Trent University. Radiation Safety Program for Users

Transcription

1 Trent University Radiation Safety Program for Users

2 2 Emergency Procedures In case of a radioactive spill: 1. Notify everyone in the immediate vicinity and have them move away from the affected area. Do not let anyone leave the general area until they have been checked for contamination. Perform urgent first aid if necessary. 2. Inform Trent University Security ( ) of the incident. They will secure the affected area/room and put into action the Radioactive Incident Response Plan. 3. Inform the Radiation Safety Officer ( x7061) who will direct the clean-up and decontamination program. 4. If safety won t be compromised, confine the spill by covering it with absorbent material. A chemical spill kits are located in SC 132.1, DNA A 119, LHS C 261 and LHS D Once the hazard has been assessed by the RSO, begin decontamination procedures as outlined in this manual. If unsure of the hazard, BACK AWAY. Wait for the appropriate personnel to assist/direct the cleanup.

3 3 This manual is provided to assist you in maintaining high standards of safety practices and programs in adherence to the obligations of the Nuclear Safety and Control Act, the Regulations made under the Act and the conditions of Trent University s Consolidated Radioisotope Licence. It is required reading for persons who use radioactive materials or sources of ionizing radiation for teaching or research at Trent University. While written for employees, students are encouraged to read, and will be expected to work according to the procedures outlined in this handbook. This manual assumes that the reader is familiar with the Trent University Laboratory Safety Handbook. The Laboratory Safety Handbook is required reading for all employees who work in science laboratories at Trent University. Contact your supervisor or the Health and Safety Advisor, Office of Risk Management for more information. Please read this manual carefully. If you have any questions about how to undertake a task or project safely, contact your supervisor. The Radiation Safety Officer can also serve as an additional resource. We trust that this manual will help you to work safely and to develop effective radiation safety procedures. We welcome your recommendations to improve both this manual and Trent University s Radiation Safety Program. Our goal is a safe environment for everyone. Mr. R. Chris Williams, M.Sc. Radiation Safety Officer Trent University December 2001 Dr. Graham Taylor V.P. Academic, License Holder Revised April 5, 2007 January 2012 October, 2013

4 4 TABLE OF CONTENTS Emergency Procedures 2 Table of Contents 4 Definitions and Glossary 6 Measurement Units Conversion Table Introduction and Purpose Purpose of Manual Mandatory Reading Responsibilities and Liabilities Disclaimer Responsibility for Radiation Safety at Trent University Student Use of Radioisotopes Permit Users Permit Holders Responsibilities of the Radiation Safety Officer Training and Authorization Radiation Safety Training Application for Radioisotope Use Permits and Project Authorization Acquisition and Receiving Prescribed Substances and Equipment Receipt of Radioactive Prescribed Substances Inventory and Storage of Radioisotopes Transportation of Radioactive Materials Transfers of Radioactive Material General Work Procedures Radiation Surveys and Monitoring Dose Monitoring Program Contamination Monitoring Sealed Source Leak Testing Decontamination Procedures for Disposal of Radioactive Waste Short-lived Isotopes (half-life <150 days) Longer-lived Isotopes (half-life >150 days) X-Ray Sources and Other Radiation Emitting Devices X Ray devices Other Radiation Devices Radiation Incidents Spill Response Process Contaminated Areas and Equipment Personnel Monitoring and Decontamination Loss, Theft and Fire Reporting Requirements Project Termination 36

5 5 Appendices Appendix 1. Permit Holder Annual Report 37 Appendix 2. Application for Radioisotope Permit 38 Appendix 3. Trent University Radioisotope Use Permit 42 Appendix 4. Quick Reference: Regulatory Quantities for Typical Radionuclides 44 Appendix 5. Radionuclide Inventory Forms 45 Appendix 6. Sample Contamination Monitoring Results Log 46 Appendix 7. Decontamination Techniques for Areas and Equipment 47 Appendix 8. Termination of Radionuclide Use Form 48 DEFINITIONS AND GLOSSARY Absorbed dose (Da): Absorbed dose (Da) means the quotient, in gray (Gy) obtained by dividing the energy absorbed through exposure to radiation by the mass of the body

