |||
December 15,1997 Changed out the dual element mechanical shaft seal on the reactor | |||
{ | |||
demineralizer pump and replaced the pump's motor bearings. | |||
[ December 16,1997 Received new Flip IFE and FFCR. | |||
December 22,1997 Replaced the stack nr'.iitor pump. Rebuilt old pump for spare. | |||
January 5,1998 Replaced capacitors in the stack gas recorder amplifier to correct a 60 cycle oscillation on the pen. | |||
{ | |||
January 27,1998 Replaced all transistors on the test signal card (XA-6) for the log | |||
[ and linear channels. | |||
January 29,1998 Cleaned and inspected the Corkin compressed air pressure regulator that supplies the transient control rod. | |||
January 29,1998 Replaced the % demand potentiometer on the console. | |||
February 9,1998 Replaced the local meter on area radiation monitor #8. | |||
February 18,1998 Performed scram failure investigation of console wiring, f | |||
L r | |||
18 Reactor PartIV I | |||
February 20,1998 Performed scram circuit modification that assures control rod g magnet power is de-energized when console key switch is in the a reset position. | |||
February 23,1998 Completed electronic tests verifying the console power pathway, the magnet power circuit, and all scram circuit wiring. | |||
April 28,1998 Completed point-to-point checks ofall reactor console interwiring verifying that as-built conditions match the circuitry shown in g facility documentation. E April 29,1998 Replaced all the transistors in the servo module's pre-amplifier and power amplifier. | |||
April 29,1998 Replaced the K-14 relay that switches regulating rod motor power to servo control for auto / square wave modes. | |||
May 5,1998 Installed a reactor primary inlet temperature alarm system. | |||
May 5,1998 Replaced the chopper in the reactor control servo system. | |||
May 12,1998 Installed 2" rigid conduit in reactor bay for electrical tie-in to the new Advanced Thermal Hydraulics Research Laboratory constructed adjacent to the reactor building. | |||
: 2. Routine Surveillance and Maintenance The OSTR has an extensive routine surveillance and maintenance (S&M) program. | |||
Examples of typical S&M checklists are presented in Figures IV.E.1 through IV.E.4. | |||
1 ms marked with an asterisk (*) are required by the OSTR Technical Specifications. | |||
I F. Reportable Occurrences There were two reportable occurrences during the reporting period. The first involved a failure I | |||
to submit a Material Balance Report, required by 10 CFR 74.12 (a)(1), within 30 days following the end ofthe reporting period. The occurrence was self-identified and was addressed E | |||
5 in detail in a report to the NRC dated September 5,1997. | |||
The second event involved a fhilure ofthe OSTR to shut down when the console manual scram button was pushed. The event was promptly reported, thoroughly investigated, the root causes were identified and effectively corrected in a timely manner. This occurrence was self-identified and was addressed in detail in a report to the NRC dated March 2,1998. | |||
I | |||
1 _r1 r o r mums e mums imms u-Table IV.A.1 ie a | |||
a 4 | |||
OSTR Operating Statistics (Using the FLIP Fuel Core) | |||
Ratisaky Wfg QQ;f_c Ql::. ;L l ;. % nyQ) a.M QQ:) jf. _ , ( ;,., , __;f';p_; 'Qg;Q;lff ikNgusg&Q l976, fyNdly171977#' 19781 ifj$ly ,*;J M RIiI/]f/1980 ijD 6 M A T gg | |||
[ j% g [fThrough; 3 PJuls;1[ddiid | |||
'IEThro $$Th[ rough}gI $[ThrdSiiiij}% | |||
l | |||
!Julfli19811 ;Juif1,1982a [JilyX1983? | |||
$Thir6ug'h7 (ThroEg6 '$ThNujE@ | |||
IBFCIP, M 'JuIE5d?.19 . | |||
:-l$I,) 88}AugNh TJhne 19783 fdni$$,3pi9 1 VJdsf38',t198dl fjelif36'A1988- Juni 30,1'982 JNnE35,51'983 JuSE30,h f8 | |||
, i Operating Hours (critical) 875 819 458 875 1255 1192 1095 1205 Megawatt Hours 451 496 255 571 1005 999 931 943 Megawatt Days 19.0 20.6 10.6 23.8 41.9 41.6 38.8 39.3 Grams2"U Used 24.0 25.9 13.4 29.8 52.5 52.4 48.6 49.3 Hours at Full Power 401 481 218 552 998 973 890 929 (1 MW) | |||
Numbers of Fuel Elements Added or Removed (-) 85 0 2 0 0 1 0 0 Number of Irradiation 44 375 329 372 348 408 396 469 Requests Seefootnotesfollowing the table. }q L. | |||
.._____o | |||
E Table IV.A.1 (continued) { | |||
a, OSTR Operating Statistics (Using the FLIP Fuel Core) | |||
H3 f Q $j@i %@ "$fAQ J7s'@/1lpys) @[6$$lpglj %.]Qj@ yyggi h[j/6@@hp%ijl fsD fi qdh1 YJa Ietti;f,o;jl9841 1985' 1986 EJulyy1987? MQ'alyJ1988sJSQ R'J Q]g@ | |||
f;.1(1989 V OJuly I 19905 !dJ61ypi99, pffd) Not M } ugE} ' | |||
$(Jh l fMNhFoEilNI!DEhhiigiE$i g li | |||
$hkh IIIrN$iE.Ejf | |||
%FLTPIliNS J M $6/19$3 Ud6N.6}158N JdEW50/1987) fJ$$if3671Nfii h$i3d,'1Ni91 U A'QigDE IEThho6sgIff$ Milirofh,1 302155d EtiEEI6,k19915 Tsii[$0 992 Operating Hours (critical) 1205 1208 1172 1352 1170 1136 iO94 1158 Megawatt Hours 946 1042 993 1001- 1025 1013 928 1002 Megawatt Days 39.4 43.4 41.4 41.7 42.7 42.2 38.6 41.8 2 | |||
Grams "U Used 49.5 54.4 51.9 52.3 53.6 53.0 48.5 52.4 Hours at Full Power 904 1024 980 987 1021 1009 909 992 (1 MW) | |||
Numbers of Fuel Elements Added or Removed (-) 0 0 OW -2W 0 -1,+1W -lW ON Number of Irradiation 407 403 387 373 290 301 286 297 Requests Seefootnotesfollowing the table. | |||
i | |||
-Q M M M M WEE M M ' | |||
M M M M M | |||
o em- - - -m m m m m m m m m ~ m m M~ | |||
Table IV.A.1 (continued) l' E | |||
OSTR Operating Statistics (Using the FLIP Fuel Core) | |||
[#$7rallEd$$I k I Pp1 rgb | |||
(($ $$iy:{17199dE$k i1993:n | |||
$(Qf33 (( @ | |||
* k [ Q 7 Q y );% f(~ Q-$$7 f JiIyilpff)5% | |||
g~ i . M hKIhEdighh iIlhThYdingh{j FJdly]fI1997 fJ6iy h 19fM!$k s2 | |||
@f$ | |||
No m 19h7 ?J65856,W995' b;f$ne'$031 g$ hrosiYfi ly(1j5996Thr36$ ' DThrouYh% | |||
f i PJen'e $571 . | |||
I uhES$}1s9 J5&E3631599 Operating Hours ' | |||
(critical) 1I80 1248 1262 1226 1124 1029 Megawatt Hours 1026 I122 I117 1105 985 927 Megawatt Days 42.7 46.7 46.6 46.0 41.0 38.6 2 | |||
Grams "U Used 53.6 58.6 58.4 57.8 51.5 48.5 Hours at Full Power (1 MW) 1000 1109 1110 1101 980 921 Numbers of Fuel Elements Added or Removed (-) 0 0 0 -lW -1, + 1m 0 Number of Irradiation Requests 329 303 324 268 282 249 (1) The reactor was shutdown on July 26,1976 for one month in order to completely refuel the reactor with a new FLIP fuel core. | |||
(2) No fuel elements were added, but one fueled foilower control rod was replaced. | |||
(3) Two fuel elements were removed due to cladding deformation. | |||
(4) One fuel element removed due to cladding deformation and one new fuel element added. | |||
(5) One fuel element removed for core excess adjustment. N Q g N - | |||
(6) No fuel elements were added, but the instrumented fuel element was replaced. | |||
(7) One fuel element removed due to cladding deformation and one used fuel element added. | |||
_J | |||
Table IV.A.2 & M R | |||
a OSTR Operating Statistics with the Original (20% Enriched) Standard TRIGA Fuel Core Kot#iticiaI7 MT!T 67A 3Ff M M P3fU#9 @4pr MCQ lf-70s WGP3?! @W5?$ Ddiffi% 3;$44 .in;TB 7;G@? M.ffgp l h6. beat '4 EMag8,jMi y 9JulMO fJull;69p : Apr ts71% R[pE1,'72j' AprI;73i iApr lj 74y s s cdhr[$,;755 1Ap 3 Ef M 65 W foM ~ filiN0 | |||
) MfhroTdhY2 du508l%g NinNigliY f>Thfough3 $Th'roush? s. Thio' ugh $ThtVugD DTh6iiakhd SThNuglid 6 Th,r,1476:roukhs fifs h0Ti3868) 692 $fE3) | |||
EM(2Pd;d5) tMaF31 Mil lME31;72I 'ftmV31;i7b IMP 31t74I !Na'r'Sid55 iM& Tit 7s! Dui16,i7i 98* 0 763 M4 e4I6WM N@Qlh[i *EWJ5"d 4 @i F3i3fPa dun'2d M fR>#$7 SNT!8'IUS ETsst#8 MM?WE SRf(4) ''h"hIm 2 | |||
Operating 904 610 567 855 598 954 705 563 794 353 6903 llours (critical) | |||
Megawatt 117.2 102.5 138.1 223.8 195.1 497.8 335.9 321.5 408.0 213.0 2553.0 llours Megawatt Days 4.9 4.3 5.8 9.3 8.1 20.7 14.1 13.4 17.0 9.0 106.4 8 | |||
6.1 5.4 7.2 11.7 10.2 26.0 17.6 16.8 21.4 10.7 133.0 llours at Full Power (250 429 369 58 - - - - - - - | |||
856 kW) | |||
H un at FuH - - 20 23 100 401 200 291 460 205 1700 Power (1 MW) | |||
Number of Fuel 70 Elements Added 2 13 1 1 1 2 2 2 0 94 to Core initi@ | |||
Number of Irradiation 429 433 391 528 347 550 452 396 357 217 4100 Requests | |||
"" I 202 236 299 102 98 249 109 183 43 39 1560 Pulses (1) Reactor went critical on March 8,1967 (70 element core; 250 kW). Note: His period length is 1.33 years as initial criticality occurred in March of 1967. | |||
(2) Reactor shut down August 22,1%9 for one month for upgrading to 1 MW (did not upgrade cooling system). Note: This period length is only 0.75 years as there was a change in the reporting period from July-June to April-March. | |||
Reactor shut down June I,1971 for one month for cooling system upgrading. | |||
g (3) 4 (4) Reactor shut down July 26,1976 for one month for refueling reactor with a new full FLIP fuel core. Note: This period length is 0.33 years. y M M M M M M M M M M - | |||
M M M M | |||
23 Reactor PartIV Table IV.A.3 i | |||
Present OSTR Operating Statistics I | |||
Operational Data Cumulative Values I F Core Annual Values - for MWH of energy produced 927 19,881 MWD ofenergy produced 38.6 828.4 Grams 235 U used 48.5 1039.6 i Number of fuel elements added to (+) | |||
or removed from (-) the core 0 81 + 3 FFCR(O Number of pulses 11 1,290 Hours reactor critical 1,029 24,603 Hours at full power (1 MW) 921 19,489 Number of startup and shutdown l checks 255 5,554 Number ofirradiation requests processed | |||
* 249 7,639 Number of 5amples irradiated 4,707 93,487 I | |||
E | |||
[ (1) Fuel Follower Control Rod. These numbers represent the core loading at the end of this reporting period. | |||
(2) Each irradiation request could authorize from 1 to 120 samples. The number of samples per irradiation request averaged 18.9 during the current reporting period. | |||
E L | |||
r- | |||
24 Reac:or Part IV I | |||
Table IV.A.4 OSTR Use Time in Terms of Specific Use Categories 1 | |||
- Cumulative Values ^ | |||
OSTR'Use Category | |||
' Ann al alues - for FLIP Core | |||
) (hours) | |||
Teaching Nepartmental and others)(i) 1,488 10,398 217 7,974 | |||
_OSU research(2) | |||
Off-campus research(2) 1,274 12,404 Forensic services 0 216(3) | |||
Reactor preclude time 1,104 16,752 Facility time (4) 57 6,939 Visitor demonstration (5) 9 312 TOTAL REACTOR USE TIME 4,149W 54,995 l | |||
I (1) See Tables III.A.2 and III.D.1 for teaching statistics. | |||
l (2) See Table III.A.3 for research statistics. | |||
(3) Prior to the 1981-1982 reporting period, forensic services were grouped under another use category and the cumulative hours have been compiled beginning with the 1981-1982 report. | |||
(4) The time OSTR spent operating to meet NRC facility license requirements. | |||
(5) This is the time that the reactor was used specifically for visitor open-house (demonstration) events. | |||
l The remainder of the visitors viewed the reactor dtuing times when the reactor was being operated l for regularly scheduled research and teaching. | |||
1 (6) Total reactor use time includes all multiple use hours added separately. | |||
I | |||
25 Reactor PartIV Table IV.A.5 OSTR Multiple Use Time") | |||
{ | |||
Annual Values Cumulative Values | |||
-[ Number ofUsem for FLIP Core | |||
' (hours} | |||
(hours) | |||
Two 280 3,256 | |||
{ | |||
Three 115 1,080 | |||
[ Four 38 402 Five 8 Ill Six 0 45.5 Seven 0 11 | |||
{ | |||
TOTAL MULTIPLE USE TIME 441(2) 4,905.5(3) | |||
[ | |||
[ | |||
[ | |||
[ | |||
[ | |||
[ | |||
r L | |||
( (1) Multiple use time is that time when two or more irradiation requests are being concurrently fulfilled by operation of the reactor. | |||
[ (2) This represents 43% of the total hours the reactor was critical during this reporting period. | |||
t (3) This represents 20% of the total hours the reactor was critical since startup with FLIP fuel in August of 1976. | |||
6. | |||
II ' | |||
Figure IV.A.1 OSTR Annual Energy Production Vs. Time (Annual Reporting Period) 50 I ,~ | |||
7 s, .- ~.\ /, | |||
''.x,N . | |||
j s. | |||
40 | |||
~.- v ~. | |||
t m | |||
$'30 Q | |||
= | |||
c 1 3 | |||
C A / | |||
[ ! | |||
$20 9 2 | |||
10 . , | |||
O I I I i i l i I l t j 77-78 79-20 81-82 83-14 85-86 87-88 89-90 91-92 93-94 95-96 97-98 76-77 78-79 90-81 22-83 24-85 86-87 88-89 90-91 92-93 94-95 96-97 Time (Annual Reporting Period) k 9 | |||
t | |||
l 27 Reactor PartIV | |||
{ | |||
Table IV.B.1 Use of OSTR. Reactor Experimentsm | |||
[ | |||
' Reactor | |||
( ' | |||
[ " | |||
2 iResearch -. Teaching n ' Forensic : Tjn c- -TOTAL 7 | |||
( A-1 0 38 0 14 52 B-3 | |||
( 175 21 0 N/A 196 B-23 0 1 0 N/A 1 | |||
{ | |||
TOTAL 175 60 0 14 249 | |||
( | |||
{ | |||
{ | |||
{ | |||
I | |||
[ | |||
{ | |||
(1) This table displays the number of times reactor experiments were used for a particular purpose. | |||
[ (2) The following tabulation gives the number of each reactor experiment used and its corresponding title: | |||
( A-1 Normal TRIGA Operation B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities B-23 Studies Using TRIGA Thermal Column | |||
{ | |||
(3) The time OSTR spent operating to meet NRC facility license requirements, f | |||
t I | |||
28 Reactor PartIV Table IV.C.1 Unplanned Reactor Shutdowns and Scrams Number of Type of Event Cause of Event Occurrences Operator withdrew the regulating rod too far while Pen.o d Scram 1 . | |||
taking the reactor to power. | |||
An apparent oscillation in safety channel response, while Safety Channel , at full power, resulted in the scram set point on the l | |||
^ | |||
Power Scram safety channel being reached. (These did not involve actual over power situations.) | |||
Operator observed the regulating rod behaving l sluggishly. The reactor was scrammed and the rod drive Manual Scram 1 assembly was inspected. Areas of wear were found on the rack and pinion. Worn parts on the drive assembly were replaced. | |||
Commercial power failure. Commercial power was Manual Scram 1 restored in about fiftenn minutes and reactor operation was resumed. | |||
Operator observed the linear power level to be tracking improperly in auto mode. Wam motor bearings on the Manual Scram 2 . | |||
regulatmg rod were diagnosed to be the problem. | |||
l Bearings were replaced. | |||
The scram set point on the safety channel (106%) was reached while balancing rods at IMW with a cadmium l Safety Channel experim ntal facility located in-core. The flux 3 | |||
Power Scram perturbation caused bu the in-core experiment resulted l in lower readings on the linear and percent power l channels relative tot he reading on the safety channel. | |||
l Square wave overshoot. Operator positioned the regulating rod too low in the core for square waving to Safety Channel IMW. The shielding effect on the fission chamber 3 | |||
Power Scram caused a slight delay in the power level signal to the servo system to drive in rod. The licensed power level was not exceeded. | |||
Transient rod air pressure level was found to be ~ 10 Manual Scram 1 psig higher than normal. Maintenance on the pressure regulator corrected the condition. | |||
29 Reactor PartIV | |||
{ | |||
[ Table IV.C.1 (continued) | |||
{ Failure of reactor to manually scram on initial operator Manual Scram 1 demand. NRC was inunediately notified. Wiring flaw was subsequently found and corrected. | |||
{ Operator noticed the linear power trace in auto mode to be several % broader than usual and that little, if any, Manual Scram I servo control of the regulating rod seemed to be going | |||
{ | |||
on. Problem was corrected by replacing the chopper in the servo module. | |||
[ Electronic noise caused spike in the period channel Period Scram I while the reactor was starting up in the 0.2 watt power range. | |||
[ | |||
[ | |||
[ | |||
[ | |||
[ | |||
{ | |||
[ | |||
{ | |||
{ | |||
[ | |||
r | |||
i? | |||
Figure IV.E.1 g a | |||
Monthly Surveillance and Maintenance (Sample Form) | |||
OSTROP 13 SURVEILLANCE & MAINTENANCE FOR THE MONTH OF TARGET DATE NOT TO DATE REMARKS & | |||
SURVEILLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUNO DATE BE EXCEEDED =* COMPLETED INITIALS | |||
*1 FUNCTIONAL CHECK OF REACTOR WATER MAXIMUM ur: anch. | |||
LEVEL ALARMS AND GREEN LIGHT ALARM MOVEMENT DN: inehu | |||
* 3 INCHES , L,G, ,, | |||
2 MEASUREMENT OF THE REACTOR PRIMARY MIN: 5 WATER pH MAX: 8.5 3 MEASUREMENT OF THE BULK SHIELD TANK MIN: 5 WATER pH MAX: 8.5 4 EMERGENCY POWER SYSTEM LtGUiO: -1* DN BATTERY CHECKS INVERTER S.G.: > 1.250 FUNCTIONAL CHECK 0 | |||
GENERATOR 1 VOLTS m 12.6V OC 5 EVACUATION HORN & P.A. EMERGENCY LIQUID: FULL SYSTEM BATTERY CHECKS S.G.: >1.250 VOLTS m 12.6V DC CORR: NONE 6 INSPECTION OF THE BRUSHES ON THE CHANGE WHEN PNEUMATIC TRANSFER SYSTEM BLOWER 1/4* LEFT MOTOR 7 GREEN UGHT BULB REPLACEMENT 75 WATT 8 CHANGE LAZY SUSAN FILTER F!LTER CHANGED 9 LUBRfCATE THE TRIGA TUBE LOADING TOOL USE GUN O!L NEED OtL? | |||
(REElj 10 REACTOR TOP CAM Ott LEVEL CHECK OSTROP 13.10 NEED OtL? [ | |||
11 PROPANE TANK UQU!D LEVEL CHECK >$0% g | |||
(% FULL) g | |||
*12 BULK WATER TEMPERATURE ALAP.M CHECK FUNCTIONAL _ q 13 PRIMARY PUMP BEARINGS OfL LEVEL CHECK OSTROP 13.13 NEED OfL? | |||
* Ltcense Requirement. , | |||
* | |||
* Date not to be exceeded is only opp!!cabfe to marked (*) Items. It is equal to the date completed last month plus six weeks. Rev. I1/S2 M M M M | |||
l f m M umm m m m m - m-Figure IV.E.2 g a | |||
Quarterly Surveillance and Maintenance (Sample Form) ' | |||
OSTROP14 SURVEILLANCE & MAINTENANCE FOR THE QUARTER OF / / 19 N5 | |||
*I I h kb hf *'' E REACTOR OPERATION COMMIITEE (ROC) AUDrr OF REACTOR OPERATIONS FOR 1 Y | |||
I QUARTER | |||
*2 QUARTERLY ROC MEETING QUARTERLY | |||
!3 FUEL ELEMENT RADIATION LEVEL MEASUREMENTS IN 223 RAr @ | |||
WATER 2* IN WATER | |||
'~ | |||
4 D4SPECTION OF THE SOLENCID VAuTS IN THE PNEUMATIC TRANSFER SYSTEM ONE 5 PNEUMATIC TRANSFER SYSTEM INSE RTION TIME CHECK 9 SENS 6 ROTAT240 RACK CIIECK FOR UNKNOWJ *AMPLES PACK SHOULD BE EMPTY 7 FUNCTIONAL CHECK OF EMERGENCY LIGHTS (SEE FUNCTIONAL CHECKSHEED 8 WATER MONITOR ALARM CHECK FUNCTIONAL 9 STACK MONITOR CHECKS (OIL DRh1 MOTORS, ILV. MOTORS 0: LED READES) PART: IISO V VOLTS | |||
*50 OAS: 900 V *50 VOLTS 10 (NOT BE!NO USED) | |||
II ARM SYSTEM ALARM CHECKS OtAN I 2 3 4 5 6 7 8 9 10 18 12 13 14 AUD FUNCTIONAL PANEL ANN | |||
! Physical Securhy Plan Requirement | |||
+ ucense Requirement E W | |||
* 7 | |||
" Date not to be exceeded is only appreaNe to marked (*) hems. k is equal to the date completed last quarter plus four monets. | |||
l l | |||
~ | |||
w w Figure IV.E.2 (continued) g N a | |||
Quarterly Surveillance and Maintenance (Sample Form) | |||
OSTROP 14 (CONTINUED) SURVEILLANCE & MAINTENANCE FOR THE GUARTER OF / / 19 I . | |||
; PJC . $ | |||
12 OPERATOR LOG p ,) g g , a) TDE b) OPERATING EXERCISE censole (RO) er as Rx. Sup. | |||
(SRO) | |||
*) Complete Operadng Exercise 13 CHECK FILTER TAPE SPef,D ON STACK MONITOR 1*!HR | |||
* 0.2 14 fNCORPORATE $0$9 & ROCAS INTO DOCUMENTATION QUARTERLY 15 (NOT BEINO USED) 16 FUNCTIONAL CHECK OF EVACUATION ALARMS ALL FUNCTIONAL 17 (NOT BEING USED) 18 STACK MONITOR ALARM CIRCUIT CHECKS ALARM ON (X)NTACT 19 ALARM TESTING OF VITAL AREA DOUBLE DOORS FUNCTIONAL a | |||
$ Physical Security Plan Requiremcat | |||
* Ucense Requirement | |||
** Date not t- N exceeded is enty applicat.le to : narked (*) Items. h is equal to the date cor | |||
* 44 last quarter plus four months. | |||
E E E E E E | |||
, 7_ | |||
:= | |||
Figure IV.E.3 $ | |||
c' Semi-Annual Surveillance and Maintenance (Sample Form) | |||
, OSTROP.15 SEMI-ANNUAL SURVEILLANCE AND MAINTENANCE FOR DATE NOT TO DATE REMARKS & | |||
SURVEILLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUND TARGET DATE BE EXCEEDED * | |||
* COMPLETED INITIALS | |||
*1 FUNCTIONAL NO WITHORAW 31 CHECKS OF al NEUTRON SOURCE COUNT RATE INTERLOCK | |||
= 5 cos a2 REACTOR - | |||
INTERLOCKS b) TRANS!ENT ROD AIR INTERLOCK NO PULSE D c) PULSE PROHIBIT ABOVE 1 kW =1kW c j d) TWO ROD WITHDRAWAL PROH BtT 1 only d I el PULSE MODE ROD MOVEMENT INTERLOCK No asovEMENT e il MAKfMUM PUL9E REACTMTY INSERTION LtMT s 42.50 f g) PULSE INTERLOCK ON RANGE SWITCH NO PULSE S | |||
*2 SAFETY , | |||
ORCUIT PERIOD SCRAM m3 see TEST | |||
*3 CONTROL TRANS SAFE- SHtM REG ROD WITH-DRAWAL, elSCRAM s2 see a DON & | |||
b) WITHDRAWAL s50 sec b DMES c) INSERTION s50 sec c | |||
'4 PULSE COMPARISON (PREVIOUS PULSE): PULSE # ,gL,g , | |||
8 s20% , | |||
MW CHANGE , | |||
*C *c | |||
'5 REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST y ** * | |||
*6 CAlt8 RAT 10N OF THE FUEL ELEMENT TEMPERATURE CHANNEL 12*C | |||
*7 MATERIALS BALANCE REPORT / FUEL MANAGEMENT REPORTS coNEf APRNL 1s APRIL 30 | |||
- EVEN SURNUP OCTOBER is OCTOBEM So | |||
'8 CLEAN!NG & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL 34N-t er CLEANED _ | |||
BARREL GUN O!L OtLED | |||
*S LUBRfCATION OF BALL-NUT DRIVE ON TRANS!ENT ROD CARRIER 3m 1 er "otv 80'8 - | |||
CUN Ott N8 10 LUSRICATION OF THE ROTATING RACK BEARINGS 10 W OfL OILED 11 CONSOLE CHECK LIST (OSTROP 15.11) OsTROP is.11 12 . CONSTANT AIR MONITOR RECORDER MAINTENANCE E W License Requirements. N | |||
** Date not to be exceeded is Only appf! cable to marked (*) Items. It is equal to the date last time plus 7 % months. Rev. If/S2 1 | |||
- c 0 | |||
l l | |||
:= w A | |||
Figure IV.E.3 (continued) 8 n | |||
a' l | |||
Semi-Annual Surveillance and Maintenance (Sample Form) t l | |||
OSTROP 15 teontinued) SEMI-7NNUAL SURVEILLANCE AND MA!NTENANCE FOR l | |||
DATE NOT TO DATE REMARKS & | |||
f LIMITS AS FOUND TARGET DATE EE EXCEEDEO** COMPLETED INITIALS l SURVEfLLANCE & MAINTENANCE TO BE PERFORMED 13 Deleted OILEO j 14 STANDARD CONTROL ROD MOTOR CHECKS l 15 Deleted 16 ION CHAMBER REStSTANCE A. SAFETY CHANNEL NONE MEASUREMENTS WITH MEGGAR Cnfo Onlyl INDUCED VOLTAGE B. % POWER CHANNEL NONE (tnfo Only) 17 FtSSION CHAMBER RES! STANCE @ 100 V. I= AMPS NONE CALCULATION @ 900 V. I- AMPS (Info Only) tJ = AMPS R= 0 R-Al l 18 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS osTaor1s.te H10H l | |||
Futt GREEN UGHT l | |||
l l | |||
l i | |||
l N | |||
l k% | |||
* Ucense Requirements. | |||
N | |||
" Date not to be exceeded is only appficabfe to marked (*) lterns. It is equat to the date test tIrne plue 7% months. Rev. I1/94 M M M M M M M M | |||
1 F 1 r7 Um | |||
:= | |||
Figure IV.E.4 g Annual Surveillance and Maintenance (Sample Form) | |||
CSTROP ISA ANNtJAL Sesvekance ed Rieheenence for the Year Page 1 AS TAROET DATE NOT TO DATE SURVEILLANCE AND MAMTENANCE TO SE PERFORMEO REMARKS & | |||
inAITS FOUND DATE 8E EXCEEDED" COMPLETED INITIALS | |||
*1 BfENNIAL INSPECTION OF CONTROL el FFCRS ROOS: | |||
08 TROP 12.0 b)TRANS | |||
*2 ANNUAL REPORT IDUE JUNE 30 + 76 DAYS 3 NOV1 OCT 1 NOV1 | |||
*3 CONTROL ROO CAlt9RATIONr elSAFE bl SHIM OSTROPS.O el ftEO 4TRANS | |||
*4 REACTOR POWER CAlfBRATION OSTROP 8.0 | |||
*S Calf 8MATION OF REACTOR TANIC WATER OSTROP 14.6 TEMPERATURE METERS | |||
*6 CONTINUOUS el Portleutete Monster AIR MONITCR RCMPP1SA CAU9 RATION: bl One Moniter | |||
*7 STACK MON! TOR el Perthdete Monitor CAUSRATION: RCMPP 13 & gg bl One Mor%r | |||
*e AREA RADIATION hvm.vn CAURPATION RCHPP 18A I I | |||
89 WATER MONITOR Calf 9 RATION RCHPP 10.0 10 REACTOR TANE AND CORE CCMPCNENT NO POWDERY INSPECTION WHITE SPOTS | |||
*11 SNM PHYSFCAL INVENTORY OSTROP 20.0 | |||
*12 EMERGENCY RESPONSE PLAN ORPd | |||
*13 STANDARD CONTROL ROO CRrVE INSPECTION OSTROP 18.13 | |||
*14 OSU POLICE AND SECURITY RETRA!N!NO | |||
*16 60.59 REPORT NOV 15 OCT 15 NOV18 | |||
*1e ONTRUSION ALARM RESPONSE DRILL RESPONSE 10Su rouCE ANO SECURITY) s6 MIN | |||
* usence Requiremente. | |||
N | |||
~ | |||
a Oeio nec te be esce.ded is ordy ePPanable se noted en name. m as equel to the date esmpleted last year plus 16 snenthe. For blennlel scense requirernante R le equel to the date templeted last tk am voere. . | |||
Rev.11/92 l | |||
l | |||
:= w Figure IV.E.4 (continued) 3 m a | |||
Annual Surveillance and Maintenance (Sample Fonn) | |||
ANNUAL SurweBanee end Maletenance for the Year Page 7, OSTROP 18.0 teentkwed) | |||
AS TARCET DATE NOT TO DATE REMARKS & | |||
LIMITS FOUND DATE SEEXCEEDED** COMPLETED INITIALS SURVEILLANCE AND MAINTENANCE TO SE PE8tFORMED 17 EMERGENCY POWER INVERTER TEST OSTROP 22.0 18 REPLACE P.A. & EVAC SYSTEM LEAD. ACID EVERY BATTERfES 4 YEARS ANNUAL SIENNIAL EVERY8 YEARS | |||
*18 REACTOR OPERATOR LICENSE CONDITIONS NRC REOUALIFICATION MEDICAL REQUAL EXAM LICENSE vervTee OPERATBe6 TTST DATE DUE DATE ERAMeeATIONS DUE DATg DATE COMPLETED CATE PA$$10 DUE DATE cut OATE OUE NAME cATE Passes OAYE eAssto OATE MAaro AS TARGET DATE NOT TO DATE REMARKS & | |||
LIMITS FOUND DATE SE EXCEEOED** COMPLETED INITIALS SURVEILLANCE AND MAINTENANCE TO BE PERFORMED 20 FUEL ELEMENT INSPECTION FOR SELECTEO PASS Pulse a Purse s ELEMENTS (S t. 82. 83. 85. 86. C3. CB. OS. D63 OO/NO GO TEST Date Date | |||
*21 DECOMM13310NING COST UPOATE N/A N/A 22 FUNCTaDNAL TEST OF TNE REACTOR WATER LOW MAXIMUM _ess LEVEL ALARM MOVEMENT | |||
~31NCHES _asse ANNUAL | |||
* CPR EVERY 3 YEARS . FIRST AfD 2S NAME REMtNDER DATE EXPLRY DATE REMINDER DATE EXPIRY DATE N | |||
,9 N | |||
N License Re<lutrements. | |||
* | |||
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1 Protection Part V I | |||
Part V PROTECTION A. Introduction This section of the report deals with the radiation protection program at the OSU Radiation Center. The purpose ofthis program is to ensure the safe use ofradiation and radioactive material in the' Center's teaching, research, and service activities, and in a similar manner to ensure the fulfillment of all regulatory requirements of the state ofOregon, the U.S. Nuclear Regulatory Commission, and other regulatory agencies. The comprehensive nature ofthe program is shown in Table V.A.1, which lists the program's major radiation protection requirements and the performance frequency for each item. | |||
The radiation protection program is implemented by a staffconsisting ofa Senior Health Physicist, a Health Physicist, a Radiation Protection Technologist, and several part-time Health Physics I Monitors (seePartII.F). Assistanceisalsoprovidedbythereactoroperationsgroup,theneutron activation analysis group, the Scientific Instrument Technician, and the Radiation Center Director. | |||
l The data contained in the following sections have been prepared to comply with the current requirements ofNuclear Regulatory Commission (NRC) Pacility License No. R-106 (Docket No. | |||
I 50-243) and the Technical Specifications contained in that license. The material has also been prepared in compliance with Oregon Office ofEnergy Rule No. 345-30-010, which requires an annualreportofenvironmentaleffectsduetoresearchreactoroperations. Asummaryofrequired data for the OSTR is provided in Part I.E for quick reference. | |||
l Within the scope ofOregon State University's radiation protection prognun, it is standard operating policy to maintain all releases ofradioactivity to the unrestricted environment and all exposures to radiation and radioactive materials at levels which are consistently "as low as reasonably achievable"(ALARA). | |||
B. Environmental Releases The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a summary of the nature and amount ofradioacti ve effluents released or discharged to the emirons beyond the efrective control ofthe licensee, as measured at, or prior to, the point ofsuch release or discharge." The liquid and gaseous effluents released, and the solid waste generated and transferred are discussed briefly below. Data regarding these effluents are also summarized in detail in the designated tables. | |||
2 Protection Part V | |||
: 1. Liquid Effluents Released | |||
: a. Liquid Effluents Released j Oregon State University has implemented a policy to reduce the volume of | |||
! radioactive liquid effluents to an absolute minimum. For example, water used during the ion exchanger resin change is now recycled as reactor makeup water. | |||
Waste water from Radiation Centerlaboratories and the OSTR is collected at a holdup tank prior to release to the sanitary sewer. Whenever possible, liquid l effluent is analyzed for radioactivity content at the time it is released to the collection point. However, liquids are always analyzed for radioactisity before the holdup tank is discharged into the unrestricted area (the sanitary sewer system). g l | |||
For this reporting period, the Radiation Center and reactor made one liquid E effluent release to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to these releases are contained in Table V.B.I.a. | |||
: b. Liquid Waste Generated and Transferred Liquid waste generated from decontamination ofTPJGA tubes and glasswnre and I | |||
from laboratory experiments is tmnsferred by the campus Radiation Safety Office I | |||
to its waste processing facility. Aqueous wastes are absorbed and disposed ofas 3 radioactive solid waste. Liquid scintillation fluid is shipped offcampus in bulk and in vials for disposal. The annual summary of liquid waste generated and transferred is contained in Table V.B.I.b. | |||
: 2. Airbome Effluents Released Airbome effluents are discussed in terms ofthe gaseous component and the particulate component. | |||
: a. Gaseous Effluents Gaseous effluents from the reactor facility are monitored by the reactor stack efiluent monitor. Monitoring is continuous (i.e., prior to, during, and afler reactor operations). It is normal for the reactor facility stack effluent monitor to begin l operation as one of the first systems in the moming and to cease operation as one ofthe last systems at the end ofthe day. All gaseous effluent data for this reporting | |||
) period are summarized in Table V.B.2. | |||
I I | |||
1 l | |||
I | |||
3 Protection Part V | |||
: b. Particulate Efiluents Particulate effluents from the reactor facility are also monitored by the reactor facility stack effluent monitor. | |||
{ Evaluation ofthe detectable particulate mdioactivityin the stack effluent confumed its origin as naturally-occurring radon daughter products, within a range of 4 | |||
approximately 1 x 10 pCi/ml to 3 x 10-" Ci/ml. This particulate mdioactivity f 2 ispredominantly "Pband2"Bi,whichisnotassociatedwithreactoroperations. | |||
'Ihere was no release ofparticulate effluents with a half-life greater than eight days and therefore the reporting ofthe average concentration ofradioactive particulates with half-lives greater than eight days is not applicable. | |||
: 3. Solid Waste Released Data for the radioactive materialin the solid waste generated and transferred during this reporting period are summarized in Table V.B.3 for both the reactor facility and the Radiation Center. Solid radioactive waste is routinely transferred to the OSU Radiation | |||
, Safety Office. Until this waste is disposed ofby the Radiation Safety Office, it is held along with other campus radioactive waste on the University's state ofOregon radioactive materials license. | |||
Solid radioactive waste is disposed ofby the University Radiation Safety Office by transfer | |||
[ to the University's radioactive waste disposal vendor, Allied Ecology Services, Inc., for burial at its installation located near Richland, Washington. | |||
C. Personnel Doses The OSTR annual reporting requirements specify that the licensee shall present a summary ofthe radiation exposure received by facility personnel and visitors. For the purposes ofthis report, the summary includes all Radiation Center personnel who may have received exposure to radiation. | |||
These personnel have been categorized into six groups: facility operating personnel, key facility research personnel, facilities senices maintenance personnel, students in laboratory classes, police and security personnel, and visitors. | |||
Facility operatmg personnel include the reactor operations and health physics staff. The dosimeters used to monitor these individuals include monthly or quarterly X-ray, beta, and gamma (Xp(G)] | |||
film or TLD badges, quarterly track-etch / albedo neutron dosimeters, either monthly or quarterly TLD (finger) extremity dosimeters, and pocket ion chambers. | |||
- o | |||
4 Protection Part V I | |||
Key facility research personnel consist ofRadiation Center staff, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or using other research facilities present at the Center. The individual dosimeuy requirements for these personnel will vary with the type ofresearch being conducted, but will generally include a monthly or quarterly X (G) film badge and TLD (finger) extremity dosimeters. If the possibility ofneutron exposure exists, researchers are also monitored with a track-etch / albedo neutron dosimeter. | |||
Facilities Services maintenance personnel are normally issued a gamma sensitive electronic dosimeter as their basic monitoring device. A few Facilities Services personnel who routinely perform maintenance on mechanical or refrigeration equipment are issued a quarterly Xp(G) TLD badge and other dosimeters as appropriate for the work being performed. | |||
Students attending laboratory classes are issued quarterly X)(G) TLD badges, TLD (finger) extremity dosimeters, and track-etch / albedo or other neution dosimeters, as appropriate. | |||
Students or small groups ofstudents who attend a one-time laboratory demonstration and do not handle radioactive materials are usually issued a gamma sensitive electronic dosimeter. These results are not included with the laboratory class students. | |||
OSU police and security personnel are issued a quarterly Xp(G) TLD badge to be used during their patrols of the Radiation Center and reactor facility. | |||
Visitors, depending on the locations visited, may be issued a gamma sensitive electronic dosimeters. g OSU Radiation Center policy does not normally allow people in the visitor category to become E l actively involved in the use or handling of radioactive maierials. | |||
l An annual summary of the radiation doses received by each of the above six groups is shown in l | |||
Table V.C. l . There were no personnel radiation exposures in excess of the limits in 10 CFR 20 l | |||
or state of Oregon regulations during the reporting period. | |||
l D. Facility Survey Data l | |||
The OSTR Technical Specifications require an annual summary ofthe radiation levels and levels of contamination observed during routine surveys performed at the facility. The Center's comprehensive area radiation monitoring program encompasses the Radiation Center as well as the OSTR, and therefore monitoring results for both facilities are reported. | |||
l I | |||
I | |||
i t | |||
5 | |||
( Protection Part V | |||
[ 1. Area Radiation Dosimeters Area monitoring dosimeters capable ofintegrating the radiation dose are located at strategic positions throughout the reactor facility and Radiation Center. All of these - | |||
dosimeters contain at least a standard personnel-type beta-ganuna film or TLD pack. In | |||
{ addition, for key locations in the reactor facility and for certain Radiation Center laboratories a CR-39 plastic track-etch neutron detector has also been included in the monitoring package. Figure V.D.1 shows the locations ofthe dosimeters in the reactor | |||
[ building and Radiation Center. | |||
The total dose equivalent recorded on the various reactor facility dosimeters is listed in | |||
[ Table V.D.1 and the total dose equivalent recorded on the Radiation Center area dosimeters is listed in Table V.D.2. Generally, the characters following the hiRC (Monitor Radiation Center) designator show the reom number or location. | |||
{ | |||
: 2. Routine Radiation and Contamination Surveys The Center's program forroutine radiation and contamination surveys consists ofdaily, weekly and monthly measurements throughout the TRIGA reactor facility and Radiation b- Center. The frequency ofthese surveys is based on the nature ofthe radiation work being carried out at a particularlocation or on other factors which indicate that surveillance over a specific area at a defined frequency is desirable. | |||
{ | |||
The primary purpose of the routine radiation and contamination survey program is to | |||
[- assure regularly scheduled surveillance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current and characteristic data on the status ofradiological conditions. A second objective of the program is to assure frequent I on-the-spot personal observations (along with recorded data), which will provide advance warning ofneeded corrections and thereby help to ensure the safe use and handling of radiationsourcesandradioactivematenals. Athirdobjective,whichisreallyderivedfrom | |||
[ successful execution of the first two objectives, is to gather and document information which will help to ensure that all phases of the operational and radiation protection | |||
{ programs are meeting the goal ofkeeping radiation doses to personnel and releases of radioactivity to the em'ironment "as low as reasonably achievable" (ALARA). | |||
[ The annual summary ofradiation and contamination levels measured during routine facility surveys for the applicable reporting period is given in Table V.D.3. | |||
[ | |||
[ | |||
r L | |||
e | |||
Protection Part V I | |||
E. Environmental Survey Data The annual reporting requirements of the OSTR Technical Specifications include "an annual I | |||
summary of environmental surveys performed outside the facility." | |||
: 1. Gamma Radiation Monitoring | |||
: a. On-site Monitoring Monitors used in the on-site gamma environmental radiation monitoring program at the Radiation Center consist of 6e reactor facility stack effluent monitor described in section V.B.2 and nine environmental monitoring stations. These g stations consist ofa polyethylene bottle placed inside a PVC tube attached to the 3 reactor building perimeter fence at a height of four feet (see Figure V.E.1). | |||
l l Each fence environmental station is equipped with an OSU supplied and processed TLD area monitor (normally three Harshaw ?LiFTLD-700chipsper 7 | |||
Li monitor in a plastic "LEGO" mount). These monitors are exchanged and processed quarterly. The total number ofTLD samples for the reporting period l | |||
was 108 (9 stations x 3 chips per station per quarter x 4 quarters per year). A summary of this TLD data is shown in Table V.E.1. | |||
Each fence environmental station also utilized a CaSO 4 TLD monitoring packet supplied and processed by Radiation Detection Company (R.D. Co.), Sunnyvale, California. Each R.D. Co. packet contained two CaSO4 TLDs and was | |||
; exchanged quarterly for a total of 72 samples during the reporting period (9 stations x 2 TLDs per station per quarter x 4 quarters per year). A summary of Radiation Detection Company's TLD data is also shown in Table V.E.1. | |||
Monthly mea.mrements of the direct gamma dose rate ( rem /h) were also made at each fence monitoring station. These measurements were made with a Bieron E micro-rem per hour survey meter containing a 1" x 1" Nal detector. E A total of 108 prem/h measurements were taken (9 stations per month x 12 months per year). The total calculated dose equivalent was determined by averaging the 12 separate rem /h measurements and multiplying this average by 8760 hours per year. A summary of this data is shown in Table V.E.1. | |||
From Table V.E.1 it is concluded that the doses recorded by the dosimeters on the TRIGA facility fence can be attributed to natural background radiation, which is about 110 mrem per year for Oregon (Refs.1,2). | |||
I I | |||
I 7 | |||
( Protection Part V | |||
(. b. Off-site Monitoring The off-site gamma environmental radiation monitoring program consists oftwenty | |||
(- | |||
monitoring stations surroundmg the Radiation Center (see Figure V.E.2) and one station located 5 miles to the south near the Corvallis Airport. | |||
{ | |||
Each off-site radiation monitoring station is equipped with an OSU-supplied and processed TLD monitor. Each monitor consists ofthree (MRCTE-1 1 has six) | |||
( ~ | |||
7 Harshaw LiF TLD-700 chips in a plastic "LEGO" mount. The mount is placed in a polyethylene bottle inside a PVC tube which is attached to the station's post p about four feet above the ground (MRCTE 21 and MRCTE 22 are mounted on i | |||
the roofof the EPA Lab. and National Forage Seed Lab., respectively). These monitors are exchanged and processed quarterly, and the total numberofTLD | |||
{ samples during the current one-year reporting period was 264 (20 stations x 3 chips per station per quarter x 4 quarters per year plus 1 station x 6 chips per station per quarter x 4 quarters per year). A summary ofthe OSU off-site TLD | |||
[ data is provided in Table V.E.2. The total number of R. D. Co. TLD samples for the reporting period was 104 (13 stations x 2 TLDs per station per quarter x 4 7 quartersperyear). AsummaryofRadiationDetectionCompany'sTLDdatafor i the off-site monitoring stations is also given in Table V.E.2. | |||
i | |||
[ In a manner similar to that described for the on-site fence stations, monthly measummentsofthedirectgammaexposurerateinmicroremperhour( rem /h) are made at each of the twenty-one off-site radiation monitoring stations. As | |||
{ noted before, these measurements are made with a Dicron micro-t em per hour survey meter containing a 1" x 1" Nal detector. A total of 252 prem/h measurements were made during the reporting period (21 stations per month x 12 | |||
[. months per year). The total dose equivalent for each station was determined by averagmg the 12 separate prem/h measurements and multiplying this average by 8760 hours per year. A summary of these data is given in Table V.E.2. | |||
After a review ofthe data in Table V.E.2, it is concluded that, like the dosimeters | |||
{ on the TRIGA facility fence, all ofthe doses recorded by the off-site dosimeters can be attributed to natural background radiation, which is about 110 mrem per year for Oregon (Refs.1,2). | |||
: 2. Soil, Water, and Vegetation Surveys The soil, water and vegetation monitoring program consists ofthe collection and analysis of a limited number of samples in each category on a quarterly basis. The program | |||
[ monitors highly unlikely radioactive material releases from either the TRIGA reactor facility I | |||
