DOCSLIB.ORG

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Hanford External Dosimetry Technical Basis Manual PNL-MA-842 PNNL-15750 Rev. 1.1 PNL-MA-842 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Hanford External Dosimetry Technical Basis Manual PNL-MA-842 B. A. Rathbone May 1, 2010 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. PACIFIC NORTHWEST NATIONAL LABORATORY operated by BATTELLE for the UNITED STATES DEPARTMENT OF ENERGY under Contract DE-AC05-76RL01830 Printed in the United States of America Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831-0062; ph: (865) 576-8401 fax: (865) 576-5728 email: [email protected] Available to the public from the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal Rd., Springfield, VA 22161 ph: (800) 553-6847 fax: (703) 605-6900 email: [email protected] online ordering: http://www.ntis.gov/ordering.htm Preface The Hanford External Dosimetry Program (HEDP) provides support to the U.S. Department of Energy’s Richland Operations Office (RL), Office of River Protection (ORP), Pacific Northwest Site Office (PNSO), and DOE contractor radiation protection organizations in determining doses-of-record from external sources of radiation. The Pacific Northwest National Laboratory (PNNL) (a) administers the HEDP in coordination with Hanford contractor radiation protection organizations to ensure consistent site-wide implementation of external dosimetry practices for Hanford workers and visitors. Coordination of dosimetry practices at Hanford is accomplished through the Hanford Personnel Dosimetry Advisory Committee (HPDAC). Technical services provided by the HEDP include personnel, area, nuclear accident, and environmental dosimetry capabilities that comply with DOE requirements in 10 CFR 835 Occupational Radiation Protection (DOE 2007a), DOE/EH-0027 Department of Energy Standard for the Performance Testing of Personnel Dosimetry Systems (DOE 1986a) and DOE/EH-0026 Handbook for the Department of Energy Accreditation Program for Personnel Dosimetry Systems (DOE 1986b) as well as DOE guidance in DOE G 441.1-1C Radiation Protection Programs Guide (DOE 2008a). The primary purposes of this Hanford External Dosimetry Technical Basis Manual are to document the design and implementation of the external dosimetry system used at Hanford, and to document the rationale for the measurement methods used. This manual includes documentation of the technical basis for the dosimeter design, processing protocols, dose calculation methodology, and recommended dosimeter use in the field, in a manner intended to demonstrate compliance with 10 CFR 835 and to ensure the defensibility of the doses of record. Secondary purposes of this manual are to provide general information on dosimeter response characteristics and guidance on the proper use and limitations of Hanford dosimeters that will be of use to Hanford radiation protection organizations. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of HEDP. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the HPDAC which is chartered and chaired by DOE. This manual supports the Radiation Protection Programs of Hanford contractors. RL, ORP, PNSO and DOE contractors overseen by these DOE offices will be implementing new requirements in the June 8, 2007 Amendment to 10 CFR 835 Occupational Radiation Protection (DOE 2007a) beginning January 1, 2010. This revision of PNL-MA-842 is consistent with the new requirements and intended for use by these entities on or after January 1, 2010. (a) Pacific Northwest National Laboratory is operated by Battelle Memorial Institute for the U.S. Department of Energy under Contract DE-AC05-76RLO 1830. Issued: May 2010 PNL-MA-842: Preface Supersedes: January 2010 Page iii THIS PAGE INTENTIONALLY LEFT BLANK Issued: May 2010 PNL-MA-842: Preface Supersedes: January 2010 Page iv Glossary absorbed dose, D (1) The absorbed dose, D, is the quotient of d by dm , where d is the mean energy imparted by ionizing radiation to matter of mass dm , thus d D dm Unit: J kg-1 The special name for the unit of absorbed dose is gray (Gy). This ICRU definition of the absorbed dose, D, as a point function, allows the specification of the spatial variations of D as well as the distribution of the absorbed dose in linear energy transfer at the point of interest. (a) (2) Absorbed dose (D) means the average energy imparted by ionizing radiation to the matter in a volume element per unit mass of irradiated material. The absorbed dose is expressed in units of rad (or gray) (1 rad = 0.01 gray). (b) The