6 or part of the body that absorbs the radiation. 6 Action level: Action level is a specific dose of radiation or other parameter that, if reached, may indicate a loss of control on the part of the licensee s radiation protection program, and triggers a requirement for a specific action to be taken. ALARA: As Low As Reasonably Achievable. All doses must be kept below dose limits and as low as achievable, economic and social factors taken into account. This is the defining philosophy behind the radiation safety internationally and within the Radiation Safety Program at Trent University. ALI: Annual Level of Intake: An ALI is the activity of a radionuclide that taken by itself would result in an effective committed dose to Reference Man of 20 msv (the annual limit), or 200 msv dose equivalent to any tissue, whichever is more restrictive. Canadian Nuclear Safety Commission (CNSC): The federal regulatory agency for the use of radioactive substances in Canada. Device: For the purposes of this guide and the application form, a device is any piece of equipment designed to use a sealed source(s) with the sealed source(s) installed and for which a Device Certification has been issued by the CNSC. Diagnostic nuclear medicine: Administration of unsealed nuclear substances to humans for diagnostic purposes related to their health care. The processing of radiopharmaceuticals and laboratory studies which are part of the diagnostic studies are included. Dismantle: To take apart prescribed equipment for the purpose of repairing, replacing, removing faulty components which may include the nuclear substance of that device (part of the licensed activity of servicing, installation and dismantling of devices containing radioisotopes). Effective dose (De): De means the sum of the products, in sievert (Sv) obtained by multiplying the equivalent dose of radiation received by and committed to each organ or tissue by the weighting factor of that organ. (See Radiation Protection Regulations Schedule 1 for specific weighting factors). Equivalent dose (ed): ed means the product, in sievert (Sv) obtained by multiplying the absorbed dose of radiation of a specific type by a weighting factor for that type. (See Radiation Protection Regulations Schedule 2 for specific weighting factors). Exemption Quantity (EQ): An EQ is a quantity of a radioactive nuclear substance which may be possessed, used, stored, transferred etc... without a license. This is specifically defined in the Nuclear Substances and Radiation Devices Regulations. Examples of some EQ quantities for commonly used isotopes can be found in appendix 4. Export: to send a nuclear substance or prescribed equipment out of Canada.

7 7 Five-year dosimetry period: The period of five calendar years beginning on January 1 of the year following the year in which the CNSC Regulations come into force, and every period of five calendar years thereafter. Human research studies: Studies which involve the administration of unsealed nuclear substances to, or external irradiation of humans for purposes not related to their personal health care are defined as human research studies. The processing of radiopharmaceuticals and laboratory studies which are part of the human research study are also included. Import: to bring a nuclear substance or prescribed equipment into Canada. Licensed Activity: A licensed activity for the purpose of this safety manual means an activity, in relation to a nuclear substance or a radiation device described below, that a licence authorises the licensee to carry on: a) possess, transfer, import, export, use or abandon a nuclear substance, prescribed equipment or prescribed information; b) mine, produce, refine, convert, enrich, process, reprocess, package, transport, manage, store or dispose of a nuclear substance; or c) produce or service prescribed equipment. Licensed Use Type: A particular use of nuclear substances as described in the Cost Recovery Fees Regulations. Location: Any land, base(s) of operations, or premises the licensee occupies, where the licensee uses or stores nuclear substances for more than 90 consecutive days. Nuclear Energy Worker (NEW): A person who is required, in the course of the person s business or occupation in connection with a nuclear substance or nuclear facility, to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public. Nuclear Substance: (a) deuterium, thorium, uranium or an element with an atomic number greater than 92; (b) a derivative or compound of deuterium, thorium, uranium or of an element with an atomic number greater than 92; (c) a radioactive nuclide or atoms that disintegrate by emission of corpuscular or electromagnetic radiations; (d) a substance that is prescribed as being capable of releasing nuclear energy or as being required for the production or use of nuclear energy; (e) a radioactive by-product of the development, production, or use of nuclear energy; and