8 Protection Part Y or the OSU Radiation Center, and also helps indicate the general trend ofthe radioactivity concentration in each of the various substances sampled. See Figure V.E.2 for the locations ofthe sampling stations for grass (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 foot radius of the reactor facility and the Radiation Center. In general, samples are collected over a local area having a radius of about ten feet at the positions indicated in Figure V.E.2. | |||
There are a total of 22 quarterly sampling locations: four soil locations, four water locations (when water is available), and fourteen vegetation locations. The total number ofsamples possible during the reporting period is 88 (16 soil samples,16 water samples, and 56 vegetation samples). | |||
The annual average concentration of total net beta radioactivity (minus tritium) for samples collected at each environmental soil, water, and vegetation sampling location (sampling station) is listed in Table V.E.3. Calculation of the total net beta disintegration rate incorporates subtraction ofonly the counting system background from the gross beta counting rate, followed by application of an appropriate counting system efficiency. | |||
j The annual average concentrations were calculated using sample results which exceeded I | |||
the lower limit ofdetection (LLD), except that sample results which were less than or equal | |||
; to the LLD were averaged in at the corresponding LLD concentration. Table V.E.4 gives the average LLD concentration and the range ofLLD values for each sample category for the current reporting period. | |||
l As used in this report, the LLD has been defined as the amount or concentration of l | |||
radioactive material (in terms of pCi per unit volume or unit mass) in a representative sample, which has a 95% probability of being detected. l l | |||
Identification ofspecific radionuclides is not routinely caried out as part ofthis monitoring program, but would be conducted ifunusual radioactivity levels above natural background were detected. However, from Table V.E.3 it can be seen that the levels ofradioactivity detected were consistent with naturally occurring radioactivity and comparable to values l reported in previous years. | |||
I i | |||
1 9 | |||
( Protection Part V | |||
[ F. Radioactive Material Shipments | |||
[ A summary ofthe radioactive material shipments originating from the TRIGA reactor facility, NRC L | |||
license R-106, is shown in Table V.F.1. A similar summary for shipments originating from the Radiation Center's state ofOregon radioactive materials license ORE 90005 is shown in Table | |||
[ V.F.2. A summary of radioactive material shipments exported under Nuclear Regulatory Commission general license 10 CFR 110.23 is shown in Table V.F.3. | |||
[ | |||
G. References . | |||
: 1. U. S. Environmental Protection Agency," Estimates ofIonizing Radiation Doses in the United States,1 %0-2000," ORP/CSD 72-1, Office ofRadiation Programs, Rockville, Maryland (1972). | |||
[ | |||
: 2. U. S. Environmental Protection Agency, " Radiological Quality ofthe Environment in the | |||
[ United States,1977," EPA 520/1-77-009, Office ofRadiation Programs; Washington, D.C. 20460 (1977). | |||
[ | |||
{ | |||
{ | |||
{ | |||
{- | |||
[ | |||
{ | |||
l L | |||
I g | |||
10 Protection pg,, y | |||
! Table V.A.1 Radiation Protection Program Requirements and Frequencies FREQUENCYJ -l~ RADIATION PROTECTION REQUIREMENT? | |||
l l | |||
Daily / Weekly / Monthly Perform routine area radiation / contamination monitoring. | |||
Weekly Perform gamma spectroscopy of the (OS1R) continuous air monitor particulate filter. | |||
Perform routine response checks of radiation monitoring instruments. | |||
l Monitor radiation levels (prem/hr) at the environmental monitoring stations. | |||
l Collect and analyze TRIGA primary, secondary, and make-up water. | |||
Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure Monthly reports. | |||
Inspect laboratories. | |||
Check emergency safety equipment. | |||
Perform neutron generator contamination survey. | |||
Calculate previous month's gaseous effluent discharge. | |||
Process and record solid waste and liquid effluent discharges. | |||
, Prepare and record radioactive material shipments. | |||
( Survey and record incoming radioactive materials receipts. | |||
As Required Perfonn and record special radiation surveys. | |||
l Perform thyroid and urinalysis bioassays. | |||
Conduct orientations and training. | |||
l Issue radiation work permits and provide health physics coverage for maintenance operations. | |||
I l | |||
Prepare, exchange and process environmental TLD packs. | |||
Collect and process environmental soil, water and vegetation samples. | |||
Conduct orientations for classes using radioactive materials. | |||
I Collect and analyze sample from reactor stack effluent line. | |||
Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure reports. | |||
Leak test and inventory scaled sources. | |||
g g Conduct floor survey of corridors and reactor bay. | |||
Inventory and inspect Radiation Center equipment located in the Corvallis Fire Department I | |||
g Haz/ Mat van and at Good Samaritan Hospital. | |||
Calibrate portable radiation monitoring instruments and personnel pocket ion chambers. | |||
Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation monitors, water monitor. and air samplers. | |||
Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA filters g as necessary, inventory and inspect Radiation Center emergency equipment. | |||
Conduct facility radiation survey of the ''Co irradiators and X-ray machine. | |||
Conduct personnel dosimeter training. | |||
Perform contamination smear survey of Radiation Center ventilation stacks. | |||
Update decommissioning logbook. | |||
I | |||
Table V.B.1.a Monthly Summary of Liquid EfUnent Releases to the Sanitary Seweg.23 | |||
, (OSTR Contribution Shown in () and Bold Print) R : | |||
2 | |||
, :t | |||
.. . . , . . . . . . . . -. p - | |||
. . , , . . ... . . . g s...i.. u ,w . | |||
,-:-- i. o gg , ..,i... , .,, ,..-.4 .. | |||
.y.-e , | |||
....tt . l .d. | |||
. . ... .o,, | |||
,.i o. ... . ......., ., . ., : , ,4,u | |||
...,.v. e . .,v. .a . ;. ,y...~,,n. . , , , + ,. | |||
~ | |||
.:. ;t a . . , , - | |||
: . . . , y . .g '.2,,s.... | |||
i | |||
.. . . . ,, - - ic < .c; , : | |||
'' ' ~" ' ~ | |||
, . , , , , , , , , ., . ....M . . . . , . ;. .: n . . . . . f .. n . ., ,. .,.,..:., | |||
m .. | |||
j - | |||
,. ..,..c.,., - | |||
.,_.,i ; . | |||
u...., ;1 . . .. | |||
: c. ;w . . , | |||
:....., , ,e | |||
~ . . . | |||
[g '.' . ' -et' : (. .a e p ; | |||
m.....- | |||
tg3g | |||
' t | |||
., ; .fo:l Unit. . ._m. _ | |||
December 97 sLLD (95%) of None Not Applicable Not Applicable sLLD (95%)') of Not Applicable 1158 (No OSTR 1.79 x 10 3 4.08 x 10 4 | |||
Contribution) | |||
Annual Total for sLLD (95%) of sLLD (95%)") | |||
None Not Applicable Not Applicable 4 Not Applicable 1158 Radiation Center 1.79 x 10-s 4.08 X 10 OSTR | |||
, Contribution to Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Above 1 | |||
4 l | |||
f (1) OSU has implemented a policy to reduce to the absolute minimum radioactive wastes disposed to the sanitary sewer. There were no liquid effluent releases | |||
; during months not listed. | |||
i (2) The OSU operational policy is to subtract only detector background from the water analysis data and not backgroemd radioactivity in the Corvallis city | |||
; water. | |||
l (3) Based on values listed in 10 CFR 20, Appendix B to 20.1001 - 20.2401 Table 3, which are applicable to sewer disposal. | |||
(4) The total volume ofliquid effluent plus diluent does not take into consideration the additional mixing with the over 250,000 gallons per year ofliquids and sewage normally discharged by the Radiation Center complex into the same sanitary sewer system. ? | |||
4 - | |||
~ | |||
(5) Less than the lower limit ofdetection at the 95% confidence level. | |||
. - . } | |||
i 7 ~ | |||
N Table V.B.I b a t E | |||
! E Annual Summary of Liquid Waste Generated and Transferred Am.a< mammed hn end TRIGA Reactor None Not Applicable Not Applicable Not Applicable Not Applicable Fac.lity i | |||
Radiation Center 9/26/97 52 *Co, 32p, 86Rb 4 x 10-2 Not Applicable (2) | |||
Laboraton.es 5/9/98 TOTAL 52 "Co, 32p, 86Rb 4 x 10-2 _ __ | |||
(1) TRIGA and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging. | |||
2' (2) The short-lived waste was held by the Radiation Safety Oflice for decay. % | |||
M M m | |||
13 Protection Part V Table V.B.2 Monthly Summary of Gaseous Effluent Releases (0 Estimated Average _ Percent of the Date of Total Estimated Total Estimated Atmospheric Diluted Applicable MPC for Discharge Radioactivity (Month and Released 4 3 | |||
^4 " " '" ^4 " * " | |||
Year) (Curies) | |||
~ (Curies) Stack) Stack) | |||
(nCi/ml) (%) | |||
July 97 0.58 0.58 4.4 x 104 1.1% | |||
August 97 0.47 0.47 3.5 x 104 0.9' '. | |||
September 97 0.33 0.33 2.6 x 104 0.7% | |||
October 97 0.40 0.40 3.0 x 104 0.8% | |||
November 97 0.39 0.39 3.0 x 108 0.8% | |||
December 97 0.50 0.50 3.9 x 104 1.0% | |||
January 98 0.28 0.28 2.2 x 10'' O.5% | |||
February 98 0.30 0.30 2.5 x 104 0.6% | |||
1 March 98 0.55 0.55 4.2 x 10 4 1.0% | |||
_ April 98 0.38 0.38 3.0 x 10 4 0.7% | |||
May 98 0.42 0.42 3.2 x 10'' O.8% | |||
June 98 0.82 0.82 6.5 x 10 4 I ANN 11AL 1.6% | |||
VALUE 5.42 5.42 3.5 x 104 0.9% | |||
i | |||
(;) Airbome effluents from the OSTR contained no detectable particulate radioactivity resulting from reactor operations, p and there were no releases of any radioisotopes in airborne effluents in concentrations greater than 20% of the L | |||
applicable effluent concentration. (20% is a value taken from the OSTR Technical Specifications.) | |||
[ (2) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detec*able radionuclide was argon-41, | |||
[ | |||
c L | |||
14 g | |||
Protection Part V Table V.B.3 Annual Summary of Solid Waste Generated and Transferred Dates of Waste Volume of g Total Quantity Pickup for Dates of Origin of Solid Waste act uns e e pment fmm Radionuclides Solid Waste Packaged") in Solid Waste OSU Waste Oregon State y, g g.,,g (Cubic Feet) (Curies) Processing University") | |||
Facility 7/2/97 TRIGA "Sc, ''Sc, "Cr, 11 0/97 9/26/97 2/5/98 Reactor 220) 5'Co, 54Mn, "Fe, 3.0 x 10-5 1/21/98 Facility "Co, i2*Sb, "'Eu 5/18/98 3/11/98 | |||
'H. 22Na, 2*Na, "Sc, d'Sc, "Fe, 906/97 11/20/97 Radiation "Co, "Rb, *Sr, 1/21/98 2/5/98 = | |||
Center 34 3.6 x 10 3 | |||
'"Cd, i22Sb, i2*Sb, 3/11/98 5/18/98 Laboratories 2q, 2''B, 22*Ra, 23 U, 2'' Am TOTAL 66 See Above 6.6 x 10'5 . . | |||
I I | |||
(j) TRIGA and Radiation Cenkt laboratory waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging. | |||
(2) Solid radioactive waste is shipped to Allied Ecology Services, Inc. l (3) Includes 3 ft' ofdewatered resin beads, i | |||
I | |||
15 Protection Part V Table V.C.1 Annual Summary of Personnel Radiation Doses Received Average Annual ~ Greatest Individual Total Person-mrem Dosem Dosem For the GroupN Whole Whole Whole Personnel Group ' | |||
Body Extremities Body Extremities , Body. Extremities (mrem) (mrem) (mrem) (mrem) (mrem) - . (mrem) | |||
Facility Operating 14 80 35 100 190 1110 Personnel Key Facility Research Personnel ND <1 ND 30 ND 30 Facilities Services Nf aintenance Personnel | |||
<1 N/A 3 N/A 4 N/A Laboratory Class Students ND <l ND 30 ND 50 Campus Police and Secunty Personnel ND N/A ND N/A ND N/A Visitors <1 N/A 20 N/A 161 N/A (g) "ND" indicates that each of the beta-gamma dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the neutron dosimeters was less than the vendor's threshold of 30 mrem, as applicable. "N/A" indicates that there was no extrernity monitoring conducted or required for the group. | |||
I | |||
16 Protection Part V Table V.D.1 I | |||
Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Total Recorded I | |||
Monitor TRIGA Reactor - Dose Equivalentm2) | |||
Facility Location (See Figure V.D.1) 4( ) entron (mrem) (mrem) | |||
MRCTNE D104: North Badge East Wall 15 ND MRCTSE MRCTSW D104: | |||
D104: | |||
South Badge East Wall South Badge West Wall 0 | |||
105 ND ND l | |||
MRCTNW D104: North Badge West Wall ND ND MRCTWN D104: West Badge North Wall 70 ND MRCTEN D104: East Badge North Wall 580 ND MRCTES D104: East Badge South Wall 1300 ND MRCTWS D104: West Badge South Wall 305 30 MRCTTOP D104: Reactor Top Badge 295 30 MRCTHXS D104A: South Badge HX Room 420 ND | |||
, MRCTHXW D104A: West Badge HX Room 20 30 MRCD-302 D302: Reactor Control Room 140 ND MRCD-302A D302A: Reactor Supervisor's Office 20'3) N/A (g) He total recorded dose equivalent values do not include natural background contribution and, except as noted, reflect the summation of the results of 12 monthly beta gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of we fast neutron dosimeters was less than the vendor's threshold of 50 to 100 mrem, as applicable. | |||
"N/A" indicates that there was no neutron monitor at that location. | |||
(2) These dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area. E 3 | |||
(3) The total recorded dose equivalent reflects the summation of four quarterly beta-gamma dosimeters. | |||
I | |||
17 Protection Part V Table V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded Radiation Center Dose Equivalent * - | |||
. Monitor Faellity Location xp(G) . Neutron LD. (See Figure V D.1) (mrem) (mrem) | |||
MRCA100 A100: Receptionist's Office NDS N/A MRCBRF A102H: Front Personnel Dosimetry Storage Rack ND* N/A MRCAl20 Al20: Stock Room NDS N/A MRCA120A Al20A: NAA Temporary Storage 175 N/A MRCA126 Al26: Campus RSO's Isotope Receiving Lab 275* N/A MRCCO-60 A128: "Co Irradiator Room $25* N/A MRCA130 A130: Shielded Exposure Room NDm N/A MRCA132 A132: TLD Equipment Room ND* N/A MRCA134-2 A134: Graduate Student Office 190* N/A MRCA138 A138: Health Physics Laboratory ND* N/A MRCA146 A146: Gamma Analyzer Room (Storage Cave) ND N/A MRCB100 B100: Gamma Analyzer Room (Storage Cave) 390 N/A MRCBI14 Bl14: a Lab (22*Ra Storage Facility) 1595 ND MRCF ' 19-1 Bil9: Source Storage Room 210* N/A MRCBI19-2 Bl19: Source Storage Room 4455 N/A MRCBI19A Bl19A: Scaled Source Storage Room 4080 3100 MRCB120 B120: Instrument Calibration Facility 20m N/A MRCB122-2 B122: Radioisotope Storage Hood 25m N/A MRCB122-3 B122: Radioisotope Research Laboratory ND* N/A MRCB124-1 B124: Radioisotope Research Lab (Hood) 10m N/A MRCB124-2 B124: Radioisotope Research Laboratory ND* N/A MRCB124-6 B124: Radioisotope Research Laboratory ND* N/A MRCB128 B128: Instrument Repair Shop ND* N/A MRCC100 C100: Radiation Center Director's Office ND* N/A MRCC106A C106A: Staff Lunch Room ND* N/A MRCC106B C106: Solvent Storage Room 90 | |||
* N/A MRCC106 H C106H: East Loading Dock ND* N/A MRCCI18 Cl18: Radiochemistry Laboratory ND* N/A Seefootnotesfollowing the table. | |||
18 Protection Part V Table V.D.2 (continued) | |||
Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center l | |||
Total Recorded Radiation Center Dose EquivalentW Monitor Facility Location xp(G) Neutron l LD. (See Figure V.D.1) (mrem) (mrem) E htRCCl20 C120: Student Counting Laboratory NDS N/A htRCCl21 C121: APEX Facility ND* N/A 5 hiRCCl22 Cl22: APEX Control Room ND N/A htRCCl23N C123: Gamma Analyzer Room (Storage Cave) 85* N/A hfRCCl23S C123: Gamma Analyzer Room ND N/A NIRCCl24 C124: Student Computer Laboratory 10m N/A htRCCl30-1 Cl30: Radioisotope Laboratory (Hood) NDW N/A h1RCCl34 Cl34: Gamma Analyzer Room (Storage Cave) ND N/A htRCD100 D100: Reactor Support Laboratory 125 N/A N1 RCD 102 D102: Pneumatic Transfer Terminal Lab 20 ND h! RCD 102-H D102H: 1st Floor Corridor at D102 ND ND NIRCD106-H D106H: 1st Floor Corridor at D106 95* N/A hfRCD200 D200: Reactor Administrators's Office ND N/A h1 RCD 202 D202: Senior Health Physicist's Office 20 N/A NIRCBRR D20CH: Rear Personnel Dosimetry Storage Rack ND* N/A hiRCD204 D204 Health Physicist Office 30m ND hiRCD300 D300: 3rd Floor Conference Room ND ND I | |||
(g) The total recorded dose equivalent values do not include natural background contribution and, except as l noted, reflect the summation of the results of 12 monthly beta-gamma dosimeters or four quarterly fast t | |||
neutron dosimeters for each location. A total dose equivalent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 50 to 100 mrem, as applicable. | |||
! "N/A" indicates that there was no neutron monitor at that location. | |||
(2) The total recorded dose, equivalent reflects the summation of four quarterly beta-gamma dosimeters. | |||
(3) The total recorded dose equivalent reflects one quarterly beta and gamma dosimeter and nine monthly beta-gamma dosimeters. | |||
I l | |||
l 19 k Protection Part V | |||
( Table V.D.3 Annual Summary of Radiation Levels and Contamination Levels Obsened | |||
( Within the Reactor Facility and Radiation Center During Routine Radiation Sun'eys | |||
{ Whole Body Contamination Accessible Location Radiation levels Levels * | |||
(See Figure V.D.1) | |||
(mrem /br) (dpm/cm2) f Average Maximum . Average . Maximum TRIGA Reactor Facility: | |||
( Reactor Top (D104) <l 100 <500* 3,169:)t Reactor 2nd Deck Area (D104) 5 35 <500 <500 Reactor Bay SW (D104) <1 5 <500 <500 Reactor Bay NW (D104) <1 15 <500 <500 Reactor Bay NE (D104) <l 15 <50 <500 Reactor Bay SE (D104) <1 19 <500* 1,480m Class Experiments (D104, D302) <1 70 <500 <500 | |||
( Demineralizer Tank-Outside Shielding (D104A) | |||
<1 50 <500* 1,296m Particulate Filter-Outside Shielding (D104A) <1 2 <500* 1,667* | |||
( Radiation Center: | |||
NAA Counting Rooms (A146,B100,Cl34) <1 5 <500 <500 Health Physics Laboratory (A138) | |||
{ <1 <1 <500 <500 "Co Irradiator Room (Al28) <1 9 <500 <500 | |||
[ Radiation Research Labs | |||
<1 11 <500 <500 t (B114, B122, B124, B132, Cl30, Cl32A) | |||
Radioactive Source Storage (Bil9A) <1 35 <500 <500 f Student Chemistry Laboratory (Cll8) <1 5 <500 <500 Student Counting Laboratory (Cl20) <1 9 <500 <500 Operations Counting Room (Cl23) <l 6 <500 <500 Pneumatic Transfer Laboratory (D102) <1 22 <500 <500 | |||
__TRIGA Tube Wash Room (D100) <l 2 <500 <500 2 | |||
(1) <500 dpm/100 cm = Less than the lower limit of detection for the portable survey instrument used. | |||
(2) The contamination shown for this location assumes 100% smearing efficiency and was immediately removed. | |||
As a result, the average contamination level at this location during the reporting period was, for all practical purposes, <500 dpm per 100 cm2. | |||
20 Protection Part V Table V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence | |||
- Total Calculated I | |||
. Dose Equivalent E | |||
Total Recorded Total Recorded (Including 5 Dose Equivalent . Dose Equivalent Background) | |||
Fence (Including (Includ.ing Based on the Environmental Background) Background) Annual Average Monitoring Based on R. D. Co. Based on OSU prem/h Station (See Figure V.E.1) | |||
TLDsW (mrem) | |||
TLDsm (mrem) | |||
Dose RateW (mrem) l MRCFE-1 100 59 4 66* 12 MRCFE-2 97 49 | |||
* 4 63 | |||
* 10 MRCFE-3 98 52 4 74 12 MRCFE-4 105 61 | |||
* 4 75 + 19 MRCFE-5 94 49 | |||
* 4 64 11 MRCFE-6 101 51 4 66 | |||
* 10 MRCFE-7 96 51 4 65 8 MRCFE-8 93 49 4 59 9 MRCFE-9 94 50 5 58 | |||
* 10 Radiation Detection Company (R.D. Co.) TLD totals include their annual natural background contribution of (1) 80 mrem for the reporting period. Average Corvallis area natural background using Radiation Detection Company TLDs totals 86 mrem for the same period. | |||
(2) OSU fence totals include a measured natural background contribution of 45 | |||
* 8 mrem. | |||
(3) i values represent the standard deviation of the total value at the 95% confidence level. | |||
I I | |||
i 21 Protection Part V Table V.E.2 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations | |||
[ | |||
Total Calculated Dose Equivalent f Total Recorded Total Recorded - (Including Background) | |||
Off-Site Dose Equivalent Dose Equivalent Based on the Radiation (Including Background) (Including Background) Annual Average Monitoring Based on R. D. Co. Based on OSU ' . prem/h Station (4 - TLDsm TLDs*") | |||
Exposure Rate") | |||
(See Figure V.E.2) (mrtm) (mrem) (mrem) | |||
MRCTE-2L f - | |||
37 | |||
* 4 46 7 MRCTE-3 102 43 4 69 | |||
* 11 MRCTE-4 94 72 12 66* 9 MRCTE-5L - | |||
43 | |||
* 4 61 | |||
* 8 MRCTE-6 100 76 16 67 7 MRCTE-7L -- | |||
38 5 63 t 13 MRCTE-8 106 56 5 69*14 MRCTE 9 102 39 4 61*10 MRCTE-10 92 f 40 | |||
* 3 54 | |||
* 9 J1RCTE-11 92 40 | |||
* 2 50*9 MRCTE12 102 55 7 66 8 | |||
( MRCTE-13L - | |||
50 | |||
* 4 61 7 MRCTE-14L -- | |||
42 3 53 10 MRCTE-15 91 49 5 55 | |||
* 8 MRCTE-16L 63 * $ | |||
66 12 MRCTE 17 92 54 | |||
* 5 52 | |||
* 11 MRCTE-18L -- | |||
62 6 | |||
{ 67 | |||
* 15 | |||
_ MRCTE-19 106 59 | |||
* 6 68 10 MRCTE-20L 68*13 64 *I3 f MRCTE-21 80 50 | |||
* 5 39 | |||
* 7 _ | |||
MRCTE-22 84 41+4 39 | |||
* 9 _ | |||
(g) Monitoring stations coded with an "L" contained one standard OSU TLD pack only. Stations not coded with an "L" contained, in addition to the OSU TLD pack. one R.D. Co. TLD monitoring pack. | |||
(2) Radiation Detection Company TLD totals include their annual natural background contribution of 80 mrem for the reporting period. Average Corvallis area natural background using Radiation Detection Company TLDs totals 86 mrem for the same period. | |||
(3) OSU off-site totals include a' measured natural background contribution of 45 | |||
* 8 mrem. | |||
(4) | |||
* values represent the standard deviation of the total value at the 95% confidence level. | |||
1 | |||
22 Protection Part V I | |||
Table V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus3 H) | |||
I for Environmental Soil, Water, and Vegetation Samples Annual Average Concentration . | |||
Location Sample g g ,, | |||
Reporting (See Figure Type- | |||
* Radioactivitym V.E.2) 1-W Water 4.17E-08 3.22E-08m pCi/cm' 4-W Water 3.48E-08 5.83 E-09* pCi/cm' i1 W Water 3.36E-08 | |||
* 2.9E-09* pCi/cm' 19-RW Water 4.20E-08 3.43 E-085 Ci/cm' 3-S Soil 1.45E-04 1.30E-04 pCi/g of dry soil 5-S Soil 1.21E-04 | |||
* 1.92E-04 pCi/g of dry soil 20-S Soil 1.22E-04 9.64E-05 pCi/g of dry soil 21-S Soil 1.53E-04 | |||
* 1.54E-04 pCi/g ofdry soit 2-G Grass 2.88E-04 4.06E-04 pCi/g of dry ash 6-G Grass 3.12E-04 4.97E-04 pCi/g of dry ash 7-G Grass 3.25E-04 5.01 E-04 pCi/g of dry ash l | |||
8G Grass 2.45 E-04 3.48E-04 pCi/g of dry ash 5 9-G Grass 2.80E-04 3.92E-04 pCi/g of dry ash 10-G Grass 2.67E-04 4.21 E-04 pCi/g of dry ash f 12 G Grass 3.51 E-04 | |||
* 4.78E-04 pCi/g of dry ash l 13-G Grass 2.62E-04 | |||
* 3.62E-04 pCi/g of dry ash 14-G Grass 2.32E-04 t 2.57E-04 pCi/g of dry ash _. | |||
15-G Grass 2.86E-04 | |||
* 3.78E-04 pCi/g of dry ash l | |||
16-G Grass 2.89E-04 i 4.26E-04 pCi/g of dry ash l | |||
17-G Grass 3.42E-04 5.44E-04 pCi/gf dry ash I8-G Grass 2.59E-04 | |||
* 3.60E-04 __ pCi/g of dry ash 22-G Grass 3.57E-04 5.64 E-04 uCi/g of dry ash I | |||
I (g) values represent the standard deviation of the average value at the 95% confidence level. | |||
(2) Less than lower limit of detection value shown. | |||
I | |||
1 I 23 l | |||
Protection Part V I | |||
Table V.E.4 I Average LLD Concentration and Range of LLD Values for I Soil, Water and Vegetation Samples l | |||
l l | |||
Sample Average Range of Reporting Type LLD Value LLD Values Units , | |||
Soil 2.49E-05 1.81E-07 to 3.46E-05 pCi/ gram of dry soil Water 3.80E-08 3.18E-08 to 6.82E-08 pCi/cm 3 1 | |||
Vegetation 2.38E-05 I 7.37E-06 to 4.11E-05 Ci/ gram of dry ash I | |||
I I | |||
I I | |||
I I | |||
I I | |||
24 Protection Table V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 Number of Shipments ' | |||
Total Shipped To Activity FBd Limited Quantity Whitel - YellowII Total OSU Oceanography 1.70 x 10-5 1 0 4 5 Corvallis, OR _ | |||
General Atomics Empty 1 0 0 1 San Diego, CA Package OSU Electrical and Computer Engineering 3 6.27 x 10 1 0 0 1 Corvallis. OR Berkeley Geochronology Center 9.74 x 10 4 12 0 1 13 Berkeley, CA l su University of California 3.12 x 10-5 1 0 2 3 g Berkeley, CA LawTence Berkeley National Laboratory g | |||
4 1.19 x 10 1 0 0 1 Berkeley, CA Stanford Unis ersity Stanford, C A 1.98 x 10 4 6 0 1 7 Idaho State University d 3.78 x 10 1 3 24 28 Pocatello, ID University of Washington 4 4.95 x 10 2 0 0 2 Seattle, WA E g | |||
University of California 4 Santa Barbara, CA 9.02 x 10 2 0 0 2 University of Wyoming 8.61 x 10 4 4 0 0 4 Laramie, WY Brigham Young 1.17 x 10 4 2 0 0 2 Provo, UT l SUNY-Plattsburgh 4 1.37 x 10 3 0 0 3 l Plattsburgh, NY l m | |||
! Columbia University 5.29 x 10 5 1 0 1 2 l Pallisades, NY g l Union College E 2,7 x 10 4 1 0 0 1 l Schenectady, NY TOTALS 4.98 x 10 d 39 3 33 75 i | |||
I | |||
25 Protection Part V Table V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 Number of Shipments Total Shipped To Activity | |||
. @@ Limited Yellow Quantity II Total There were no radioactive material shipments originating from the Radiation Center's State of Oregon License ORE 90005 during this reporting period. | |||
I I | |||
I I | |||
I I | |||
L | |||
[ | |||
[ | |||
[ | |||
r L | |||
26 Protection Part V I | |||
Table V.F.3 Annual Summary of Radioactive Material Shipments Exported I | |||
Under NRC General License 10 CFR 110.23 Number of Shipments Total Shipped To Activity N Limited Yellow Quantity II Total Vrije Universiteit 4'11 x 10'' 0 1 1 Amsterdam, The Netherlands Scottish Universities Research and Reactor Centre 4 1.69 x 10 0 1 i Scotland, UK University of Geneva 4.03 x 10'5 0 2 2 Geneva, Switzerland University of Waikat Hamilton, New Zealand 1.86 x 10 4 | |||
1 0 1 E E | |||
University of Queensland 5 3.98 x 10 0 3 3 Brisbane, Australia FAPIG Research and Reactor Centre 9.16 x 10 7 2 0 2 Yokosuka, Japan Universite Paris-Sud 2.61 x 10 ' 0 1 1 Paris. France TOTALS 8.52 x 10 5 3 8 11 l | |||
l I | |||
I I | |||
I | |||
L 27 Pc'otection | |||
{ Part V TRIGA Facility and Radiation Center Area Dosimeter Locations | |||
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28 Protection Part V Figure V. E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence N= ' | |||
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. BUILDING | |||
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29 Protection | |||
{ Part V Figure V. E. 2 Monitoring Stations for the OSU TRIGA Reactor | |||
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1 l Work Part VI Part VI lI l | |||
i WORK lI A. Summary h Radiation Center offers a large variety ofresources for teaching, research, and service related l to radiation and radioactive materials. Some ofthese are discussed in detail in otherparts ofthis l report' Thepurposeofthispartistosummarizetheteaching,research,andserviceeffortscanied out during the current reporting period. | |||
B. Teaching The most important responsibility of the Radiation Center and reactor is to support OSU's academic programs. Implementation ofthis support occurs through direct involvement of the I Center's staff and facilities in the teaching prograrns of various departments and through participation in University research programs. For example, during the current reporting period, the Radiation Center accommodated 69 OSU academic classes involving a number ofdifferent l academic departments. In addition, portions ofclasses from other Oregon universities were also supported by the Radiation Center. The OSU teaching programs (not including research) utilized I 1,156 hours ofreactor time. Tables III.A.1 and III.D.1 plus section VI.C.5 provide more detailed information on the use of the Radiation Center and reactor for instruction and training. | |||
C. Research and Service Almost all Radiation Center research and service work is tracked by means ofa project system. | |||
When a request for facility use is received, a number is assigned to the project, a project cover sheet is generated, and the project is added to the database. The database includes such information as the project number, data about the person and institution requesting the work, a description of the project, Radiation Center resources needed, the Radiation Center project I manager, estimated costs for the project, and the funding source. | |||
Table VI.C.1 provides a summary ofinstitutions and agencies which used the Radiation Center | |||
: during this reporting period. This table also includes additional information about the number of j academic personnel involved, the number ofstudents involved, and the number ofuses logged for each organization. Details on graduate student research which used the Radiation Center are given | |||
!l in Table VI.C.2. | |||
I | |||
" Part VI l | |||
l The major table in this section is Table VI.C.3. This table provides a listing of the research and l service projects carried out during this reporting period and lists information relating to the I personnel and institution involved, the type ofproject, and the funding agency. Projects which used the reactor are indicated by an asterisk. | |||
In addition to identifying specific projects carried out during the current reporting period, Part VI also highlights major Radiation Center capabilities in research and service. These unique Center | |||
! functions are described in sections VI.C.1 through VI.C.8. | |||
: 1. Neutron Activation Analysis l Neutron activation analysis (NAA) stands at the forefront oftechniques for the quantitative multi-element analysis ofmajor, minor, trace and rare elements. The principle involved in NAA consists of first irradiating a sample with neutrons in a nuclear reactor such as the OSTRtoproducespecificradionuclides. Aftertheirradiation,thecharacteristicgamma l rays emitted by the decaying radionuclides are quantitatively measured by suitable l semiconductor radiation detectors, and the gamma rays detected at a particular energy am usually indicative ofa specific radionuclide's presence. Data reduction ofgamma ray spectra by means of a computer then yields the concentrations ofvarious elements in samples being studied. With sequential instrumental NAA it is possible to measure quantitatively about 35 elements in small samples (5 to 100 mg), and for activatable gl g | |||
l elements, the lower limit ofdetection is on the order ofparts per million or parts per billion, I depending on the element. | |||
\ l | |||
; The Radiation Center's NAA laboratory has analyzed for the major, minor, and trace 1 element content in many thousands ofsamples covering essentially the complete spectrum of material types and involving virtually every scientific and technical field. I While some reseat chers perform their own sample counting on their own or on Radiation Center equipment, the Radiation Center provides a complete NAA service for researchels andoths who may require it. This includes sample preparation, sequential irmdiation and i counting, and data reduction and analysis. l Data on NAA research and service performed during this reporting period are included in Table VI.C.3. | |||
: 2. Forensic Studies Neutmn activation analysis can also be advantageously used in enmmal investigations. The l principle underlying such application usually involves matching trace element profiles in objects or substances by NAA. This in tum can help identify materials or products (e.g., | |||
3 | |||
(' Work Part Y1 h identify the manufacturer ofa given object), and in some cases can match bullets and other materialsrecoveredfrom'a victimtosimilarmaterialsobtainedfromsuspects Materials which have been analyzed by the Radiation Center for forensic purposes include bullets, | |||
[- metals, paint, fuses, coats, glass, meat, and salts. | |||
{ Forensic studies performed in this reporting period are included in the listings in Tables VI.C.1 and VI.C 3. | |||
[ '3. Irradiations As described throughout this report, a major capability ofthe Radiation Center involves the irradiation ofa large variety ofsubstances with gamma rays and neutrons. Detailed data on these irradiations and their use during this reporting period are included in Part III as well as in section C of this part. | |||
{ | |||
: 4. Radiological Emergency Response Services The R adiation Center has an emergency response team capable ofresponding to all types ofradiological accidents. This team directly supports the City ofCorvallis and Benton | |||
(_ County emergency response organizations and medical facilities. The team can also provide assistance at the scene ofany radiological incident anywhere in the state ofOregon on behalfofthe Oregon Radiation Protection Services and the Oregon OfSee ofEnergy. | |||
{ | |||
The Radiation Centermaintains dedicated stocks ofradiological emergency response | |||
[ equipment and instrumentation. These items are located at the Radiation Center, at the Good Samaritan Hospital, and in the Linn/Benton Region 5 HAZMAT vehicle. | |||
[ During the current reporting period, the Radiation Center emergency response team conducted several training sessions and exercises, but was not required to respond to any actualincidents. | |||
In conjunction with the OSU Department ofNuclear Enginming, Radiation Center staff | |||
[ provide ongoing support to the state ofOregon's emergency response plan for the Trojan NuclearPowerPlant. Althoughthereactoritselfisnowshutdown,Trojanstillmusthave an emergency plan for the fuel kept in the spent fuel storage ponds. About seven persons | |||
[ residing in the R adiation Center hold either primary, second shift or attemate positions in the Trojan Emergency Plan and would work in the Emergency Operations Centerin Salem or in the Emergency Operations Facility at Trojan in the event of an incident. | |||
k r | |||
L r | |||
4 l Work Part VI During the past year, Radiation Center personnel attended training sessions, participated in drills and exercises, and provided advice relating to emergency response to a Troj an incident, but no one was required to respond to a real Trojan emergency. | |||
: 5. Training and Instruction In addition to the academic laboratory classes and courses discussed in Parts III.A.2, III.D, and VI.B, and in addition to the routine trammg needed to meet the requirements of the OSTR emergency response plan, physical security plan, and operator requalification program,theRadiationCenterisalsousedforspecialtrainingprograms RadtationCenter staffare xellexperiencedinconductingthesespecialprograms,andregularlyoffertmimng in areas such as research reactor operations, research reactor management, research reactor radiation protection, radiological emergency response, reactor behavior (for nuclear power plant operators), neutron activation analysis, nuclear chemistry, and nuclear safety analysis. | |||
Special training programs generally fall into one ofseveral categories: visiting faculty and research scientists; Intemational Atomic Energy Agency (IAEA) fellows; special short-term courses; or individual reactor operator ot health physics training programs. During this reporting period there were a large number of such people as shown in Part II.B. | |||
As has been the practice since 1985, the HAZMAT R esponse Teams Radiological Course was taught this year from May 4-7,1998 at HAMMER, Richland, Washington. | |||
: 6. Radiation Protection Services The primary purpose ofthe radiation protection program at the Radiation Center is to support the instruction and research conducted at the Center. However, due to the high quality of the program and the level ofexpertise and equipment available, the Radiation Center is also able to provide health physics services in support ofthe OSU Radiation Safety Office and to assist other state and federal agencies. The Radiation Center does not compete with private industry, but supplies health physics services which are not readily available elsewhere. In the case of support provided to state agencies, this definitely helps to optimize the utilization of state resources. | |||
The Radiation Center is capable ofproviding health physics services in any of the areas which are discussed in Part V. These include personnel monitoring, radiation surveys, sealed source leak testmg, packagmg and shipment ofradioactive materials, calibration and repair of radiation monitoring instruments (discussed in detail in Section VI.C.7), | |||
radioactive waste disposal, radioactive material hood flow surveys, and radiation safety analysis and audits. | |||
_ _ -- ~ | |||
5 Work Part VI The Radiation Center also provides services and technical support as a radiation laboratory to the Oregon State Health Division (OSHD) in the event of a radiological emergency within the state ofOregon. In this role, the Radiation Center will provide gamma-ray spectroscopy analysis ofwater, soil, milk, food products, vegetation, and air samples collected by OSHD radiological response field teams. As part ofthe ongoing prepamtion for this emergency support, the Radiation Center participates in inter-institution drills and cross-calibrations. | |||
: 7. Radiological Instrument Repair and Calibration i While repair ofnuclear instrumentation is a practical necessity, routine calibration ofthese mstruments is a licensing and regulatory requirement which must be met. As a result, the Radiation Center operates a radiation instrument repair and calibration facility which can accommodate a wide variety of equipment. | |||
The Center's scientific instrument repair facility performs maintenance and repair on all types of radiation detection and other nuclear instrumentation. Since the Radiation Center's own programs regularly utilize a wide range ofnuclear instruments, components I for most common repairs are often on hand and repair time is therefore minimized. | |||
In addition to the instrument repair capability, the Radiation Center has a facility for calibrating essentially all types ofradiation monitoring instruments. This includes typical portable monitoring instrumentation for the detection and measurement ofalpha, beta, I gamma, and neutron radiation, as well as instruments designed forlow-level environmental monitoring. Higher range instmments for use in radiation accident situations can also be calibrated in most cases. Instmment calibrations are performed using radiation sources I certified by the National institute of Standards and Technology (NIST) or traceable to NIST. | |||
I Table VI.C.4 is a summary of the instruments which were calibrated in support of the Radiation Center's instructional and research programs and the OSTR Emergency Plan, while Table VI.C.5 shows instruments calibrated for other OSU departments and non-OSU agencies. Table VI.C.6 shows instruments repaired for non-Radiation Center j departments and agencies. It should be noted that the Radiation Center only calibrates and I repairs instruments for local, state and federal agencies. | |||
l m | |||
4 | |||
__-n | |||
6 Work Part VI I | |||
: 8. Consultation Radiation Center staff are able to provide consultation services in any of the areas I | |||
discussed in this annual report, but in particular: research reactor operations and use, g radiation protection, neutron activation analysis, neutron radiography, radiological a emergency response, and radiotracer methods. | |||
Records are not normally kept of such consultations, as they often take the form of telephone conversations with researchers encountering problems or plannmg the design of experiments. Many faculty members housed in the Radiation Center have ongoing consulting functions with various agencies, in addition to sitting on numerous committees in advisory capacities. | |||
I i I I | |||
I 1 | |||
I I | |||
7 | |||
( wo,k Part VI Table VI.C.1 Institutions and Agencies Which Utilized the Radiation Center | |||
[ | |||
Number. | |||
"" ' Number of Number of 'of' | |||
( Institution . | |||
Projects .- | |||
Faculty Students . ' Uses of.. | |||
y,,olved Involved Center: | |||
Facilitien | |||
[ | |||
' Oregon State Universitym Corvallis, Oregon 44 12 18 271m | |||
[ U.S. Environmental Protection Agency NA Corvallis, Oregen 1 NA I U. S. Forest Service | |||
[ Corvallis, Oregon 1 NA NA 1 | |||
* Center for the Study of First Americans Corvallis, Oregon i NA NA 1 | |||
{ | |||
Good Samaritan Ilospital Corvallis, Oregon i NA NA 8 Corvallis Fire Department Corvallis, Oregon i NA NA 8 Oregon Office of Energy | |||
[ Salem, Oregon 1 NA NA 44 | |||
* University of Oregon 3 4 9 3 Eugene, Oregon | |||
{ | |||
' Oregon Episcopal School y 3 g Portland, Oregon 3 | |||
*Geovic Ltd. | |||
Beaverton, Oregon I NA NA 2 Rogue Community College | |||
{ Grants Pass, Oregon 3 ; j g Central Oregon Community College g j ; | |||
( Bend, Oregon i Pacific Northwest National Laboratories Richland, Washington 1 I I 2 (1) Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center. | |||
f (2) This number does not include ongoing projects being performed by residents of the Radiation Center such as the APEX project, others in the Department of Nuclear Engineering or Department of Chemistry, projects conducted by Dr. W. D. | |||
Loveland, which involve daily use of Radiation Center facilities. | |||
* Project which involves the OSTR. | |||
I L | |||
e | |||
8 I Table VI.C.1 (continued) | |||
Institutions and Agencies Which Utilized the Radiation Center | |||
-Number Number of. Number of .of Institution Faculty l Students . Uses of | |||
.. Projects Involved ' Involved Center : | |||
Facilities | |||
* University of Washington 2 | |||
Seattle, Washington 3 3 3 l | |||
E | |||
* Idaho State University 6 3 13 13 Pocatello, Idaho | |||
* Berkeley Geochronology Center i NA NA 28 Berkeley, California | |||
*Califomia State University Chico, Califomia | |||
* San Jose State University i I 2 1 San Jose, Califomia m | |||
' California State University Northridge, California g g g i | |||
*Pomona College j | |||
; g ; | |||
I Claremont, Califomia | |||
* Stanford University 4 3 3 8 Stanford, Califomia | |||
' University of California Energy Institute 1 1 1 2 Berkeley, California E | |||
' University of California at Santa Barbara 1 1 5 5 Santa Barbara, California | |||
! ' University of California at Los Angeles y g g l Los Angeles, California MX Gems and Minerals Stanton, California 1 NA NA 3 | |||
* Montana State University Bozeman, Montana i I 2 I | |||
' University of Utah Salt Lake City, Utah | |||
; 3 g g g g | |||
l *Brigham Young University 3 2 2 3 Provo, Utah l | |||
* Project which involves the OSTR. | |||