special unit of absorbed dose is the rad, where 1 rad = 1 erg per gram. One Gy = 100 rad. The material of interest for absorbed dose (as used in this manual) is typically soft tissue or a phantom approximating soft tissue in composition, but may also include detector materials such as air, methane, silicon, or TLD chip. accident dosimetry Determination of high levels of deep absorbed dose resulting from uncontrolled conditions. accreditation The DOE process of granting accreditation based on onsite assessment against the DOELAP handbook (DOE 1986a) and dosimeter performance testing against the DOELAP standard (DOE 1986b). Accreditation must be updated every two years. air kerma-to-dose-equivalent The numerical quantity that relates the air kerma to the dose conversion factors equivalent at a specified depth in a phantom of specified geometry (Ck factors) and composition. Factors are a function of the photon energy and angular distribution. (a) This is the definition given by the International Commission on Radiation Units and Measurements in ICRU Report 51 Quantities and Units in Radiation Protection Dosimetry (ICRU 1993). It is also the definition used in ANSI/HPS N13.11-2009 American National Standard for Dosimetry - Personnel Dosimetry Performance - Criteria for Testing (HPS 2009). (b) This is the definition given by DOE in 10 CFR 835 (DOE 2007a). The DOE definition might better be characterized as “average absorbed dose” in the volume element or tissue of interest. In this manual, the term “absorbed dose” may used in a manner consistent with either the DOE or the ICRU definition. Issued: May 2010 PNL-MA-842: Glossary Supersedes: May 2010 Page v ALARA ALARA is an acronym for "As Low As is Reasonably Achievable," which is the approach to radiation protection to manage and control exposures (both individual and collective) to the work force and to the general public to as low as is reasonable, taking into account social, technical, economic, practical, and public policy considerations. ALARA is not a dose limit but a process which has the objective of attaining doses as far below the applicable limits of this part as is reasonably achievable. albedo effect As used in this document, the neutron dosimeter response caused by the moderating and backscattering properties of a phantom or the human thorax for neutron radiation. alpha radiation Alpha particles are defined as a helium nucleus with a plus-2 positive charge. ambient dose equivalent, H*(d) Denoted as H*(d) at a point in a radiation field is the dose equivalent that would be produced by the corresponding expanded and aligned field in the ICRU sphere at a depth, d, on the radius opposing the direction of the aligned field. The SI unit of ambient dose equivalent is joule per kilogram (J kg-1) and its special name is sievert (Sv). The special unit of ambient dose equivalent is rem. One sievert = 100 rem. Ambient dose equivalent is an operational quantity. angular response The response of a dosimeter or instrument as a function of the angle of incidence of radiation (where normal incidence is designated as zero degrees). The data may be normalized to the response at zero degrees. angular dependence Angular dependence of response (same meaning as angular response). background In the 10 CFR 835 definition, background means radiation from (i) naturally occurring radioactive materials which have not been technologically enhanced; (ii) cosmic sources; (iii) global fallout as it exists in the environment (such as from the testing of nuclear explosive devices); (iv) radon and its progeny in concentrations or levels existing in buildings or the environment which have not been elevated as a result of current or prior activities; and (v) consumer products containing nominal amounts of radioactive material, or producing nominal amounts of radiation. beta particle An electron or positron emitted from a nucleus during beta decay. beta radiation Radiation consisting of beta particles. bias, B The average of the performance quotients, Pi for n dosimeters, for a specified radiation category and test quantity n i=1 Pi B P = n Issued: May 2010 PNL-MA-842: Glossary Supersedes: May 2010 Page vi calibration Calibration means to adjust and/or determine either: (1) The response or reading of an instrument relative to a standard (e.g., primary, secondary, or tertiary) or to a series of conventionally true values; or (2) The strength of a radiation source relative to a standard (e.g., primary, secondary, or tertiary) or conventionally true value.