8 (f) 8 a radioactive substance or radioactive item that was used for the development or production of, or in connection with the use of, nuclear energy. One-year Dosimetry Period: The period of one calendar year beginning on January 1 of the year following the year in which these Regulations come into force, and every period of one calendar year thereafter is referred to as a one-year dosimetry period. Package: To put a nuclear substance or prescribed equipment into a form of containment for purposes of transport. Possess: To have the care and control of a nuclear substance or prescribed equipment. Radiation: The emission by a nuclear substance, the production using a nuclear substance, or the production at a nuclear facility of, an atomic or subatomic particle or electromagnetic wave with sufficient energy for ionization. Radiation Device: (a) a device that contains more than the exemption quantity of a nuclear substance and that enables the nuclear substance to be used for its radiation properties; and, (b) a device that contains a radium luminous compound.

9 Radiation Contamination Meter: An instrument that is capable of measuring the activity of radioisotopes (becquerels, cpm). Radiation Survey Meter: An instrument that is capable of measuring radiation dose rates (mrem/h or msv/h). Radioisotope: An isotope of an element which produces ionizing radiation. 9 Sealed Source: A radioactive nuclear substance in a sealed capsule or in a cover to which the substance is bonded, where the capsule or cover is strong enough to prevent contact with or the dispersion of the substance under the conditions for which the capsule or cover is designed. Source in Device: A sealed source which remains in a device giving mechanical protection from damage during use. Store: To lay away for future purposes. Therapeutic Nuclear Medicine: The administration of unsealed nuclear substances to humans for therapeutic purposes related to their health care; the processing of radio pharmaceuticals and laboratory studies which are part of the therapy are included. Transfer: To change the possession of a nuclear substance or prescribed equipment from one person to another. Transport: To handle, carry, store in transit, and receive goods at the final destination. Transport includes normal and accident conditions encountered in carriage and in storage during transit. Unsealed Source: A source other than a sealed source. Use: To put into operation. Worker: A person who performs an activity that is referred to in the licence.

10 Measurement Units Conversion Table 1. * 1 Bq = 1 disintegration/second The rad (rad) is replaced by the gray (Gy) 1 kilorad (Krad) = 10 grays (Gy) 1 rad (rad) = 10 milligrays (mgy) 1 millirad (mrad) = 10 micrograys ( Gy) 1 microrad ( rad) = 10 nanograys (ngy) The gray (Gy) replaces the rad (rad) 1 gray (Gy) = 100 rad (rad) 1 milligray (mgy) = 100 millirad (mrad) 1 microgray ( Gy) = 100 microrad ( rad) 1 nanogray (nngy) = 100 nanonrad (nrad) 10 The rem (rem) is replaced by the sievert (Sv) 1 kilorem (krem) = 10 sieverts (Sv) 1 rem (rem) = 10 millisieverts (msv) 1 millirem (mrem) = 10 microsieverts ( Sv) 1 microrem ( rem) = 10 nanonsieverts (nsv) The sievert (Sv) replaces the rem (rem) 1 sievert (Sv) = 100 rem (rem) 1 millisievert (msv) = 100 millirem (mrem) 1 microsievert ( Sv) = 100 microrem ( rem) 1 nanosievert (nsv) = 100 nanonrem (nrem) The curie (Ci) is replaced by the becquerel (Bq)* 1 kilocurie (kci) = 37 terabecquerels (TBq) 1 curie (Ci) = 37 gigabecquerels (GBq) 1 millicurie (mci) = 37 megabecquerels (MBq) 1 microcurie ( Ci) = 37 kilobecquerels (kbq) 1 nanocurie (nci) = 37 becquerels (nbq) The becquerel (Bq)* replaces the curie (Ci) 1 terabecquerel (TBq) = 27 curies (Ci) 1 gigabecquerel (GBq) = 27 millicuries (mci) 1 megabecquerel (MBq) = 27 microcuries ( Ci) 1 kilobecquerel (kbq) = 27 nanocuries (nci) 1 becquerel (Bq) = 27 picocuries (pci)