I | |||
9 Work pg,,y, Table VI.C.1 (continued) | |||
Institutions and Agencies Which Utilized the Radiation Center Number I " # | |||
' Number of. Number of of | |||
- Institution. ~ p,"o3 Faculty Students _ Uses of-Involved Involved - Center I Facilities | |||
' University of Wyoming 2 2 2 5 Laramie, Wyoming | |||
* Colorado College 3 3 2 Colorado Springs, Colorado 3 I ' University of Colorado Boulder, Colorado 6 1 1 4 I ' State University of Nebraska Lincoln, Nebraska I I I I | |||
' University of Arizona I Tucson, Arizona I I I I | |||
' Eastern New Mexico University y , , | |||
Portales, New Mexico | |||
*New Mexico Tech Socorro, New Mexico 1 I 2 | |||
* Texas Tech University Lubbock, Texas 3 2 3 3 | |||
' Trinity University I San Antonio, Texas I I I I | |||
* University of New Orleans New Orleans, Louisiana 3 3 | |||
* Southern Indiana University Evansville, Indiana 3 | |||
'Carlton College 2 2 4 2 Northfield Minnesota | |||
' University of Dayton I Dayton, Ohio I I I I | |||
* Franklin and Marshall College I I 2 I Lancaster, Pennsylvania | |||
* State University of New York at Plattsburgh | |||
[ Plattsburgh, New York | |||
[ | |||
* Project which involves the OSTR. | |||
E' L | |||
10 Work Part VI Table VI.C.1 (continued) I Institutions and Agencies Which Utilized the Radiation Center | |||
' Number . | |||
I Numberof . Number df -of-Institution' Faculty Students Uses of. | |||
. Projects - | |||
Involved- -Involved Center-I | |||
- Facilities | |||
' City Co:iege of New York i I 2 1 New York, New York | |||
* State University of New York at Stonybrook | |||
, 3 3 , | |||
Stonybrook, New York | |||
* Columbia University Pallisades, New York | |||
* Williams College | |||
; , g Williamstown, Massachusetts | |||
* Smith College Northampton, Massachusetts 1 1 1 2 l 3 | |||
; | |||
* George Washington University 1 1 2 1 Washington, D.C. | |||
' North Carolina State University l Raleigh, North Carolina | |||
*Clemson University 1 I I 2 Clemson, South Carolina | |||
* University of Florida 3 2 2 2 Gainesville, Florida 5 | |||
* Union Colleg 1 3 4 1 Schenectady, New York | |||
*FAPIG Radiation Research Nagasaka,Yokosuka, Japan 1 2 | |||
* Scottish Universities Research and Reactor Centre Glasgow, Scotland, United Kingdom i l 15 3 Borealis Technical Limited London, England, United Kingdom i NA NA 5 5 | |||
*Universite Paris-Sud Paris, France 1 NA NA I | |||
' University de Pierre et Marie Curie y y ; g Paris, France | |||
* Project which involves the OSTR. | |||
I | |||
t 1I | |||
( Work Part VI Table VI.C.1 (continued) | |||
Institutions and Agencies Which Utilized the Radiation Center | |||
[ | |||
- Number | |||
. Number of | |||
[ Institution Faculty Students Uses of, Pro % Involved Involved Center Facilities | |||
*Vrije Universiteit Amsterdam Amsterdam, The Netherlands I i 1 6 | |||
( *GEO N Geneva, Switzerland 1 NA NA 1 | |||
* University of Geneva Geneva, Switzerland 3 2 5 5 | |||
' University of Queensland Brisbane,Queensland, Australia 4 | |||
* University of Waikato | |||
, ; g Hamilton. New Zealand 3 TOTALS 134 81 133 586 | |||
{ | |||
{ | |||
{ | |||
{ | |||
{ l 1 | |||
* Project which involves the OSTR. | |||
L t | |||
.....w.. . . .. | |||
Table VI.C.2 U o[ | |||
Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topie Brigham Young University l | |||
( | |||
l E Lee Bray MS Geology Nelson Petrogenesis of the Absaroka Volcanic l Supergroup, WY. | |||
Kevin Hae Hae MS Geology Kowallis Subsidence and Uplift History of the Uinta Basin from Apatite Fission Track Analysis. | |||
Cal State University, Northridge t | |||
Barbara Chinn MS Geological Sciences Weigand Detailed Isotopic Modelling of the Origin of Miocene Lavas from the Northern Channel l Islands. | |||
City College of New York Scott Chesman PhD Earth and Env. Sciences Steiner Delineation of the Trondjemite-Tonalite-Granite Terrain of Southern New York and Connecticut. | |||
Romana Novack MS Earth and Env. Sciences Steiner Delineation of the Trondjemite-Tonalite-Granite 1emin of Southern New York and Connecticut. | |||
2 a | |||
5 m M M M M M M M M | |||
Table VI.C.2 @ | |||
n Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topie Columbia University Diane hicDaniel PhD Earth Sciences Hemming Assessment of Correlation between Climatic Changes and Differences in Provenance in the Amazon Drainage Basin. | |||
Eastern New Mexico University Douglas Anderson hiA Anthropology Constantopoulos X-ray Fluorescence Spectrometry of Narbona Pass Chert: A Chemical Characterization Study. | |||
Idaho State University Jason Casper hts Geology Hughes Geology of Circular Butte Volcano. | |||
Jason Casper hts Geology Hughes Petrography and Geochemistry of Volcanic Centers near the Test Area North on the INEL. | |||
Dave Clovis Not Known Hughes Student in Geology 615 John Glover Not Known Hughes Student in Geology 615. | |||
Jay hiatarese Not Known Hughes Student in Geology 615. | |||
N a | |||
4C | |||
Table VI.C.2 ej E Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic I crin McKnight Not Known Hughes Student in Geology 615. | |||
Jennifer Parker MS Geology Hughes Geochemistry and Stratigraphy of the Tuff of Wooden Shoe Butte. | |||
Scott Serrano Not Known Hughes Student in Geology 615. | |||
Ian Warren Not Known Hughes Student in Geology 615. | |||
Anni Watkins MS Geology Hughes Not Determined. | |||
Paul Wetmore MS Geology Hughes Accumulation Rates and Stratigraphy ofINEEL Basalts. | |||
Karen Wright MS Geology Hughes Not Determined. | |||
Montana State University Charles Lindsay MS Earth Sciences Feeley Geochemistry of High-K Lavas and Co-genetic Instrusions from Sepulchur Mountain and Electric Peak Yellowstone National Park. | |||
l l | |||
I I | |||
:s i | |||
1 | |||
_ _ _______L_____ __ ?___ | |||
. - - - .__, - - - - - . - - 4 Table VI.C.2 y Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic North Carolina State University Sonja Ingram MS Marine Earth & At. Sciences Fodor Trace Element Distinctions among Plagioclases in Hawaiian Tholeiitic and Alkalic Magmas. | |||
Oregon State University Sabooh Asghar MS Nuclear Engineering Reyes Core Makeup Tank Recirculation, Drainage and Condensation Behasior. | |||
Martin Attfield Post-Doc. Chemistry Sleight Delta Phase UO3. | |||
Darren Boone MS Nuclear Engineering Higginbotham Evaluation of Hormetic Effect of Gamma Radiation on Pinto Bean Seeds. | |||
Tom Brannan MS Nuclear Engineering Higginbotham Evaluation of Radionuclide.;in Various Sewer Sludge Samples. | |||
Mike Cantaloub MS Nuclear / Civil Engineering Higginbotham Determination of Non-aqueous Phase Liquid (NAPL) Contamination in Saturated and Unsaturated Aquifer Material using Radon as an Indicator. | |||
Jin Young Choi PhD Agricultural Chemistry Kerkvliet Undecided. | |||
N bG | |||
Table VI.C.2 @ E | |||
. n Graduate Student Reseant Vhich Utilized the Radiation Center Student's Name DeRree Academic Department Faculty Advisor Thesis Topie Sarah Colpo hts Nuclear Engineering Reyes Counter Current Flow Limitation in the APEX Facility's Pressurizer Surge Line. | |||
Scott Crail hiS Nuclear Engineering Higginbotham Detection of Potentially Contaminated Garbage Entering a City Garbage Disposal Site. | |||
Erica | |||
==Dearstyne PhD Agricultural Chemistry Kerkvliet Fate of T Cells in TCDD-Treated hiice:== | |||
Anergy of Apoptsis? | |||
Bmce Eversmeyer PhD Oceanography Prahl Suspended Solid Description of Columbia River Particulates. | |||
Phil Gaffkin PhD Chemistry Dept Chen Use of Gamma Irradiation to Evaluate its Potential for Crosslinking Peptides and Nucleotides. | |||
Sebastian Geiger PhD Geosciences Haggerty Diffusion in Geologic hiaterials. | |||
Sebastian Geiger PhD Geosciences Geiger Fluid Flow in Fractures, Reactive Flow and Coupled Flow Phenomena. | |||
hiarish Giri PhD Chemical Engineering Rochefort Impurities in Plastics. | |||
2 a | |||
3 M M M M - | |||
M M M M M M | |||
Table VLC.2 5 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Facuhy Advisor Ihesis Topic Sung Mo Kang MS Forest Products Morrell Fungi Colonization of Douglas Fir Sapwood and their Role in Biological Discoloration. | |||
Janine Katanic MS Nuclear Engineering Higley RHP 587 Class project: Evaluation of the Hormetic Effect of Radiation on Pinto Bean Seeds. | |||
Young Kim MS Civil Engineering Semprini Bioremediation of Chloroform Contamination. | |||
Fugen Li PhD Food Science Barnes Molecular Biology of Cystatin C, a Cystein Protease Inhibitor. | |||
1 Mark Mankowski MS Forest Products Morrell Biology of Carpenter Ants in the Pacific Northwest and its Relationship with Fungal Decay in Buildings. | |||
Robert Nartley PhD Geosciences Buckosic Unknown. | |||
Oleg Povetko MS Nuclear Engineering Higley Long-Lived Radionuclide Migration through Soils. | |||
Rodney Prell PhD Agricultural Chemistry Kerkvliet Role of B7 Co-stimulation in TCDD Immunotoxicity. | |||
Mari Rios MS Physics Krane Neutron Cross Section Measurements'of Radioactive Ge-68 and Gd-148. | |||
2 a | |||
3C | |||
Table VLC.2 # E A | |||
Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topic Carl Ruby PhD Agricultural Chemistry Kerkvliet involvement of NFKB in TCDD Immunctoxicity. | |||
Christopher Rusher MS Nuclear Engineering Reyes Level Swellin a Boiling Pool. | |||
David Shepherd PhD Agricultural Chemistry Kerkvliet A T-Cell Receptor-Transgenic Model for Immunoticity Testing. | |||
! Christopher Sinton PhD Oceanography Duncan Age and Compostion of Two Large Igneous l | |||
Provinces: The North Atlantic Volcanic Rifled Margin and the Caribbean Plateau. | |||
Mark Strohecker MS Nuclear Engineering Reyes Flow Modeling of the APEX Facility's IRWST. | |||
Daniel Strom MS Botany / Plant Pathology Rivin Clonal Analysis of Maise Meristem. | |||
Beth Vorderstrasse PhD Agricultural Chemistry Kerkvliet Dendritic Cells: Role in TCDD-Induced Suppression of CTL Activity. | |||
Dan Wachs MS Nuclear Engineering Reyes Prediction and Modeling of Thermal Stratification in the Cold Legs of the OSU APEX Facility. | |||
; Oliver Woodhouse PhD Oceanography Falkner Osmium Behavior in the Aqueous Marine l Environment. | |||
1 a | |||
sus ums num sum t | |||
Table VI.C.2 # | |||
Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic 1 | |||
1 Rockie Yarwood PhD Microbiology Bottomley 2,4-D Degradation by Soil Micro-organisms. | |||
Li Yoon MS Botany / Plant Pathology Rivin Clonal Analysis of Maise Meristem. | |||
Lissa Zyromski PhD Chemistry Loveland Measurement of Fusion Enhancements with neutron-rich Stable and Radioactive Projectiles. | |||
San Jose State Unisersity : | |||
Laura Parent MS Geology DeBari Petrologic and Structural Evolution of the Cardinal Peak Pluton. | |||
Scottish Univ. Res. & Rx Centre T. Barry PhD Leicester University Pringle Mongolian Basalts / Tectonics J. Blecher PhD Oxford University Pringle Aden Volcanic Differentiation. | |||
S. Carn PhD Cambridge University Pringle Indonesian Volcanics. | |||
L Chambers PhD Edinburgh University Pringle North M! antic Teniary Province. | |||
H. Dixon PhD Bristol University Pringle Subglacial Volcanics. | |||
N | |||
:t G2 | |||
Table VI.C.2 @ S n | |||
Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic C. Harford PhD Bristol University Pringle Montserrat Volcanic Hazards. | |||
E. Heath PhD Lancaster University Pringle St. Vincent Volcano Hazards. | |||
G. May PhD Aberdeen University Pringle Chilean Basins. | |||
S. McElderry PhD Liverpool University Pringle Chilean Tertiary Faulting. | |||
Y. Najman PhD Edinburgh University Pringle Himalayan Foredeep. | |||
M. Purvis PhD Edinburgh University Pringle Turkish Basin Tectonics. | |||
R. Shelton PhD Queens University Pringle North Channel Basin Evolution. | |||
A. Sowerbutts PhD Edinburgh University Pringle Sardinia Evolution. | |||
G.Steele PhD Aberdeen University Pringle Cerro Rico Silver. | |||
R. White PhD Leicester University Pringle Caribean Crustal Growth. | |||
N i | |||
3 m M M M M M M M - | |||
M M ] | |||
Table VI.C.2 { | |||
m. | |||
Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic 1 | |||
Stanford University i | |||
Daniel Stockli PhD Geological & Env. Sciences Dumitru Timing of Extensional Faulting in the Northern Basin and Range Provina, and the Structured and Thermal Transition to the Central Sierra Nevada. | |||
Benjamin Surpless PhD Geological & Env. Sciences Miller Geological Evolution of the Sierra Nevada - Basin | |||
! and Range Transition Zone. | |||
i Da Zhou PhD Geological & Env. Sciences Dumitru Amalgamation and UpliA History of the Tian Shan, Western Chma. | |||
SUNY at Stony Brook Troy Rasbury PhD Earth and Space Sciences Hanson . Use of Fission Track Dating of Various Authigenic Calcite and Phosphate Minerals to Determine the Time of Sedimentation with a View to Calibrating the Geologic Record. | |||
Texas Tech University j Melissa Batum MS Geosciences Barnes Comparison of Granites Across a Proterozoic- | |||
, Archean Boundary. | |||
l | |||
. $S l | |||
Table VI.C.2 5 O s. | |||
Graduate Student Research Which Utilized the Radiation Cettter Student's Name Degree Academic Department Faculty Advisor Thesis Topic Mi-ae Jeon MS Geosciences Barnes Elemental and Isotopic Exchange in Granite During Metamorphism. | |||
Sang-yun Lee PhD Geosciences Barnes Granite Petrogenesis and Core Complex Formation, Ruby Mtns. NV. | |||
The University of Waikato Ming Hung Ho Ph.D. Earth Sciences Kamp Thermo-tectonic History of Marlborough, New Zealand. | |||
U.C. Berkeley Chad Cole MS Nuclear Engineering Olander Evaluation of Processess to Determine the ! | |||
Amount of Uranium in Mixed Waste. | |||
UCLA Amy Young PhD Earth and Space Sciences Davidson Petrogeneis, Stratigraphy and Origin of Damavand Volcano, Iran. | |||
Union Col'ege Mike Bullen BSc Geology Gaiver Provenance of the Ukelayet Flysch, Kamchatka, Russia. | |||
N 2 . | |||
3 L | |||
. _ , - - - m - ,, - - - -, ,, -, - - . - -. - - | |||
Table VI.C.2 @ | |||
~ | |||
Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topic Jorge Mora PhD Env. Sciences, SUNY, Albany Ganer UpliA and Evolution of the Venezeulan Andes. | |||
Univ. of California, Santa Barbara Andy Cahrst PhD Geological Sciences Gans Tectonic Studies in Eastern-Most Russia. | |||
Jon Nauert MS Geological Sciences Gans Volcanism in the Eldorado Mountains, Southern Nevada. | |||
Jaime Toro Not Known Geological Sciences Gans Cretaceous and Tertiary History of Alaska's Brooks Range and Russia's Chukotka Peninsula. | |||
University of Colorado-Boulder Philip Verplank PhD CIRES Farmer Geochemistry of the Organ Needle Pluton in South-central New Mexico. | |||
University of Florida Ann Heatherington Post-Doc. Geology Mueller Crustal Evolutica Along the Western Boundary of the Wyoming Crater, Stephanie Jenkins MS Geology Mueller Age and Origin of the Albermarle Group, Carolina State Belt. | |||
2' bd | |||
Table VI.C.2 W Graduate Student Research Which Utilized the Radiation Center | |||
{ | |||
Student's Name Degree Academie Department Faculty Advisor Thesis Topic University of Geneva Mercedes Hernandez PhD Mineralogy Singer Petrology and Geochronology of the Catalan Coastal Ranges Batholith, NE Spain. | |||
Robert Marschick PhD Mineralogy Singer Cretaceous Cu (-Fe) Mineralization in the Punta del Cobre Belt, Northern Chile. | |||
Osman Partak PhD Mineralogy Singer Geochemistry and Geochronology of the Merson l Ophiolite within the Eastern Mediterranean Tectonic Frame. | |||
Thao Ton-That MS Mineralogy Singer Ar-40/Ar-39 Dating of Basaltic Lava Flows and the Geology of the Lago Buenos Aires Region, Santa Cruz Province, Argentina. | |||
Yann Vincze MS Mineralogy Singer Ar-10/Ar-39 Incremental Heating Studies of Latest Pleistocene and Holocene Lava and Tephra: Implications for the Last Glaciation in the Southern Andes. | |||
University of New Orleans Judy Wilson MS Geology & Geophysics Johnson Volcanic Hazards in the Cascade Range. | |||
N a | |||
G M M M M M M M M M M M M | |||
Table VI.C.2 @ | |||
n Graduate Student Research Which Utilized IIe Radiation Center | |||
* Student's Name Degree Academic Depanneemt Faculty Advisor . Thesis Topic ; | |||
University of Oregon f | |||
3 Jacqui Coll Post Doc. Pharmacy Ayres Trace Metals in Drug Suspensiort I i | |||
I Christopher Descantes ' PhD Anthropology Ayres Archeological Study of Yap, Micronesia. j Scott Fitzpatrick PhD Anthropology Ayres Stone Tool Materials and Sources on Easter Island. | |||
Roland Goodgame Not Known Reed Characterization of Alteration and Mineralization ! | |||
in Komatiite. | |||
L I | |||
Katic Rorrer MA Anthropology Ayres Pacific Archeology ; | |||
Epi Suafo'a MA Anthropology Ayres Pacife Archeology Stephen Twyerould PhD Geological Sciences Reed The Geology and Genesis of the Ernest Henry Fe- [ | |||
i oxide, Cu-Au deposit, Queensland Australia. ) | |||
i Helen Vallianatos PhD Anthropology Goles Palcodietary Reconstruction and Effects of , | |||
1 Diagenesis. j Joan Wozniak PhD Anthropology Ayres Easter Island Archeological Settlement and Early [ | |||
Agriculture. l N | |||
2 m ! | |||
Gm i | |||
P E L i | |||
? | |||
Table VLC.2 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Adsisor Thesis Topic University of Washington Scott Barboza PhD Geological Sciences Bergantz The Dynamics of Dehydration Melting. | |||
Kyle Bland MS Geological Sciences Bergantz The Generation of H3bridized Magmas. | |||
Rebecca Chrisfield MS Geological Sciences Stewart History of Faulting and Uplift of the Coast Ranges ofOregon and Washington. | |||
University of Wyoming Bradford Burton PhD Geology / Geophysics Murphy Structural and Thermal History of Harrison Pass Pluton, NV. | |||
Thomas Kalakay PhD Geology / Geophysics Murphy Structural and Themal History of Pioneer Batholith, MT. | |||
L- _ -. | |||
Table VI.C.3 #M 4 | |||
Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding 321 Murphy University of Wyoming Fission Track Dating Thermal column irradiations of Geophysics, U apatite and zircon samples for fission ofWyoming track production to determine rock age. | |||
335 Kowallis Brigham Young Fission Track Dating Dating of natural rocks and minerals National University via fission track raethodology. Science Foundation 444 Duncan Oregon State University Ar-40 /Ar-39 Dating of Production of Ar-39 from K-39 to Oceanography, Oceanographic Samples measure radiometric ages on basaltic OSU rocks from ocean basins. | |||
480 Higginbotham Oregon State University Technical Support to the Technical support to Oregon DOE Radiation State of Oregon and the Department of Human Center, OSU Resources to assist in emergency preparedness for the PGE-Trojan facility. | |||
481 Winans Oregon Health Sciences Instrument Calibration Calibration of radiation survey Oregon Health Univ. instruments. Sciences University 488 Farmer Oregon State University Instrument Calibration Calibration of portable radiation Radiation survey instruments for radiation users Center, OSU on OSU campus. | |||
2 INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements A G | |||
M M M M M M M m M M M M M M - M | |||
--x . - _ _ _ _ _ - | |||
Table VI.C.3 { | |||
n Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Titic Description , | |||
Funding 519 Livingstone U.S. EPA Instrument Calibration Calibration of portab!c radiation USEPA-survey meters using the standard RC Conallis protocol. | |||
521 Vance University of Fission Track Studies Thermal column irradiation of zircon University of Washington and other samples to induce Iission Washington tracks in catcher foils for dating. | |||
547 Boese EPA - Newport Sunty Instrument Calibration of GM and other portable USEPA, Calibration sunty meters as per standard OSU Cincinnati, OH protocol. | |||
554 Niles Oregon Office of Energy Instrument Calibration Instrument calibration of sunty Oregon meters for PUC truck inspectors. Depadment of Transportation 632 Thompson Oregon State Police RadiologicalInstrument Calibration of radiological Oregon State Crime Lab. Calibration instruments used at the OSP Crime Crime Laboratory Laboratory 664 Higginbotham Oregon State University Instrument Calibration Calibration of radiation sunty Radiation instruments. Center, OSU 665 Higginbothrm Oregon State University Instrument Calibration Calibration of radiation sunty Radiation instruments. Center, OSU t | |||
INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements 5 a g G4 L _ _ _ _ _ _ _ | |||
1 l | |||
Table VI.C.3 !! M s. | |||
l Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding 708 Reyes Oregon State University AP600 Long-Term Cooling Fabricate and test scale model of US Nuclear Test section of Westinghouse AP600 Regulatory t reactor cooling system. Commission l | |||
7II Mattson Oregon State University Diagnostic Biology Sterilization of bovine blood serum in Vet. Med. | |||
the Co-60 irradiator. Diagnostic Laboratory, OSU 745 Wiggs Oregon Health Sciences Gamma Sterilization of Irradiation of various medicinals Oregon Health l Univ. Various Materials using the Co-60 irradiator to OHSU- Sciences specified doses for purposes of University sterilization. | |||
752 Barnes Oregon State University Schistoma Cell Culture Feeder layer irradiations to 2.5 krad. OSU l Gamma irradiation of hamsters and Biochemistry & | |||
l other laboratory animals. Biophysics 815 Morrell Oregon State University Sterilization of Wood Sterilization of wood samples to 2.5 Forest Products, Samples Mrads in Co-60 irradiator for fungal OSU evaluations. | |||
920 Becker Berkeley Geochronology Ar-39/Ar-40 Age Dating Production of Ar-39 from K-39 to Berkeley i Center determine ages in various Geochronology anthropologic and geologic materials. Center 930 McWilliams Stanford University Ar-40/Ar-39 Dating of Irradiation of r&.eral grain samples Geophysics, Geological Samples for specified times to allow Ar-40/A Stanford 39 dating. University l | |||
2 INAA - Instrumental Net :ron . ictivation Analysis REE - Rare Earth Elements % | |||
G l | |||
l M M M M M M M M M M M M M | |||
O Table VI.C.3 ' | |||
o{ | |||
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title . Description Funding 931 Keriatiet Oregon State University TCDD Effects on T-Cell Co-60 irradiation of spleen cells from Agriculture Activation mice to study the effects ofTCDD on Chemistry, OSU T-cell activation using T-h cell clones. | |||
932 Dumitru Stanford University Fission Track Dating Thermal column irradiation of Geology, geological samples for fission track Stanford age-dating. University 995 Bottomley Oregon State University Herbicide Mineralization in Soil sterilization in the Co40 Crop & Soil | |||
- AgriculturalSoils irradiator. Science, OSU 1002 Singer University of Geneva Ar-40/Ar-39 Dating of CLICIT irradiation ofgeological University of Young GeologicalMaterials materials such as volcanic rocks from Geneva sea floor, etc. for Ar-40/Ar-39 dating. | |||
1018 Gashwiler Occupational Health Lab Calibration of Nuclear Calibrate radiation suney meters. Occupational Instruments Health Laboratory 1020 Gans Univ. of California. Tectonic Studies in Eastern- Irradiation for Ar-40/Ar-39 dating National Santa Barbara Most Russia using the CLICIT or dummy fuel Science element. Foundation 1025 Semprini Oregon State University Sterilization of Subsurface Soil sterilization in order to Civil Soil investigate the bioremediation of Engineering, chloroform contamination. OSU INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elenwnts N A g Zw | |||
Table VI.C.3 !! 8 A. | |||
Listing of Major Research and Senice Projects Performed or in Pmgress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding 1072 Rasmussen Army Corps of Instrument Calibration Calibration of radiation detection U.S. Army Engineers instmments. Engineer District, Portland. | |||
1073 Pringle Scottish Univ. Res. & Argon 40/39 Dating of Age dating of various materials using Scottish Univ. | |||
Rx Centre Rock Minerals the Ar-40/Ar-39 ratio method. Research & | |||
Reactor Centre 1074 Wijbrans Faculty of Earth 40Ar-39 Ar Dating of 40Ar-39Ar dating of rocks and Vrije Sciences Rocks and Minerals minerals. Universiteit, Amsterdam l 1075 Lederer Univ. of California Activation Analysis Irradiation of small, stainless steel UC Berkeley l Energy Institute Experiment for NE Class discs for use in a nuclear engineering radiation measurements laboratory. ' | |||
1097 Loveland Oregon State University Speciation of Pu in the Measurement of the chemicat Chemisty, OSU Aquatic Environment speciation of Pu in fresh water. | |||
1098 Loveland Oregon State University Fusion Enhancement with Measurement of fusion enhancements Chemisty, OSU n-rich Projectiles with n-rich stable and radioactive projectiles. ; | |||
1109 Prahl Oregon State University Suspended Solid Evaluation of the form, sources and Geosciences, Description of Columbia fates of suspended Columbia River OSU River Particulates particulate materials. | |||
INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements I | |||
amm oss uma mas amm uma man sums amm num nas sums aus num amm uma ame | |||
7_ 7 1, | |||
i Table VI.C.3 { | |||
Listing of Major Research and Service Projects Peifva..ed or In Progress at the Radiation Center and Their Funding Agencies fI r | |||
Project Uwr(s) Nanne Organizataen Name Project Title Description , Fanding i f | |||
i118 Larson Oregon State University Primary Phytoplankton Evaluation of the primary production Forest f Production Studies at of phytoplankton in Crater Lake and . Resources, OSU ! | |||
Crater Lake lakes in Mount Rainier, Olympic, I and North Cascades NationalParks ! | |||
using C-14 and liquid scintilation counting. | |||
1120 Rivin Oregon State University Clonal AnalysisofMaise Testing to determine if an isolated Botany, OSU i Meristem mutated gene is required for past l embryonic meristem formation or ! | |||
l function. | |||
i125 Streck University of Geneva Crystallization in Determination of mobility of trace GEOMAR last. | |||
Ignimbrite E, Gran Canary elements during cooling of tuff E - Germany [ | |||
, using INAA. j i | |||
i i127 Tsukahara FAPIG Radiation Res. Kyoto Fission Track Age Irradiation of samples in the thermal FAPIG Lab. Dating column for fission track age dating. Radiation Research Lab., . | |||
Japan i129 Hughes Idaho State University Chemical Characterization Evaluation of high Icvel radioactive INEL l of Vitrification Eroducts waste melter performance by University , | |||
determination of the degree of Consonium l homogenization, the diffusion rates (MIT) and the number and types of phases remaining aAer vitrification. | |||
a ! | |||
2 INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements A j 4g -* | |||
11 | |||
i Table VLC.3 U o[ | |||
Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) lOme Organization Name Project Title Description Funding i138 Ilughes Idaho State University Thesis and Faculty Use ofINAA to support a large USDOE Research Using INAA of variety of research projects imching (Reactor Use Geologic Materials the geochemistry of rocks in Idaho Sharing) and surrounding regions. This l includes support for two graduate classes Geology 615 and 625. | |||
1161 Reed University of Oregon Characterization of Characterization of komatiites from LSDOE Alteration and Australia for rare ca th element and (Reactor Use Mineralization in Komatiite platinum group element abundances Sharing) to evaluate their economic mineral resource potential. | |||
I177 Garver Union College Fission Track Analysis of Use of thermal column irradiations to Union College, Rock Ages perfor n fission track analysis with a NY view to the determination or rock ages. | |||
I178 Hughes Idaho State University Ar/Ar Radiometric Dating Imtstigation of the evolution of the National of Geological Samples Snake River Plain volcanic system. Science Foundation (EPSCoR) 1185 Elting University of Oregon Instrument Calibration Radiological instrument cahtration University of for the EmironmentalIIcalth and Oregon Safety Office INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements 2 | |||
4 3 | |||
M M M M M M M M M M M M M M M M M M M a | |||
i > w umms umma I | |||
Table VI.C.3 ? | |||
n Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding I186 Fitzgerald University of Arizona Fission Track Dating Thermal column irradiation of University of geological samples for fission track Arizona age-dating. | |||
I187 Sivaramakrishnan Oregon State University Radiation Effects on Determination ofirradiation effects Radiation Gallium Arsenide on semiconductois, and gallium Center, OSU arsenide in particular. The project starts with gamma irradiation and progresses to alpha, beta and neutrons later. | |||
I188 Salinas Rogue Community Photoplankton Growth in Liquid scintillation counting of C-14 Rogue College Southern Oregon Lakes radiotracer samples produced in a Community photoplankton study of four southern College Oregon lakes: Miller Lake, Lake of the Woods, Diamond Lake, and Waldo Lake. | |||
I190 Higginbotham Oregon State University Use of Radon as a Tracer Determination of non-aqueous phase Radiation for NAPL Determination liquid (NAPL) contamination in Center, OSU saturated and unsaturated aquifer material using radon as an indicator. | |||
1191 Vasconcelos Department of Earth Ar-39/Ar-40 Age Dating Production of Ar-39 from K-39 to Earth Sci., | |||
Sciences determine ages in various University of anthropologic and geologic materials. Queensland, Australia INAA = Instrumeatal Neutron Activation Analysis REE - Rare Earth Elements 2 | |||
4 g 3w | |||
Table VI.C.3 $ | |||
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies | |||
{ | |||
Project User (s) Name Organization Name Project Title Description Funding 1192 Ifigginbotham Oregon State University Evaluation of Analysis of several samples of sewer Radiation Radionuclides in Seuer sludge to determine the types and Center, OSU Sludge quantities of any radionuclides present. | |||
I193 Smith Oregon State University Irradiation of Viruses inactivation of viruses by gamma ray Food Sci. & | |||
irradiation. Technology, OSU 1196 Higley Oregon State University Dose Response Effects on Evaluation of the possible hormetic Radiation Bean Seeds effects in irradiated pinto bean seeds. Center, OSU Class project associated with RHP 587. | |||
1200 Moody Bechtel Hanford Stabilization of 90Sr and Geochemical study ofdesorption of CH2M Hill Incorporated 100 Area Cr(6+) Using strontium and chromium from Phosphatic Material Hanford soils, adsorption of Sr and Cr on various phosphates, and the determination of the solubility product of strontium hydroxyapatites. | |||
1201 Hanson SUNY at Stony Brook High Precision Dating of Use of fission track dating of various USDOE Sedimentary Material authigenic calcite and phosphate minerals to determine the time of sedimentation with a view to calibrating the geologic remrd. | |||
N INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements % | |||
3 M M M M M M M M M M M M M M M | |||
Table VI.C.3 @ | |||
n Listing of Majnr Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description , | |||
Funding 1203 Aulich Energy & Env. Plastics Pyrolysis Determination of Cs, Sb, Sn, V, Cu, Radiation Research Center Ti, Sr, Ce and Zr at the ppb levelin Center, OSU process matrices of oil, resin and char to evaluate the ability of the process to remove these clernents. | |||
1205 Kelley The Open University Argon-39/ Argon-40 Age Determination of the ages ofurious The Open Dating ofMinerals minerals by use of the argon- University, UK 39/ argon-40 ratio technique. | |||
12 % Hughes Idaho State University Chemical Correlation of NAA ofbasaltic rocks obtained from Idaho Water Volcanic Units on INEEL drill core and surface locations to Resources evaluate thelocal and regional Research Inst. | |||
stratigraphy beneath vanous facilities on the INEEL to determine the Wahy of the aquifer system. | |||
1209 Scholle London Coin Galleries Authenticity of Medieval Use of NAA to evaluate 5-6 London Coin Siher Coins Romanian medieval silver coinsin an Galleries attempt to corapare authentic coins to some with questioned authenticity. | |||
1215 Brinkly Emerald Diagnostics Sterilization of Latex Irradiation oflatex solutions in order Emerald Laboratory Solutions to sterilize the material for biological Diagnostics research products. Laboratory INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements N | |||
4 m G (A L. . | |||
y m ,_ .-- | |||
Table VI.C.3 $ | |||
Listing of Major Research and Service Projects Performed er in Progress at the Radiation Center and Their Funding Agencies | |||
{ | |||
Project User (s) Name Organization Name Project Title Description Funding 1225 Roden-Tice SUNY College at Fission Track Analysis of Analysis of the thermal history of Radiatien Plattsburgh Apatite and Zircon Triassic basins in Connecticut using Center, OSU fission track age dating methods. | |||
1229 Binney Oregon State University Production of Copper-67 Investigation of the feasibility of the Nuclear production of the medicalisotope Engineering Cu67 from enriched Zn67 by using Dept., OSU the n-p reaction and a medium power research reactor. | |||
1230 Lamperti City of Corvallis Analysis ofIndustrial Sampling and counting of effluent Radiation Efiluent from local industries in order to Center, OSU determine the presence and magnitude of any radionuclides. | |||
1231 Adams University of Utah Rare Earth Elements in the Evaluation of REEs in nater as a USDOE Coso Geothermal System method of differentiating the various (Reactor Use reservoirs iri the Coso system Sharing) geothermat field. | |||
1232 Bergantz University of Chemical evolution of the Evaluation of the mechanics involved USDOE Washington lower crust with the growth of the continental (Reactor Use crust and the origin of chemical Sharing) diversity in volcanic rocks. | |||
INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements N | |||
A G | |||
M M M M M M M M M M M M M M M | |||
Table VI.C.3 @ | |||
n Listing of Major Research and Senice Projects Performed or la Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Nanne Project Title Descripties Funding 1236 Farmer University of Colorado- Geochemistry of the Organ Identification of the processes USDOE Boulder Needle Pluton, New Mexico responsible for the generation of (Reactor Use silicic magma using samples from the Sharing) | |||
Organ Needle pluton in south-central New Mexico 1237 Mueller University of Florida Early Crustal Ew>lution Evaluation of ancient crustal USDOE cv...ps..cnts with unusual Nd isotopic (Reactor Use compositions to better constrain the Sharing) origin of these segments. | |||
1238 Roden-Tice SUNY College at Fission Track Analysis of Use offission track dating to analyze USDOE Plattsburgh Apatite and Zircon thermal histories ofvanous (Reactor Use mountains, including: Olympic - Sharing) | |||
Moutains, WA; Adirondack Mountains, NY; Ouachita Mountains, Himalayas; Klamath Mountains, OR. | |||
1239 Garver Union College Timing of Uplift and Use offission track analysis to USDOE Provenance ofSediments determine the timing of uplift and the (Reactor Use from Orogenic Highlands provenance ofsediment:: died from Sharing) orogenic highlands. | |||
INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements ?1 54 L | |||
i l | |||
I Table VLC.3 w= | |||
i?. | |||
= | |||
Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and Their Funding Agencies l | |||
Project User (s) Name Organization Name Project Title Description Funding i | |||
1240 Hirt College of the Siskiyous Vertical Zonation of the Development of a compositional USDOE i | |||
Paradise Pluton, Sierra profile for the upper part of the SE (Reactor Use Nevada, CA Sierra batholith in the region between Sharing) l Golden Trout Creek and Forester Pass. | |||
1241 Steiner City College of New Delineation of TTG Terrain Delineation of trondhjemite-tonalite- USDOE York of Southern New York & granite terrain to resolse the problem (Reactor Use Connecticut of source rock and the timing of Sharing) major prograde metamorphic esents. | |||
1243 McBirney University ofOregon Differentiation of the Completion of the most thorough USDOE Skaergaard intmsion investigation of magmatic (Reactor Use differentiation ever completed. Sharing) 1244 Reed University of Oregon Geology and Genesis of the Determination of the gains and losses USDOE Ernest Henry Deposit, of trace elements due to ore (Reactor Use Queensland Australia formation in the Ernest Henry Fe-Cu- Sharing) | |||
Au deposit. | |||
1247 Johnson Texas Tech. University Genesis of Pre-Accretion Determination of the process USDOE Plutoas in the Blue Mtns, responsible for magma generation in (Reactor Use OR order to provide important tectonic Sharing)}} | |||
Latest revision as of 17:39, 17 December 2020
| ML20155E812 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 06/30/1998 |
| From: | Binney S, Kathryn Brock, Carver D Oregon State University, CORVALLIS, OR |
| To: | |
| Shared Package | |
| ML20155E804 | List: |
| References | |
| NUDOCS 9811050190 | |
| Download: ML20155E812 (206) | |
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I LIST OF FIGURES g 5 Figure Title Page I.D.1 Floor Plan of the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-11 l III.A.1 Cutaway View of Standard TRIGA Mark II Core Arrangement . . . . . . . III-19 III.A.2 Horizontal Section of TRIGA Mark II Reactor . . . . . . . . . . . . . . . . . . . . III-20 III.A.3 Vertical Section of TRIGA Mark II Reactor . . . . . . . . . . . . . . . . . . . . . . . III-21 J III.C.1 Gammacell 220 "Co Irradiator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-22 IV.A.1 OSTR Annual Energy Production vs. Time (Annual Reporting Period) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-26 IV.E.1 Monthly Surveillance and Maintenance (Sample Form) . . . . . . . . . . . . . IV-30 IV.E.2 Quarterly Surveillance and Maintenance (Sample Form) . . . . . . . . . . . . . IV-31 IV.E.3 Semi-Annual Surveillance and Maintenance (Sample Form) . . . . . . . . . . IV-33 IV.E.4 Annual Surveillance and Maintenance (Sample Form) . . . . . . . . . . . . . . IV-35 V.D.1 TRIGA Facility and Radiation Center Area Dosimeter Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-2 7 I V.E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence . . . . . . . . . . . . . . . . . . . . . . . . . . V-28 V.E.2 Monitoring Stations for the OSU TRIGA Reactor . . . . . . . . . . . . . . . . . . V-29 I I l
i Anturl Report cf the l Oreg:n St:te University Radiation Center and TRIGA Reactor l July 1,1997 -June 30,1998 l 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-AC07-76ERO1953) for University Reactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc. 4 C. Oregon Office of Energy, OOE Rule No. 345-030-010. Edited by: S. E. Binney, Director With contributions from: K. M. Brock, Health Physicist D. R. Carver, Radiation Protection Technologist M. R. Conrady, Analytical Support Manager D.K. Dalton, Administrative Assistant B. Dodd, Director A. D. Hall, Reactor Supervisor J. F. Higginbotham, Reactor Administrator L. M. James, Office Specialist ' R. A. Keen, Office Coordinator D. S. Pratt, Senior Health Physicist L. J. Robinson, Word Processor S. P. Smith, Scientific Instrument Technician E. G. Schotfort, Project Manager D. C. West, Office Specialist 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 1998 _--_ __ _ J
I I .g Annual Report of the l .E Oregon State University Radiation Center and TRIGA Reactor l Table of Contents b PART I- OVERVIEW I A. B. Acknowledgements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-l Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 1 l C. In trod ucti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-2 D. -l E. Overview of the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-3 Summary of OSTR Environmental and Radiation Protection Data . . . . . . . . . . . . . . . . . I-5
- 1. Liquid Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 5
- 2. Liquid Waste Generated and Transferred . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-5
- 3. Airborne Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 ig 4. Solid Waste Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-6 E 5. Radiation Exposure Received by Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-7
- 6. Number of Routine Onsite and Offsite Monitoring Measurements and Samp l es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I- 8 F. Hi sto ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-9 I PART II- PEOPLE A. Fac ul ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II - l B. Visiting Scientists and Special Trainees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-6 C. OSU Graduate S tudents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-7 D. Business, Administrative and Clerical Staff. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-8 E. Reactor Operations Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-8 F. Radiation Protection Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-8 G. Scientific Support Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-9 H. OSU Radiation Safety Office Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-9 lI I. Co mmittees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-9
- 1. Reactor Operations Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
l . . . . . . . II-9 l 2. Radiation Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-10
- 3. Radiation Center Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-10 I
PART III- FACILITIES
= I A. Research Reactor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- l
- 1. Descriptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- l
- 2. Utilization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-2
- a. Instructio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-2 l
- b. Research . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-3 g B. Analytical Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-3 g
- 1. Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-3
- 2. U tilization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 C. Radioisotope Irradiation Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4
- 1. Descriptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 D.