Load more

Recommended publications
  • Fucus Gardneri Using Gamma-Ray Spectroscopy
    Determination of 131I Uptake in Fucus Gardneri Using Gamma-Ray Spectroscopy Determination de 1'Accumulation de I dans Fucus Gardneri par Spectroscopie Gamma A thesis submitted to the Division of Graduate Studies of the Royal Military College of Canada By Kristine Margaret Mattson In Partial Fulfillment of the Requirements for the Degree of Master of Applied Science in Nuclear Engineering August 2011 © This thesis may be used within the Department of National Defence, but copyright for open publication remains the property of the author. Library and Archives Bibliotheque et Canada Archives Canada Published Heritage Direction du in Branch Patrimoine de I'edition 395 Wellington Street 395, rue Wellington Ottawa ON K1A 0N4 Ottawa ON K1A 0N4 Canada Canada Your file Votre reference ISBN: 978-0-494-83402-2 Our file Notre reference ISBN: 978-0-494-83402-2 NOTICE: AVIS: The author has granted a non­ L'auteur a accorde une licence non exclusive exclusive license allowing Library and permettant a la Bibliotheque et Archives Archives Canada to reproduce, Canada de reproduire, publier, archiver, publish, archive, preserve, conserve, sauvegarder, conserver, transmettre au public communicate to the public by par telecommunication ou par I'lnternet, preter, telecommunication or on the Internet, distribuer et vendre des theses partout dans le loan, distrbute and sell theses monde, a des fins commerciales ou autres, sur worldwide, for commercial or non­ support microforme, papier, electronique et/ou commercial purposes, in microform, autres formats. paper, electronic and/or any other formats. The author retains copyright L'auteur conserve la propriete du droit d'auteur ownership and moral rights in this et des droits moraux qui protege cette these.
    [Show full text]
  • UCSF Radiation Safety Training Manual
    ` UNIVERSITY OF CALIFORNIA, SAN FRANCISCO RADIATION SAFETY TRAINING MANUAL SEPTEMBER, 1996 This information is being provided in accordance with the following State requirements: CALIFORNIA RADIATION CONTROL REGULATIONS 17CAC30280(a) (1) Each user shall inform individuals working in or frequenting any portion of a controlled area as to the presence of sources of radiation; instruct such individuals in safety problems associated therewith and in precautions or procedures to minimize radiation exposure; and instruct such individuals in the provisions of department regulations and licenses applicable for the protection of personnel. RADIATION SAFETY TRAINING MANUAL TABLE OF CONTENTS SECTION DESCRIPTION PAGE INTRODUCTION 1 CHAPTER 1 PROPERTIES OF IONIZING RADIATION 2 A Structure of the Atom 2 B Atomic Nomenclature 3 C Beta Particles 3 D Radioactive Decay 5 E Gamma and X-rays 5 F Other Modes of Decay 7 G Bremsstrahlung - A Type of X-ray 7 CHAPTER 2 UNITS FOR MEASURING IONIZING RADIATION 8 A Roentgen: The Unit of Exposure 8 B Rad: The Unit of Absorbed Dose 8 C Rem: The Dose Equivalent Unit 9 D Curie: The Unit of Activity 9 CHAPTER 3 MAXIMUM PERMISSIBLE EXPOSURES 11 A Guidelines for Radiation Exposure 11 B Maximum Permissible Dose (MPD) 11 C How Does the MPD Compare with Other Sources of Radiation Exposure? 13 D What is the Risk at the MPD? 14 E Special Safeguards for Pregnant Women 16 CHAPTER 4 BIOLOGICAL EFFECTS OF RADIATION 20 A Somatic and Genetic Effects 20 B Increase in Cancer Incidence 21 C Genetic Damage 21 D Exposure of Unborn Children
    [Show full text]
  • Digital Radiation Meter
    Digital Radiation Meter 840024 Instruction Manual Digital Radiation Meter 840024 Copyright ©2011 by Sper Scientific ALL RIGHTS RESERVED Printed in the USA The contents of this manual may not be reproduced or transmitted in any form or by any means electronic, mechanical, or other means that do not yet exist or may be developed, including photocopying, recording, or any information storage and retrieval system without the express permission from Sper Scientific. 7720 E. Redfield Rd. Suite #7, Scottsdale, AZ 85260 Tel: (480) 948-4448 Fax: (480) 967-8736 Web: www.sperscientific.com - 2 - TABLE OF CONTENTS INTRODUCTION. 4 CAUTION . 5 KEYPAD . 6 OPERATING PROCEDURES . 7 METER SETUP . 8 ESTABLISHING BACKGROUND LEVELS . 10 AREA MONITORING . 11 CHECK SURFACE CONTAMINATION . 12 CHECK AN OBJECT . 14 MAINTENANCE AND CALIBRATION . 15 RADIATION AND RADIOACTIVITY . 17 SPECIFICATIONS . 21 WARRANTY . 23 NOTICE . 24 - 3 - INTRODUCTION This manual provides the necessary information for proper use and care of Sper Scientific Model 840024 Radiation Meter. We recommend reading this manual completely prior to using the instrument. It also contains valuable information about the nature of ionizing radiation that should be understood by the user so that accurate measurements can be made. This Radiation Meter features selectable measurement scales, adjustable audible alarm and auto power off. It uses a thin wall glass Geiger-Mueller (GM) tube that will detect Beta and Gamma ionizing radiation and X-rays. The GM tube generates an electrical pulse each time radiation passes through the tube. These pulses are then electronically detected and displayed in either SI units (micro-sieverts per hour) or conventional units (milliroentgens per hour).