11 1.0 INTRODUCTION AND PURPOSE 11 Canadians are exposed to ionizing radiation every day from a variety of natural (cosmic rays, minerals) and man-made (medical, nuclear powerplants) sources. In Canada, we are exposed to an average of 0.3 msv 0.5 msv of cosmic radiation per year, 0.2 msv 2 msv per year from the earth s crust and radon depending on where you live and msv per year from isotopes of potassium and carbon which are in our bodies naturally. We call the sum of these doses the background radiation dose. Some areas of the world such as areas in Brazil and Kerala, India have times higher background dose levels. The most commonly asked question involving radiation is What is the safe level of radiation? A great deal of research has been done on this question. The prevailing opinion at present is that the risk of a deleterious effect due to radiation is a function of the dose. That is to say that the risk increases as the total accumulated dose increases. The dose due to radiation exposure is a function of the intensity of the exposure, the type of radiation (alpha particle, beta particle, gamma ray, x-ray, neutrons) and the length of time of the exposure. All these factors affect the total dose an individual may receive and thus affect the risk. We attempt to limit an individual s dose by limiting the intensity of the exposure through shielding, maintaining a suitable distance from the source and by limiting the time that people can be exposed to these sources of radiation. Experts use a linear non-threshold (LNT) model to estimate the risk. They assume that any exposure has some risk and that there is no level below which damage does not occurs. They also assume the effects at low doses are directly proportional to consequences at very high doses. All of this makes it sound like any exposure should be avoided at all costs. However, compared to other commonplace things that we do, the risk of death as a result of exposure to radiation is really quite small. For example, smoking 1.4 cigarettes in your life increases your chance of premature death by one in a million. Drinking one half litre of wine in your life increases your chance of premature death by one in a million. Living 1.5 years on a site boundary of a typical nuclear power plant increases your chance of premature death by one in a million (source: Readings in Risk, Eds. Glickman S.T. and Gough M., 1990). Many things that we do in our day to day lives can increase the risk of premature death by considerably more than one in a million. There is, however, a great deal of controversy regarding the LNT model. Many radiation protection experts would argue that the assumptions in this model are wrong and that there is a minimum limit of exposure at which biological effects occur. However, for the time-being the current regulatory policy is to use the LNT model as the basis for setting dose limits. The use of radioactive substances contributes greatly to many fields of scientific endeavour. However, any exposure to ionizing radiation has the potential to be a health hazard. Hazards from radiation may arise from exposure to external sources of radiation (such as X -rays, gamma rays or particles) or from the effects of radioactive materials taken into the body. Limiting the exposure of individuals to ionizing radiation can reduce the risk of cellular damage. It is particularly important that the people exposed to radiation on a regular basis during the course of their work are monitored to ensure that their exposure does not exceed what are considered to be safe levels. The Canadian Nuclear Safety Commision (CNSC) has granted Trent University a Consolidated Radioisotope Licence which allows Trent University to approve the use of certain radioisotopes