- 2. Utilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 Laboratories and Classrooms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4 l
- 1. Desc ription . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-4
- 2. Utilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-5 E. Instrument Repair and Calibration Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6
- 1. D escripti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6 E
- 2. U tilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6 m G. Li braries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6
- 1. Desc riptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-6
- 2. Utilizatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H I-7 PART IV - REACTOR A. Operating S tatistics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-1 B. Experiments Performed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV- 1
- 1. Approved Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV- 1
- 2. Inactive Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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-4
- 2. 10 CFR 50.59 Changes to Reactor Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . IV-9
- 3. 10 CFR 50.59 Changes to Reactor Experiments . . . . . . . . . . . . . . . . . . . . . . . . IV-16 i E. Surveillance and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-17
- 1. Non-Routine Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-17
- 2. Routine Surveillance and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-18 F. Reportable Occurrences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-18 ,
1 1
1 P.m PART V- PROTECTION A. Introd ucti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V- 1 B. i Environmental Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-1
- 1. Liquid Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-2 2.
Airborne Effluents Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-2 3. l C. Solid Waste Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-3 Personnel Doses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-3 D. Facility S urvey Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-4 1. Area Radiation Dosimeters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-5
- 2. Routine Radiation and Contamination Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . V-5 E. Environmental Survey Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-6 I 1. Gamma Radiation Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-6
- 2. Soil, Water, and Vegetation Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-7 F. Radioactive Material Shipments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-9 G.
References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-9 I PART VI- WORK A. S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI- l B. Teachi ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI- 1 C. l Research and Service . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-l
- 1. Neutron Activation Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-2 2.
Forensic S tudies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-2 3. Irradiations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-3
- 4. Radiological Emergency Response Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-3
- 5. Training and Instruction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-4 1 6.
Radiation Protection Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-4
- 7. Radiological Instrument Repair and Calibration . . . . . . . . . . . . . . . . . . . . . . . . . VI-5 8.
Co nsultation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-6 l l PA.RT VII- WORDS L A. Publications in Print . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII- l B. Th e se s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII -7 C. Reports Submitted for Publication . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-8 D. Documents in Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-9 1. P ublications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-9 [ 2. Theses...................................................... . VII-10 E. Presentations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII- 10 F. Public Relations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-14
l i j LIST OF TABLES Table Title P. age I, III.A.1 OSU Courses Using the OSTR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-8 III.A.2 OSTR Teaching Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-9 III.A.3 OSTR Research Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- 10 III.B.1 Radiation Center Spectrometry Systems: Ganuna, Low Energy Photon, Alpha . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III- 1 1 III.B.2 Radiation Center Liquid Scintillation Counting Systems . . . . . . . . . . . . . III-12 I III.B.3 Radiation Center Proportional Counting Systems . . . . . . . . . . . . . . . . . . III-13 III.B.4 Thermoluminescent Dosimeter Systems . . . . . . . . . . . . . . . . . . . . . . . . . . III-14 III.C.1 Oammacell 220 *Co Irradiator Use . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-15 III.D.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-16 IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) . . . . . . . . . . . . . . IV-19 IV.A.2 OSTR Operating Statistics with the Original (20% Enriched) Standard TRIGA Fuel Core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-22 IV.A.3 Present OSTR Operating Statistics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-23 IV.A.4 OSTR Use Time in Terms of Specific Use Categories . . . . . . . . . . . . . . . IV-24 IV.A.5 OSTR Multiple Use Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-25 IV.B.1 Use of OSTR Reactor Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-27 IV.C.1 Unplanned Reactor Shutdowns and Scrams . . . . . . . . . . . . . . . . . . . IV-2 8 V.A.1 Radiation Protection Program Requirements and Frequencies . . . . . . . . . V-10 I I
i 4 i 1 l
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LIST OF TABLES (Continued) Table Title ! Page l V.B. I .a Monthly Summary of Liquid Effluent Releases to the Sanitary I S ewer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V- 1 1 V.B. I .b Annual Summary of Liquid Waste Generated and Transferred . . . . . . . . . V-12 i V.B.2 Monthly Summary of Gaseous Effluent Releases . . . . . . . . . . . . . . . . . . . V-13 V.B.3 Annual Summary of Solid Waste Generated and l Transferred . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V- 14 I V.C.1 Annual Summary of Personnel Radiation Doses Received . . . . . . . . . . . . V-15 I V.D.1 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-16 ' V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-17 , V.D.3 Annual Summary of Radiation Levels and Contamination Levels j Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-19 V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence . . . . . . . . . . . V-20 j V.E.2 Total Dose Equivalent at the Off-Site Gamma Radiation
- E Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-21 V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity 3
(Minus H) for Environmental Soil, Water, and Vegetation S ampl es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-22 V.E.4 Average LLD Concentration and Range of LLD Values for Soil, Water and Vegetation Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-23 l V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 . . . . . . . . . . . . . V-24
I LIST OF TABLES (Continued) Table Title Page V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License O RE 9 000 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-25 V.F.3 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 . . . . . . . . . . . . . . . . . . . . . . . V-26 VI.C.1 Institutions and Agencies Which Utilized the Radiation C e n t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V I -7 VI.C.2 Graduate Student Research Which Utilized the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-12 VI.C.3 Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies . . , . . . . . . VI-26 VI.C.4 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and the l Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-61 l VI.C.5 Summary of Radiological Instrumentation Calibrated to Support Other OSU Departments and Other Agencies . . . . . . . . . . . . . . . . . . . . . . . VI-62 l VI.C.6 Summary of Radiological Instrument Repair Activities for Non-Radiation Center Departments and Agencies . . . . . . . . . . . . . . . . . . . VI-63 VII.F.1 Summary of Visitors to the Radiation Center . . . . . . . . . . . . . . . . . . . . . VII-15 1 I I
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1 Overview Part1 Part I OVERVIEW A. Acknowledgments Many individuals and organizations help the Radiation Center succeed, and in recognition ofthis, the staffof the OSU Radiation Center and TRIGA Reactor would like to extend its appreciation to all of those who contributed to the information and events contained in this report: to the University administration; to those to provided our funding, particularly the state ofOregon and the U. S. Department ofEnergy (USDOE); to our regulators; to the researchers, the students, and others who used the Radiation Center; to OSU Facilities Services; to OSU Security Ser ices and the Oregon State Police; and to the OSU Department ofPrinting and Mailing, who provide a consistent and quality service in this report. We most camestly say,"thank you." The Center would not be able to accomplish all that is shown in this report without the diligent efforts ofall ofits staff. These times ofbudget cuts have meant that each person has had to work harder with less help. It is to their credit that we have managed to maintain our level and quality of service. To each one..."thank you." Putting this report together each year is a major effort for several people. Only those who have been involved can fully understand what a greatjob Linda James has done at the data-gathering, organization and keyboarding of this annual report. Thanks, Linda! B. Executive Summary The data from this reporting year show that the use of the Radiation Center and OSTR has still increased, despite being "maxed" out in many areas. This increase has been achieved by greater efficiencies. A good illustration of this is in reactor use hours. The reactor was busy an average of40hoursperweek. Additionaluserswereaccommodatedbyincreasingthenumberofpeople who were simultaneously using the different reactor facilities. This year there were two or more users on the reactor for a total of 441 hours. The OSTR supported 29 different OSU classes this year, mostly in the Department ofNuclear Engineering. The number ofhours for courses (up 29% from last year) roughly equaled the number ofhotr spent supporting research projects (about 1490 hours each). Eighty-five percent of the OSTR research hours were in support ofoff-campus research projects. The number ofsamples irradiated in the reactor during this reporting period was 4,707, which is over 1,000 more than the average. The percent ofunfunded OSTR use hours (3 %) decreased by a factor oftwo from last
2 Overview Parti I year. This is the result of an initial attempt to move to a more full cost recovery basis for services provided by the Center. The OSTR continues to be the facility of choice for many of the "Ar/*Ar geochronology laboratories around the world. Personnel at the Radiation Center conducted 101 tours of the facility, accommodating 1,081 visitors. The visitors included elementary, middle school, high school, and college students; relatives and friends; faculty; current and prospective clients; national laboratory and industrial g scientists and engineers; and state, federal and in. ernatical officials. The Radiation Center is a g significant positive attraction on campus because visitors almost always go away with a good impression of the facility and of Oregon State University. Research proj ects ofpersonnel housed in the Radiation Center totaled approximately $ 1.2 million for this year. l The Radiation Center projects database initiated a fewyears ago continues to provide a useful way oftracking the many different aspects of work at the facility. The number ofproj ects supported this year was 134. Reactor projects comprised about 93% of all projects. The contracts supporting these research proj ects totaled approximately $3,000,000. This year the Radiation E Center serviced 81 research faculty and 133 students (for a total of 586 uses of Center facihties) E from 63 different institutions,65% ofwhich were from other states and 16% ofwhich were from outside the U. S. and Canada. So while the Center's primary mission is local, it is also a facility with a national and international clientele. With the closing ofthe State of Oregon's environmental radiological monitoring laboratory in Portland, the Radiation Center is essentially now the only place in the state where radiological monitoring can be performed. The Radiation Center web site provides an easy way for potential users to evaluate the Center's facilities and capabilities as well as to apply for a project and check use charges. The address is: http://www.ne..orst.edu/ facilities / radiation _ center. (check it out!) C. Introduction The current annual report ofthe Oregon State University Radiation Center and TRIGA Reactor follows the usual format by including information relating to the entire Radiation Center rather than just the reactor. However, the information is still presented in such a manner that data on the g reactor may be examined separately,ifdesired. It should be noted that all annual data given in this E report cover the period from July 1,1997 through June 30,1998. Cumulative reactor operating I I'
1 3 Overview Parti data in this report relate only to the FLIP-fueled core. This covers the period from August 1,1976 through June 30,1998. For a summary ofdata on the reactor's original 20% enriched core, the reader is referred to Table IV.A.2 in Part IV of this report or to the 1976-77 annual report if a more comprehensive review is needed. In addition to providing general information about the activities ofthe Radiation Center, this report is designed to meet the reporting requirements ofthe U. S. Nuclear Regulatory Commission, the U. S. Department of Energy, and the Oregon Office of Energy. Because of this, the report is divided into several distinct parts so that the reader may easily find the sections ofinterest. D. Overview of the Radiation Center The Radiation Center is a unique facility which serves the entire OSU campus, all other institutions within the Oregon University System, and many other colleges and universities throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforcement, energy, health, and environmental quality, and renders assistance to Oregon industry. In addition, the Radiation Center provides permanent office and laboratory space for the OSU Department ofNuclear Engineering, the OSU Radiation Safety Office, the Institute ofNuclear Science and Engineering, and for the OS U nuclear chemistry, radiation chemistry, and geo- and cosmochemistry programs. There is no other universityfacility with the combinedcapabilities ofthe OSURadiation Center in the western halfofIhe UnitedStates. Located in the Radiation Center are major items ofspecialized equipment and unique teaching and research facilities. Figurel.D.1 shows the layout ofthese facilities at the Radiation Center. They include a TRIGA Mark Il research nuclear reactor; a "Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associated germanium detectors; a neutron radiography facility capable oftaking still or very high speed radiographs; and a variety ofinstruments for radiation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with up-to-date instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laboratories for animal and plant experiments involving radioactivity; a facility for repair and calibration of mchation protection instrumentation; and facilities for pachging radioxtive materials for shipment to national and international destinations. A major non-nuclear facility housed in the Radiation Center is the one-quarter scale thermal hydraulic advanced plant expenmental (APEX) test facility for the Westinghouse AP600 reactor design. The AP600 is a next-generation nuclear reactor design which incorporates many passive safetyfeaturesaswellasconsiderablysimplifiedplantsysternsandequipment. APEXoperates at pressures up to 400 psia and temperatures up to 450 F using electrical heaters instead of
4 Overview Parti nuclear fuel. All major components of the AP600 are included in APEX and all systems are appropriately scaled to enable the experimental measurements to be used for safety evaluations and licensing ofthe full scale plant. This world-class facility meets exacting quality assurance criteria to provide assurance of safety as well as validity of the test results. Also added to the Radiation Center this past year is the Advanced Thermal Hydraulics Research Laboratory, which will be used for state-of-the-art two-phase flow experiments. The Radiation Center staff regularly provides direct support and assistance to OSU teaching and research programs. Areasofexpertisecommonlyinvolvedinsucheffortsincludenuclearengineering, nuclear and radiation chenustry, neutron activation analysis, radiation effects on biological systems, radiation dosimetry, environmental radioactivity, production ofshort-lived radioisotopes, radiation shielding, nuclear instrumentation, emergency response, transportation ofradioactive materials, instrument calibration, radiation health physics, mdioactive waste disposal, end other related areas. In addition to formal academic and research support, the Center's staffprovides a wide variety of other services including public tours and instructional programs, and professional consultation associated with the feasibility, design, safety, and execution ofexperiments using radiation and radioactive materials. I I I I I
5 Overview Parti [I E. Summary of Environmental and Radiation Protection Data
- 1. Liquid Effluents Released (See Table V.B.I.a)
- a. Total estimated quantity of radioactivity sLLD (95%) of released (to the sanitary sewer)<o(2) 1.79 x 10-5 Ci
- b. Detectable radionuclides in the liquid waste N/A I c. Estimated average concentration of released radioactive material at the point of release sLLD (95%) of 4.08 x 104 Ci/ml l
1
- d. Percent of applicable monthly average concentration for released liquid radioactive material at the point of release N/A I
- e. Total volume ofliquid effluent released, including diluent (3) 1,158 gallons
- 2. Liquid Waste Generated and Transferred (See Table V.B.I.b)
- a. Volume ofliquid waste packagedW 52 gallons
- b. Detectable radionuclides in the waste 32p, wCo, "Rb
- c. Total quantity of radioactivity in the waste 4.0 x 10-2 Ci I 1 I (1) OSU has implemented a policy to reduce radioactive wastes disposed to the sanitary sewer to l
the absolute minimum. (2) The OSU operational policy is to subtract only detector background from our water analysis data and not background radioactivity in the Corvallis city water. 1 (3) Total volume ofeffluent plus diluent does not take into consideradon the additional nuxmg with the over 250,000 gallons per year ofliquids and sewage normally discharged by the Radiation Center I complex into the same sanitary sewer system. (4) TRIG A and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer l l to its waste processing facility for solidification and final packaging. 1 l
6 Overview Part1
- 3. Airbome Effluents Released (See Table V.B.2)
- a. Total estimated quantity ofradioactivity I
released 5.42 Ci
- b. Detectable radionuclides in the gaseous waste") d"Ar (ti,f = 1.83 hr)
- c. Estimated average atmospheric diluted concentration of d!Ar at the point ofrelease 3.5 x 10-8 Ci/ml
- d. Percent of applicable monthly average concentration for diluted concentration l
of 4'Ar at the point of release 0.9%
- e. Total estimated release of radioactivity in particulate form with half-lives greater than 8 daysG) None
- 4. Solid Waste Released (See Table V.B.3)
- a. Total amount of solid waste packaged and disposed of 66 f1 3 3
- b. Detectable radionuclides in the solid waste H,22Na, 24Na, 46Sc, 47 Sc, 5'Cr, 58Co, 59e, 6 Co, s6Rb, "Sr, "3Cd,i22Sb, i24Sb, g 204 T1,2"Bi, 226Ra, E 238U, 24 Am
- c. Total radioactivity in the solid waste 6.6 x 10-5 Ci (1) Routine gamma spectmscopy analysis ofthe gaseous radioactivity in the stack discharge indicated that it was virtually all d'Ar.
(2) Evaluation ofthe detectable particulate radioactivity in the stack discharge confumed its origin as naturally occurring radon daughter products, predominantly2 "Pb and 2"Bi, which are not associated with reactor operations.
7 Overview Part1 [' 5. Radiation Exposure Received by Personnel (See Table V.C.1)W
- a. Facility Operating Personnel
{: (mrem) (1) Average whole body 11 [ (2) Average extremities 80 (3) Maximum whole body 35 (4) Maximum extremities 100
- b. Key Facility Research Personnel i
[ Average whole body (1) <1 (2) Average extremities 2 [ (3) Maximum whole body ND (4) Maximum extremities 30 [ c. Facilities Services Maintenance Personnel r (1) Average whole body <1 L (2) Maximum whole body 1
- d. Laboratory Class Students
{ (1) Average whole body <1 ( (2) Average extremities 1 (3) Maximum whole body 10 (4) Maximum extremities 80 [.
- e. Campus Police and Security Personnel
[' (1) Average whole body ND (2) Maximum whole body ND
- f. Visitors
[. (1) Average whole body <1 (2) Maximum whole body 20 [ { (1) "ND"indime that each ofthe beta-gamma dosimeters during the reporting period was less than , the vendor's gamma dose reporting threshold of10 mrem or that each ofthe neutron dosimeters L was less than the vendor's threshold of 30 mrem, as applicable. c
-___-___-______f
8 Overview Part i
- 6. Number of Routine Onsite and Offsite Monitoring Measurements and Samples I
- a. Facility Survey Data (1) Area Radiation Dosimeters (See Table V.D.1)
(a) Beta-gamma dosimeter measurements 148 (b) Neutron dosimeter measurements 48 (2) Radiation and Contamination Survey Measurements (See Table V.D.3) ~6000
- b. Environmental Survey Data (1) Gamma Radiation Monitoring (See Tables I'
V.E.1 and V.E.2) (a) Onsite monitoring
- OSU TLD monitors 108 E
-- Radiation Detection Co. TLD monitors 72 E
- Monthly rem /h measurements 108 (b) Offsite monitoring
-- OSU TLD monitors 264
-- Radiation Detection Co. TLD monitors 104
- Monthly rem /h measurements 252 (2) Soil, Water and Vegetation Surveys (See Table V.E.3)
(a) Soil samples 16 (b) Water samples 14 (c) Vegetation samples 56 I l l l i
9 m.wiew I F. History A brief chronology of the key dates and events in the history of the OSU Radiation Center and the TRIGA reactor is given below: l June 1964 Completion of the first phase of the Radiation Center, consisting of 32,397 square feet of office and laboratory space, under the direction of founding Director, C. H. Wang. July 1964 Transfer of the 0.1 W AGN 201 reactor to the Radiation Center. I This reactor was initially housed in the Mechanical Engineering Department and first went critical in January,1959. October 1966 Completion of the second phase of the Radiation Center, consisting of 9,956 square feet of space for the TRIGA reactor and associated laboratories and offices. March 1967 Initial criticality of the Oregon State TRIGA Reactor (OSTR). I The reactor was licensed to operate at a maximum steady state power level of 250 kW and was fueled with 20% enriched fuel. October 1967 Formal dedication of the Radiation Center. August 1969 OSTR licensed to operate at a maximum steady state power of 1 I MW, but could do so only for short periods of time due to lack of cooling capacity. I June 1971 OSTR cooling capacity upgraded to allow continuous operation at 1 MW. April 1972 OSTR Site Certificate issued by the Oregon Energy Facility Siting Council. September 1972 OSTR area fence installed. December 1974 AGN-201 reactor permanently shut down. March 1976 Completion of 1600 square feet of additional space to accommodate the rapidly expanding nuclear engineering program. l July 1976 OSTR refueled with 70% enriched FLIP fuel. July 1977 Completion of a second 1600 square feet of space to bring the Radiation Center complex to its current total of 45,553 square feet. January 1980 Major upgrade of the electronics in the OSTR control console.
10 Overview Part1 January 1980 Major upgrade of the electronics in the OSTR control console. July 1980 AGN-201 reactor decommissioned and space released for unrestricted use. June 1982 Shipment of the original 20% enriched OSTR fuel to Westinghouse Hanford Corporation. December 1984 C. H. Wang retired as director. C. V. Smith became new director. I August 1986 Director C. V. Smith left to become Chancellor of the University of Wisconsin-Madison. A. G. Johnson became new Director. December 1988 AGN-201 components transferred to Idaho State University for use in their AGN-201 reactor program. December 1989 OSTR licensed power increased to 1.1 MW. l June 1990 Installation of a 7000 Ci 6 Co Gammacell irradiator. l March 1992 25th anniversary of the OSTR initial criticality. l November 1992 Start of APEX plant construction. June 1994 Retirement of Director A. G. Johnson. B. Dodd became new I Director. l August 1994 APEX inauguration ceremony. August 1995 Major extemal refurbishment: new roof; complete repaint; rebuilt parking lot; addition of landscaping and lightine, i l March 1998 Start of ATHRL construction. l l I I I
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1 People pa,, y Part II I PEOPLE l This part contains a listing of all people who were residents of the Radiation Center or who worked a I significant amount oftime at the Center during this reporting period. Sections A, B and C list the academic staff, trainees, and students, while sections D through G give the Radiation Center's operating staff. Section H shows the OSU Radiation Safety Oflice staff, and section I provides the composition ofcommittees involving Ceriter personnel. It should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are listed in this part. Summary information on the number ofpeople involved is given in Table VI.C.1, while individual names and projects are listed in Tables VI.C.2 and VI.C.3. A. Professional and Research Faculty Attfield, Martin P. Faculty Research Associate Chemistry l I *Binney, Stephen E. I Professor Nuclear Engineering Chairman, OSTR Reactor Operations Committee
- Brock, Kathryn M.
Faculty Research Assistant l Health Physicist
*Conard, Bobb! L.
Senior Faculty Research Assistant College of Oceanic md Atmospheric Sciences
*Conrady, Michael R.
L Faculty Research Assistant i Analytical Support Manager + l L Craig, A. Morrie Professor { College of Veterinary. Medicine m L
- OSTR users for research and/or teaching.
m
2 People Part11 Daniels, Malcohn g Professor Emeritus E Chemistry
*Dodd, Brian Director, Radiation Center Director, Institute of Nuclear Science and Engineering Professor Nuclear Engineering and Radiation Health Physics Fekou-Youmbi, Valentin I
Faculty Research Associate Chemistry Groome, John T. Faculty Research Assistant APEX Facility Operations Manager Nuclear Engineering l Guncerson, Chris E. Faculty Research Assistant APEX Facility Operator / Test Engineer Nuclear Engineering Hart, Lucas P. Faculty Research Associate Chemistry
'Higginbotham, Jack F.
Reactor Administrator Associate Professor g Nuclear Engineering and Radiation Health Physics s
*Higley, Kathryn A.
Assistant Professor Nuclear Engineering and Radiation Health Physics Hovermale, Jeannette T. Faculty Research Assistant College of Veterinary Medicine I
- OSTR users for research and/or teaching.
L 3 People { Part11 Johnson, Arthur G. {- Director Emeritus, Radiation Center Professor Emeritus [ Nuclear Engineering and Radiation Health Physics Johnson, Richard A. [ Adjunct Faculty Nuclear Engineering Klein, Andrew C. Acting Department Head [. Department ofNuclear Engineering Director, Oregon Space Grant Program Professor [ Nuclear Engineering
*Krane, Kenneth S.
[ t Chair, Physics Department Professor Physics [ Krebs, Rolf (. Faculty Research Associate Crop and Soil Science Lafi, Abd Y. Faculty Research Associate APEX Research Analyst [ Nuclear Engineering [ *Loveland, Walter D. 1:afessor Chemistry MacVicar, Robert President Emeritus {
*Meredith, Charlotte C.
Faculty Research Assistant { College of Oceanic and Atmospheric Sciences f~ f r
- OSTR users for research and/or teaching.
r J
People Part11 l Mommer, Niels K. Faculty Research Associate g Physics a Palmer, Todd S. E E Assistant Professor Nuclear Engineering
*Pastorek, Christine SeniorInstructor Chemistry Popovich, Milosh I' Vice President Emeritus 5
*Prahl, Frederick G. g a
Professor College of Oceanic and Atmospheric Sciences
*Pratt, David S.
Faculty Research Assistant Senior Health Physicist . Reyes, Jr., Jos6 N. APEX PrincipalInvestigator Professor Nuclear Engineering El 3 Ringle, John C. l Professor l Nuclear Engmeenng j Associate Dean of the Graduate School i Robinson, Alan H. Department Head Emeritus Nuclear Engineering l
*Schmitt, Roman A.
Professor Emeritus Chemistry I
- OSTR users for research and/or teaching.
l
5 People Part11
*Schutfort, Erwin G.
Faculty Research Assistant Radiation Center Project Manager
- Sparrow, Margaret Senior Research Assistant College of Oceanic and Atmospheric Sciences
*Sullivan, Barbara E.
Faculty Research Assistant I College ofOceanic and Atmospheric Sciences Wang, Chih H. I Director Emeritus, Radiation Center Professor Emeritus Nuclear Engineering Young, Roy A. I Professor Emeritus Botany and Plant Pathology Yundt, Michael S. Faculty Research Assistant I APEX Instrument Specialist / rest Engineer Nuclear Engineering I I . I I b [ r L
- OSTR users for research and/or teaching.
l
1 6 P:ople Part11 I l l B. Visiting Scientists and Special Trainees Advisor or Research Name Field (Afiliation) Program Director Foreman, Katherine Saturday Academy Mentorship Program W. D. Loveland Crescent Valley High School l Corvallis, Oregon Jovanovic, Ana G. Visiting Undergraduate Student E. G. Schtitfort l Chemical Engineering Baylor University Lekas, David Visiting Undergraduate Student W. D. Loveland l l Chemistry Uppsala Universitet, Sweden l Less, Greg Undergraduate Student W. D. Loveland Chemistry i Oregon State University l l Menge, Duncan Saturday Academy Mentorship Program W. D. Loveland l Crescent Valley High School Corvallis, Oregon .
*Nakazawa, Yuko NSF Research Experience for K. S. Krane l
Undergraduates Program State University of New York l at Stonybrook l E l Ngemvijit, Narippawaj Visiting Faculty J. F. Higginbotham l Thailand
- Reel, Justin NSF Research Experience for K. S. Krane Undergraduates Program Camegie-Mellon University
- Shivers, Robert J. Student Research Assistant W. D. Loveland Environmental Science Oregon State University Wallin, Petra Visiting Undergraduate Student W. D. Loveland Chemistry Royal Institute of Technology, Sweden Xiao, Zejun Project Manager J. N. Reyes Reactor Thermalhydraulic Lab Nuclear Power Institute of China Chengdu, China l
- OSTR users for research and/or teaching.
7 People party C. OSU Graduate Students Degree Name Program Field Advisor Al-Hussan, Khalid A. PhD Nuclear Engineering A. C. Klein Alves, Mauro A. PhD Physics J. A. Gardner Asghar, Sabooh MS Nuclear Engineering T. S. Palmer Baik, Seung-Hyuk PhD Nuclear Engineering J. F. Higginbotham Boone, Darren M. MS Radiation Health Physics J. F. Higginbotham Brice, Derek J. MS Nuclear Engineering T. S. Palmer Cantaloub, Michael G. MS Radiation Health Physics J. F. Higginbotham Chinudomsub, Kittisak MS Radiation Health Physics J. F. Higginbotham Colpo, Sarah E. MS Nuclear Engineering J. N. Reyes
*Crail, Scott A. MS Radiation Health Physics J. F. Higginbotham Crowley, Paul R. MS Radiation Health Physics J. F. Higginbotham Day, Travis D. MS Chemistry W. D. Loveland Dunn, John R. MS Chemistry W. D. Loveland Ellis, Christopher P. MS Nuclear Engineering J. N. Reyes Jue, Tracy M. MS Radiation Health Physics S. E. Binney Keillor, Martin E. PhD Nuclear Engineering S. E. Binney Kellar, Marvin G. MS Radiation Health Physics B. Dodd Kim, Kang Seog PhD Nuclear Engineering T. S. Palmer Kropp, Edward K. MS Radiation Health Physics S. E. Binney Lee, Hsing Hui PhD Nuclear Engineering A. C. Klein '
Leon, Laura M. MS Radiation Health Physics J. F. Higginbotham Marianno, Craig M. PhD Radiation Health Physics K. A. Higley Menn, Scott A. MS Radiation Health Physics K. A. Higley Miller, Robert E. MS Radiation Health Physics K. A. Higley l Pagh, Richard T. PhD Nuclear Engineering A. C. Klein l Potter, Nathan K. MS Radiation Health Physics K. A. Higley
*Povetko, Oleg G. PhD
{ Radiation Health Physics K. A. Higley Richardson, Eric L. MS Nuclear Engineering T. S. Palmer Rios, Maribel G. MS Physics K. S. Krane Rusher, Christopher D. MS Nuclear Engineering J. N. Reyes Saiyut, Kittiphong PhD Nuclear Engineering J. F. Higginbotham
*Schntfort, Erwin G. MS Geosciences C. Field Schwab, Kristen E. MS Radiation Health Physics K. A. Higley Strohecker, Mark F. MS Nuclear Engineering T. S. Palmer Tiyapun, Kanokrat PhD Radiation Health Physics S. E. Binney Uyeda Jr., Graydon S. MS Nuclear Engineering J. N. Reyes l Wachs, Daniel M. MS Nuclear Engineer'ng J. N. Reyes Walker, Matthew J. MS Radiation Health Physics J. F. Higginbotham Welter, Kent B. PhD Nuckar Engineering T. S. Palmer l Zyromski, Kristiana E. PhD Chemistry W. D. Loveland
- OSTR users for research and/or teaching.