    [Show full text]
  • VMAT Decontamination Standard Operating Procedure (2004)
    VMAT DECONTAMINATION STANDARD OPERATING PROCEDURE Completed April 2004; presented at the 2004 National Disaster Medical System Conference, Dallas TX. Authors and affiliations: • Camille DeClementi, VMD – ASPCA Animal Poison Control Center, Urbana IL • Eric K. Dunayer, MS, VMD – ASPCA Animal Poison Control Center, Urbana IL • Sharon Gwaltney-Brant, DVM, PhD, DABVT, DABT – ASPCA Animal Poison Control Center, Urbana IL • Mark Lloyd, DVM – VMAT Program Leadership Committee Chair and Deputy Team Commander VMAT-1, Department of Homeland Security, East Setauket NY • Lisa A. Murphy, VMD, DABT – VMAT-2, Department of Homeland Security and ASPCA Animal Poison Control Center, Urbana IL • Hany Youssef, BVs, DVM, MS – ASPCA Animal Poison Control Center, Urbana IL *Please direct correspondence and inquiries to Dr. Lisa Murphy at USDA-APHIS-VS, 160 Worcester-Providence Rd., Sutton MA 01590 OPERATING GUIDELINES • The following guidelines are to be used by the Veterinary Medical Assistance Teams (VMAT). These are basic procedures that may need to be modified depending on the nature of a specific mission involving decontamination of animals. • Safety of personnel will be of greatest importance in all decontamination missions. The goal is to protect the public, animals, property, and the environment without becoming part of the problem. • This document shall be reviewed and updated as needed, with dates reflecting the time of any changes. VMAT DECONTAMINATION TEAM ORGANIZATION • VMAT Decontamination (DECON) Team • The VMAT DECON team will function as a unit of VMAT when a mission involving the decontamination of animals has been identified. The team will be composed of VMAT team members that have met all required selection and training requirements.
    [Show full text]
  • Recommendations on Management of Radioactive Materials in Sewage Sludge and Ash at Publicly Owned Treatment Works
    United States United States Environmental DOE/EH-0668 Department of Energy Protection Agency EPA 832-R-03-002B Interagency Steering Committee on Radiation Standards Final Report ISCORS Assessment of Radioactivity in Sewage Sludge: Recommendations on Management of Radioactive Materials in Sewage Sludge and Ash at Publicly Owned Treatment Works ISCORS Technical Report 2004-04 This document resulted from interagency discussions. The Interagency Steering Committee on Radiation Standards, Sewage Sludge Subcommittee, is composed of representatives from the Environmental Protection Agency (EPA), Nuclear Regulatory Commission (NRC), Department of Energy, Department of Defense, State of New Jersey, the city of Cleveland and the county of Middlesex, New Jersey. This document has not been approved by the respective agencies and does not represent the official position of any participating agency at this time. ISCORS Assessment of Radioactivity in Sewage Sludge: Recommendations on Management of Radioactive Materials in Sewage Sludge and Ash at Publicly Owned Treatment Works Developed by the Sewage Sludge Subcommittee United States United States Nuclear United States Environmental Regulatory Department of Protection Commission Energy Agency State of New Jersey Middlesex County Northeast Ohio Department of Utilities Regional Environmental Authority Sewer District Protection ISCORS Technical Report 2004-04 Date Published: February 2005 ACKNOWLEDGMENTS The Sewage Sludge Subcommittee of the Federal Interagency Steering Committee on Radiation Standards (ISCORS) (1) conducted a survey to collect information concerning radioactive materials in sewage sludge and ash from Publicly Owned Treatment Works (POTWs), (2) performed dose modeling to help with the interpretation of the results of the survey, and (3) developed a guidance on radioactive materials in sewage sludge and ash for POTW owners and operators.