12 12 in teaching and research. The administration of this licence is the responsibility of the Radiation Safety Officer (RSO). The Radiation Safety Officer derives authority from, and is advisory to the Vice-President Research and International, who is the Applicant Authority. The Radiation Safety Officer authorizes and controls the use of radioactive materials or radiation-emitting devices by the issue of permits. Permits are granted only to qualified personnel or to Research Project Leaders with adequate experience. Permit Holders are responsible for ensuring that all activities undertaken under their authority are consistent with established procedures and the conditions of the Radioisotope Licence and their permit. The effectiveness of the Radiation Safety Program is monitored by the Radiation Safety Officer. The Radiation Safety Officer will conduct annual laboratory inspections and periodic spotchecks to ensure that appropriate safety precautions and procedures are in place. CNSC inspectors will also periodically conduct inspections of University facilities to ensure compliance with CNSC regulations and the conditions established by the University s Consolidated Radioisotope Licence. The purpose of Trent University s Radiation Safety Program is to ensure that the use of radioactive material in the pursuit of scientific knowledge does not constitute an unnecessary risk to Trent personnel, students and the public. 1.1 PURPOSE OF MANUAL The purpose of this manual is: to define radiation safety responsibilities and accountabilities within the University; to outline specific policies and procedures which may apply; and to outline basic emergency procedures. 1.2 MANDATORY READING Every employee working or intending to work with radioisotopes or radiation-emitting devices at Trent University must read this document. 1.3 RESPONSIBILITIES AND LIABILITIES Everyone actively engaged in the use of radioisotopes or radiation-emitting devices is legally responsible for safety performance. All personnel must meet the requirements of the Canadian Nuclear Safety Control Act and its associated regulations. It is expected that adherence to this manual is a good starting point for establishing an acceptable radiation safety program within each laboratory. More detailed and specific safety procedures and practices may be necessary and everyone is encouraged to develop and use practices which exceed the basic safety practices outlined in this manual. Any deviation from this manual should be toward safer practices. Everyone should be able to justify that reasonable care and deliberation has been exercised before the implementation of any

13 changes. By not adhering to the recommended practices in this manual or safer alternatives, individual liability may increase. Therefore, always take reasonable care to ensure that safety considerations are included in all work involving radioisotopes DISCLAIMER This manual is intended to provide basic guidelines and practices for safe work with radioisotopes or radiation-emitting devices. The procedures may be supplemented with safer work practices where applicable. This manual is by no means all encompassing and any omission is not an excuse for unsafe practices. In all cases the Permit Holder is ultimately responsible for establishing safe work practices and must insist on the use of such (proper procedures) in order to eliminate unnecessary hazards. The Permit Holder must identify and supplement this manual with safe procedures and training, specific to the needs of their radiation safety programs, when any subject area is not adequately covered by this manual.

14 2.0 RESPONSIBILITY FOR RADIATION SAFETY AT TRENT UNIVERSITY 14 Board of Governors President Vice-President Research and International (Applicant Authority as of March 1, 2012) Vice- President Academic and Provost Dean Of Arts and Science (Science) Research Fund Administration Principle Investigator Faculty Supervisor (Permit Holders) Permit Users Canadian Nuclear Safety Commission Students Science Facilities Manager RSO, BSO, LSO 2.1 STUDENT USE OF RADIOISOTOPES IN FORMAL CLASSROOM INSTRUCTION Permit Applicants who wish to have students use radioisotopes or radiation-emitting devices in formal graduate or undergraduate courses within a classroom setting at Trent University should include the name and title of the course under the category of Other Users when applying for a Permit. The application should include a description of the work to be performed by the student(s). Permit Holders and Permit Users are required to complete the Trent University Radiation Safety course before working with isotopes or radiation-emitting devices at Trent University. Students may be authorized to work under a valid permit without completing the Radiation Safety course if the following conditions are met: 1. The Permit Holder or a Designated Permit User, who is adequately trained in the safe handling of radioactive materials, provides formal radiation safety instruction to the students prior to the use of radioactive materials or radiation-emitting devices in class; and, 2. The students are directly supervised by the Permit Holder or a Designated Permit User during their initial work with radioactive materials or radiation-emitting devices until the supervisor is assured that they can work with the material safely and confidently. Directly supervised is defined as line of sight which means that the supervisor is essentially watching everything that the student is doing; and, 3. The use of radioactive materials or radiation-emitting devices is consistent with the conditions authorized by the permit and will only occur in an authorized teaching space