8 People Part11 D. Business, Administrative and Clerical Staff Director, Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B. Dodd Business Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. C. Campbell Office Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. K. Dalton ( Office Specialists . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. C. West L. M. James l Custodian . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E. Cimbri Office Coordinator (Nuclear Engineering) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . R. A. Keen
- Word. Processing Technician (Nuclear Engineering) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L. J. Robinson Word Processing Tecimician (APEX - Nuclear Engineering) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . T. L. Culver l
E. Reactor Operations Ssaff I Princij ,al Security Officer, Senior Reactor Operator . . . . . . . . . . . . . . . . . . . . . . . B. Dodd Reactor Administrator, Senior Reactor Operator . . . . . . . . . . . . . . . . . J. F. Higginbotham Reacto Supervisor, Senior Reactor Operator . . . . . . . . . . . . . . . . . . . . . . . . . . A. D. Hall Senior i'eactor Operator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. P. Smith l (from 3/12/98) G. M. Wachs Reactor oprator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. A. Crail (from 3/12/98) N. A. Carstens l Reactor Operator Trainec . . . . . . . . . . . . . (from 9/30/97 through 3/11/98) N. A. Carstens (from 9/30/97 through 3/11/98) G. M. Wachs i l l F. Radiation Protection Staff l Serior Health Physicist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D . S . Pratt [ Health Physicist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . K. M. Brock
- l. Radiation Protection Technologist ......................... . . . . D. R. Carver Health Physics Monitors (Students) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J. Bergman J. Davidson J. Lewis M. Sellers K. Hulse l
People Part11 G. Scientific Support Staff I Analytical Support Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M. R. Conrady Projects Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E. G. Schtitfort Geochemist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S . G ei g er I Neutron Activation Analysis Technicians (Students) . . . . . . . . . . . . . . . . . . . . . . I. Davis A. Ham M. Kelman P. Richards R. Shivers I Scientific Instrument Technician . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. P. Smith Nuclear Instrumentation Support . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. Menn t I IL OSU Radiation Safety Office Staff Radiation Safety Officer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . R. H. Farmer I Radiation Specialists . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. L. Harlan (through 721/97) E. F. Forter (from 9/29/97) S. R. Reese I Office Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . K. L. Miller Lab Technician . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L. C. Meeks Student Technicians . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. Menn l B. Kowash I. Committees
- 1. Reactor Operations Committee Name Affiliation l S. E. Binney, Chair . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Nuclear Engineering j D. L. Amort . . . . . . . . (through 12B1/97) Electrical and Computer Engineering B. Dodd . . . . . . . . . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering il A. D. Hall . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center l J. F. Higginbotham . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering A.C.Klein . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Nuclear Engineering M. E. Magana . . . . . . . . . . . . . . . . . . . . . . . Electrical and Computer Engineering l D. S. Pratt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center W. J. Richards . . . . . . . . . . . . . . . . . . . . . . McClellan Nuclear Radiation Center J. C. Ringle . . . . . . . . . . . . . . . . . . . . . . Nuclear Engineering and Graduate School W. H. Warnes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Mechanical Engineering Q
10 People Part11
- 2. Radiation Safety Committee (OSU)
Name Affiliation T. Wolpert, Chair . . . . . . . . . . . . . . . . . . . . . . . . . . Botany and Plant Pathology J. Higginbotham, Vice Chair . . . . . . . Radiation Center and Nuclear Engineering R. Collier . . . . . . . . . . . . . . . . . . . . . . . . . . . Oceanic and Atmospheric Sciences T. Dreher . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Agricultural Chemistry R. Farmer, Secretary and RSO . . . . . . . . . . . . . . . . . . . . . . Radiation Safety Office B. Francis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Environmental Health and Safety M. McCambridge (ex officio) . . . Vice President for Finance and Administration D. ' Nelson . . . . . . . . . . . . . . . . . . . . . . . . . . . . Oceanic and Atmospheric Sciences C. Rivin . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Botany and Plant Pathology C. S now . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Exercise and Sport Science J. S teiner . . . . . . . . . . . . . . . . . . . . . . . . . . . . USDA-ARS/ Crop and Soil Science l I. Wong . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Biochemistry / Biophysics
- 3. Radiation Center Safety Committee
[ Name 4ffiliation l
- W. D. Loveland, Chair . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Chemistry S. C. Campbell . . . . . . . . . . . . . . . . . . . . . . . (through 5/28/98) Radiation Center M. R. Conrady . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center B. Dodd . . . . . . . . . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering A. D. Hall . . . . . . . . . . . . . . . . . . . . . . . . . . . . (through 5/28/98) Radiation Center J. F. Higginbotham . . . . . . . . . . . . . . . Radiation Center and Nuclear Engineering D. S. Pratt . . . . . . . . . . . . . ............... . . . . . . . . . . . . Radiation Center S. P. Smith . . . . . . . . . . . . . . . . . . . . . . . . . . . (through 5/28/98) Radiation Center D. R. Carver . . . . . . . . . . . . . . . . . . . . . . . . (from 5/19/98) Radiation Center J. T. Groome . . . . . . . . . . . . . . . . . . . . . . . . . (from 5/29/98) Radiation Center K. L. Miller . . . . . . . . . . . . . . . . . . . . . . . . . . . (from 5/29/98) Radiation Safety
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Facilities Part til Part III FACILITIES I A. Research Reactor .g E 1. Description The Oregon S tate University TRIGA Reactor (OSTR) is a water-cooled, swinnung pool type ofresearch reactor which uses uranium / zirconium hydride fuel elements in a circular ' grid array. The reactor core is surrounded by a ring ofgraphite which serves to reflect neutrons back into the core. The core is situated near the bottom of a 22-foot deep water-filled tank, and the tank is surrounded by a concrete bioshield which acts as a radiation shield and structural support. See Figures III.A.1, III.A.2 and III.A.3. The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at a I maximum steady state power of1.1 MW and can also be pulsed up to a peak power of about 2500 MW. The OSTR has a number ofdifferentirradiation facilities including a pneumatic transfer tube, a rotating rack, a thermal column, four beam ports, five sampleholding (dummy) fuel I elements for special in-core irradiations, and a cadmium-lined in-core irradiation tube for experiments requiring a high energy neutron flux. The pneu m atic trans fer facility enables samples to be inserted and removed from the core in a few seconds. Consequently, this facility is normally used for neutron activation analysis involving short lived radionuclides. On the other hand,the rotating rackis used l for much longer irradiation ofsamples (e.g., hours). The rack consists ofa circular array of40 tubular positions, each ofwhich can hold two sample tubes. The rotation ofthe rack ensures that each sample will receive an identical irradiation. The reactor's thermal columa consists of a large stack ofgraphite blocks which slows I down neutrons from the reactor core in order to increase thermal neutron activation of samples. Graphite blocks are removed from the thermal column to enable samples to be positioned inside for irradiation. The beam ports are tubular pendu udons in the reactor's main concrete shield which enable neutron and gamma radiation to stream from the core when a beam port's shield plugs are l removed. Two of the OSTR's beam ports are permanently configured for neutron radiography while the other two may be used for a variety of experiments. I 1
1 1 2 l Pan 111 l Facilities Ifsamples which are to be irradiated require a large neutron fluence, especially from higher i energy neutrons, then such samples may be inserted into a d ummy fuel element. This device will then be placed into one of the core's inner grid positions which would normally be occupied by a fuel element. ' The cadmium-lined in-core irradiation tube enables samples to be irradiated in a high flux region near the center ofthe core. The cadmium lining in the facility elimimtm thermal neutrons and thus permits sample exposure to higher energy neutrons only. The cadmium-lined end of this air-filled aluminum irmdiation tube is inserted into an inner grid position of the reactor core which would normally be occupied by a fuel element.
- 2. Utilization The two main uses of the OSTR are instruction and research. During this reporting period, the reactor was in use an average of40 hours during a typical work week. Since the normal reactor operations week of45 hours included several longer, after-hours mns this year.
- a. Instruction Instructional use ofthe reactor is twofold. First, it is used significantly for classes in nuclear engineenng, radiation health physics, and chemistry at both the graduate and undergraduate levels to demonstrate numerous principles which have been presented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many demonstrations and instructional experiments an be performed using the OSTR which cannot be carried out with a commercial power reactor. Shorter-term demonstration experiments are also performed for many undergraduate students in physics, chemistry, and biology classes, as well as for visitors from other universities and colleges, from high schools, and from public groups.
The second instructional application of the OSTR involves education ofreactor operators, operations managers, and radiation health physicists. The OSTR is in a unique position to provide such education since curricula must include hands-on experience at an operating reactorand la associated laboratories. The many types of educational programs that the Miation Center provides are more fully l described in Part VI(section VI.s 'i) of this report. During this reporting period the OSTR accommodated 29 different OSU academic classes. In addition, portions ofclasses from other Oregon universities El E were also supported by the OSTR. The OSU teaching programs utilized 1488 l l I
l 3 l Facilities l Part til hours of reactor time. Tables III.A.1 and III.A.2, as well as Table III.D.1, provide detailed information on the use of the OSTR for instruction and training.
- b. Research The OSTRis a unique and valuable tool for a wide variety ofresearch applications and serves as an excellent source ofneutrons and/or gamma radiation. The most popular experimental technique requiring reactor use is neutron activation analysis I
(NAA). This is a particularly sensitive method of elemental analysis which is h
- described in more detail in Part VI (section VI.C.1). Part III.B provides a listing of equipment used in NAA at the Radiation Center.
l The OSTR's irradiation facilities provide a wide range ofneutron flux levels and neutron flux qualities, which are sufficient to meet the needs ofmost researchers. I This is true not only for NAA, but also for other experimental purposes such as geochronology using the "Ar/* Ar ratio t,echnique or fission track methods. I During this reporting period, the OSTR accommodated 98 funded research projects which utilized 1,448 hourt. of reactor time, and 16 unfunded research projects which utilized 43 hours of reactor time. Details of the l reactor's use specifically for resemh are given in Table III.A.3. Additional information regarding reactor use forresearch, thesis, and service can be found in Tables VI.C.1 through VI.C.3. In these tables OSTR use is indicated with an I asterisk. I B. Analytical Equipment
- 1. Description The Radiation Center has a great variety ofradiation detection instrumentation. Much of this equipment involves the latest in counting technology as represented by the state-of-the-art gamma ray spectrometers with their associated computers and germanium detectors. Tables III.B.1 through III.B.4 provide a brieflisting of typical laboratory I counting devices present at the Center. Much additional equipment for use in the classroom and an extensive inventory ofportable radiation detection instrumentation are also available.
h I L F
4 I Facilities Part111 I
- 2. Utilization Radiation Center nuclear instnunentation receives intensive use in both teaching and research applications. In addition, service projects also use these systems and the g combined use often results in 24-hour per day schedules for many of the analytical E instruments. Use ofRadiation Center equipment extends beyond that '.xated at the Center and instrumentation is commonly made available on a loan basis to OSU researchers in g
other departments. C. Radioisotope Irradiation Sources I:;
- 1. Description i
l The Radiation Center is equipped with a Gammacell 220 *Co irradiator (Fig. III.C.1), which is capable ofdelivering high doses ofgamma radiation over a range ofdose rates i to a variety of materials. Typically, the irradiator is used by researchers wishing to perform mutation and other biological effects studies; studies in the area ofradiation chemistry; dosimeter testing; l sterilization offood materials, soils, sediments and other media; gamma radiation damage studies; and other such applications. In addition to the "Co irradiator, the Center is also equipped with a variety ofsmaller "Co, "7Cs,226Ra, plutonium-beryllium,and other isotopic sealed sources of various radioactivity levels which are available for use as irradiation sources.
- 2. Utilization During this reporting period there was a diverse group ofprojects using the "Co irradiator.
These projects included the irradiation ofa variety ofbiological materials inchiding different types ofseeds. In addition, the irradiator was used for sterilization ofseveral media and g the evaluation of the radiation effects on different materials. Table III.C.1 provides use E data for the Gammacell 220 irradiator. D. I i Laboratories and Classrooms
- 1. Description I
The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate classes offered by various OSU academic departments or off-campus groups. I
I Facilities s Part til I Instructional facilities available at the Center include a laboratory especially equipped for teaching radiochemistry and a nuclear instrumentation teaching laboratory equipped with modular sets ofcounting equipment which can be configured to accommodate a variety of experiments invclving se measurement ofmany types ofradiation. The Center also has three student computer rooms equipped with a large number ofpersonal computers and workstations. In addition to these dedicated instmetional facilities, many other research laboratories and pieces ofspecialized equipment are regularly used for teaching. In particular, classes are I routinely given access to appropriate state-of-the-art gamma spectrometry equipment located in Centerlaboratories. A numberofclasses also regularly use the reactcr and the reactor bay as an integral part of their instructional coursework. I There are two classrooms in the Radiation Center which are capable ofholding about 35 I and 18 students, respectively. In addition, there are two smaller conference rooms and a library that are suitable for graduate classes and thesis examinations. As a service to the student body, the Radiation Center also provides an office area for the student chapters of the American Nuclear Society and the Health Physics Society. This reporting period saw continued high utilization ofthe Radiation Center's thermal l hydraulics laboratory. This laboratory is being used by a member of the nuclear engineering faculty to accommodate a one-quarter scale model of the Westinghouse Electric Corporation AP600 reactor. The AP600 is a next generation reactor which I features simplicity, passive safety and standardization in its design. The multi-million dollar advanced plant experimental (APEX) facility was fully utilized by the U. S. Nuclear Regulatory Commission to provide licensing data and to test safety systems in "beyond design basis" accidents. The fully scaled, integral model APEX facility uses electrical heating elements to simulate the fuel elements, operates at 450 F and 400 psia and l responds at twice real time. It is the only facility ofits type in the world and is owned by the U. S. Department of Energy, designed by Westinghouse, and operated by OSU. In addition, during this year a new building, the Advanced Thermal Hydraulics Research Laboratory (ATHRL), was constructed next to the Reactor Building. Two-phase flow experiments will be conducted in the ATHRL.
- 2. Utilization I All ofthe laboratories and classrooms are used extensively during the academic year. For example, a listing of 84 courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table III.D. l . Table III.A.1 gives a separate listing o f the 29 classes specifically accommodated by the reactor during the f reporting period.
I
Facilities Pert 111 I E. Instrument Repair and Calibration Facility
- 1. Description I
The Radiation Center has a facility for the repair and calibration ofessentially all types of I radiation monitoring instrumentation. This includes instruments for the detection and i measurement of alpha, beta, gamma, and neutron radiation. It encompasses both high g range instmments for measunng intense radiation fields and low range instruments used to E) measure environmental levels of radioactivity. The Center's instrument calibration 1 capability is described more completely in Section VI.C.7 of this report. l ,
- 2. Utilization 11 The Center'sm ' stmment repair and calibration facility is used regularly throughout each year j and is absolutely essential to the continued operation of the many different programs g carried out at the Center. In addition, the absence ofany comparable facility in the state Ei has led to a greatly expanded instrument calibration program for the Center, including calibration ofessentially all radiation detection instruments usedbystate andfederal agencies in the state ofOregon. This includes instruments used on the OSU campus and i l
all other institutions in the Oregon University System, plus instruments from the Oregon Health Division's Radiation Protection Services, the Oregon Oflice of Energy, the Oregon Public Utilities Commission, the Oregon Health Sciences University, the Army Corps of l3 Engineers, and the U. S. Environmental Protection Agency. Additionalinformation g regarding instrument repair and calibration efforts, is given in Tables VI.C.4, VI.C.5, and B VI.C.6. F. Libraries
- 1. Description .
1 The Radiation Center has libraries containing significant collections of texts, research reports, and videotapes relating to nuclear science, nuclear engineering, and radiation protection. The Radiation Center is also a regular recipient ofa great variety ofpublications from l l l commercial publishers in the nuclear field, from many ofthe professional nuclear societies, from the U. S. Department of Energy, the U. S. Nuclear Regulatory Commission, and lI l other federal agencies. Therefore, Center libraries maintain a current collection ofleading l research and regulatory documentation in the nuclear area. In addition, the Center has a collection over 50 sets ofnuclear power reactor safety analysis and environmental reports specifically prepared by utilities for their facilities. l Il
7 . Facilities Part111 The Center maintains an up-to-date set of reports from such organizations as the Intemational Commission on Radiological Protection, the National Council on Radiation Protection and Measurements, and the Intemational Commission on Radiological Units. Sets of the current U.S. Code ofFederal Regulations for the U.S. Nuclear Regulatory Commission, the U.S. Departmem of Transportation and other appropriate federal agencies, plus regulations ofvarious state regulatory agencies are also available at the Center. The R ndiation Center videotape library has over one hundmd tapes on nuclear engineering, radiationprotection and radiological emergency response topics. In addition, the Radiation Center uses videotapes for most of the technical orientations which are required for personnel working with radiation and radioactive materials. These tapes are produced, recorded, and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center.
- 2. Utilization Radiation Center libraries are used mainly to provide referen. ~ wer al on an as-needed basis. They receive extensive use during the academic year. In addition, the orientation videotapes are used intensively during the beginning of each term and periodically thereafter.
I I I I 1 1 i L_ r~"
8 Facilitias Part111 I Table III.A.1 OSU Courses Using the OSTR I Course Number ' NE 111 Course Name'- Introduction to Nuclear Engineering l NE 113 Introduction to Nuclear Engineering NE 233 Nuclear Radiation Detection and Instrumentation RHP 233 Nuclear Radiation Detection and Instrumentation l NE 429 Nuclear Reactor Laboratory l NE 457 Nuclear Reactor Laboratory , RHP 480 Field Practices in Radiation Protection NE 484 Applied Radiation Safety RHP 484 Applied Radiation Safety NE 486 Radiation Dosimetry RHP 486 Radiation Dosimetry RHP 488 Radioecology l NE 503 Thesis (Nuclear Engineering) RHP 503 Thesis (Radiation Health Physics) RHP 506 Projects NE 559 Nuclear Reactor Laboratory RHP 580 Advanced Field Practices in Radiation Protection RHP 584 Advanced Applied Radiation Safety RHP 586 Advanced Radiation Dosimetry RHP 588 Advanced Radioecology NE 603 Resis (Nuclear Engineering) General Chemistry for Science Majors CH 222 g CH 462 Experimental Chemistry II E CH 503 Desis (Chemistry) GEO 503 nesis (Geosciences) OC 503 Resis (Oceanography) Adventures in Learning Visiting Students SMILE Visitirig Students Earth Week Celebration Visiting Students I I m_____. _.
I 9 Facilities partfjj Table III.A.2 OSTR Teaching Hours
.. Cumulative Values Description Annual Values for FLIP Core (hours)
(hours) Departmental 473 6,747
- E Nuclear Engineering 425 Chemistry 40 Adventures in Learning 4
4H 2 SMILE _, 1 Earth Week 1 i Geosciences0) 0 Oceanic and Atmospheric Sciencesm 0 Special Classes and Projects (2) 1,015 3,652 TOTAL TEACHING HOURS (3A5) 1,488 10,399 (i) Some use hours by these departments are not shown under " Teaching Hours," but are reflected under Thesis Research, both funded and unfunded. (2) A variety ofeducational classes were conducted which involved on' e-time meetings for orientation or support purposes. These included: high school science classes, new student programs support, community college classes, and classes from other universities. In addition, this category includes 974 hours of reactor operator training. (3) See Table III.D.1 for classes and student enrollment. (4) See Table IV.A.5 for a summary of all reactor use categories. Total teaching hours reflect all time the reactor was in use for teaching, and because of this the total I (5) hours include time the reactor itself may not actually have been in operation.
10 Facilities Part 111 I Table III.A.3 OSTR Research Hours Types of Research Annual Values Camulative Values for FLIP Core l (hours) (hours) OSU Research 217 7,974 Off-Campus Research 1,274 12,404 l 1 l TOTAL RESEARCII IIOURSU) L491 20,378 I l I I I (1) Total research hours statistics: (a) 97% (1,448 hours) ofthe total research hours were user-funded by federal, state, or other organizations. (b) 3% (43 hours) of the total research hours were user-unfunded studies in support of graduate thesis research or other academic investigations. Reactor costs for this research were absorbed (funded) by the OSU Radiation Center. l
I1 Facilities Part111 Table III.B.1 Radiation Center Spectrometry Systems: Gamma, Low Energy Photon, Alpha Rel. Efric. Room System (%) B100 Adcam 8k MCA, Ortec HP Ge 26.8 B100 Adcam 8k MCA, Ortec HP Ge 38.1 B100 Adcam 8k MCA, EG&G HPGe 30.0 B100 Adcam 8k MCA, Ortec HP Ge 28.8 D102 Adcam 8k MCA, Ortec Ge(Li) 27.0 C120 Ace 1,4k Ortec, Nal(TI) 3x3 N/A C123 Adcam 8K MCA, Canberra Ge(Li) 16.6 A138 H.P. Scaler, Nal(Tl) 2x2 N/A C134 Ace,4k Ortec, Ortec Si(Li) N/A C134 Adcam 8k MCA, PGT Ge(Li) 19.3 Cl34 Adcam 8k MCA, PGT LEP N/A I Cl34 Adcam 8k MCA, Ortec LEP N/A C120 Ace 3,4k Ortec,576A Alpha Spectrometer N/A I L [ E o m
12 Fccilities Part 111 Table III.B.2 Radiation Center Liquid Scintillation Counting Systems 1 Room - System 1 I l C120 Beckman, Betamate I C120 Beckman, Betamate ( C118 Beckman, Betamate C118 Beckman, Betamate i B136 Beckman, LS 6500 l l I I
13 Facilities Partlli ( Table III.B.3 { Radiation Center Proportional Counting Systems [ Room > System ?: C120 NMC 1, PCS C120 NMC 2, Pt . ( C120 NMC 3, PCS C120 NMC, PCC-1IT and DS 2 [ A124 NMC ACS 84 A138 Protean MPC 9400 A138 Tennelec LB 5100 Auto Counting System w/ IBM PC ( { ( { { [ [ _.__a
i i 14 .. Facilities Part 111 Table III.B.4 Thermoluminescent Dosimeter Systems l Room System: ; C120 Harshaw Model 2000 A132 Harshaw Medel 2000 I' D I
L 1 1 15 ( Facilities Part M I Table III.C.1 Gammacell 220 6 Co Irradiator Use (2809 Ci: 7/1/97) Purpose of Dose Range. - Number of _ Use Time Irradiation: Samples -(rads) Irradiations (hours) Blood serum, 2.50 x 106 Sterilization wood, soil, to 34 584 plastic tubes 4.0 x 106 { 1.0 x 10 6 Material Memory chips, to 9 [ Evaluation gemstones 2.0 x 10 7 371 Com, bean 4.0 x 10' Botanical Studies seeds, nectarines, to 27 22 other food items 2.5 x 106 I Calfserum, 2.0 x 10 3 spleen cells, Biological Studie: to 45 79 blood, peptid 2.5 x 10 6 DNA bases l TOTALS 115 1,056 [ [ [ [ [ { L
I6 Facilities Part W Table III.D.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number of Students Course Credit . Course Title Fall Winter Spring Summer 1997 1998 1998 1998 Nuclear Engineering Department Courses NE 1Il' 3 Introduction to Nuclear Engineering 35 - - - NE 112 3 Introduction to Nuclear Engineering - 30 - - NE 113' 3 Introduction to Nuclear Engineering - - 26 - NE 231 3 Nuclear and Radiation Physics 14 - - - RHP 231 3 Nuclear and Radiation Physics 9 - - NE 232 3 Nuclear and Radiation Physics - 14 - RHP 232 3 Nuclear and Radiation Physics 4 - - NE 233* 0 Nuclear Radiation Detection and instrumentation - - 11 - - RHP 233* 0 Nuclear Radiation Detection and Instrumentation - - 7 - NE 319 3 Societal Aspects of Nuclear Technology 47 - - - NE 361 3 Nuclear Reactor Systems - 6 - - NE 381 3 Principles of Radiation Safety 5 - - - RHP 381 3 Principles of Radiation Safety 11 - - - RHP 401 1 16 Research - 1 1 - RHP 405 1 16 Reading & Conference 1 - - NE 406 1 16 Projects 1 - - - g NE 407 1 Nuclear Engineering Seminar 13 11 10 - E RHP 410 1 12 Internship 1 - 1 - NE 429" 3 ST: Nuclear Reactor Laboratory 6 5 5 - NE 444 3 Nuclear Fuel Cycle - 12 - - RHP 444 3 Nuclear Fuel Cycle - 10 - -- RHP 450 3 Principles of Nuclear Medicine - - 6 - NE 454 3 Nuclear Reactor Analysis 6 - - - NE 455 3 Nuclear Reactor Analysis - 5 - - NE 456 3 Nuclear Reactor Analysis 5 NE 467 4 Nuclear Reactor Thermal Hydraulics 7 - - - NE 417 3 Nuclear Power Systems Design - 5 - - NE 472 3 Nuclear Power Systems Design - - 5 -- RHP 480" 13 Field Practices in Radiation Protection 3 3 I NE 484" 3 Applied Radiation Safety 6 - - -
= Special Topics ST
- =
OSTR used occasionally for demonstration and/or experiments.
- = OSTR used heavily.
17 Facilities Part111 Table III.D.1 (continued) Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number ofStudents -
' Course Credit ' Course Title Fall Winter Spring Summer 1997 1998 1998 1998-RHP 484" 3 Applied Radiation Safety 9 - - -
NE 486* 3 Radiation Dosimetry - - 4 - RIIP 486* 3 Radiation Dosimetry - - 7 - I RIIP 487 3 Radiation Biology - - 9 - RilP 488* 3 Radioecology - 1 - - RHP 501 1 16 Research - I NE 503' l 16 Thesis 4 3 1 3 1 - RIIP 503* l 16 Thesis 8 6 6 2 NE 50S l 16 Reading and Conference - I - - RHP 505 1-16 Reading and Conference 2 - 3 I NE 506' l 16 Projects - - 1 - I RHP 506 1-16 Projects 1 - 1 NE 507 1 Seminar 2 1 2 - RHP 510 1-12 Internship - - 1 - NE $35 3 Nuclear Radiation Shielding - - 3 - RHP535 3 Nuclear Radiation Shielding - - 9 - NE 543 3 Radioactive Waste Management - 3 - - RHP $43 3 Radioactive Waste Management - 7 - - NE $44 3 Nuclear Fuel Cycle - 1 - I RHP 544 3 Nuclear Fuel Cycle - 7 - - RH.P550 3 Principles of Nuclear hiedicine - - 5 - NE 554 3 Advanced Nuclear Reactor Analysis 1 - - - NE $55 3 Advanced Nuclear Reactor Analysis - 2 - - NE 556 3 Advanced Nuclear Reactor Analysis - - 2 - I NE 559" i ST/ Nuclear Reactor Lab I I I - NE 567 4 Advanced Nuclear Reactor Thermal Hydraulics 3 - - - NE 568 3 Nuclear Reactor Safety - - 5 ~ I NE 571 3 Nuclear Power Systems Design - 2 - NE 572 3 Nuclear Power Systems Design - - 1 2 RHP 580" l-3 Field Practice Radiation Protection 2 - - -
=
ST Special Topics
* =
OSTR used occasioaally for demonstration and/or experiments.
** =
L OSTR used heavily, c
18 Facilities Part111 I Table III.D.1 (continued) Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number of Students - Course : Credit Course Title Fall Winter Spring Summer 1997 1998 1998 1998 RHP 584*
- 3 Applied Radiation Safety 4 - - -
RHP $85 3 Environmental Aspects of Nuclear Systems 13 - - - RHP 586* 3 Advanced Radiation Dosimetry - - 1 - RHP 587 3 Radiation Biology - - 7 - RHP 588* 3 Radioecology - 5 - - RHP 589 i ST: Computer Modeling Lab - 4 - - l RHP 599 1 ST: Principles of Nuclear Medicine - - 1 - RHP 599 2 ST: Principles of Nuclear Medicine - - 1 - l NE 603* l-16 Thesis - - - 2 ( RHP 603 1 16 Resis - 3 3 - NE 607 I Nuclear Engineering Seminar 2 1 1 - ( RHP 607 Nuclear Engineering Seminar l 1 - - 2 - 3 RHP 610 1 12 Internship - 1 - - NE 654 3 Neutron Transport neorv 6 - - - Courses from Other Departments CH 222' 5 General Chemistry (Science Majors) - 456 - - CH 462* 3 Experimental Chemistry 11 Laboratory - 26 - - CH 503 1-16 Thesis (Chemistry) 2 1 1 - CHE 101 3 Chemical Engineering Orientation 40 - - - CE 356 3 Technoloev and Environmental Systems - - 45 .. Courses from Other Institutions CH 223 PCC Chemistry - - - 40 g RH 289 LBCC Alternate Enerev Sources 12 30 - - E GS 105 CCC General Science - - - - GS 105 LBCC General Science - 84 - - CH 223 LBCC l Nuclear Enerev _
- - 44 - M NOTE:
This tsble does not include the thesis courses from other OSU departments (see Table VI.C.2). ST = Special Topics
* =
OSTR used occasionally for demonstration and/or experiments.
** =
OSTR used heavily. I
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1 Reactor Part IV lI I Part IV l REACTOR A. Operating Statistics For the current reporting period, some of the operating statistics for the OSTR showed a slight drop as shown in this section. Operating data by individual category are given in Table IV. A.1 and annual energy production is plotted in Figure IV.A. I . Table IV.A.2 is included mainly for reference and summarizes the operating statistics for the original 20% enriched fuel. The thermal energy generated in the reactor during this reporting period was 38.6 megant days (MWD). The cumulative thermal energy generated by the FLIP core now totals 828.4 MWD from August 1,1976 through June 30,1998. Reactor use time averaged approximately 89.3% of the normal nine-hour, five-day per week schedule. Tables IV.A.3 through IV.A.5 detail the operating statistics applicable to this reporting period. I No fuel elements were removed or added during the reporting period. The reactor core excess reactivity increased slightly (~5 c) over this reporting period. This slight increase is due to the erbium poison in the fuel elements burning at a faster rate than the fuel. B. Experiments Performed
- 1. Approved Experiments During the current reporting period there were seven approved reactor experiments available for use in reactor-related programs. The following list ofreactor experiments l identifies the seven approved experiments. Missing numbers signify reactor experiments which are in the inactive file and are not currently being used. These are listed in the next section.
, A-1 Normal TRIGA Operation (No Sample Irradiation). B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities. l B-11 Irradiation ofMaterials Involving Specific Quantities ofUranium and Thorium in the Standard OSTR Irradiation Facilities. I B-12 . Exploratory Experiments. I
2 Reactor Part IV I B-23 Studies Using TRIGA Thermal Column. B-29 Reactivity Worth of Fuel. B-31 TRIGA Flux Mapping. Of the approved experiments on the active list, three were used during the reporting g period. A tabulation ofinformation relating to reactor experiment use is given in Table 5 IV.B.1, and includes a listing of the experiments which were used, how often each was used, and the general purpose of the use. l
- 2. Inactive Experiments Presently 30 experiments are in the inactive file. This consists ofexperiments which have been performed in the past and may be reactivated. Many of these experiments are now I
performed under the more genemi expenments listed in the presious section. The following 5 l list identifies these 30 inactive experiments. l A-2 Measurement of Reactor Power Level via Mn Activation. j A-3 Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack. A-4 Neutron Flux Measurements in TRIGA. A-5 Copper Wire Irradiation. A-6 In-core Irradiation of LiF Crystals. A-7 Investigation ofTRIGA's Reactor Bath Water Temperature Coefficient and High Power Level Power Fluctuation. l B-1 Activation Analysis of Stone Meteorites, Other Meteorites, and Terrestria I Rocks. m B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column. B-4 Flux Mapping. B-5 In-core Irradiation of Foils for Neutron Spectral Measurements. B-6 Measurements of Neutron Spectra in Extemal Irradiation Facilities. B-7 Measurements of Gamma Doses in External Irradiation Facilities. B-8 Isotope Production. B-9 Neutron Radiography. B-10 Neutron Diffraction. B-13 This experiment number was changed to A-7. B-14 Detection of Chemically Bound Neutrons. l l I
3 Reactor PartIV B-15 This experiment number was changed to C-1. B-16 Production and Preparation of"F. B-17 Fission Fragment Gamma Ray Angular Correlations. B-18 A Study of Delayed Status (n, y) Produced Nuclei. B-19 Instrument Timing via Light Triggering. I B-20 Sinusoidal Pile Oscillator. B-21 Beam Port #3 Neutron Radiography Facility. B-22 Water Flow Measurements Through TRIGA Core. B-24 General Neutron Radiography. B-25 Neutron Flux Monitors. B-26 Fast Neutron Spectrum Generator. B-27 Neutron Flux Determination Adjacent to the OSTR Core. B-28 Gamma Scan of Sodium (TED) Capsule. B-30 NAA of Jet, Diesel, and Furnace Fuels. C-1 PuO2 Transient Experiment. I C. Unplanned Shutdowns Therewerefifteenunplannedreactorscramsduringthecunentreportingperiod. Ascramoccurs when the control rods drop in as a result of an automatic trip or as a result ofthe operator pushing I the manual trip button. Table IV.C.1 contains a summary ofthe unplanned scrams, including a brief description of the cause ofeach. D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59 The information contained in this section of the report provides a summary of the changes I performed during the reporting period under the provisions of 10 CFR 50.59. For each item listed, there is a briefdescription ofthe action taken and a sununary ofthe applicable safety evaluation. m Although it may not be specifically stated in each of the following safety evaluations, all actions taken under 10 CFR 50.59 were implemented only after it was established by the { OSTR Reactor Operations Committee (ROC) that the proposed activity did not require a change in the facility's Technical Specifications and did not introduce or create an - unreviewed safety question as defined in 10 CFR 50.59(a)(2). U ___J
Reactor Partly I
- 1. 10 CFR 50.59 Changes to the Reactor Facility There were five changes to the reactor facility during the reporting period.
- a. Installation ofa Separate Cleanup Systemfor the Bulk Shielding Tank (1) Description The cleanup system for the water in the bulk shielding tank (BST) was I
replaced to allow for complete separation between the water in the B ST and that in the pnmary reactor tank. This separation prosided the capability for the operations staff to place a chemical tracer in the water of the BST tank in order to confinn whether that tank was the source of the water leakage from the thermal column and beam port No. 2. The cleanup system also serves the function ofensuring excellent water quality to prevent corrosion ofthe stainless steel liner installed in January and February of 1997. The new system is housed in the D106 Mecht.nical Room and has siphon breaks 1 inch below the low water level. This vill prevent accidental drainmg of the BST. l It was proposed that the operations staffte move the existing cleanup lines and valves (DVl9 and DV2) which are identified in Fig.1.60 of the OSTR training manual. The ends ofthe piping were capped offat the 12 foot level. The BST cleanup system was installed f.fter being satisfactorily tested by the Reactor Supervisor. (2) Safety Evaluation The proposed facility change did not increase the probability ofaccidentally draining water from the Bulk Shielding Tank or from the reactor tank nor did it cause any corrosion problems with the primary system, since it was constructed with PVC pipe. ;
- b. Replacement ofthe Rack and Drive Gear on the Regulating Rod 1
(1) Description Inspection ofthe regulatory rod drive system on September 10,1997 revealed that the rack had experienced significant wear and was in need of replacement. Unfortunately, the manufacturer ofthe rod drive system was
5 \ Reactor PartIV unable to provide replacement parts for the rack, drive gear, draw tube ) bearing, or drive bearing. These parts were available at the Radiation Center in the form of the new stepper rod drive which had been aw aiting installation pending final work on the development ofinterfacing and installation procedures. These parts were exactly the same as those in the existing l regulatory rod with the single exception that the stepper motor rack was made of brass instead of steel. Telephone conversations with General Atomic confirmed that the stepper motor purchased by OSU was the same model which had been placed in service at other facilities as direct replacement for theolderroddrivedesigns. Sincethemanufacturerhadsuccessfullymoved to using brass as the rack material in rod drives, the OSTR stafIwas confident l that the brass rack would perform its intended function and that it satisfied the ! need for an equivalent replacement part. Therefore it was proposed that the parts be replaced with those from the new stepper motor. The control rod drive maintenance shall be performed in j accordance with OSTROP 12," Control Rod Maintenance, Removal and E Replacement Procedures." j (2) Safety Evaluation The control rod drive mechanism was designed to maintain positive control over the insertion or removal ofreactivity from the core. The parts described did not diminish the ability ofthe drive system to serve this function. There I was no identified failure mode which could lead to an inadvertent reactivity insertion, and hence there was no new unreviewed safety concem as a result of the use of the brass rack instead of the steel rack. An increased rate of wear will occur with the brass versus the steel; however, the maintenance and inspection prognun already in place will be sufficient to identify when the wear reaches the point that the rack would need replacement again.
- c. AP600 Addition to the Radiation Center (1) Description Dr. Jose Reyes's AP600 project entered a new phase which required that t
additional laboratory space (Advanced Thermal Hydraulic Research Laboratory) be constructed adjacent to the Radiation Center's Reactor Building. There were two issues which arose from the perspective of the reactor facility. i i
l 6 Reactor PartIV I
- 1) The installation of the electrical power for the new addition was accomplished by a tie-in to the existing subdistribution panel "A"in the D-106 Mechanical Room.
- 2) Does a seismic concem exist because ofthe location of the new building adjacent to the reactor building?
Electrical Power Tie-in he installation of the electrical power for the new addition was accomplished by a tie-in to the existing sub-distribution panel"A" in the D-106 Mechanical Room. He Project Manual required that conduit routing be verified with "the l owner" prior to installation. It also required that all conduit inside the reactor bay be rigid or intermediate metallic conduit and that all reactor bay penetrations be sealed. The sealing was required to be one of the following methods: (1) provide mechanical fire-stop fittings with UL-listed fire rating equal to wall or (2) seal opening around conduit with UL-listed foamed siliconeelastomercompound. Andfinally,expansionjointswererequiredto be installed where conduit crossed building expansion or seismic joints. l Seismic Concem The architect, gLAs Architectural Group, stated that the new addition was actually a free-standmg structure, decoupled from the existmg reactor building, and would in no way interact with the seismic integrity of the reactor facility. g, The new addition is being built to current seismic standards. m (2) Safety Evaluation The conduit runs were sufficiently sealed and routed so that the integrity of the reactor bay was maintained. Thus the current ability of the facility to contain a potential release ofradioactive material was unaffected, and there was no I increased safety concern. EI El The seismic concem was adequately addn'ssed by the new building complying with current building code. There was no safety concem with regards to the seismic interaction between the two buildings.
- d. Modification to the Scram Circuit System (1) Description On February 17,1998 at 0855, the reactor failed to scram when the manual l
l
7 Reactor PartIV scram button was depressed. The reactor had been operating for 14 minutes at a power level of 15 W. Reactor shutdown was achieved within two seconds by the operator checking the key switch and finding that it clicked from the reset into the operate position. He then retried the manual scram button, and it operated properly. Subsequent investigation discovered that the TB2-3 to TBl-9 jumper was not present. At sometime in the past, a connection had been made between TB 1-9 and TB 10-10 which was further connected to the B deck of the console key switch. This in turn was connected to the AC (neutral) at TB10-4. The consequence was that an attemate path wns created to supply power to the control rod magnets. When the key switch was in the reset position, the scram bus was disabled, so
' instead ofthe magnet power being disrupted, the alternate pow er source kept the magnets energized, resulting in the failure to scram.
It was proposed that the facility be modified:
- 1) to remove the connection between TB1-9 and TB10-10 and
- 2) to reinstall thejumper between TB2-3 and TB1-9.
I In addition, the Scientific Instrument Technician electronically checked the rest of the scram loop circuitry to provide assurance that the as-built condition matched the circuitry shown in the facility documentation. The semi-annual S&M 15.11, Console Checklist, was conducted prior to restart ofthe facility. It was furtherproposed that a modification be made to the startup procedure, OSTROP 2, to add a scram test which would confirm that the control rod l magnetic power was de-energized when the console key switch was in the reset position. (2) Safety Evaluation The proposed facility change returned the operate permissive circuitry to its original, as designed configuration and hence removed the possibility that the scram bus could be rendered inoperative by positioning the console key switch L in the reset position. The procedural change provided operational verification before each startup that indeed the magnetic power was de-energized when { the. console key switch was in the rest position. n u
8 Reactor PartIV I Additional testing ofthe remainder ofthe scrrr. cimuitry was completed and the results confumed that there were no further desiations from the as designed circuit. These proposed changes permitted compliance with the requirement in the Technical Specifications that scrams identified in Table I ofsection 3.5.3 be operable when the reactor is unsecured. These changes corrected an identified malfunction ofequipment which was evaluated in the safety analysis
~
mport. They did not introduce a possibility for a different type ofmalfunction, and clearly the overall margin of safety was increased by ensuring that the l scrams are operable during all phases of operation.