    [Show full text]
  • Study of a Position Sensing Gas Proportional Detector for Decommissioning
    University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Masters Theses Graduate School 5-2020 Study of a Position Sensing Gas Proportional Detector for Decommissioning Christopher Echterling University of Tennessee Follow this and additional works at: https://trace.tennessee.edu/utk_gradthes Recommended Citation Echterling, Christopher, "Study of a Position Sensing Gas Proportional Detector for Decommissioning. " Master's Thesis, University of Tennessee, 2020. https://trace.tennessee.edu/utk_gradthes/5597 This Thesis is brought to you for free and open access by the Graduate School at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Masters Theses by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. To the Graduate Council: I am submitting herewith a thesis written by Christopher Echterling entitled "Study of a Position Sensing Gas Proportional Detector for Decommissioning." I have examined the final electronic copy of this thesis for form and content and recommend that it be accepted in partial fulfillment of the requirements for the degree of Master of Science, with a major in Nuclear Engineering. Jason Hayward, Major Professor We have read this thesis and recommend its acceptance: Lawrence Heilbronn, Eric Lukosi Accepted for the Council: Dixie L. Thompson Vice Provost and Dean of the Graduate School (Original signatures are on file with official studentecor r ds.) Study of a Position Sensing Gas Proportional Detector for Decommissioning A Thesis Presented for the Master of Science Degree The University of Tennessee, Knoxville Christopher Echterling May 2020 ii Copyright © 2019 by Christopher Echterling All rights reserved.
    [Show full text]
  • HNF-55634 - Rev 00.Pdf
    RADIOLOGICAL DATE: Jan 27, 2015 By Janis D. Aardal at 4:31 pm, Jan 27, 2015 Approved for Public Release; Further Dissemination Unlimited HNF-55634 Revision 0 Hanford External Dosimetry Technical Basis Program Manual Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Contractor for the U.S. Department of Energy under Contract DE-AC06-09RL14728 P.O. Box 650 Richland, Washington 99352 Approved for Public Release; Further Dissemination Unlimited HNF-55634 Revision 0 Hanford External Dosimetry Technical Basis Program Manual Document Type: TR Program/Project: RSS R. L. Hill Mission Support Alliance Date Published January 2015 Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Contractor for the U.S. Department of Energy under Contract DE-AC06-09RL14728 P.O. Box 650 Richland, Washington 99352 By Janis D. Aardal at 4:32 pm, Jan 27, 2015 Release Approval Date Approved for Public Release; Further Dissemination Unlimited HNF-55634 Revision 0 TRADEMARK DISCLAIMER Reference herein to any specific commercial product, process, or service by tradename, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. This report has been reproduced from the best available copy. Printed in the United States of America HNF-55634 Revision 0 PREFACE The Hanford External Dosimetry Program (HEDP) provides support to the U.S. Department of Energy’s (DOE) Richland Operations Office (RL), Office of River Protection (ORP), and DOE contractor radiation protection organizations in determining doses-of-record from external sources of radiation.
