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Revised April 26, 2010 Pdf Icon[1.6 MB (115 Pages)] ORAU TEAM Dose Reconstruction Project for NIOSH Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services Page 1 of 115 DOE Review Release 05/03/2010 Document Title: Document Number: ORAUT-TKBS-0048 Revision: 01 Site Profile for the Brookhaven National Effective Date: 04/26/2010 Laboratory Type of Document: TBD Supersedes: Revision 00 Subject Expert(s): Lori Arent, Samuel Chu, John A. Devanney, Leo Faust, Robert L. Morris, Eugene Potter, and Elyse M. Thomas Site Expert(s): N/A Approval: Signature on File Approval Date: 04/23/2010 Melton H. Chew, Document Owner Concurrence: Signature on File Concurrence Date: 04/22/2010 John M. Byrne, Objective 1 Manager Concurrence: Keith A. McCartney Signature on File for Concurrence Date: 04/23/2010 Edward F. Maher, Objective 3 Manager Concurrence: Signature on File Concurrence Date: 04/23/2010 Kate Kimpan, Project Director Approval: Signature on File Approval Date: 04/26/2010 James W. Neton, Associate Director for Science New Total Rewrite Revision Page Change FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVIS ION, OR PAGE CHANGE, REPLACE THE PRIOR REVISION AND DISCARD / DESTROY ALL COPIES OF THE P RIOR REVIS ION. Document No. ORAUT-TKBS-0048 Revision No. 01 Effective Date: 04/26/2010 Page 2 of 115 PUBLICATION RECORD EFFECTIVE REVISION DATE NUMBER DESCRIPTION 08/30/2006 00 New Site Profile for the Brookhaven National Laboratory. First approved issue. Incorporates internal and NIOSH formal review comments. Training required: As determined by the Task Manager. Initiated by Melton H. Chew. 04/26/2010 01 Revision to incorporate SEC language, BNL comments, and clarifies that background radiation is not included in occupational exposure. References were consolidated at the end of the document. Incorporates formal internal and NIOSH review comments. Constitutes a total rewrite of the document. Training required: As determined by the Objective Manager. Initiated by Melton H. Chew. Document No. ORAUT-TKBS-0048 Revision No. 01 Effective Date: 04/26/2010 Page 3 of 115 TABLE OF CONTENTS SECTION TITLE PAGE Acronyms and Abbreviations ............................................................................................................... 7 1.0 Introduction ............................................................................................................................ 10 1.1 Purpose ...................................................................................................................... 11 1.2 Scope ......................................................................................................................... 11 1.2.1 Site Description ............................................................................................... 11 1.2.2 Occupational Medical Dose............................................................................. 12 1.2.3 Occupational Environmental Dose .................................................................. 12 1.2.4 Occupational Internal Dose ............................................................................. 12 1.2.5 Occupational External Dosimetry .................................................................... 12 1.2.6 Attributions and Annotations ........................................................................... 12 2.0 Site Description ...................................................................................................................... 13 2.1 Introduction ................................................................................................................. 13 2.2 Purpose ...................................................................................................................... 13 2.3 Scope ......................................................................................................................... 13 2.4 Site Description and General Information ................................................................... 13 2.4.1 Brookhaven Graphite Research Reactor, Building 701 ................................... 15 2.4.2 High Flux Beam Reactor, Building 750 ............................................................ 20 2.4.3 Medical Research Center, Building 490 .......................................................... 21 2.4.4 Brookhaven Medical Research Reactor, Building 491 ..................................... 21 2.4.5 Positron Emission Tomography, Building 906 ................................................. 22 2.4.6 Cosmotron, Building 902 ................................................................................. 22 2.4.7 Alternating Gradient Synchrotron, 900 Series Buildings .................................. 22 2.4.8 Brookhaven LINAC Isotope Producer, Building 931 ........................................ 27 2.4.9 Tandem Van de Graaff, Building 901 .............................................................. 27 2.4.10 National Synchrotron Light Source, Building 725 ............................................ 29 2.4.11 Relativistic Heavy Ion Collider Complex, Building 1000 Series ........................ 29 2.4.12 Hot Laboratory, Building 801 ........................................................................... 31 2.4.13 High Intensity Radiation Development Laboratory, Building 830 ..................... 33 2.4.14 Chemistry Department, Building 555 ............................................................... 33 2.4.15 Physics Department, Building 510................................................................... 34 2.4.16 Other Miscellaneous Radiological Research Facilities .................................... 34 2.4.16.1 LMFR Support, Building 820 ............................................................. 34 2.4.16.2 Hot Machine Shop, Building 530 ....................................................... 34 2.4.16.3 Health Physics and Safety Instrumentation, Building 535 ................. 35 2.4.17 Waste Management Facility, Radwaste Reclamation Building, Building 865 .................................................................................................... 35 2.4.18 Radiological Waste Decontamination Facility, Building 650............................. 36 2.5 Isotopes of Concern ................................................................................................... 36 2.6 Magnitude of Site Activity ........................................................................................... 41 2.7 Major Incidents ........................................................................................................... 46 2.8 Radiological Access Controls ..................................................................................... 47 3.0 Occupational Medical Dose .................................................................................................... 48 3.1 Purpose ...................................................................................................................... 48 3.2 Scope ......................................................................................................................... 48 3.3 Examination Frequency .............................................................................................. 48 3.4 Equipment and Techniques ........................................................................................ 49 Document No. ORAUT-TKBS-0048 Revision No. 01 Effective Date: 04/26/2010 Page 4 of 115 3.5 Entrance Air Kerma in Air ........................................................................................... 50 3.6 Organ Dose Calculations ............................................................................................ 52 3.6.1 Organ Dose from Collimated Exposure ........................................................... 52 3.6.2 Organ Dose from Poorly Collimated Exposure ................................................ 52 3.6.3 Skin Dose ....................................................................................................... 53 3.7 Dose Reconstruction .................................................................................................. 54 3.8 Uncertainty ................................................................................................................. 54 4.0 Occupational Environmental Dose ......................................................................................... 59 4.1 Introduction ................................................................................................................. 59 4.2 Purpose ...................................................................................................................... 59 4.3 Scope ......................................................................................................................... 59 4.4 Ambient External Radiation ........................................................................................ 59 4.4.1 Use of Offsite Monitoring ................................................................................. 59 4.4.2 Applicability for Dose Reconstruction .............................................................. 60 4.5 Inhalation of Onsite Airborne Radionuclides ............................................................... 60 4.5.1 Stack Monitoring ............................................................................................. 60 4.5.2 Estimates of Potential Inhalation Intake .......................................................... 61 4.6 Ingestion ....................................................................................................................
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