- e. Installation ofa Temperature Monitor on the Primary Water Return Line (1) Description As the staffof the reactor facility continued to investigate the source of the water leak fmm the thermal column and beam port No. 2, it became apparent that when the temperature of the reactor tank primary water dropped below 23 C, there was an increase in waterleakage from both facilities. In order to minimize leakage from these facilities, the reactor primary cooling system had been operated with the administrative goal of maintaining the primary temperature above 23 C. In order to aid the operator in monitoring the status of the primary water temperature, it was proposed that a facility modification be performed to install a thermocouple on the outside ofthe primary piping downstream of PV6. This thermocouple was connected to a control unit located in the control room. The unit provided the operator with both an g
audible and visual alarm when the primary water temperature drops below a E set point value. t Installation of the type K thermocouple used a non-invasive technique of strapping the thermocouple to the outside surface of the return leg of the primary cooling system. The location was on the 24 foot level, under the deck plating and adjacent to the current thermocouple used to monitor reactor inlet temperature. The thermocouple lead was routed to the control room using existing conduits and was connected to the alarm / monitor unit (Love Controls Temperature Control Unit) in the right side cabinet. AC power for the new unit comes from an existing 120V power strip in the right hand side cabinet. An audio and visual alann with acknowledge capability was also designed into the circuit. The circuit was installed in the right hand side cabinet adj acent to l l
i 9 l Reactor partjy I the temperature control unit. l The advantage o f the new system is that it has alarm eapability to warn the operator when the temperature of the retum water is below the set point. The set point is specified and changed by the Reactor Supervisor based on the g leakage history and the demands of the operating schedule. It was initially set 3 to alarm when the water temperature dropped below 23*C. I This system serves to notify the reactor operator when the primary temperature drops below the set point. The operator's actions are to either secure the primary cooling system to prevent further cooling or to notify the Reactor Supervisor, who has the authority to continue cooling based on other considerations. For example, the Reactor Supervisor will authorize cooling the primary water below the set point during power calibration opemtion. The consequence ofcontinued cooling is the increased possibility ofwater leakage from the thermal column and beam port No. 2. (2) Safety Evaluation There was no unreviewed safety concem from the installation ofthis monitor, The thermocouple was mounted using a technique currently employed on the existing temperature channel. The mounting materials were stainless steel, and hence there was no corrosion concem. The mounting did not require drilling into the existing piping, so there was no concem regarding leakage of air or water through the thermocouple mount. l 2. 10 CFR 50.59 Changes to Reactor Procedures There was one change to reactor procedures which were reviewed, approved and performed under the provisions of 10 CFR 50.59 during the reporting period,
- a. Revisions to the Radiation Center and OSTR Emergency Response Plan (1) Description As a result of the annual review of the Radiation Center and OSTR Emergency Response Plan, a number ofchanges to the plan were needed.
The majority ofthe corrections were typograpideal and grammatical errors or were updates which reflected staffchanges. The emergency plan was also I I
10 Reactor Part lY I updated to conform to the revised Appendix I of NUREG-0849. The detailed description of the evaluation and implementation of this revision to l1 Appendix I is given in Record #97-4 of Emergency Response Plan activities. One other change was to correct the plan to reflect the change from semi-l annual calibration ofportable instmments to an annual schedule. The details i of these changes are given below. , 1 ? l l Cover Pace , Changed the last revision date to " November 1997." ' All Chanced Paces Added or changed the revision date to "11/97." l Pace i. ii. iii. Table of Contents Retyped the table into the current word processing program. On pages ii and l iii, changed the current page number from 7-5 through 7-17 to 7-6 through 7-18. Pace 3-1. Orecon Office of Enercy (OOE) i Corrected the reference to OOE rules from "30-005 and 30-010" to "345-030-0005 and 345-030-0010". Pace 4-4. footnote (1) Changed the last sentence from "This value is 8.13 x 10-4 (0.0008) of the 15 mrem action level ..." to "This value is 1.63 x 10-4 (0.00016) ofthe 75 mrem l action level ...". 1 Pace 5-4. footnote (1) l l Changed the last sentence from: 4 This value is 8.13 x 10 (0.0008) ofthe 15 mrem action level specified, ........ To: 1
( l1 { Reactor PartIV { 4 This value is 1.63x10 (0.00016) ofthe 75 mrem action level specified ........ Pane 7-5. 7.1.4. Protective Actions for Personnel and Onerational Events [ Moved from page 7.5 to 7.6 Page 7-11. Part 7.2.4 Protective Actions for Notification ofUnusual Events f Changed from: h) A battery-operated public address device (bullhom)is available in the emergency equipment locker in the ESC to communicate protective [ actions and other information to personnel at the assembly area. ( h) A battery-operated public address device (bullhom)is available in the emergency equipment locker in B134 to communicate protective actions and other information to personnel at the assembly area. Pane 8-2. Part 8.2.1 Portable and Fixed Radiological Monitors [ (1) Changedparta)numberiv)Neutronsurveymeters(BF3detectors and rem meters). [ To: number iv) Neutron survey meters. [ (2) Changed v) Alpha survey meters (gas flow and scintillation). To: v) Alpha survey meters. (3) Deleted - vi) Tritium survey meter (gas flow). [ (4) Changed - vii) to vi) ( Pane 8-8. Part 8.3.5 Medical Treatment Changed: iv) The radiological emergency footlocker at the hospital, which contains [ all the equipment necessary for monitoring and decontamination, will . r
12 Reactor PartIV have been set up near the restricted treatment area. The typical , contents of this box are detailed in Appendix B. l l l To: iv) The radiological emergency cabinet at the hospital, which contains all the equipment necessary for monitoring and decontamination, will have been set up near the restricted treatment area. The typical contents of this cabinet are detailed in Appendix B. Pace 10-3. Part 10.4.1 Reauired Maintenance and Minimum Calibration Freauency Changed: b) All portable survey instruments are repaired as necessary and calibrated at least semiannually. To: b) All portable survey instruments are repaired as necessary and l calibrated at least annually. Apnendix B. nace B-1. nart B.2 Semi-Annual Emercency and Safety Equipment Insnection checklist Changed: a) Good Samaritan Hospital Emergency Department footlocker. I To: a) Good Samaritan Hospital Emergency Department cabinet. Annendix B. nace B-2 Added: Under A 2 - Exchange Batteries and check for proper operation. Under A 4 - 100 moist towelettes. Replace if dried out. l Apnendix B. Pace B-3. Item B. B134 Small Emercency Ea cinment Cabinet
#15 1
l
13 Reactor PartIV Changed: Four rolls of masking tape (replace annually) To: Four rolls of masking tape. Replace if discolored, dry, or brittle. Annendix B. Pace B-4 Item A: Changed - Good Samaritan Hospital (Foot Locker). TO: Good Samaritan Hospital (Cabinet). l Item A-9: Changed 4 rolls of 1 1/2" masking tape. Note that the tape is usable, i.e., not dried out or shriveled up. TO: 3-4 rolls ofi l/2" masking tape. Replace ifdiscolored, dry, or brittle. Annendix B. nace B-5 Item B # 6: Changed - 2 rolls masking tape. TO: 2 rolls masking tape. Replace if discolored, dry, or brittle. Item B, Box 2 #9: Changed - Masking tape TO: Masking tape. Replace if discolored, dry, or brittle. Item B, Box 3 #f: Chantved - Masking tape TO: Masking tape. Replace if discolored, dry, or brittle. Appendix. nace B-6 Box #5, Item 3a: Changed - Replace the battery in the air sampler. TO: Note date on battery, replace the battery in the air sampler biannually Box #5, Item 5: Deleted item a. Check and replace batteries. Changed item b to a. Annendix B. nace B-7 Box #5, Item 10: Changed - 2 flashlights. TO: 2 flashlights. Replace batteries and check for proper operation.
14 Reactor l'artIV I Item C, #2: Changed - 2 flashlights. TO: 2 flashlights. Replace batteries and check for proper operation. Annendix B. nace B-10. item _A Changed item 1 title from "A100 Cabinet" to "B134 Large Cabinet" Changed item b. from "...large decon kit..." to ' ...large decon kit #1. ." Added item "c. Check large decon kit #2 (see item C. on next page)." Deleted entire item 2, "B126B Cabinet," including items a and b. Renumbered remaining items 3 and 4 to be items 2 and 3 Accendix B. case B-10. item B Number 1 : Changed - Verify the quantity and quality ofthe following small kit items: (ReSil or mplace as necessary to meet the mmimum quantity indicated for each item). TO: Verify the quantity and quality ofthe following small kit items: (Refill or replace as necessary to meet the minimum quantity indicated for each item or g ifitems are unusable). g Deleted the column for "Cl22" from the table. Anoendix B. nace B-11 Item C, # 1 : Changed - Verify the quantity and quality of the following large decon items: (Refill or replace as necessary to meet the minimum quantity l indicated for each item). l TO: Verify the quantity and quality ofthe following small kit items: (Refill or E replace as necessary to meet the muumum quantity indicated for each item or 5 ifitems are unusable). Changed table for Large Decon Kit item rooms from A 100 to B 134# 1, and B126B to B134#2. Attachment B: Revisions to the OSU Radiation Center and g TRIGA Reactor Emergency Response Plan E Implementing Procedures (ERIPs) I I
15 Reactor PartIV [ Pace E-2-1 footnote (1) { 4 Changed the last sentence from"This i ahie is 8.13 x 10 (0.0008) ofthe 15 mrem action level specified, .... to "This value is 1.63 x 104 (0.00016) ofthe [ 75 mrem action level specified, .... Pace E-5-6 Anoendix B { Made consistent with initials D. R. Carver, added J. T. Groome under APEX [ Facility Operator and M. Yundt under APEX I & C Technician. [ Pace E-5-16. Checklist for the Initial Emereency Resnonse Action of the Radiation Protection Technolocist Changed S. P. Smith to D. R. Carver.
~
Pace E-5-17. Checklist for the Initial Emercency Response Action of the Radiation Center Recentionist [ Changed C. L. Hall to D. C. West. NEW Pace E-5-18 Inserted new Page E-5-18 with the following text. Renumbered previous page E-5-18 to become E-5-19. { CHECKLIST FOR THE INITIAL EMERGENCY RESPONSE ACTION OF THE BUILDING CHECKERS
.NAME CORRIDOR E. G. Torne A K. M. Brock B M. R. Conrady C
[ A.D. Hall D S. E. Binney E F L
16 Reactor Partly ERIP 7. nace E-7-4 Inserted new version of Radiation Center Directory. l Pace E-7-6 For Radiological Assessment Team, deleted "E. F. Forrer" and "S. R. Smith," and added "D. R. Carver" in alphabetical order by last name. For Historian,1st Choice, changed "C. L. Hall" to "D. C. West". For Historian, 2nd Choice, changed "J. R. Smith" to "L. M. James". (2) Safety Evaluation l The only change in the plan which changed from the original intent was the definition ofaction level for the duration ofa fire which would require the l declaration ofan Unusual Event. In the previous plan it wm defined as 10 minutes and in Appendix I as 15 minutes. Since there wm no documented or institutional memory for the basis ofselecting the 10 minute period, the ROC Emergency Plan Review Subcommittee felt it wm not a decrease in the effectiveness of the plan if the NRC definition of15 minutes wm used instead. The annual calibration criterion for the portable survey i instruments is actually the industry standard of practice and does not increase the chance that a given instrument would be incapable of l performing its intended function. All of the other changes corrected g typographical and grammatical errors or updated personnel lists. Since E these changes made the plan easier to read, the plan's effectiveness actually improved.
- 3. 10 CFR 50.59 Changes to Reactor Experiments There were no changes to reactor experiments during this reporting period.
I I I I
17 Reactor PartIV E. Surveillance and Maintenance [ 1. Non-Routine Maintenance September 3,1997 Completed the installation ofa new deionized water make up and ( clean up system for the bulk shielding tank. September 15,1997 Refurbished the regulating rod drive assembly. Replaced the rack [ and pinion gears, the pinion shan and bearing, and the draw tube sleeve bearings. [ September 17,1997 Replaced the reactor building water heater. -[ December 4,1997 Inspected and performed maintenance on the chemical injection pump in the reactor secondary cooling system. December 5,1997 Replaced the bearings on the regulating rod motor. December 15,1997 Changed out the dual element mechanical shaft seal on the reactor { demineralizer pump and replaced the pump's motor bearings. [ December 16,1997 Received new Flip IFE and FFCR. December 22,1997 Replaced the stack nr'.iitor pump. Rebuilt old pump for spare. January 5,1998 Replaced capacitors in the stack gas recorder amplifier to correct a 60 cycle oscillation on the pen. { January 27,1998 Replaced all transistors on the test signal card (XA-6) for the log [ and linear channels. January 29,1998 Cleaned and inspected the Corkin compressed air pressure regulator that supplies the transient control rod. January 29,1998 Replaced the % demand potentiometer on the console. February 9,1998 Replaced the local meter on area radiation monitor #8. February 18,1998 Performed scram failure investigation of console wiring, f L r
18 Reactor PartIV I February 20,1998 Performed scram circuit modification that assures control rod g magnet power is de-energized when console key switch is in the a reset position. February 23,1998 Completed electronic tests verifying the console power pathway, the magnet power circuit, and all scram circuit wiring. April 28,1998 Completed point-to-point checks ofall reactor console interwiring verifying that as-built conditions match the circuitry shown in g facility documentation. E April 29,1998 Replaced all the transistors in the servo module's pre-amplifier and power amplifier. April 29,1998 Replaced the K-14 relay that switches regulating rod motor power to servo control for auto / square wave modes. May 5,1998 Installed a reactor primary inlet temperature alarm system. May 5,1998 Replaced the chopper in the reactor control servo system. May 12,1998 Installed 2" rigid conduit in reactor bay for electrical tie-in to the new Advanced Thermal Hydraulics Research Laboratory constructed adjacent to the reactor building.
- 2. Routine Surveillance and Maintenance The OSTR has an extensive routine surveillance and maintenance (S&M) program.
Examples of typical S&M checklists are presented in Figures IV.E.1 through IV.E.4. 1 ms marked with an asterisk (*) are required by the OSTR Technical Specifications. I F. Reportable Occurrences There were two reportable occurrences during the reporting period. The first involved a failure I to submit a Material Balance Report, required by 10 CFR 74.12 (a)(1), within 30 days following the end ofthe reporting period. The occurrence was self-identified and was addressed E 5 in detail in a report to the NRC dated September 5,1997. The second event involved a fhilure ofthe OSTR to shut down when the console manual scram button was pushed. The event was promptly reported, thoroughly investigated, the root causes were identified and effectively corrected in a timely manner. This occurrence was self-identified and was addressed in detail in a report to the NRC dated March 2,1998. I
1 _r1 r o r mums e mums imms u-Table IV.A.1 ie a a 4 OSTR Operating Statistics (Using the FLIP Fuel Core) Ratisaky Wfg QQ;f_c Ql::. ;L l ;. % nyQ) a.M QQ:) jf. _ , ( ;,., , __;f';p_; 'Qg;Q;lff ikNgusg&Q l976, fyNdly171977#' 19781 ifj$ly ,*;J M RIiI/]f/1980 ijD 6 M A T gg [ j% g [fThrough; 3 PJuls;1[ddiid
'IEThro $$Th[ rough}gI $[ThrdSiiiij}%
l
!Julfli19811 ;Juif1,1982a [JilyX1983?
$Thir6ug'h7 (ThroEg6 '$ThNujE@
IBFCIP, M 'JuIE5d?.19 .
- -l$I,) 88}AugNh TJhne 19783 fdni$$,3pi9 1 VJdsf38',t198dl fjelif36'A1988- Juni 30,1'982 JNnE35,51'983 JuSE30,h f8
, i Operating Hours (critical) 875 819 458 875 1255 1192 1095 1205 Megawatt Hours 451 496 255 571 1005 999 931 943 Megawatt Days 19.0 20.6 10.6 23.8 41.9 41.6 38.8 39.3 Grams2"U Used 24.0 25.9 13.4 29.8 52.5 52.4 48.6 49.3 Hours at Full Power 401 481 218 552 998 973 890 929 (1 MW)
Numbers of Fuel Elements Added or Removed (-) 85 0 2 0 0 1 0 0 Number of Irradiation 44 375 329 372 348 408 396 469 Requests Seefootnotesfollowing the table. }q L.
.._____o
E Table IV.A.1 (continued) { a, OSTR Operating Statistics (Using the FLIP Fuel Core) H3 f Q $j@i %@ "$fAQ J7s'@/1lpys) @[6$$lpglj %.]Qj@ yyggi h[j/6@@hp%ijl fsD fi qdh1 YJa Ietti;f,o;jl9841 1985' 1986 EJulyy1987? MQ'alyJ1988sJSQ R'J Q]g@ f;.1(1989 V OJuly I 19905 !dJ61ypi99, pffd) Not M } ugE} '
$(Jh l fMNhFoEilNI!DEhhiigiE$i g li
$hkh IIIrN$iE.Ejf
%FLTPIliNS J M $6/19$3 Ud6N.6}158N JdEW50/1987) fJ$$if3671Nfii h$i3d,'1Ni91 U A'QigDE IEThho6sgIff$ Milirofh,1 302155d EtiEEI6,k19915 Tsii[$0 992 Operating Hours (critical) 1205 1208 1172 1352 1170 1136 iO94 1158 Megawatt Hours 946 1042 993 1001- 1025 1013 928 1002 Megawatt Days 39.4 43.4 41.4 41.7 42.7 42.2 38.6 41.8 2
Grams "U Used 49.5 54.4 51.9 52.3 53.6 53.0 48.5 52.4 Hours at Full Power 904 1024 980 987 1021 1009 909 992 (1 MW) Numbers of Fuel Elements Added or Removed (-) 0 0 OW -2W 0 -1,+1W -lW ON Number of Irradiation 407 403 387 373 290 301 286 297 Requests Seefootnotesfollowing the table. i
-Q M M M M WEE M M '
M M M M M
o em- - - -m m m m m m m m m ~ m m M~ Table IV.A.1 (continued) l' E OSTR Operating Statistics (Using the FLIP Fuel Core) [#$7rallEd$$I k I Pp1 rgb (($ $$iy:{17199dE$k i1993:n
$(Qf33 (( @
- k [ Q 7 Q y );% f(~ Q-$$7 f JiIyilpff)5%
g~ i . M hKIhEdighh iIlhThYdingh{j FJdly]fI1997 fJ6iy h 19fM!$k s2
@f$
No m 19h7 ?J65856,W995' b;f$ne'$031 g$ hrosiYfi ly(1j5996Thr36$ ' DThrouYh% f i PJen'e $571 . I uhES$}1s9 J5&E3631599 Operating Hours ' (critical) 1I80 1248 1262 1226 1124 1029 Megawatt Hours 1026 I122 I117 1105 985 927 Megawatt Days 42.7 46.7 46.6 46.0 41.0 38.6 2 Grams "U Used 53.6 58.6 58.4 57.8 51.5 48.5 Hours at Full Power (1 MW) 1000 1109 1110 1101 980 921 Numbers of Fuel Elements Added or Removed (-) 0 0 0 -lW -1, + 1m 0 Number of Irradiation Requests 329 303 324 268 282 249 (1) The reactor was shutdown on July 26,1976 for one month in order to completely refuel the reactor with a new FLIP fuel core. (2) No fuel elements were added, but one fueled foilower control rod was replaced. (3) Two fuel elements were removed due to cladding deformation. (4) One fuel element removed due to cladding deformation and one new fuel element added. (5) One fuel element removed for core excess adjustment. N Q g N - (6) No fuel elements were added, but the instrumented fuel element was replaced. (7) One fuel element removed due to cladding deformation and one used fuel element added. _J
Table IV.A.2 & M R a OSTR Operating Statistics with the Original (20% Enriched) Standard TRIGA Fuel Core Kot#iticiaI7 MT!T 67A 3Ff M M P3fU#9 @4pr MCQ lf-70s WGP3?! @W5?$ Ddiffi% 3;$44 .in;TB 7;G@? M.ffgp l h6. beat '4 EMag8,jMi y 9JulMO fJull;69p : Apr ts71% R[pE1,'72j' AprI;73i iApr lj 74y s s cdhr[$,;755 1Ap 3 Ef M 65 W foM ~ filiN0
) MfhroTdhY2 du508l%g NinNigliY f>Thfough3 $Th'roush? s. Thio' ugh $ThtVugD DTh6iiakhd SThNuglid 6 Th,r,1476:roukhs fifs h0Ti3868) 692 $fE3)
EM(2Pd;d5) tMaF31 Mil lME31;72I 'ftmV31;i7b IMP 31t74I !Na'r'Sid55 iM& Tit 7s! Dui16,i7i 98* 0 763 M4 e4I6WM N@Qlh[i *EWJ5"d 4 @i F3i3fPa dun'2d M fR>#$7 SNT!8'IUS ETsst#8 MM?WE SRf(4) h"hIm 2 Operating 904 610 567 855 598 954 705 563 794 353 6903 llours (critical) Megawatt 117.2 102.5 138.1 223.8 195.1 497.8 335.9 321.5 408.0 213.0 2553.0 llours Megawatt Days 4.9 4.3 5.8 9.3 8.1 20.7 14.1 13.4 17.0 9.0 106.4 8 6.1 5.4 7.2 11.7 10.2 26.0 17.6 16.8 21.4 10.7 133.0 llours at Full Power (250 429 369 58 - - - - - - - 856 kW) H un at FuH - - 20 23 100 401 200 291 460 205 1700 Power (1 MW) Number of Fuel 70 Elements Added 2 13 1 1 1 2 2 2 0 94 to Core initi@ Number of Irradiation 429 433 391 528 347 550 452 396 357 217 4100 Requests
"" I 202 236 299 102 98 249 109 183 43 39 1560 Pulses (1) Reactor went critical on March 8,1967 (70 element core; 250 kW). Note: His period length is 1.33 years as initial criticality occurred in March of 1967.
(2) Reactor shut down August 22,1%9 for one month for upgrading to 1 MW (did not upgrade cooling system). Note: This period length is only 0.75 years as there was a change in the reporting period from July-June to April-March. Reactor shut down June I,1971 for one month for cooling system upgrading. g (3) 4 (4) Reactor shut down July 26,1976 for one month for refueling reactor with a new full FLIP fuel core. Note: This period length is 0.33 years. y M M M M M M M M M M - M M M M
23 Reactor PartIV Table IV.A.3 i Present OSTR Operating Statistics I Operational Data Cumulative Values I F Core Annual Values - for MWH of energy produced 927 19,881 MWD ofenergy produced 38.6 828.4 Grams 235 U used 48.5 1039.6 i Number of fuel elements added to (+) or removed from (-) the core 0 81 + 3 FFCR(O Number of pulses 11 1,290 Hours reactor critical 1,029 24,603 Hours at full power (1 MW) 921 19,489 Number of startup and shutdown l checks 255 5,554 Number ofirradiation requests processed
- 249 7,639 Number of 5amples irradiated 4,707 93,487 I
E [ (1) Fuel Follower Control Rod. These numbers represent the core loading at the end of this reporting period. (2) Each irradiation request could authorize from 1 to 120 samples. The number of samples per irradiation request averaged 18.9 during the current reporting period. E L r-
24 Reac:or Part IV I Table IV.A.4 OSTR Use Time in Terms of Specific Use Categories 1
- Cumulative Values ^
OSTR'Use Category
' Ann al alues - for FLIP Core
) (hours)
Teaching Nepartmental and others)(i) 1,488 10,398 217 7,974 _OSU research(2) Off-campus research(2) 1,274 12,404 Forensic services 0 216(3) Reactor preclude time 1,104 16,752 Facility time (4) 57 6,939 Visitor demonstration (5) 9 312 TOTAL REACTOR USE TIME 4,149W 54,995 l I (1) See Tables III.A.2 and III.D.1 for teaching statistics. l (2) See Table III.A.3 for research statistics. (3) Prior to the 1981-1982 reporting period, forensic services were grouped under another use category and the cumulative hours have been compiled beginning with the 1981-1982 report. (4) The time OSTR spent operating to meet NRC facility license requirements. (5) This is the time that the reactor was used specifically for visitor open-house (demonstration) events. l The remainder of the visitors viewed the reactor dtuing times when the reactor was being operated l for regularly scheduled research and teaching. 1 (6) Total reactor use time includes all multiple use hours added separately. I
25 Reactor PartIV Table IV.A.5 OSTR Multiple Use Time") { Annual Values Cumulative Values -[ Number ofUsem for FLIP Core
' (hours}
(hours) Two 280 3,256 { Three 115 1,080 [ Four 38 402 Five 8 Ill Six 0 45.5 Seven 0 11 { TOTAL MULTIPLE USE TIME 441(2) 4,905.5(3) [ [ [ [ [ [ r L ( (1) Multiple use time is that time when two or more irradiation requests are being concurrently fulfilled by operation of the reactor. [ (2) This represents 43% of the total hours the reactor was critical during this reporting period. t (3) This represents 20% of the total hours the reactor was critical since startup with FLIP fuel in August of 1976. 6.
II ' Figure IV.A.1 OSTR Annual Energy Production Vs. Time (Annual Reporting Period) 50 I ,~ 7 s, .- ~.\ /,
.x,N .
j s. 40
~.- v ~.
t m
$'30 Q =
c 1 3 C A / [ !
$20 9 2
10 . , O I I I i i l i I l t j 77-78 79-20 81-82 83-14 85-86 87-88 89-90 91-92 93-94 95-96 97-98 76-77 78-79 90-81 22-83 24-85 86-87 88-89 90-91 92-93 94-95 96-97 Time (Annual Reporting Period) k 9 t
l 27 Reactor PartIV { Table IV.B.1 Use of OSTR. Reactor Experimentsm [
' Reactor
( ' [ " 2 iResearch -. Teaching n ' Forensic : Tjn c- -TOTAL 7 ( A-1 0 38 0 14 52 B-3 ( 175 21 0 N/A 196 B-23 0 1 0 N/A 1 { TOTAL 175 60 0 14 249 ( { { { I [ { (1) This table displays the number of times reactor experiments were used for a particular purpose. [ (2) The following tabulation gives the number of each reactor experiment used and its corresponding title: ( A-1 Normal TRIGA Operation B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities B-23 Studies Using TRIGA Thermal Column { (3) The time OSTR spent operating to meet NRC facility license requirements, f t I
28 Reactor PartIV Table IV.C.1 Unplanned Reactor Shutdowns and Scrams Number of Type of Event Cause of Event Occurrences Operator withdrew the regulating rod too far while Pen.o d Scram 1 . taking the reactor to power. An apparent oscillation in safety channel response, while Safety Channel , at full power, resulted in the scram set point on the l
^
Power Scram safety channel being reached. (These did not involve actual over power situations.) Operator observed the regulating rod behaving l sluggishly. The reactor was scrammed and the rod drive Manual Scram 1 assembly was inspected. Areas of wear were found on the rack and pinion. Worn parts on the drive assembly were replaced. Commercial power failure. Commercial power was Manual Scram 1 restored in about fiftenn minutes and reactor operation was resumed. Operator observed the linear power level to be tracking improperly in auto mode. Wam motor bearings on the Manual Scram 2 . regulatmg rod were diagnosed to be the problem. l Bearings were replaced. The scram set point on the safety channel (106%) was reached while balancing rods at IMW with a cadmium l Safety Channel experim ntal facility located in-core. The flux 3 Power Scram perturbation caused bu the in-core experiment resulted l in lower readings on the linear and percent power l channels relative tot he reading on the safety channel. l Square wave overshoot. Operator positioned the regulating rod too low in the core for square waving to Safety Channel IMW. The shielding effect on the fission chamber 3 Power Scram caused a slight delay in the power level signal to the servo system to drive in rod. The licensed power level was not exceeded. Transient rod air pressure level was found to be ~ 10 Manual Scram 1 psig higher than normal. Maintenance on the pressure regulator corrected the condition.
29 Reactor PartIV { [ Table IV.C.1 (continued) { Failure of reactor to manually scram on initial operator Manual Scram 1 demand. NRC was inunediately notified. Wiring flaw was subsequently found and corrected. { Operator noticed the linear power trace in auto mode to be several % broader than usual and that little, if any, Manual Scram I servo control of the regulating rod seemed to be going { on. Problem was corrected by replacing the chopper in the servo module. [ Electronic noise caused spike in the period channel Period Scram I while the reactor was starting up in the 0.2 watt power range. [ [ [ [ [ { [ { { [ r
i? Figure IV.E.1 g a Monthly Surveillance and Maintenance (Sample Form) OSTROP 13 SURVEILLANCE & MAINTENANCE FOR THE MONTH OF TARGET DATE NOT TO DATE REMARKS & SURVEILLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUNO DATE BE EXCEEDED =* COMPLETED INITIALS
*1 FUNCTIONAL CHECK OF REACTOR WATER MAXIMUM ur: anch.
LEVEL ALARMS AND GREEN LIGHT ALARM MOVEMENT DN: inehu
- 3 INCHES , L,G, ,,
2 MEASUREMENT OF THE REACTOR PRIMARY MIN: 5 WATER pH MAX: 8.5 3 MEASUREMENT OF THE BULK SHIELD TANK MIN: 5 WATER pH MAX: 8.5 4 EMERGENCY POWER SYSTEM LtGUiO: -1* DN BATTERY CHECKS INVERTER S.G.: > 1.250 FUNCTIONAL CHECK 0 GENERATOR 1 VOLTS m 12.6V OC 5 EVACUATION HORN & P.A. EMERGENCY LIQUID: FULL SYSTEM BATTERY CHECKS S.G.: >1.250 VOLTS m 12.6V DC CORR: NONE 6 INSPECTION OF THE BRUSHES ON THE CHANGE WHEN PNEUMATIC TRANSFER SYSTEM BLOWER 1/4* LEFT MOTOR 7 GREEN UGHT BULB REPLACEMENT 75 WATT 8 CHANGE LAZY SUSAN FILTER F!LTER CHANGED 9 LUBRfCATE THE TRIGA TUBE LOADING TOOL USE GUN O!L NEED OtL? (REElj 10 REACTOR TOP CAM Ott LEVEL CHECK OSTROP 13.10 NEED OtL? [ 11 PROPANE TANK UQU!D LEVEL CHECK >$0% g (% FULL) g
*12 BULK WATER TEMPERATURE ALAP.M CHECK FUNCTIONAL _ q 13 PRIMARY PUMP BEARINGS OfL LEVEL CHECK OSTROP 13.13 NEED OfL?
- Ltcense Requirement. ,
- Date not to be exceeded is only opp!!cabfe to marked (*) Items. It is equal to the date completed last month plus six weeks. Rev. I1/S2 M M M M
l f m M umm m m m m - m-Figure IV.E.2 g a Quarterly Surveillance and Maintenance (Sample Form) ' OSTROP14 SURVEILLANCE & MAINTENANCE FOR THE QUARTER OF / / 19 N5
*I I h kb hf * E REACTOR OPERATION COMMIITEE (ROC) AUDrr OF REACTOR OPERATIONS FOR 1 Y
I QUARTER
*2 QUARTERLY ROC MEETING QUARTERLY
!3 FUEL ELEMENT RADIATION LEVEL MEASUREMENTS IN 223 RAr @
WATER 2* IN WATER
'~
4 D4SPECTION OF THE SOLENCID VAuTS IN THE PNEUMATIC TRANSFER SYSTEM ONE 5 PNEUMATIC TRANSFER SYSTEM INSE RTION TIME CHECK 9 SENS 6 ROTAT240 RACK CIIECK FOR UNKNOWJ *AMPLES PACK SHOULD BE EMPTY 7 FUNCTIONAL CHECK OF EMERGENCY LIGHTS (SEE FUNCTIONAL CHECKSHEED 8 WATER MONITOR ALARM CHECK FUNCTIONAL 9 STACK MONITOR CHECKS (OIL DRh1 MOTORS, ILV. MOTORS 0: LED READES) PART: IISO V VOLTS
*50 OAS: 900 V *50 VOLTS 10 (NOT BE!NO USED)
II ARM SYSTEM ALARM CHECKS OtAN I 2 3 4 5 6 7 8 9 10 18 12 13 14 AUD FUNCTIONAL PANEL ANN
! Physical Securhy Plan Requirement
+ ucense Requirement E W
- 7
" Date not to be exceeded is only appreaNe to marked (*) hems. k is equal to the date completed last quarter plus four monets.
l l
~
w w Figure IV.E.2 (continued) g N a Quarterly Surveillance and Maintenance (Sample Form) OSTROP 14 (CONTINUED) SURVEILLANCE & MAINTENANCE FOR THE GUARTER OF / / 19 I .
; PJC . $
12 OPERATOR LOG p ,) g g , a) TDE b) OPERATING EXERCISE censole (RO) er as Rx. Sup. (SRO)
*) Complete Operadng Exercise 13 CHECK FILTER TAPE SPef,D ON STACK MONITOR 1*!HR
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*18 REACTOR OPERATOR LICENSE CONDITIONS NRC REOUALIFICATION MEDICAL REQUAL EXAM LICENSE vervTee OPERATBe6 TTST DATE DUE DATE ERAMeeATIONS DUE DATg DATE COMPLETED CATE PA$$10 DUE DATE cut OATE OUE NAME cATE Passes OAYE eAssto OATE MAaro AS TARGET DATE NOT TO DATE REMARKS &
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1 Protection Part V I Part V PROTECTION A. Introduction This section of the report deals with the radiation protection program at the OSU Radiation Center. The purpose ofthis program is to ensure the safe use ofradiation and radioactive material in the' Center's teaching, research, and service activities, and in a similar manner to ensure the fulfillment of all regulatory requirements of the state ofOregon, the U.S. Nuclear Regulatory Commission, and other regulatory agencies. The comprehensive nature ofthe program is shown in Table V.A.1, which lists the program's major radiation protection requirements and the performance frequency for each item. The radiation protection program is implemented by a staffconsisting ofa Senior Health Physicist, a Health Physicist, a Radiation Protection Technologist, and several part-time Health Physics I Monitors (seePartII.F). Assistanceisalsoprovidedbythereactoroperationsgroup,theneutron activation analysis group, the Scientific Instrument Technician, and the Radiation Center Director. l The data contained in the following sections have been prepared to comply with the current requirements ofNuclear Regulatory Commission (NRC) Pacility License No. R-106 (Docket No. I 50-243) and the Technical Specifications contained in that license. The material has also been prepared in compliance with Oregon Office ofEnergy Rule No. 345-30-010, which requires an annualreportofenvironmentaleffectsduetoresearchreactoroperations. Asummaryofrequired data for the OSTR is provided in Part I.E for quick reference. l Within the scope ofOregon State University's radiation protection prognun, it is standard operating policy to maintain all releases ofradioactivity to the unrestricted environment and all exposures to radiation and radioactive materials at levels which are consistently "as low as reasonably achievable"(ALARA). B. Environmental Releases The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a summary of the nature and amount ofradioacti ve effluents released or discharged to the emirons beyond the efrective control ofthe licensee, as measured at, or prior to, the point ofsuch release or discharge." The liquid and gaseous effluents released, and the solid waste generated and transferred are discussed briefly below. Data regarding these effluents are also summarized in detail in the designated tables.
2 Protection Part V
- 1. Liquid Effluents Released
- a. Liquid Effluents Released j Oregon State University has implemented a policy to reduce the volume of
! radioactive liquid effluents to an absolute minimum. For example, water used during the ion exchanger resin change is now recycled as reactor makeup water. Waste water from Radiation Centerlaboratories and the OSTR is collected at a holdup tank prior to release to the sanitary sewer. Whenever possible, liquid l effluent is analyzed for radioactivity content at the time it is released to the collection point. However, liquids are always analyzed for radioactisity before the holdup tank is discharged into the unrestricted area (the sanitary sewer system). g l For this reporting period, the Radiation Center and reactor made one liquid E effluent release to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to these releases are contained in Table V.B.I.a.
- b. Liquid Waste Generated and Transferred Liquid waste generated from decontamination ofTPJGA tubes and glasswnre and I
from laboratory experiments is tmnsferred by the campus Radiation Safety Office I to its waste processing facility. Aqueous wastes are absorbed and disposed ofas 3 radioactive solid waste. Liquid scintillation fluid is shipped offcampus in bulk and in vials for disposal. The annual summary of liquid waste generated and transferred is contained in Table V.B.I.b.
- 2. Airbome Effluents Released Airbome effluents are discussed in terms ofthe gaseous component and the particulate component.
- a. Gaseous Effluents Gaseous effluents from the reactor facility are monitored by the reactor stack efiluent monitor. Monitoring is continuous (i.e., prior to, during, and afler reactor operations). It is normal for the reactor facility stack effluent monitor to begin l operation as one of the first systems in the moming and to cease operation as one ofthe last systems at the end ofthe day. All gaseous effluent data for this reporting
) period are summarized in Table V.B.2. I I 1 l I
3 Protection Part V
- b. Particulate Efiluents Particulate effluents from the reactor facility are also monitored by the reactor facility stack effluent monitor.
{ Evaluation ofthe detectable particulate mdioactivityin the stack effluent confumed its origin as naturally-occurring radon daughter products, within a range of 4 approximately 1 x 10 pCi/ml to 3 x 10-" Ci/ml. This particulate mdioactivity f 2 ispredominantly "Pband2"Bi,whichisnotassociatedwithreactoroperations.
'Ihere was no release ofparticulate effluents with a half-life greater than eight days and therefore the reporting ofthe average concentration ofradioactive particulates with half-lives greater than eight days is not applicable.
- 3. Solid Waste Released Data for the radioactive materialin the solid waste generated and transferred during this reporting period are summarized in Table V.B.3 for both the reactor facility and the Radiation Center. Solid radioactive waste is routinely transferred to the OSU Radiation
, Safety Office. Until this waste is disposed ofby the Radiation Safety Office, it is held along with other campus radioactive waste on the University's state ofOregon radioactive materials license. Solid radioactive waste is disposed ofby the University Radiation Safety Office by transfer [ to the University's radioactive waste disposal vendor, Allied Ecology Services, Inc., for burial at its installation located near Richland, Washington. C. Personnel Doses The OSTR annual reporting requirements specify that the licensee shall present a summary ofthe radiation exposure received by facility personnel and visitors. For the purposes ofthis report, the summary includes all Radiation Center personnel who may have received exposure to radiation. These personnel have been categorized into six groups: facility operating personnel, key facility research personnel, facilities senices maintenance personnel, students in laboratory classes, police and security personnel, and visitors. Facility operatmg personnel include the reactor operations and health physics staff. The dosimeters used to monitor these individuals include monthly or quarterly X-ray, beta, and gamma (Xp(G)] film or TLD badges, quarterly track-etch / albedo neutron dosimeters, either monthly or quarterly TLD (finger) extremity dosimeters, and pocket ion chambers.
- o
4 Protection Part V I Key facility research personnel consist ofRadiation Center staff, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or using other research facilities present at the Center. The individual dosimeuy requirements for these personnel will vary with the type ofresearch being conducted, but will generally include a monthly or quarterly X (G) film badge and TLD (finger) extremity dosimeters. If the possibility ofneutron exposure exists, researchers are also monitored with a track-etch / albedo neutron dosimeter. Facilities Services maintenance personnel are normally issued a gamma sensitive electronic dosimeter as their basic monitoring device. A few Facilities Services personnel who routinely perform maintenance on mechanical or refrigeration equipment are issued a quarterly Xp(G) TLD badge and other dosimeters as appropriate for the work being performed. Students attending laboratory classes are issued quarterly X)(G) TLD badges, TLD (finger) extremity dosimeters, and track-etch / albedo or other neution dosimeters, as appropriate. Students or small groups ofstudents who attend a one-time laboratory demonstration and do not handle radioactive materials are usually issued a gamma sensitive electronic dosimeter. These results are not included with the laboratory class students. OSU police and security personnel are issued a quarterly Xp(G) TLD badge to be used during their patrols of the Radiation Center and reactor facility. Visitors, depending on the locations visited, may be issued a gamma sensitive electronic dosimeters. g OSU Radiation Center policy does not normally allow people in the visitor category to become E l actively involved in the use or handling of radioactive maierials. l An annual summary of the radiation doses received by each of the above six groups is shown in l Table V.C. l . There were no personnel radiation exposures in excess of the limits in 10 CFR 20 l or state of Oregon regulations during the reporting period. l D. Facility Survey Data l The OSTR Technical Specifications require an annual summary ofthe radiation levels and levels of contamination observed during routine surveys performed at the facility. The Center's comprehensive area radiation monitoring program encompasses the Radiation Center as well as the OSTR, and therefore monitoring results for both facilities are reported. l I I
i t 5 ( Protection Part V [ 1. Area Radiation Dosimeters Area monitoring dosimeters capable ofintegrating the radiation dose are located at strategic positions throughout the reactor facility and Radiation Center. All of these - dosimeters contain at least a standard personnel-type beta-ganuna film or TLD pack. In { addition, for key locations in the reactor facility and for certain Radiation Center laboratories a CR-39 plastic track-etch neutron detector has also been included in the monitoring package. Figure V.D.1 shows the locations ofthe dosimeters in the reactor [ building and Radiation Center. The total dose equivalent recorded on the various reactor facility dosimeters is listed in [ Table V.D.1 and the total dose equivalent recorded on the Radiation Center area dosimeters is listed in Table V.D.2. Generally, the characters following the hiRC (Monitor Radiation Center) designator show the reom number or location. {
- 2. Routine Radiation and Contamination Surveys The Center's program forroutine radiation and contamination surveys consists ofdaily, weekly and monthly measurements throughout the TRIGA reactor facility and Radiation b- Center. The frequency ofthese surveys is based on the nature ofthe radiation work being carried out at a particularlocation or on other factors which indicate that surveillance over a specific area at a defined frequency is desirable.