    [Show full text]
  • Radiation Safety Manual
    Wayne State University Radiation Safety Manual Office of Environmental Health and Safety Radiation Safety-Health Physics 5425 Woodward, Suite 300 Detroit, Michigan 48202 www.oehs.wayne.edu Version 2.08 This is a controlled document. The Office of Environmental Health and Safety restricts routine distribution. Persons in possession of this document may have uncontrolled copies and should call OEHS for revision level status. (November 2017) EMERGENCY CONTACT INFORMATION Office of Environmental Health and Safety……………………………………………313-577-1200 Wayne State University Police Department………………………………………..….313-.577-2222 Radiation Emergency Response If this emergency involves a fire, explosion, or any other situation where your life or health is in immediate danger, evacuate the area and contact the WSU Police Department at 577- 2222 from a safe location. While on the phone with the police dispatcher, be sure to let them know: • The location of the emergency • The nature of the emergency • The types of hazardous materials involved (radiation, biohazards, or chemicals,) • Your name • Your current location Stay at the phone until help arrives. Emergency response personnel will want to make sure you are not injured, and may need your help to properly address the situation. DO NOT LEAVE THE AREA UNTIL HELP ARRIVES! If the situation permits, secure your radioactive and other hazardous material as best you can prior to evacuating the lab. Return radioactive material to the storage area, place hazardous liquids in spill trays or pans, and pour bleach on infectious material. Shut off any gas appliances, centrifuges, fume hoods, and other lab equipment. Close windows and doors as you are vacating the area.
    [Show full text]
  • Letter Re Examples of Local/Non-Agreement State Efforts
    1800 M Street, N.W. Morgan Lwis Washington, D.C. 20036-5869 &Bockius 202-467-7000 COUNSELORS AT LAW FaxL 202-467-7176 BY EMAIL AND HAND - DELIVERY Don Silverman 202-467-7502 dsilverman•,morqanlewis.com July 27, 2001 James Lieberman, Esq. Office of General Counsel U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Re: Examples of Local/Non-Agreement State Efforts to Regulate Atomic Energy Act Materials Dear Jim: In accordance with our prior conversations and in anticipation of the August 2 meeting between UniTech Services Group, Inc. (UniTech) representatives and the NRC of Staff, I am providing you with six copies of a brief summary containing examples regulatory requirements that have been imposed by local or non-Agreement State governments on radioactive material subject to the Nuclear Regulatory Commission's (NRC) exclusive regulatory authority under the Atomic Energy Act (AEA materials). The package also contains some relevant supporting reference materials. While these are not the only examples that could be identified, we believe that they are sufficient to demonstrate the nature of UniTech's concern and the need for corrective or clarifying action by the NRC. As you review the enclosed materials, please note that in each case the primary, if not exclusive, purpose of the regulation is to protect workers or the public from the radiation hazards of AEA materials. Local and non-Agreement State governments simply may not regulate in the preempted field, let alone in a manner that is more stringent than, and potentially in conflict with, NRC requirements. Philadelphia Washington New York Los Angeles Miami Harrisburg Pittsburgh Princeton I-WA/639357.1 London Brussels Frankfurt Tokyo )C.
    [Show full text]
  • Notice to Radioactive Materials
    Wayne State University Radiation Safety Manual Office of Environmental Health and Safety Radiation Safety-Health Physics 5425 Woodward, Suite 300 Detroit, Michigan 48202 www.oehs.wayne.edu Version 2.09 This is a controlled document. The Office of Environmental Health and Safety restricts routine distribution. Persons in possession of this document may have uncontrolled copies and should call OEHS for revision level status. (January 2021). EMERGENCY CONTACT INFORMATION Office of Environmental Health and Safety……………………………………………313-577-1200 Wayne State University Police Department………………………………………..….313-.577-2222 Radiation Emergency Response If this emergency involves a fire, explosion, or any other situation where your life or health is in immediate danger, evacuate the area and contact the WSU Police Department at 577- 2222 from a safe location. While on the phone with the police dispatcher, be sure to let them know: • The location of the emergency • The nature of the emergency • The types of hazardous materials involved (radiation, biohazards, or chemicals,) • Your name • Your current location Stay at the phone until help arrives. Emergency response personnel will want to make sure you are not injured, and may need your help to properly address the situation. DO NOT LEAVE THE AREA UNTIL HELP ARRIVES! If the situation permits, secure your radioactive and other hazardous material as best you can prior to evacuating the lab. Return radioactive material to the storage area, place hazardous liquids in spill trays or pans, and pour bleach on infectious material. Shut off any gas appliances, centrifuges, fume hoods, and other lab equipment. Close windows and doors as you are vacating the area.