{ The primary purpose of the routine radiation and contamination survey program is to [- assure regularly scheduled surveillance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current and characteristic data on the status ofradiological conditions. A second objective of the program is to assure frequent I on-the-spot personal observations (along with recorded data), which will provide advance warning ofneeded corrections and thereby help to ensure the safe use and handling of radiationsourcesandradioactivematenals. Athirdobjective,whichisreallyderivedfrom [ successful execution of the first two objectives, is to gather and document information which will help to ensure that all phases of the operational and radiation protection { programs are meeting the goal ofkeeping radiation doses to personnel and releases of radioactivity to the em'ironment "as low as reasonably achievable" (ALARA). [ The annual summary ofradiation and contamination levels measured during routine facility surveys for the applicable reporting period is given in Table V.D.3. [ [ r L e
Protection Part V I E. Environmental Survey Data The annual reporting requirements of the OSTR Technical Specifications include "an annual I summary of environmental surveys performed outside the facility."
- 1. Gamma Radiation Monitoring
- a. On-site Monitoring Monitors used in the on-site gamma environmental radiation monitoring program at the Radiation Center consist of 6e reactor facility stack effluent monitor described in section V.B.2 and nine environmental monitoring stations. These g stations consist ofa polyethylene bottle placed inside a PVC tube attached to the 3 reactor building perimeter fence at a height of four feet (see Figure V.E.1).
l l Each fence environmental station is equipped with an OSU supplied and processed TLD area monitor (normally three Harshaw ?LiFTLD-700chipsper 7 Li monitor in a plastic "LEGO" mount). These monitors are exchanged and processed quarterly. The total number ofTLD samples for the reporting period l was 108 (9 stations x 3 chips per station per quarter x 4 quarters per year). A summary of this TLD data is shown in Table V.E.1. Each fence environmental station also utilized a CaSO 4 TLD monitoring packet supplied and processed by Radiation Detection Company (R.D. Co.), Sunnyvale, California. Each R.D. Co. packet contained two CaSO4 TLDs and was
- exchanged quarterly for a total of 72 samples during the reporting period (9 stations x 2 TLDs per station per quarter x 4 quarters per year). A summary of Radiation Detection Company's TLD data is also shown in Table V.E.1.
Monthly mea.mrements of the direct gamma dose rate ( rem /h) were also made at each fence monitoring station. These measurements were made with a Bieron E micro-rem per hour survey meter containing a 1" x 1" Nal detector. E A total of 108 prem/h measurements were taken (9 stations per month x 12 months per year). The total calculated dose equivalent was determined by averaging the 12 separate rem /h measurements and multiplying this average by 8760 hours per year. A summary of this data is shown in Table V.E.1. From Table V.E.1 it is concluded that the doses recorded by the dosimeters on the TRIGA facility fence can be attributed to natural background radiation, which is about 110 mrem per year for Oregon (Refs.1,2). I I
I 7 ( Protection Part V (. b. Off-site Monitoring The off-site gamma environmental radiation monitoring program consists oftwenty (- monitoring stations surroundmg the Radiation Center (see Figure V.E.2) and one station located 5 miles to the south near the Corvallis Airport. { Each off-site radiation monitoring station is equipped with an OSU-supplied and processed TLD monitor. Each monitor consists ofthree (MRCTE-1 1 has six) ( ~ 7 Harshaw LiF TLD-700 chips in a plastic "LEGO" mount. The mount is placed in a polyethylene bottle inside a PVC tube which is attached to the station's post p about four feet above the ground (MRCTE 21 and MRCTE 22 are mounted on i the roofof the EPA Lab. and National Forage Seed Lab., respectively). These monitors are exchanged and processed quarterly, and the total numberofTLD { samples during the current one-year reporting period was 264 (20 stations x 3 chips per station per quarter x 4 quarters per year plus 1 station x 6 chips per station per quarter x 4 quarters per year). A summary ofthe OSU off-site TLD [ data is provided in Table V.E.2. The total number of R. D. Co. TLD samples for the reporting period was 104 (13 stations x 2 TLDs per station per quarter x 4 7 quartersperyear). AsummaryofRadiationDetectionCompany'sTLDdatafor i the off-site monitoring stations is also given in Table V.E.2. i [ In a manner similar to that described for the on-site fence stations, monthly measummentsofthedirectgammaexposurerateinmicroremperhour( rem /h) are made at each of the twenty-one off-site radiation monitoring stations. As { noted before, these measurements are made with a Dicron micro-t em per hour survey meter containing a 1" x 1" Nal detector. A total of 252 prem/h measurements were made during the reporting period (21 stations per month x 12 [. months per year). The total dose equivalent for each station was determined by averagmg the 12 separate prem/h measurements and multiplying this average by 8760 hours per year. A summary of these data is given in Table V.E.2. After a review ofthe data in Table V.E.2, it is concluded that, like the dosimeters { on the TRIGA facility fence, all ofthe doses recorded by the off-site dosimeters can be attributed to natural background radiation, which is about 110 mrem per year for Oregon (Refs.1,2).
- 2. Soil, Water, and Vegetation Surveys The soil, water and vegetation monitoring program consists ofthe collection and analysis of a limited number of samples in each category on a quarterly basis. The program
[ monitors highly unlikely radioactive material releases from either the TRIGA reactor facility I
8 Protection Part Y or the OSU Radiation Center, and also helps indicate the general trend ofthe radioactivity concentration in each of the various substances sampled. See Figure V.E.2 for the locations ofthe sampling stations for grass (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 foot radius of the reactor facility and the Radiation Center. In general, samples are collected over a local area having a radius of about ten feet at the positions indicated in Figure V.E.2. There are a total of 22 quarterly sampling locations: four soil locations, four water locations (when water is available), and fourteen vegetation locations. The total number ofsamples possible during the reporting period is 88 (16 soil samples,16 water samples, and 56 vegetation samples). The annual average concentration of total net beta radioactivity (minus tritium) for samples collected at each environmental soil, water, and vegetation sampling location (sampling station) is listed in Table V.E.3. Calculation of the total net beta disintegration rate incorporates subtraction ofonly the counting system background from the gross beta counting rate, followed by application of an appropriate counting system efficiency. j The annual average concentrations were calculated using sample results which exceeded I the lower limit ofdetection (LLD), except that sample results which were less than or equal
- to the LLD were averaged in at the corresponding LLD concentration. Table V.E.4 gives the average LLD concentration and the range ofLLD values for each sample category for the current reporting period.
l As used in this report, the LLD has been defined as the amount or concentration of l radioactive material (in terms of pCi per unit volume or unit mass) in a representative sample, which has a 95% probability of being detected. l l Identification ofspecific radionuclides is not routinely caried out as part ofthis monitoring program, but would be conducted ifunusual radioactivity levels above natural background were detected. However, from Table V.E.3 it can be seen that the levels ofradioactivity detected were consistent with naturally occurring radioactivity and comparable to values l reported in previous years. I i
1 9 ( Protection Part V [ F. Radioactive Material Shipments [ A summary ofthe radioactive material shipments originating from the TRIGA reactor facility, NRC L license R-106, is shown in Table V.F.1. A similar summary for shipments originating from the Radiation Center's state ofOregon radioactive materials license ORE 90005 is shown in Table [ V.F.2. A summary of radioactive material shipments exported under Nuclear Regulatory Commission general license 10 CFR 110.23 is shown in Table V.F.3. [ G. References .
- 1. U. S. Environmental Protection Agency," Estimates ofIonizing Radiation Doses in the United States,1 %0-2000," ORP/CSD 72-1, Office ofRadiation Programs, Rockville, Maryland (1972).
[
- 2. U. S. Environmental Protection Agency, " Radiological Quality ofthe Environment in the
[ United States,1977," EPA 520/1-77-009, Office ofRadiation Programs; Washington, D.C. 20460 (1977). [ { { { {- [ { l L
I g 10 Protection pg,, y ! Table V.A.1 Radiation Protection Program Requirements and Frequencies FREQUENCYJ -l~ RADIATION PROTECTION REQUIREMENT? l l Daily / Weekly / Monthly Perform routine area radiation / contamination monitoring. Weekly Perform gamma spectroscopy of the (OS1R) continuous air monitor particulate filter. Perform routine response checks of radiation monitoring instruments. l Monitor radiation levels (prem/hr) at the environmental monitoring stations. l Collect and analyze TRIGA primary, secondary, and make-up water. Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure Monthly reports. Inspect laboratories. Check emergency safety equipment. Perform neutron generator contamination survey. Calculate previous month's gaseous effluent discharge. Process and record solid waste and liquid effluent discharges. , Prepare and record radioactive material shipments. ( Survey and record incoming radioactive materials receipts. As Required Perfonn and record special radiation surveys. l Perform thyroid and urinalysis bioassays. Conduct orientations and training. l Issue radiation work permits and provide health physics coverage for maintenance operations. I l Prepare, exchange and process environmental TLD packs. Collect and process environmental soil, water and vegetation samples. Conduct orientations for classes using radioactive materials. I Collect and analyze sample from reactor stack effluent line. Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure reports. Leak test and inventory scaled sources. g g Conduct floor survey of corridors and reactor bay. Inventory and inspect Radiation Center equipment located in the Corvallis Fire Department I g Haz/ Mat van and at Good Samaritan Hospital. Calibrate portable radiation monitoring instruments and personnel pocket ion chambers. Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation monitors, water monitor. and air samplers. Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA filters g as necessary, inventory and inspect Radiation Center emergency equipment. Conduct facility radiation survey of the Co irradiators and X-ray machine. Conduct personnel dosimeter training. Perform contamination smear survey of Radiation Center ventilation stacks. Update decommissioning logbook. I
Table V.B.1.a Monthly Summary of Liquid EfUnent Releases to the Sanitary Seweg.23 , (OSTR Contribution Shown in () and Bold Print) R : 2
, :t
.. . . , . . . . . . . . -. p -
. . , , . . ... . . . g s...i.. u ,w .
,-:-- i. o gg , ..,i... , .,, ,..-.4 ..
.y.-e ,
....tt . l .d.
. . ... .o,,
,.i o. ... . ......., ., . ., : , ,4,u
...,.v. e . .,v. .a . ;. ,y...~,,n. . , , , + ,.
~
.:. ;t a . . , , -
- . . . , y . .g '.2,,s....
i
.. . . . ,, - - ic < .c; , :
' ~" ' ~
, . , , , , , , , , ., . ....M . . . . , . ;. .: n . . . . . f .. n . ., ,. .,.,..:.,
m .. j -
,. ..,..c.,., -
.,_.,i ; .
u...., ;1 . . ..
- c. ;w . . ,
- ....., , ,e
~ . . .
[g '.' . ' -et' : (. .a e p ; m.....- tg3g
' t
., ; .fo:l Unit. . ._m. _
December 97 sLLD (95%) of None Not Applicable Not Applicable sLLD (95%)') of Not Applicable 1158 (No OSTR 1.79 x 10 3 4.08 x 10 4 Contribution) Annual Total for sLLD (95%) of sLLD (95%)") None Not Applicable Not Applicable 4 Not Applicable 1158 Radiation Center 1.79 x 10-s 4.08 X 10 OSTR , Contribution to Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Above 1 4 l f (1) OSU has implemented a policy to reduce to the absolute minimum radioactive wastes disposed to the sanitary sewer. There were no liquid effluent releases
- during months not listed.
i (2) The OSU operational policy is to subtract only detector background from the water analysis data and not backgroemd radioactivity in the Corvallis city
- water.
l (3) Based on values listed in 10 CFR 20, Appendix B to 20.1001 - 20.2401 Table 3, which are applicable to sewer disposal. (4) The total volume ofliquid effluent plus diluent does not take into consideration the additional mixing with the over 250,000 gallons per year ofliquids and sewage normally discharged by the Radiation Center complex into the same sanitary sewer system. ? 4 -
~
(5) Less than the lower limit ofdetection at the 95% confidence level.
. - . }
i 7 ~ N Table V.B.I b a t E ! E Annual Summary of Liquid Waste Generated and Transferred Am.a< mammed hn end TRIGA Reactor None Not Applicable Not Applicable Not Applicable Not Applicable Fac.lity i Radiation Center 9/26/97 52 *Co, 32p, 86Rb 4 x 10-2 Not Applicable (2) Laboraton.es 5/9/98 TOTAL 52 "Co, 32p, 86Rb 4 x 10-2 _ __ (1) TRIGA and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging. 2' (2) The short-lived waste was held by the Radiation Safety Oflice for decay. % M M m
13 Protection Part V Table V.B.2 Monthly Summary of Gaseous Effluent Releases (0 Estimated Average _ Percent of the Date of Total Estimated Total Estimated Atmospheric Diluted Applicable MPC for Discharge Radioactivity (Month and Released 4 3
^4 " " '" ^4 " * "
Year) (Curies)
~ (Curies) Stack) Stack)
(nCi/ml) (%) July 97 0.58 0.58 4.4 x 104 1.1% August 97 0.47 0.47 3.5 x 104 0.9' '. September 97 0.33 0.33 2.6 x 104 0.7% October 97 0.40 0.40 3.0 x 104 0.8% November 97 0.39 0.39 3.0 x 108 0.8% December 97 0.50 0.50 3.9 x 104 1.0% January 98 0.28 0.28 2.2 x 10 O.5% February 98 0.30 0.30 2.5 x 104 0.6% 1 March 98 0.55 0.55 4.2 x 10 4 1.0% _ April 98 0.38 0.38 3.0 x 10 4 0.7% May 98 0.42 0.42 3.2 x 10 O.8% June 98 0.82 0.82 6.5 x 10 4 I ANN 11AL 1.6% VALUE 5.42 5.42 3.5 x 104 0.9% i (;) Airbome effluents from the OSTR contained no detectable particulate radioactivity resulting from reactor operations, p and there were no releases of any radioisotopes in airborne effluents in concentrations greater than 20% of the L applicable effluent concentration. (20% is a value taken from the OSTR Technical Specifications.) [ (2) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detec*able radionuclide was argon-41, [ c L
14 g Protection Part V Table V.B.3 Annual Summary of Solid Waste Generated and Transferred Dates of Waste Volume of g Total Quantity Pickup for Dates of Origin of Solid Waste act uns e e pment fmm Radionuclides Solid Waste Packaged") in Solid Waste OSU Waste Oregon State y, g g.,,g (Cubic Feet) (Curies) Processing University") Facility 7/2/97 TRIGA "Sc, Sc, "Cr, 11 0/97 9/26/97 2/5/98 Reactor 220) 5'Co, 54Mn, "Fe, 3.0 x 10-5 1/21/98 Facility "Co, i2*Sb, "'Eu 5/18/98 3/11/98
'H. 22Na, 2*Na, "Sc, d'Sc, "Fe, 906/97 11/20/97 Radiation "Co, "Rb, *Sr, 1/21/98 2/5/98 =
Center 34 3.6 x 10 3
'"Cd, i22Sb, i2*Sb, 3/11/98 5/18/98 Laboratories 2q, 2B, 22*Ra, 23 U, 2 Am TOTAL 66 See Above 6.6 x 10'5 . .
I I (j) TRIGA and Radiation Cenkt laboratory waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging. (2) Solid radioactive waste is shipped to Allied Ecology Services, Inc. l (3) Includes 3 ft' ofdewatered resin beads, i I
15 Protection Part V Table V.C.1 Annual Summary of Personnel Radiation Doses Received Average Annual ~ Greatest Individual Total Person-mrem Dosem Dosem For the GroupN Whole Whole Whole Personnel Group ' Body Extremities Body Extremities , Body. Extremities (mrem) (mrem) (mrem) (mrem) (mrem) - . (mrem) Facility Operating 14 80 35 100 190 1110 Personnel Key Facility Research Personnel ND <1 ND 30 ND 30 Facilities Services Nf aintenance Personnel
<1 N/A 3 N/A 4 N/A Laboratory Class Students ND <l ND 30 ND 50 Campus Police and Secunty Personnel ND N/A ND N/A ND N/A Visitors <1 N/A 20 N/A 161 N/A (g) "ND" indicates that each of the beta-gamma dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the neutron dosimeters was less than the vendor's threshold of 30 mrem, as applicable. "N/A" indicates that there was no extrernity monitoring conducted or required for the group.
I
16 Protection Part V Table V.D.1 I Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Total Recorded I Monitor TRIGA Reactor - Dose Equivalentm2) Facility Location (See Figure V.D.1) 4( ) entron (mrem) (mrem) MRCTNE D104: North Badge East Wall 15 ND MRCTSE MRCTSW D104: D104: South Badge East Wall South Badge West Wall 0 105 ND ND l MRCTNW D104: North Badge West Wall ND ND MRCTWN D104: West Badge North Wall 70 ND MRCTEN D104: East Badge North Wall 580 ND MRCTES D104: East Badge South Wall 1300 ND MRCTWS D104: West Badge South Wall 305 30 MRCTTOP D104: Reactor Top Badge 295 30 MRCTHXS D104A: South Badge HX Room 420 ND , MRCTHXW D104A: West Badge HX Room 20 30 MRCD-302 D302: Reactor Control Room 140 ND MRCD-302A D302A: Reactor Supervisor's Office 20'3) N/A (g) He total recorded dose equivalent values do not include natural background contribution and, except as noted, reflect the summation of the results of 12 monthly beta gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of we fast neutron dosimeters was less than the vendor's threshold of 50 to 100 mrem, as applicable.
"N/A" indicates that there was no neutron monitor at that location.
(2) These dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area. E 3 (3) The total recorded dose equivalent reflects the summation of four quarterly beta-gamma dosimeters. I
17 Protection Part V Table V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded Radiation Center Dose Equivalent * -
. Monitor Faellity Location xp(G) . Neutron LD. (See Figure V D.1) (mrem) (mrem)
MRCA100 A100: Receptionist's Office NDS N/A MRCBRF A102H: Front Personnel Dosimetry Storage Rack ND* N/A MRCAl20 Al20: Stock Room NDS N/A MRCA120A Al20A: NAA Temporary Storage 175 N/A MRCA126 Al26: Campus RSO's Isotope Receiving Lab 275* N/A MRCCO-60 A128: "Co Irradiator Room $25* N/A MRCA130 A130: Shielded Exposure Room NDm N/A MRCA132 A132: TLD Equipment Room ND* N/A MRCA134-2 A134: Graduate Student Office 190* N/A MRCA138 A138: Health Physics Laboratory ND* N/A MRCA146 A146: Gamma Analyzer Room (Storage Cave) ND N/A MRCB100 B100: Gamma Analyzer Room (Storage Cave) 390 N/A MRCBI14 Bl14: a Lab (22*Ra Storage Facility) 1595 ND MRCF ' 19-1 Bil9: Source Storage Room 210* N/A MRCBI19-2 Bl19: Source Storage Room 4455 N/A MRCBI19A Bl19A: Scaled Source Storage Room 4080 3100 MRCB120 B120: Instrument Calibration Facility 20m N/A MRCB122-2 B122: Radioisotope Storage Hood 25m N/A MRCB122-3 B122: Radioisotope Research Laboratory ND* N/A MRCB124-1 B124: Radioisotope Research Lab (Hood) 10m N/A MRCB124-2 B124: Radioisotope Research Laboratory ND* N/A MRCB124-6 B124: Radioisotope Research Laboratory ND* N/A MRCB128 B128: Instrument Repair Shop ND* N/A MRCC100 C100: Radiation Center Director's Office ND* N/A MRCC106A C106A: Staff Lunch Room ND* N/A MRCC106B C106: Solvent Storage Room 90
- N/A MRCC106 H C106H: East Loading Dock ND* N/A MRCCI18 Cl18: Radiochemistry Laboratory ND* N/A Seefootnotesfollowing the table.
18 Protection Part V Table V.D.2 (continued) Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center l Total Recorded Radiation Center Dose EquivalentW Monitor Facility Location xp(G) Neutron l LD. (See Figure V.D.1) (mrem) (mrem) E htRCCl20 C120: Student Counting Laboratory NDS N/A htRCCl21 C121: APEX Facility ND* N/A 5 hiRCCl22 Cl22: APEX Control Room ND N/A htRCCl23N C123: Gamma Analyzer Room (Storage Cave) 85* N/A hfRCCl23S C123: Gamma Analyzer Room ND N/A NIRCCl24 C124: Student Computer Laboratory 10m N/A htRCCl30-1 Cl30: Radioisotope Laboratory (Hood) NDW N/A h1RCCl34 Cl34: Gamma Analyzer Room (Storage Cave) ND N/A htRCD100 D100: Reactor Support Laboratory 125 N/A N1 RCD 102 D102: Pneumatic Transfer Terminal Lab 20 ND h! RCD 102-H D102H: 1st Floor Corridor at D102 ND ND NIRCD106-H D106H: 1st Floor Corridor at D106 95* N/A hfRCD200 D200: Reactor Administrators's Office ND N/A h1 RCD 202 D202: Senior Health Physicist's Office 20 N/A NIRCBRR D20CH: Rear Personnel Dosimetry Storage Rack ND* N/A hiRCD204 D204 Health Physicist Office 30m ND hiRCD300 D300: 3rd Floor Conference Room ND ND I (g) The total recorded dose equivalent values do not include natural background contribution and, except as l noted, reflect the summation of the results of 12 monthly beta-gamma dosimeters or four quarterly fast t neutron dosimeters for each location. A total dose equivalent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 50 to 100 mrem, as applicable. ! "N/A" indicates that there was no neutron monitor at that location. (2) The total recorded dose, equivalent reflects the summation of four quarterly beta-gamma dosimeters. (3) The total recorded dose equivalent reflects one quarterly beta and gamma dosimeter and nine monthly beta-gamma dosimeters. I l
l 19 k Protection Part V ( Table V.D.3 Annual Summary of Radiation Levels and Contamination Levels Obsened ( Within the Reactor Facility and Radiation Center During Routine Radiation Sun'eys { Whole Body Contamination Accessible Location Radiation levels Levels * (See Figure V.D.1) (mrem /br) (dpm/cm2) f Average Maximum . Average . Maximum TRIGA Reactor Facility: ( Reactor Top (D104) <l 100 <500* 3,169:)t Reactor 2nd Deck Area (D104) 5 35 <500 <500 Reactor Bay SW (D104) <1 5 <500 <500 Reactor Bay NW (D104) <1 15 <500 <500 Reactor Bay NE (D104) <l 15 <50 <500 Reactor Bay SE (D104) <1 19 <500* 1,480m Class Experiments (D104, D302) <1 70 <500 <500 ( Demineralizer Tank-Outside Shielding (D104A)
<1 50 <500* 1,296m Particulate Filter-Outside Shielding (D104A) <1 2 <500* 1,667*
( Radiation Center: NAA Counting Rooms (A146,B100,Cl34) <1 5 <500 <500 Health Physics Laboratory (A138) { <1 <1 <500 <500 "Co Irradiator Room (Al28) <1 9 <500 <500 [ Radiation Research Labs
<1 11 <500 <500 t (B114, B122, B124, B132, Cl30, Cl32A)
Radioactive Source Storage (Bil9A) <1 35 <500 <500 f Student Chemistry Laboratory (Cll8) <1 5 <500 <500 Student Counting Laboratory (Cl20) <1 9 <500 <500 Operations Counting Room (Cl23) <l 6 <500 <500 Pneumatic Transfer Laboratory (D102) <1 22 <500 <500 __TRIGA Tube Wash Room (D100) <l 2 <500 <500 2 (1) <500 dpm/100 cm = Less than the lower limit of detection for the portable survey instrument used. (2) The contamination shown for this location assumes 100% smearing efficiency and was immediately removed. As a result, the average contamination level at this location during the reporting period was, for all practical purposes, <500 dpm per 100 cm2.
20 Protection Part V Table V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence
- Total Calculated I
. Dose Equivalent E
Total Recorded Total Recorded (Including 5 Dose Equivalent . Dose Equivalent Background) Fence (Including (Includ.ing Based on the Environmental Background) Background) Annual Average Monitoring Based on R. D. Co. Based on OSU prem/h Station (See Figure V.E.1) TLDsW (mrem) TLDsm (mrem) Dose RateW (mrem) l MRCFE-1 100 59 4 66* 12 MRCFE-2 97 49
- 4 63
- 10 MRCFE-3 98 52 4 74 12 MRCFE-4 105 61
- 4 75 + 19 MRCFE-5 94 49
- 4 64 11 MRCFE-6 101 51 4 66
- 10 MRCFE-7 96 51 4 65 8 MRCFE-8 93 49 4 59 9 MRCFE-9 94 50 5 58
- 10 Radiation Detection Company (R.D. Co.) TLD totals include their annual natural background contribution of (1) 80 mrem for the reporting period. Average Corvallis area natural background using Radiation Detection Company TLDs totals 86 mrem for the same period.
(2) OSU fence totals include a measured natural background contribution of 45
- 8 mrem.
(3) i values represent the standard deviation of the total value at the 95% confidence level. I I
i 21 Protection Part V Table V.E.2 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations [ Total Calculated Dose Equivalent f Total Recorded Total Recorded - (Including Background) Off-Site Dose Equivalent Dose Equivalent Based on the Radiation (Including Background) (Including Background) Annual Average Monitoring Based on R. D. Co. Based on OSU ' . prem/h Station (4 - TLDsm TLDs*") Exposure Rate") (See Figure V.E.2) (mrtm) (mrem) (mrem) MRCTE-2L f - 37
- 4 46 7 MRCTE-3 102 43 4 69
- 11 MRCTE-4 94 72 12 66* 9 MRCTE-5L -
43
- 4 61
- 8 MRCTE-6 100 76 16 67 7 MRCTE-7L --
38 5 63 t 13 MRCTE-8 106 56 5 69*14 MRCTE 9 102 39 4 61*10 MRCTE-10 92 f 40
- 3 54
- 9 J1RCTE-11 92 40
- 2 50*9 MRCTE12 102 55 7 66 8
( MRCTE-13L - 50
- 4 61 7 MRCTE-14L --
42 3 53 10 MRCTE-15 91 49 5 55
- 8 MRCTE-16L 63 * $
66 12 MRCTE 17 92 54
- 5 52
- 11 MRCTE-18L --
62 6 { 67
- 15
_ MRCTE-19 106 59
- 6 68 10 MRCTE-20L 68*13 64 *I3 f MRCTE-21 80 50
- 5 39
- 7 _
MRCTE-22 84 41+4 39
- 9 _
(g) Monitoring stations coded with an "L" contained one standard OSU TLD pack only. Stations not coded with an "L" contained, in addition to the OSU TLD pack. one R.D. Co. TLD monitoring pack. (2) Radiation Detection Company TLD totals include their annual natural background contribution of 80 mrem for the reporting period. Average Corvallis area natural background using Radiation Detection Company TLDs totals 86 mrem for the same period. (3) OSU off-site totals include a' measured natural background contribution of 45
- 8 mrem.
(4)
- values represent the standard deviation of the total value at the 95% confidence level.
1
22 Protection Part V I Table V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus3 H) I for Environmental Soil, Water, and Vegetation Samples Annual Average Concentration . Location Sample g g ,, Reporting (See Figure Type-
- Radioactivitym V.E.2) 1-W Water 4.17E-08 3.22E-08m pCi/cm' 4-W Water 3.48E-08 5.83 E-09* pCi/cm' i1 W Water 3.36E-08
- 2.9E-09* pCi/cm' 19-RW Water 4.20E-08 3.43 E-085 Ci/cm' 3-S Soil 1.45E-04 1.30E-04 pCi/g of dry soil 5-S Soil 1.21E-04
- 1.92E-04 pCi/g of dry soil 20-S Soil 1.22E-04 9.64E-05 pCi/g of dry soil 21-S Soil 1.53E-04
- 1.54E-04 pCi/g ofdry soit 2-G Grass 2.88E-04 4.06E-04 pCi/g of dry ash 6-G Grass 3.12E-04 4.97E-04 pCi/g of dry ash 7-G Grass 3.25E-04 5.01 E-04 pCi/g of dry ash l
8G Grass 2.45 E-04 3.48E-04 pCi/g of dry ash 5 9-G Grass 2.80E-04 3.92E-04 pCi/g of dry ash 10-G Grass 2.67E-04 4.21 E-04 pCi/g of dry ash f 12 G Grass 3.51 E-04
- 4.78E-04 pCi/g of dry ash l 13-G Grass 2.62E-04
- 3.62E-04 pCi/g of dry ash 14-G Grass 2.32E-04 t 2.57E-04 pCi/g of dry ash _.
15-G Grass 2.86E-04
- 3.78E-04 pCi/g of dry ash l
16-G Grass 2.89E-04 i 4.26E-04 pCi/g of dry ash l 17-G Grass 3.42E-04 5.44E-04 pCi/gf dry ash I8-G Grass 2.59E-04
- 3.60E-04 __ pCi/g of dry ash 22-G Grass 3.57E-04 5.64 E-04 uCi/g of dry ash I
I (g) values represent the standard deviation of the average value at the 95% confidence level. (2) Less than lower limit of detection value shown. I
1 I 23 l Protection Part V I Table V.E.4 I Average LLD Concentration and Range of LLD Values for I Soil, Water and Vegetation Samples l l l Sample Average Range of Reporting Type LLD Value LLD Values Units , Soil 2.49E-05 1.81E-07 to 3.46E-05 pCi/ gram of dry soil Water 3.80E-08 3.18E-08 to 6.82E-08 pCi/cm 3 1 Vegetation 2.38E-05 I 7.37E-06 to 4.11E-05 Ci/ gram of dry ash I I I I I I I I I
24 Protection Table V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 Number of Shipments ' Total Shipped To Activity FBd Limited Quantity Whitel - YellowII Total OSU Oceanography 1.70 x 10-5 1 0 4 5 Corvallis, OR _ General Atomics Empty 1 0 0 1 San Diego, CA Package OSU Electrical and Computer Engineering 3 6.27 x 10 1 0 0 1 Corvallis. OR Berkeley Geochronology Center 9.74 x 10 4 12 0 1 13 Berkeley, CA l su University of California 3.12 x 10-5 1 0 2 3 g Berkeley, CA LawTence Berkeley National Laboratory g 4 1.19 x 10 1 0 0 1 Berkeley, CA Stanford Unis ersity Stanford, C A 1.98 x 10 4 6 0 1 7 Idaho State University d 3.78 x 10 1 3 24 28 Pocatello, ID University of Washington 4 4.95 x 10 2 0 0 2 Seattle, WA E g University of California 4 Santa Barbara, CA 9.02 x 10 2 0 0 2 University of Wyoming 8.61 x 10 4 4 0 0 4 Laramie, WY Brigham Young 1.17 x 10 4 2 0 0 2 Provo, UT l SUNY-Plattsburgh 4 1.37 x 10 3 0 0 3 l Plattsburgh, NY l m ! Columbia University 5.29 x 10 5 1 0 1 2 l Pallisades, NY g l Union College E 2,7 x 10 4 1 0 0 1 l Schenectady, NY TOTALS 4.98 x 10 d 39 3 33 75 i I
25 Protection Part V Table V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 Number of Shipments Total Shipped To Activity
. @@ Limited Yellow Quantity II Total There were no radioactive material shipments originating from the Radiation Center's State of Oregon License ORE 90005 during this reporting period.
I I I I I I L [ [ [ r L
26 Protection Part V I Table V.F.3 Annual Summary of Radioactive Material Shipments Exported I Under NRC General License 10 CFR 110.23 Number of Shipments Total Shipped To Activity N Limited Yellow Quantity II Total Vrije Universiteit 4'11 x 10 0 1 1 Amsterdam, The Netherlands Scottish Universities Research and Reactor Centre 4 1.69 x 10 0 1 i Scotland, UK University of Geneva 4.03 x 10'5 0 2 2 Geneva, Switzerland University of Waikat Hamilton, New Zealand 1.86 x 10 4 1 0 1 E E University of Queensland 5 3.98 x 10 0 3 3 Brisbane, Australia FAPIG Research and Reactor Centre 9.16 x 10 7 2 0 2 Yokosuka, Japan Universite Paris-Sud 2.61 x 10 ' 0 1 1 Paris. France TOTALS 8.52 x 10 5 3 8 11 l l I I I I
L 27 Pc'otection { Part V TRIGA Facility and Radiation Center Area Dosimeter Locations { mCTm SCTEM Reactor Facility 3rd Floor Reactor Factitty 2nd Floor V V MCTTOP h EME (> MRCTW g y\
"I 5
j
" ~
~
D104 Reactor
~7 D104 Reactor i
- ~ O D104 "ac*r y Bay
[ h Bay : i W,_ U4 2 R
._ :V g E>)StCTSW MCTSE d mCo-200 *bd ,,
"'"A g J33o3 mCo-300<1 gE
[ DM . 6 x D202 D200 22 12 0106 D102 pg D100 lt " "
*E
~"~
[- 0206 .A MRCB419f A Tied h TEE"> l MCBRR y *C V # # (B121C-1 3N -122 ! Reactor Facility 4th Floor I koad
'MW Dock' 19 I l8123 ,
C122 MCC-123S D400 = un {_ 4*c8-120 040 8 _-= 5E { - 20C-121 ~ A 2 B11 NtCB-1 -6 MRCS-124-[ MRCB. 124-Q A M CS-12 2-2 C121 A A V I Y MRCC-124f5
.g34 MRCB-114 ,,
.B126A A126 A134 B114 ,B1268 C124 C-120 -
N U 3 3 ' k mCC-126 E102 { MCB-N A136 B108 E126 B128 C126 A124 C120 NtCA-1 E104 [ 9tCC4184 E124 B106 B130 C128 E122 A140 { E100
% % A1 b -C130 1 E120
- - um.42 m .m. B104 B132 C130 E104 6-----
gg UI32Al l . C118 E
. " " E118 kA120 A144 B102 B134 C132 " C116 E M-J 120
, C115 E112E1I4" pg2 A pCC-134 NtCA-14d. kB-100
~
[ C114 A116 A146 B100 lB136 C134 l 6-- C108 { . _ _ _A,r
- Lf gy c
)
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1 l Work Part VI Part VI lI l i WORK lI A. Summary h Radiation Center offers a large variety ofresources for teaching, research, and service related l to radiation and radioactive materials. Some ofthese are discussed in detail in otherparts ofthis l report' Thepurposeofthispartistosummarizetheteaching,research,andserviceeffortscanied out during the current reporting period. B. Teaching The most important responsibility of the Radiation Center and reactor is to support OSU's academic programs. Implementation ofthis support occurs through direct involvement of the I Center's staff and facilities in the teaching prograrns of various departments and through participation in University research programs. For example, during the current reporting period, the Radiation Center accommodated 69 OSU academic classes involving a number ofdifferent l academic departments. In addition, portions ofclasses from other Oregon universities were also supported by the Radiation Center. The OSU teaching programs (not including research) utilized I 1,156 hours ofreactor time. Tables III.A.1 and III.D.1 plus section VI.C.5 provide more detailed information on the use of the Radiation Center and reactor for instruction and training. C. Research and Service Almost all Radiation Center research and service work is tracked by means ofa project system. When a request for facility use is received, a number is assigned to the project, a project cover sheet is generated, and the project is added to the database. The database includes such information as the project number, data about the person and institution requesting the work, a description of the project, Radiation Center resources needed, the Radiation Center project I manager, estimated costs for the project, and the funding source. Table VI.C.1 provides a summary ofinstitutions and agencies which used the Radiation Center
- during this reporting period. This table also includes additional information about the number of j academic personnel involved, the number ofstudents involved, and the number ofuses logged for each organization. Details on graduate student research which used the Radiation Center are given
!l in Table VI.C.2.
I
" Part VI l
l The major table in this section is Table VI.C.3. This table provides a listing of the research and l service projects carried out during this reporting period and lists information relating to the I personnel and institution involved, the type ofproject, and the funding agency. Projects which used the reactor are indicated by an asterisk. In addition to identifying specific projects carried out during the current reporting period, Part VI also highlights major Radiation Center capabilities in research and service. These unique Center ! functions are described in sections VI.C.1 through VI.C.8.
- 1. Neutron Activation Analysis l Neutron activation analysis (NAA) stands at the forefront oftechniques for the quantitative multi-element analysis ofmajor, minor, trace and rare elements. The principle involved in NAA consists of first irradiating a sample with neutrons in a nuclear reactor such as the OSTRtoproducespecificradionuclides. Aftertheirradiation,thecharacteristicgamma l rays emitted by the decaying radionuclides are quantitatively measured by suitable l semiconductor radiation detectors, and the gamma rays detected at a particular energy am usually indicative ofa specific radionuclide's presence. Data reduction ofgamma ray spectra by means of a computer then yields the concentrations ofvarious elements in samples being studied. With sequential instrumental NAA it is possible to measure quantitatively about 35 elements in small samples (5 to 100 mg), and for activatable gl g
l elements, the lower limit ofdetection is on the order ofparts per million or parts per billion, I depending on the element. \ l
- The Radiation Center's NAA laboratory has analyzed for the major, minor, and trace 1 element content in many thousands ofsamples covering essentially the complete spectrum of material types and involving virtually every scientific and technical field. I While some reseat chers perform their own sample counting on their own or on Radiation Center equipment, the Radiation Center provides a complete NAA service for researchels andoths who may require it. This includes sample preparation, sequential irmdiation and i counting, and data reduction and analysis. l Data on NAA research and service performed during this reporting period are included in Table VI.C.3.
- 2. Forensic Studies Neutmn activation analysis can also be advantageously used in enmmal investigations. The l principle underlying such application usually involves matching trace element profiles in objects or substances by NAA. This in tum can help identify materials or products (e.g.,
3 (' Work Part Y1 h identify the manufacturer ofa given object), and in some cases can match bullets and other materialsrecoveredfrom'a victimtosimilarmaterialsobtainedfromsuspects Materials which have been analyzed by the Radiation Center for forensic purposes include bullets, [- metals, paint, fuses, coats, glass, meat, and salts. { Forensic studies performed in this reporting period are included in the listings in Tables VI.C.1 and VI.C 3. [ '3. Irradiations As described throughout this report, a major capability ofthe Radiation Center involves the irradiation ofa large variety ofsubstances with gamma rays and neutrons. Detailed data on these irradiations and their use during this reporting period are included in Part III as well as in section C of this part. {
- 4. Radiological Emergency Response Services The R adiation Center has an emergency response team capable ofresponding to all types ofradiological accidents. This team directly supports the City ofCorvallis and Benton
(_ County emergency response organizations and medical facilities. The team can also provide assistance at the scene ofany radiological incident anywhere in the state ofOregon on behalfofthe Oregon Radiation Protection Services and the Oregon OfSee ofEnergy. { The Radiation Centermaintains dedicated stocks ofradiological emergency response [ equipment and instrumentation. These items are located at the Radiation Center, at the Good Samaritan Hospital, and in the Linn/Benton Region 5 HAZMAT vehicle. [ During the current reporting period, the Radiation Center emergency response team conducted several training sessions and exercises, but was not required to respond to any actualincidents. In conjunction with the OSU Department ofNuclear Enginming, Radiation Center staff [ provide ongoing support to the state ofOregon's emergency response plan for the Trojan NuclearPowerPlant. Althoughthereactoritselfisnowshutdown,Trojanstillmusthave an emergency plan for the fuel kept in the spent fuel storage ponds. About seven persons [ residing in the R adiation Center hold either primary, second shift or attemate positions in the Trojan Emergency Plan and would work in the Emergency Operations Centerin Salem or in the Emergency Operations Facility at Trojan in the event of an incident. k r L r
4 l Work Part VI During the past year, Radiation Center personnel attended training sessions, participated in drills and exercises, and provided advice relating to emergency response to a Troj an incident, but no one was required to respond to a real Trojan emergency.
- 5. Training and Instruction In addition to the academic laboratory classes and courses discussed in Parts III.A.2, III.D, and VI.B, and in addition to the routine trammg needed to meet the requirements of the OSTR emergency response plan, physical security plan, and operator requalification program,theRadiationCenterisalsousedforspecialtrainingprograms RadtationCenter staffare xellexperiencedinconductingthesespecialprograms,andregularlyoffertmimng in areas such as research reactor operations, research reactor management, research reactor radiation protection, radiological emergency response, reactor behavior (for nuclear power plant operators), neutron activation analysis, nuclear chemistry, and nuclear safety analysis.
Special training programs generally fall into one ofseveral categories: visiting faculty and research scientists; Intemational Atomic Energy Agency (IAEA) fellows; special short-term courses; or individual reactor operator ot health physics training programs. During this reporting period there were a large number of such people as shown in Part II.B. As has been the practice since 1985, the HAZMAT R esponse Teams Radiological Course was taught this year from May 4-7,1998 at HAMMER, Richland, Washington.