    [Show full text]
  • Final Report: ISCORS Assessment of Radioactivity in Sewage Sludge
    Disclaimer - For assistance accessing this document or additional information, please contact [email protected]. United States United States Environmental DOE/EH-0668 Department of Energy Protection Agency EPA 832-R-03-002B Interagency Steering Committee on Radiation Standards Final Report ISCORS Assessment of Radioactivity in Sewage Sludge: Recommendations on Management of Radioactive Materials in Sewage Sludge and Ash at Publicly Owned Treatment Works ISCORS Technical Report 2004-04 This document resulted from interagency discussions. The Interagency Steering Committee on Radiation Standards, Sewage Sludge Subcommittee, is composed of representatives from the Environmental Protection Agency (EPA), Nuclear Regulatory Commission (NRC), Department of Energy, Department of Defense, State of New Jersey, the city of Cleveland and the county of Middlesex, New Jersey. This document has not been approved by the respective agencies and does not represent the official position of any participating agency at this time. ISCORS Assessment of Radioactivity in Sewage Sludge: Recommendations on Management of Radioactive Materials in Sewage Sludge and Ash at Publicly Owned Treatment Works Developed by the Sewage Sludge Subcommittee United States United States Nuclear United States Environmental Regulatory Department of Protection Commission Energy Agency State of New Jersey Middlesex County Northeast Ohio Department of Utilities Regional Environmental Authority Sewer District Protection ISCORS Technical Report 2004-04 Date Published: February 2005 ACKNOWLEDGMENTS The Sewage Sludge Subcommittee of the Federal Interagency Steering Committee on Radiation Standards (ISCORS) (1) conducted a survey to collect information concerning radioactive materials in sewage sludge and ash from Publicly Owned Treatment Works (POTWs), (2) performed dose modeling to help with the interpretation of the results of the survey, and (3) developed a guidance on radioactive materials in sewage sludge and ash for POTW owners and operators.
    [Show full text]
  • Rad Handbook
    Contents I. Foreword II. General Policies and Procedures 1.0 Introduction 1.1 General Policy Statement 1.2 Access to Records and Program Documents 1.3 ALARA Principle 2.0 Program Administration and Responsibilities 2.1 Administration 2.2 Radiation Safety Committee 2.3 Authorized Investigator and X-Ray Registrant Responsibilities 2.4 Radiation Worker Responsibilities 2.5 Office of Research Safety Services 3.0 University License and X-Ray Registrations 3.1 Illinois Department of Nuclear Safety 3.2 Broad-Scope License 3.3 Radioactive Materials in Human Subjects 3.4 X-Ray Registrations 4.0 Investigator Applications and Authorizations 4.1 General Information 4.2 Authorized User Qualifications 4.3 New Applications 4.4 Adding Radionuclides 4.5 Increases in Quantity of Radionuclides 4.6 Five Year Reviews 4.7 Irradiator Applications 5.0 Radiation Worker Registration and Personnel Dosimetry 5.1 Registration Requirement 5.2 New Radiation Worker Packet 5.3 Radiation Worker Registration Form 5.4 Training Videotape 5.5 Posted Radiation Worker List Requirement 5.6 Dosimetry Requirement 5.7 Types of Dosimeters 5.8 Minimum Reportable Doses 5.9 Control Dosimeters 5.10 Deep and Shallow Dose 5.11 Proper Use of Dosimeters 5.12 Instructions to Dosimetry Coordinators 5.12.1 Series Code 5.12.2 Wear Dates 5.12.3 Distributing Dosimeters 5.12.4 Collecting Dosimeters 5.12.5 Changes in Service 5.12.6 Temporary Dosimeters 5.12.7 Classes 5.12.8 Fees 5.12.9 Reports 6.0 Training 6.1 The Importance of Training 6.2 Authorized User or X-Ray Registrant Responsibilities 6.3 ORS Training Resources 7.0 Security, Theft, and Loss 8.0 Violations 8.1 IDNS Regulatory Penalties 8.2 Enforcement Actions for Items of Noncompliance III.
    [Show full text]