- 6. Radiation Protection Services The primary purpose ofthe radiation protection program at the Radiation Center is to support the instruction and research conducted at the Center. However, due to the high quality of the program and the level ofexpertise and equipment available, the Radiation Center is also able to provide health physics services in support ofthe OSU Radiation Safety Office and to assist other state and federal agencies. The Radiation Center does not compete with private industry, but supplies health physics services which are not readily available elsewhere. In the case of support provided to state agencies, this definitely helps to optimize the utilization of state resources.
The Radiation Center is capable ofproviding health physics services in any of the areas which are discussed in Part V. These include personnel monitoring, radiation surveys, sealed source leak testmg, packagmg and shipment ofradioactive materials, calibration and repair of radiation monitoring instruments (discussed in detail in Section VI.C.7), radioactive waste disposal, radioactive material hood flow surveys, and radiation safety analysis and audits.
_ _ -- ~ 5 Work Part VI The Radiation Center also provides services and technical support as a radiation laboratory to the Oregon State Health Division (OSHD) in the event of a radiological emergency within the state ofOregon. In this role, the Radiation Center will provide gamma-ray spectroscopy analysis ofwater, soil, milk, food products, vegetation, and air samples collected by OSHD radiological response field teams. As part ofthe ongoing prepamtion for this emergency support, the Radiation Center participates in inter-institution drills and cross-calibrations.
- 7. Radiological Instrument Repair and Calibration i While repair ofnuclear instrumentation is a practical necessity, routine calibration ofthese mstruments is a licensing and regulatory requirement which must be met. As a result, the Radiation Center operates a radiation instrument repair and calibration facility which can accommodate a wide variety of equipment.
The Center's scientific instrument repair facility performs maintenance and repair on all types of radiation detection and other nuclear instrumentation. Since the Radiation Center's own programs regularly utilize a wide range ofnuclear instruments, components I for most common repairs are often on hand and repair time is therefore minimized. In addition to the instrument repair capability, the Radiation Center has a facility for calibrating essentially all types ofradiation monitoring instruments. This includes typical portable monitoring instrumentation for the detection and measurement ofalpha, beta, I gamma, and neutron radiation, as well as instruments designed forlow-level environmental monitoring. Higher range instmments for use in radiation accident situations can also be calibrated in most cases. Instmment calibrations are performed using radiation sources I certified by the National institute of Standards and Technology (NIST) or traceable to NIST. I Table VI.C.4 is a summary of the instruments which were calibrated in support of the Radiation Center's instructional and research programs and the OSTR Emergency Plan, while Table VI.C.5 shows instruments calibrated for other OSU departments and non-OSU agencies. Table VI.C.6 shows instruments repaired for non-Radiation Center j departments and agencies. It should be noted that the Radiation Center only calibrates and I repairs instruments for local, state and federal agencies. l m 4 __-n
6 Work Part VI I
- 8. Consultation Radiation Center staff are able to provide consultation services in any of the areas I
discussed in this annual report, but in particular: research reactor operations and use, g radiation protection, neutron activation analysis, neutron radiography, radiological a emergency response, and radiotracer methods. Records are not normally kept of such consultations, as they often take the form of telephone conversations with researchers encountering problems or plannmg the design of experiments. Many faculty members housed in the Radiation Center have ongoing consulting functions with various agencies, in addition to sitting on numerous committees in advisory capacities. I i I I I 1 I I
7 ( wo,k Part VI Table VI.C.1 Institutions and Agencies Which Utilized the Radiation Center [ Number.
"" ' Number of Number of 'of'
( Institution . Projects .- Faculty Students . ' Uses of.. y,,olved Involved Center: Facilitien [
' Oregon State Universitym Corvallis, Oregon 44 12 18 271m
[ U.S. Environmental Protection Agency NA Corvallis, Oregen 1 NA I U. S. Forest Service [ Corvallis, Oregon 1 NA NA 1
- Center for the Study of First Americans Corvallis, Oregon i NA NA 1
{ Good Samaritan Ilospital Corvallis, Oregon i NA NA 8 Corvallis Fire Department Corvallis, Oregon i NA NA 8 Oregon Office of Energy [ Salem, Oregon 1 NA NA 44
- University of Oregon 3 4 9 3 Eugene, Oregon
{
' Oregon Episcopal School y 3 g Portland, Oregon 3
*Geovic Ltd.
Beaverton, Oregon I NA NA 2 Rogue Community College { Grants Pass, Oregon 3 ; j g Central Oregon Community College g j ; ( Bend, Oregon i Pacific Northwest National Laboratories Richland, Washington 1 I I 2 (1) Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center. f (2) This number does not include ongoing projects being performed by residents of the Radiation Center such as the APEX project, others in the Department of Nuclear Engineering or Department of Chemistry, projects conducted by Dr. W. D. Loveland, which involve daily use of Radiation Center facilities.
- Project which involves the OSTR.
I L e
8 I Table VI.C.1 (continued) Institutions and Agencies Which Utilized the Radiation Center
-Number Number of. Number of .of Institution Faculty l Students . Uses of
.. Projects Involved ' Involved Center :
Facilities
- University of Washington 2
Seattle, Washington 3 3 3 l E
- Idaho State University 6 3 13 13 Pocatello, Idaho
- Berkeley Geochronology Center i NA NA 28 Berkeley, California
*Califomia State University Chico, Califomia
- San Jose State University i I 2 1 San Jose, Califomia m
' California State University Northridge, California g g g i
*Pomona College j
; g ;
I Claremont, Califomia
- Stanford University 4 3 3 8 Stanford, Califomia
' University of California Energy Institute 1 1 1 2 Berkeley, California E ' University of California at Santa Barbara 1 1 5 5 Santa Barbara, California
! ' University of California at Los Angeles y g g l Los Angeles, California MX Gems and Minerals Stanton, California 1 NA NA 3
- Montana State University Bozeman, Montana i I 2 I
' University of Utah Salt Lake City, Utah
; 3 g g g g
l *Brigham Young University 3 2 2 3 Provo, Utah l
- Project which involves the OSTR.
I
9 Work pg,,y, Table VI.C.1 (continued) Institutions and Agencies Which Utilized the Radiation Center Number I " #
' Number of. Number of of
- Institution. ~ p,"o3 Faculty Students _ Uses of-Involved Involved - Center I Facilities
' University of Wyoming 2 2 2 5 Laramie, Wyoming
- Colorado College 3 3 2 Colorado Springs, Colorado 3 I ' University of Colorado Boulder, Colorado 6 1 1 4 I ' State University of Nebraska Lincoln, Nebraska I I I I
' University of Arizona I Tucson, Arizona I I I I
' Eastern New Mexico University y , ,
Portales, New Mexico
*New Mexico Tech Socorro, New Mexico 1 I 2
- Texas Tech University Lubbock, Texas 3 2 3 3
' Trinity University I San Antonio, Texas I I I I
- University of New Orleans New Orleans, Louisiana 3 3
- Southern Indiana University Evansville, Indiana 3
'Carlton College 2 2 4 2 Northfield Minnesota
' University of Dayton I Dayton, Ohio I I I I
- Franklin and Marshall College I I 2 I Lancaster, Pennsylvania
- State University of New York at Plattsburgh
[ Plattsburgh, New York [
- Project which involves the OSTR.
E' L
10 Work Part VI Table VI.C.1 (continued) I Institutions and Agencies Which Utilized the Radiation Center
' Number .
I Numberof . Number df -of-Institution' Faculty Students Uses of.
. Projects -
Involved- -Involved Center-I
- Facilities
' City Co:iege of New York i I 2 1 New York, New York
- State University of New York at Stonybrook
, 3 3 ,
Stonybrook, New York
- Columbia University Pallisades, New York
- Williams College
; , g Williamstown, Massachusetts
- Smith College Northampton, Massachusetts 1 1 1 2 l 3
- George Washington University 1 1 2 1 Washington, D.C.
' North Carolina State University l Raleigh, North Carolina *Clemson University 1 I I 2 Clemson, South Carolina
- University of Florida 3 2 2 2 Gainesville, Florida 5
- Union Colleg 1 3 4 1 Schenectady, New York
*FAPIG Radiation Research Nagasaka,Yokosuka, Japan 1 2
- Scottish Universities Research and Reactor Centre Glasgow, Scotland, United Kingdom i l 15 3 Borealis Technical Limited London, England, United Kingdom i NA NA 5 5
*Universite Paris-Sud Paris, France 1 NA NA I ' University de Pierre et Marie Curie y y ; g Paris, France
- Project which involves the OSTR.
I
t 1I ( Work Part VI Table VI.C.1 (continued) Institutions and Agencies Which Utilized the Radiation Center [
- Number
. Number of
[ Institution Faculty Students Uses of, Pro % Involved Involved Center Facilities
*Vrije Universiteit Amsterdam Amsterdam, The Netherlands I i 1 6
( *GEO N Geneva, Switzerland 1 NA NA 1
- University of Geneva Geneva, Switzerland 3 2 5 5
' University of Queensland Brisbane,Queensland, Australia 4
- University of Waikato
, ; g Hamilton. New Zealand 3 TOTALS 134 81 133 586
{ { { { { l 1
- Project which involves the OSTR.
L t
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Table VI.C.2 U o[ Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topie Brigham Young University l ( l E Lee Bray MS Geology Nelson Petrogenesis of the Absaroka Volcanic l Supergroup, WY. Kevin Hae Hae MS Geology Kowallis Subsidence and Uplift History of the Uinta Basin from Apatite Fission Track Analysis. Cal State University, Northridge t Barbara Chinn MS Geological Sciences Weigand Detailed Isotopic Modelling of the Origin of Miocene Lavas from the Northern Channel l Islands. City College of New York Scott Chesman PhD Earth and Env. Sciences Steiner Delineation of the Trondjemite-Tonalite-Granite Terrain of Southern New York and Connecticut. Romana Novack MS Earth and Env. Sciences Steiner Delineation of the Trondjemite-Tonalite-Granite 1emin of Southern New York and Connecticut. 2 a 5 m M M M M M M M M
Table VI.C.2 @ n Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topie Columbia University Diane hicDaniel PhD Earth Sciences Hemming Assessment of Correlation between Climatic Changes and Differences in Provenance in the Amazon Drainage Basin. Eastern New Mexico University Douglas Anderson hiA Anthropology Constantopoulos X-ray Fluorescence Spectrometry of Narbona Pass Chert: A Chemical Characterization Study. Idaho State University Jason Casper hts Geology Hughes Geology of Circular Butte Volcano. Jason Casper hts Geology Hughes Petrography and Geochemistry of Volcanic Centers near the Test Area North on the INEL. Dave Clovis Not Known Hughes Student in Geology 615 John Glover Not Known Hughes Student in Geology 615. Jay hiatarese Not Known Hughes Student in Geology 615. N a 4C
Table VI.C.2 ej E Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic I crin McKnight Not Known Hughes Student in Geology 615. Jennifer Parker MS Geology Hughes Geochemistry and Stratigraphy of the Tuff of Wooden Shoe Butte. Scott Serrano Not Known Hughes Student in Geology 615. Ian Warren Not Known Hughes Student in Geology 615. Anni Watkins MS Geology Hughes Not Determined. Paul Wetmore MS Geology Hughes Accumulation Rates and Stratigraphy ofINEEL Basalts. Karen Wright MS Geology Hughes Not Determined. Montana State University Charles Lindsay MS Earth Sciences Feeley Geochemistry of High-K Lavas and Co-genetic Instrusions from Sepulchur Mountain and Electric Peak Yellowstone National Park. l l I I
- s i
1 _ _ _______L_____ __ ?___
. - - - .__, - - - - - . - - 4 Table VI.C.2 y Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic North Carolina State University Sonja Ingram MS Marine Earth & At. Sciences Fodor Trace Element Distinctions among Plagioclases in Hawaiian Tholeiitic and Alkalic Magmas.
Oregon State University Sabooh Asghar MS Nuclear Engineering Reyes Core Makeup Tank Recirculation, Drainage and Condensation Behasior. Martin Attfield Post-Doc. Chemistry Sleight Delta Phase UO3. Darren Boone MS Nuclear Engineering Higginbotham Evaluation of Hormetic Effect of Gamma Radiation on Pinto Bean Seeds. Tom Brannan MS Nuclear Engineering Higginbotham Evaluation of Radionuclide.;in Various Sewer Sludge Samples. Mike Cantaloub MS Nuclear / Civil Engineering Higginbotham Determination of Non-aqueous Phase Liquid (NAPL) Contamination in Saturated and Unsaturated Aquifer Material using Radon as an Indicator. Jin Young Choi PhD Agricultural Chemistry Kerkvliet Undecided. N bG
Table VI.C.2 @ E
. n Graduate Student Reseant Vhich Utilized the Radiation Center Student's Name DeRree Academic Department Faculty Advisor Thesis Topie Sarah Colpo hts Nuclear Engineering Reyes Counter Current Flow Limitation in the APEX Facility's Pressurizer Surge Line.
Scott Crail hiS Nuclear Engineering Higginbotham Detection of Potentially Contaminated Garbage Entering a City Garbage Disposal Site. Erica
Dearstyne PhD Agricultural Chemistry Kerkvliet Fate of T Cells in TCDD-Treated hiice:
Anergy of Apoptsis? Bmce Eversmeyer PhD Oceanography Prahl Suspended Solid Description of Columbia River Particulates. Phil Gaffkin PhD Chemistry Dept Chen Use of Gamma Irradiation to Evaluate its Potential for Crosslinking Peptides and Nucleotides. Sebastian Geiger PhD Geosciences Haggerty Diffusion in Geologic hiaterials. Sebastian Geiger PhD Geosciences Geiger Fluid Flow in Fractures, Reactive Flow and Coupled Flow Phenomena. hiarish Giri PhD Chemical Engineering Rochefort Impurities in Plastics. 2 a 3 M M M M - M M M M M M
Table VLC.2 5 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Facuhy Advisor Ihesis Topic Sung Mo Kang MS Forest Products Morrell Fungi Colonization of Douglas Fir Sapwood and their Role in Biological Discoloration. Janine Katanic MS Nuclear Engineering Higley RHP 587 Class project: Evaluation of the Hormetic Effect of Radiation on Pinto Bean Seeds. Young Kim MS Civil Engineering Semprini Bioremediation of Chloroform Contamination. Fugen Li PhD Food Science Barnes Molecular Biology of Cystatin C, a Cystein Protease Inhibitor. 1 Mark Mankowski MS Forest Products Morrell Biology of Carpenter Ants in the Pacific Northwest and its Relationship with Fungal Decay in Buildings. Robert Nartley PhD Geosciences Buckosic Unknown. Oleg Povetko MS Nuclear Engineering Higley Long-Lived Radionuclide Migration through Soils. Rodney Prell PhD Agricultural Chemistry Kerkvliet Role of B7 Co-stimulation in TCDD Immunotoxicity. Mari Rios MS Physics Krane Neutron Cross Section Measurements'of Radioactive Ge-68 and Gd-148. 2 a 3C
Table VLC.2 # E A Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topic Carl Ruby PhD Agricultural Chemistry Kerkvliet involvement of NFKB in TCDD Immunctoxicity. Christopher Rusher MS Nuclear Engineering Reyes Level Swellin a Boiling Pool. David Shepherd PhD Agricultural Chemistry Kerkvliet A T-Cell Receptor-Transgenic Model for Immunoticity Testing. ! Christopher Sinton PhD Oceanography Duncan Age and Compostion of Two Large Igneous l Provinces: The North Atlantic Volcanic Rifled Margin and the Caribbean Plateau. Mark Strohecker MS Nuclear Engineering Reyes Flow Modeling of the APEX Facility's IRWST. Daniel Strom MS Botany / Plant Pathology Rivin Clonal Analysis of Maise Meristem. Beth Vorderstrasse PhD Agricultural Chemistry Kerkvliet Dendritic Cells: Role in TCDD-Induced Suppression of CTL Activity. Dan Wachs MS Nuclear Engineering Reyes Prediction and Modeling of Thermal Stratification in the Cold Legs of the OSU APEX Facility.
- Oliver Woodhouse PhD Oceanography Falkner Osmium Behavior in the Aqueous Marine l Environment.
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Table VI.C.2 # Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic 1 1 Rockie Yarwood PhD Microbiology Bottomley 2,4-D Degradation by Soil Micro-organisms. Li Yoon MS Botany / Plant Pathology Rivin Clonal Analysis of Maise Meristem. Lissa Zyromski PhD Chemistry Loveland Measurement of Fusion Enhancements with neutron-rich Stable and Radioactive Projectiles. San Jose State Unisersity : Laura Parent MS Geology DeBari Petrologic and Structural Evolution of the Cardinal Peak Pluton. Scottish Univ. Res. & Rx Centre T. Barry PhD Leicester University Pringle Mongolian Basalts / Tectonics J. Blecher PhD Oxford University Pringle Aden Volcanic Differentiation. S. Carn PhD Cambridge University Pringle Indonesian Volcanics. L Chambers PhD Edinburgh University Pringle North M! antic Teniary Province. H. Dixon PhD Bristol University Pringle Subglacial Volcanics. N
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Table VI.C.2 @ S n Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic C. Harford PhD Bristol University Pringle Montserrat Volcanic Hazards. E. Heath PhD Lancaster University Pringle St. Vincent Volcano Hazards. G. May PhD Aberdeen University Pringle Chilean Basins. S. McElderry PhD Liverpool University Pringle Chilean Tertiary Faulting. Y. Najman PhD Edinburgh University Pringle Himalayan Foredeep. M. Purvis PhD Edinburgh University Pringle Turkish Basin Tectonics. R. Shelton PhD Queens University Pringle North Channel Basin Evolution. A. Sowerbutts PhD Edinburgh University Pringle Sardinia Evolution. G.Steele PhD Aberdeen University Pringle Cerro Rico Silver. R. White PhD Leicester University Pringle Caribean Crustal Growth. N i 3 m M M M M M M M - M M ]
Table VI.C.2 { m. Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Thesis Topic 1 Stanford University i Daniel Stockli PhD Geological & Env. Sciences Dumitru Timing of Extensional Faulting in the Northern Basin and Range Provina, and the Structured and Thermal Transition to the Central Sierra Nevada. Benjamin Surpless PhD Geological & Env. Sciences Miller Geological Evolution of the Sierra Nevada - Basin ! and Range Transition Zone. i Da Zhou PhD Geological & Env. Sciences Dumitru Amalgamation and UpliA History of the Tian Shan, Western Chma. SUNY at Stony Brook Troy Rasbury PhD Earth and Space Sciences Hanson . Use of Fission Track Dating of Various Authigenic Calcite and Phosphate Minerals to Determine the Time of Sedimentation with a View to Calibrating the Geologic Record. Texas Tech University j Melissa Batum MS Geosciences Barnes Comparison of Granites Across a Proterozoic- , Archean Boundary. l . $S l
Table VI.C.2 5 O s. Graduate Student Research Which Utilized the Radiation Cettter Student's Name Degree Academic Department Faculty Advisor Thesis Topic Mi-ae Jeon MS Geosciences Barnes Elemental and Isotopic Exchange in Granite During Metamorphism. Sang-yun Lee PhD Geosciences Barnes Granite Petrogenesis and Core Complex Formation, Ruby Mtns. NV. The University of Waikato Ming Hung Ho Ph.D. Earth Sciences Kamp Thermo-tectonic History of Marlborough, New Zealand. U.C. Berkeley Chad Cole MS Nuclear Engineering Olander Evaluation of Processess to Determine the ! Amount of Uranium in Mixed Waste. UCLA Amy Young PhD Earth and Space Sciences Davidson Petrogeneis, Stratigraphy and Origin of Damavand Volcano, Iran. Union Col'ege Mike Bullen BSc Geology Gaiver Provenance of the Ukelayet Flysch, Kamchatka, Russia. N 2 . 3 L
. _ , - - - m - ,, - - - -, ,, -, - - . - -. - - Table VI.C.2 @
~
Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academie Department Faculty Advisor Thesis Topic Jorge Mora PhD Env. Sciences, SUNY, Albany Ganer UpliA and Evolution of the Venezeulan Andes. Univ. of California, Santa Barbara Andy Cahrst PhD Geological Sciences Gans Tectonic Studies in Eastern-Most Russia. Jon Nauert MS Geological Sciences Gans Volcanism in the Eldorado Mountains, Southern Nevada. Jaime Toro Not Known Geological Sciences Gans Cretaceous and Tertiary History of Alaska's Brooks Range and Russia's Chukotka Peninsula. University of Colorado-Boulder Philip Verplank PhD CIRES Farmer Geochemistry of the Organ Needle Pluton in South-central New Mexico. University of Florida Ann Heatherington Post-Doc. Geology Mueller Crustal Evolutica Along the Western Boundary of the Wyoming Crater, Stephanie Jenkins MS Geology Mueller Age and Origin of the Albermarle Group, Carolina State Belt. 2' bd
Table VI.C.2 W Graduate Student Research Which Utilized the Radiation Center { Student's Name Degree Academie Department Faculty Advisor Thesis Topic University of Geneva Mercedes Hernandez PhD Mineralogy Singer Petrology and Geochronology of the Catalan Coastal Ranges Batholith, NE Spain. Robert Marschick PhD Mineralogy Singer Cretaceous Cu (-Fe) Mineralization in the Punta del Cobre Belt, Northern Chile. Osman Partak PhD Mineralogy Singer Geochemistry and Geochronology of the Merson l Ophiolite within the Eastern Mediterranean Tectonic Frame. Thao Ton-That MS Mineralogy Singer Ar-40/Ar-39 Dating of Basaltic Lava Flows and the Geology of the Lago Buenos Aires Region, Santa Cruz Province, Argentina. Yann Vincze MS Mineralogy Singer Ar-10/Ar-39 Incremental Heating Studies of Latest Pleistocene and Holocene Lava and Tephra: Implications for the Last Glaciation in the Southern Andes. University of New Orleans Judy Wilson MS Geology & Geophysics Johnson Volcanic Hazards in the Cascade Range. N a G M M M M M M M M M M M M
Table VI.C.2 @ n Graduate Student Research Which Utilized IIe Radiation Center
- Student's Name Degree Academic Depanneemt Faculty Advisor . Thesis Topic ;
University of Oregon f 3 Jacqui Coll Post Doc. Pharmacy Ayres Trace Metals in Drug Suspensiort I i I Christopher Descantes ' PhD Anthropology Ayres Archeological Study of Yap, Micronesia. j Scott Fitzpatrick PhD Anthropology Ayres Stone Tool Materials and Sources on Easter Island. Roland Goodgame Not Known Reed Characterization of Alteration and Mineralization ! in Komatiite. L I Katic Rorrer MA Anthropology Ayres Pacific Archeology ; Epi Suafo'a MA Anthropology Ayres Pacife Archeology Stephen Twyerould PhD Geological Sciences Reed The Geology and Genesis of the Ernest Henry Fe- [ i oxide, Cu-Au deposit, Queensland Australia. ) i Helen Vallianatos PhD Anthropology Goles Palcodietary Reconstruction and Effects of , 1 Diagenesis. j Joan Wozniak PhD Anthropology Ayres Easter Island Archeological Settlement and Early [ Agriculture. l N 2 m ! Gm i P E L i
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Table VLC.2 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Adsisor Thesis Topic University of Washington Scott Barboza PhD Geological Sciences Bergantz The Dynamics of Dehydration Melting. Kyle Bland MS Geological Sciences Bergantz The Generation of H3bridized Magmas. Rebecca Chrisfield MS Geological Sciences Stewart History of Faulting and Uplift of the Coast Ranges ofOregon and Washington. University of Wyoming Bradford Burton PhD Geology / Geophysics Murphy Structural and Thermal History of Harrison Pass Pluton, NV. Thomas Kalakay PhD Geology / Geophysics Murphy Structural and Themal History of Pioneer Batholith, MT. L- _ -.
Table VI.C.3 #M 4 Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding 321 Murphy University of Wyoming Fission Track Dating Thermal column irradiations of Geophysics, U apatite and zircon samples for fission ofWyoming track production to determine rock age. 335 Kowallis Brigham Young Fission Track Dating Dating of natural rocks and minerals National University via fission track raethodology. Science Foundation 444 Duncan Oregon State University Ar-40 /Ar-39 Dating of Production of Ar-39 from K-39 to Oceanography, Oceanographic Samples measure radiometric ages on basaltic OSU rocks from ocean basins. 480 Higginbotham Oregon State University Technical Support to the Technical support to Oregon DOE Radiation State of Oregon and the Department of Human Center, OSU Resources to assist in emergency preparedness for the PGE-Trojan facility. 481 Winans Oregon Health Sciences Instrument Calibration Calibration of radiation survey Oregon Health Univ. instruments. Sciences University 488 Farmer Oregon State University Instrument Calibration Calibration of portable radiation Radiation survey instruments for radiation users Center, OSU on OSU campus. 2 INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements A G M M M M M M M m M M M M M M - M
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Table VI.C.3 { n Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Titic Description , Funding 519 Livingstone U.S. EPA Instrument Calibration Calibration of portab!c radiation USEPA-survey meters using the standard RC Conallis protocol. 521 Vance University of Fission Track Studies Thermal column irradiation of zircon University of Washington and other samples to induce Iission Washington tracks in catcher foils for dating. 547 Boese EPA - Newport Sunty Instrument Calibration of GM and other portable USEPA, Calibration sunty meters as per standard OSU Cincinnati, OH protocol. 554 Niles Oregon Office of Energy Instrument Calibration Instrument calibration of sunty Oregon meters for PUC truck inspectors. Depadment of Transportation 632 Thompson Oregon State Police RadiologicalInstrument Calibration of radiological Oregon State Crime Lab. Calibration instruments used at the OSP Crime Crime Laboratory Laboratory 664 Higginbotham Oregon State University Instrument Calibration Calibration of radiation sunty Radiation instruments. Center, OSU 665 Higginbothrm Oregon State University Instrument Calibration Calibration of radiation sunty Radiation instruments. Center, OSU t INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements 5 a g G4 L _ _ _ _ _ _ _
1 l Table VI.C.3 !! M s. l Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding 708 Reyes Oregon State University AP600 Long-Term Cooling Fabricate and test scale model of US Nuclear Test section of Westinghouse AP600 Regulatory t reactor cooling system. Commission l 7II Mattson Oregon State University Diagnostic Biology Sterilization of bovine blood serum in Vet. Med. the Co-60 irradiator. Diagnostic Laboratory, OSU 745 Wiggs Oregon Health Sciences Gamma Sterilization of Irradiation of various medicinals Oregon Health l Univ. Various Materials using the Co-60 irradiator to OHSU- Sciences specified doses for purposes of University sterilization. 752 Barnes Oregon State University Schistoma Cell Culture Feeder layer irradiations to 2.5 krad. OSU l Gamma irradiation of hamsters and Biochemistry & l other laboratory animals. Biophysics 815 Morrell Oregon State University Sterilization of Wood Sterilization of wood samples to 2.5 Forest Products, Samples Mrads in Co-60 irradiator for fungal OSU evaluations. 920 Becker Berkeley Geochronology Ar-39/Ar-40 Age Dating Production of Ar-39 from K-39 to Berkeley i Center determine ages in various Geochronology anthropologic and geologic materials. Center 930 McWilliams Stanford University Ar-40/Ar-39 Dating of Irradiation of r&.eral grain samples Geophysics, Geological Samples for specified times to allow Ar-40/A Stanford 39 dating. University l 2 INAA - Instrumental Net :ron . ictivation Analysis REE - Rare Earth Elements % G l l M M M M M M M M M M M M M
O Table VI.C.3 ' o{ Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title . Description Funding 931 Keriatiet Oregon State University TCDD Effects on T-Cell Co-60 irradiation of spleen cells from Agriculture Activation mice to study the effects ofTCDD on Chemistry, OSU T-cell activation using T-h cell clones. 932 Dumitru Stanford University Fission Track Dating Thermal column irradiation of Geology, geological samples for fission track Stanford age-dating. University 995 Bottomley Oregon State University Herbicide Mineralization in Soil sterilization in the Co40 Crop & Soil
- AgriculturalSoils irradiator. Science, OSU 1002 Singer University of Geneva Ar-40/Ar-39 Dating of CLICIT irradiation ofgeological University of Young GeologicalMaterials materials such as volcanic rocks from Geneva sea floor, etc. for Ar-40/Ar-39 dating.
1018 Gashwiler Occupational Health Lab Calibration of Nuclear Calibrate radiation suney meters. Occupational Instruments Health Laboratory 1020 Gans Univ. of California. Tectonic Studies in Eastern- Irradiation for Ar-40/Ar-39 dating National Santa Barbara Most Russia using the CLICIT or dummy fuel Science element. Foundation 1025 Semprini Oregon State University Sterilization of Subsurface Soil sterilization in order to Civil Soil investigate the bioremediation of Engineering, chloroform contamination. OSU INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elenwnts N A g Zw
Table VI.C.3 !! 8 A. Listing of Major Research and Senice Projects Performed or in Pmgress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding 1072 Rasmussen Army Corps of Instrument Calibration Calibration of radiation detection U.S. Army Engineers instmments. Engineer District, Portland. 1073 Pringle Scottish Univ. Res. & Argon 40/39 Dating of Age dating of various materials using Scottish Univ. Rx Centre Rock Minerals the Ar-40/Ar-39 ratio method. Research & Reactor Centre 1074 Wijbrans Faculty of Earth 40Ar-39 Ar Dating of 40Ar-39Ar dating of rocks and Vrije Sciences Rocks and Minerals minerals. Universiteit, Amsterdam l 1075 Lederer Univ. of California Activation Analysis Irradiation of small, stainless steel UC Berkeley l Energy Institute Experiment for NE Class discs for use in a nuclear engineering radiation measurements laboratory. ' 1097 Loveland Oregon State University Speciation of Pu in the Measurement of the chemicat Chemisty, OSU Aquatic Environment speciation of Pu in fresh water. 1098 Loveland Oregon State University Fusion Enhancement with Measurement of fusion enhancements Chemisty, OSU n-rich Projectiles with n-rich stable and radioactive projectiles. ; 1109 Prahl Oregon State University Suspended Solid Evaluation of the form, sources and Geosciences, Description of Columbia fates of suspended Columbia River OSU River Particulates particulate materials. INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements I amm oss uma mas amm uma man sums amm num nas sums aus num amm uma ame
7_ 7 1, i Table VI.C.3 { Listing of Major Research and Service Projects Peifva..ed or In Progress at the Radiation Center and Their Funding Agencies fI r Project Uwr(s) Nanne Organizataen Name Project Title Description , Fanding i f i118 Larson Oregon State University Primary Phytoplankton Evaluation of the primary production Forest f Production Studies at of phytoplankton in Crater Lake and . Resources, OSU ! Crater Lake lakes in Mount Rainier, Olympic, I and North Cascades NationalParks ! using C-14 and liquid scintilation counting. 1120 Rivin Oregon State University Clonal AnalysisofMaise Testing to determine if an isolated Botany, OSU i Meristem mutated gene is required for past l embryonic meristem formation or ! l function. i125 Streck University of Geneva Crystallization in Determination of mobility of trace GEOMAR last. Ignimbrite E, Gran Canary elements during cooling of tuff E - Germany [ , using INAA. j i i i127 Tsukahara FAPIG Radiation Res. Kyoto Fission Track Age Irradiation of samples in the thermal FAPIG Lab. Dating column for fission track age dating. Radiation Research Lab., . Japan i129 Hughes Idaho State University Chemical Characterization Evaluation of high Icvel radioactive INEL l of Vitrification Eroducts waste melter performance by University , determination of the degree of Consonium l homogenization, the diffusion rates (MIT) and the number and types of phases remaining aAer vitrification. a ! 2 INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements A j 4g -* 11
i Table VLC.3 U o[ Listing of Major Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) lOme Organization Name Project Title Description Funding i138 Ilughes Idaho State University Thesis and Faculty Use ofINAA to support a large USDOE Research Using INAA of variety of research projects imching (Reactor Use Geologic Materials the geochemistry of rocks in Idaho Sharing) and surrounding regions. This l includes support for two graduate classes Geology 615 and 625. 1161 Reed University of Oregon Characterization of Characterization of komatiites from LSDOE Alteration and Australia for rare ca th element and (Reactor Use Mineralization in Komatiite platinum group element abundances Sharing) to evaluate their economic mineral resource potential. I177 Garver Union College Fission Track Analysis of Use of thermal column irradiations to Union College, Rock Ages perfor n fission track analysis with a NY view to the determination or rock ages. I178 Hughes Idaho State University Ar/Ar Radiometric Dating Imtstigation of the evolution of the National of Geological Samples Snake River Plain volcanic system. Science Foundation (EPSCoR) 1185 Elting University of Oregon Instrument Calibration Radiological instrument cahtration University of for the EmironmentalIIcalth and Oregon Safety Office INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements 2 4 3 M M M M M M M M M M M M M M M M M M M a
i > w umms umma I Table VI.C.3 ? n Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description Funding I186 Fitzgerald University of Arizona Fission Track Dating Thermal column irradiation of University of geological samples for fission track Arizona age-dating. I187 Sivaramakrishnan Oregon State University Radiation Effects on Determination ofirradiation effects Radiation Gallium Arsenide on semiconductois, and gallium Center, OSU arsenide in particular. The project starts with gamma irradiation and progresses to alpha, beta and neutrons later. I188 Salinas Rogue Community Photoplankton Growth in Liquid scintillation counting of C-14 Rogue College Southern Oregon Lakes radiotracer samples produced in a Community photoplankton study of four southern College Oregon lakes: Miller Lake, Lake of the Woods, Diamond Lake, and Waldo Lake. I190 Higginbotham Oregon State University Use of Radon as a Tracer Determination of non-aqueous phase Radiation for NAPL Determination liquid (NAPL) contamination in Center, OSU saturated and unsaturated aquifer material using radon as an indicator. 1191 Vasconcelos Department of Earth Ar-39/Ar-40 Age Dating Production of Ar-39 from K-39 to Earth Sci., Sciences determine ages in various University of anthropologic and geologic materials. Queensland, Australia INAA = Instrumeatal Neutron Activation Analysis REE - Rare Earth Elements 2 4 g 3w
Table VI.C.3 $ Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies { Project User (s) Name Organization Name Project Title Description Funding 1192 Ifigginbotham Oregon State University Evaluation of Analysis of several samples of sewer Radiation Radionuclides in Seuer sludge to determine the types and Center, OSU Sludge quantities of any radionuclides present. I193 Smith Oregon State University Irradiation of Viruses inactivation of viruses by gamma ray Food Sci. & irradiation. Technology, OSU 1196 Higley Oregon State University Dose Response Effects on Evaluation of the possible hormetic Radiation Bean Seeds effects in irradiated pinto bean seeds. Center, OSU Class project associated with RHP 587. 1200 Moody Bechtel Hanford Stabilization of 90Sr and Geochemical study ofdesorption of CH2M Hill Incorporated 100 Area Cr(6+) Using strontium and chromium from Phosphatic Material Hanford soils, adsorption of Sr and Cr on various phosphates, and the determination of the solubility product of strontium hydroxyapatites. 1201 Hanson SUNY at Stony Brook High Precision Dating of Use of fission track dating of various USDOE Sedimentary Material authigenic calcite and phosphate minerals to determine the time of sedimentation with a view to calibrating the geologic remrd. N INAA -Instrumental Neutron Activation Analysis REE - Rare Earth Elements % 3 M M M M M M M M M M M M M M M
Table VI.C.3 @ n Listing of Majnr Research and Senice Projects Performed or In Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Name Project Title Description , Funding 1203 Aulich Energy & Env. Plastics Pyrolysis Determination of Cs, Sb, Sn, V, Cu, Radiation Research Center Ti, Sr, Ce and Zr at the ppb levelin Center, OSU process matrices of oil, resin and char to evaluate the ability of the process to remove these clernents. 1205 Kelley The Open University Argon-39/ Argon-40 Age Determination of the ages ofurious The Open Dating ofMinerals minerals by use of the argon- University, UK 39/ argon-40 ratio technique. 12 % Hughes Idaho State University Chemical Correlation of NAA ofbasaltic rocks obtained from Idaho Water Volcanic Units on INEEL drill core and surface locations to Resources evaluate thelocal and regional Research Inst. stratigraphy beneath vanous facilities on the INEEL to determine the Wahy of the aquifer system. 1209 Scholle London Coin Galleries Authenticity of Medieval Use of NAA to evaluate 5-6 London Coin Siher Coins Romanian medieval silver coinsin an Galleries attempt to corapare authentic coins to some with questioned authenticity. 1215 Brinkly Emerald Diagnostics Sterilization of Latex Irradiation oflatex solutions in order Emerald Laboratory Solutions to sterilize the material for biological Diagnostics research products. Laboratory INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements N 4 m G (A L. . y m ,_ .--
Table VI.C.3 $ Listing of Major Research and Service Projects Performed er in Progress at the Radiation Center and Their Funding Agencies { Project User (s) Name Organization Name Project Title Description Funding 1225 Roden-Tice SUNY College at Fission Track Analysis of Analysis of the thermal history of Radiatien Plattsburgh Apatite and Zircon Triassic basins in Connecticut using Center, OSU fission track age dating methods. 1229 Binney Oregon State University Production of Copper-67 Investigation of the feasibility of the Nuclear production of the medicalisotope Engineering Cu67 from enriched Zn67 by using Dept., OSU the n-p reaction and a medium power research reactor. 1230 Lamperti City of Corvallis Analysis ofIndustrial Sampling and counting of effluent Radiation Efiluent from local industries in order to Center, OSU determine the presence and magnitude of any radionuclides. 1231 Adams University of Utah Rare Earth Elements in the Evaluation of REEs in nater as a USDOE Coso Geothermal System method of differentiating the various (Reactor Use reservoirs iri the Coso system Sharing) geothermat field. 1232 Bergantz University of Chemical evolution of the Evaluation of the mechanics involved USDOE Washington lower crust with the growth of the continental (Reactor Use crust and the origin of chemical Sharing) diversity in volcanic rocks. INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements N A G M M M M M M M M M M M M M M M
Table VI.C.3 @ n Listing of Major Research and Senice Projects Performed or la Progress at the Radiation Center and Their Funding Agencies Project User (s) Name Organization Nanne Project Title Descripties Funding 1236 Farmer University of Colorado- Geochemistry of the Organ Identification of the processes USDOE Boulder Needle Pluton, New Mexico responsible for the generation of (Reactor Use silicic magma using samples from the Sharing) Organ Needle pluton in south-central New Mexico 1237 Mueller University of Florida Early Crustal Ew>lution Evaluation of ancient crustal USDOE cv...ps..cnts with unusual Nd isotopic (Reactor Use compositions to better constrain the Sharing) origin of these segments. 1238 Roden-Tice SUNY College at Fission Track Analysis of Use offission track dating to analyze USDOE Plattsburgh Apatite and Zircon thermal histories ofvanous (Reactor Use mountains, including: Olympic - Sharing) Moutains, WA; Adirondack Mountains, NY; Ouachita Mountains, Himalayas; Klamath Mountains, OR. 1239 Garver Union College Timing of Uplift and Use offission track analysis to USDOE Provenance ofSediments determine the timing of uplift and the (Reactor Use from Orogenic Highlands provenance ofsediment:: died from Sharing) orogenic highlands. INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements ?1 54 L
i l I Table VLC.3 w= i?.
=
Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and Their Funding Agencies l Project User (s) Name Organization Name Project Title Description Funding i 1240 Hirt College of the Siskiyous Vertical Zonation of the Development of a compositional USDOE i Paradise Pluton, Sierra profile for the upper part of the SE (Reactor Use Nevada, CA Sierra batholith in the region between Sharing) l Golden Trout Creek and Forester Pass. 1241 Steiner City College of New Delineation of TTG Terrain Delineation of trondhjemite-tonalite- USDOE York of Southern New York & granite terrain to resolse the problem (Reactor Use Connecticut of source rock and the timing of Sharing) major prograde metamorphic esents. 1243 McBirney University ofOregon Differentiation of the Completion of the most thorough USDOE Skaergaard intmsion investigation of magmatic (Reactor Use differentiation ever completed. Sharing) 1244 Reed University of Oregon Geology and Genesis of the Determination of the gains and losses USDOE Ernest Henry Deposit, of trace elements due to ore (Reactor Use Queensland Australia formation in the Ernest Henry Fe-Cu- Sharing) Au deposit. 1247 Johnson Texas Tech. University Genesis of Pre-Accretion Determination of the process USDOE Plutoas in the Blue Mtns, responsible for magma generation in (Reactor Use OR order to provide important tectonic Sharing)}}