15 listed on the approved permit. 15 This does not include the use of radioactive material or devices containing radioactive material or which emit radiation except in a formal class room teaching setting in a course approved by the Senate of Trent University. Honours Thesis projects are considered Research for the purposes of this program and Honours thesis students must take the Radiation Safety Course. 2.2 RESEARCH USE OF RADIOACTIVE MATERIAL: PERMIT USERS Permit Holders may wish to name students, technical assistants or university employees as Permit Users who would be authorized to use the radioisotopes or radiation-emitting devices obtained under their permit. Individuals named as Permit Users on permit applications are required to complete the Trent University Radiation Safety course as a condition of approval as a Permit User. Permit Users are responsible for complying with the procedures and precautions contained within the radioisotope licence, the permit, this manual and any additional instruction or precautions provided by the Permit Holder. Every Permit User is required to comply with the Canadian Nuclear Safety Act, its regulations and licence conditions. 2.3 RESEARCH USE OF RADIOACTIVE MATERIAL: PERMIT HOLDERS Permit Holders are: a) qualified university personnel in academic departments/programmes that offer courses involving experimental/instructional work with radioisotopes or radiation-emitting devices; or, b) qualified research project leaders who require the use of radioisotopes or radiationemitting devices for their research, who have applied for and received authorization for work involving radioisotopes or radiationemitting devices from the Radiation Safety Officer. Authorization is granted in the form of a radioisotope permit issued to the Permit Holder by the Radiation Safety Officer. Permit Holders are responsible for the safe use of those radioisotopes and radiation-emitting devices authorized by their permit. Permit Holders should be familiar with established radiation safety procedures including the conditions established by the Trent University Radioisotope Licence, their Permit, and by this manual. All Permit Holders are required to complete the Trent University Radiation Safety Course. The responsibilities of Permit Holders include: a) ensuring that the required facilities, equipment and instruments are available for controlling radiation hazards, b) ensuring that students and Permit Users receive the supervision and instruction necessary

16 16 for controlling radiation hazards, c) ensuring that radioactive materials are stored or handled only in locations authorized by the Permit, d) ensuring that the project does not exceed the allotment of radioactive materials authorized by the Permit, e) ensuring that a complete and accurate inventory of radioisotopes is maintained at all times, f) ensuring that a complete and accurate record of all disposed radioactive materials is maintained at all times, and the records are maintained for at least three (3) years, g) ensuring that only authorized persons have access to radioactive materials, h) ensuring that licences, permits, warning signs and labels are posted as required by the Radioisotope Licence, the Permit and this Manual, i) establishing routine laboratory procedures to ensure that: 1) external radiation levels are monitored and maintained within permissible limits, 2) a suitable form of contamination monitoring is undertaken on a regular basis and records are maintained of the results of contamination monitoring for at least three (3) years as per the procedures in this manual. 3) radiation sources are properly labelled and stored, and, 4) experiments that will be in progress after normal working hours will be properly attended, j) ensuring that Students and Permit Users wear Thermoluminescent detectors (TLD) or pocket dosimeters if required by the Permit; k) ensuring that all radiation incidents are reported to the Radiation Safety Officer. l) ensuring that radioisotopes or radiation-emitting devices are only shipped or transported from Trent University with the approval of the Radiation Safety Officer and in compliance with the Transportation of Dangerous Goods Act and the CNSC Transport and Packaging Regulations. m) ensuring that an annual report is completed and submitted to the Radiation Safety Officer within 14 days of the end of each calendar year or at the end of the project. This annual report shall take the form of that shown in Appendix RESPONSIBILITIES OF THE RADIATION SAFETY OFFICER The Radiation Safety Officer (RSO) derives authority from and is advisory to the Vice-President Resarch and International of Trent University, who is the applicant authority for the radioisotope licence issued to Trent University by the Canadian Nuclear Safety Commission. The RSO is responsible for co-ordinating and controlling all activities at the University related to radiation safety. The RSO has the following authority: a) to authorize and control, by the issue of permits, the use of radiation-emitting materials and devices within the limits of the relevant consolidated or individual licences issued by the CNSC and the X-ray regulations made under the Occupational Health and Safety Act, b) to suspend the use, at Trent University, of radiation-emitting materials and devices,

17 17 regardless of any other source of authorization, c) to produce and continually review Trent University Radiation Safety Policy and Procedures, d) to organize and administer a campus-wide radioactive waste collection and disposal service in accordance with established procedures as per the Trent University Radioactive Waste Management System RSO SOP. e) to ensure that each incident involving spills of more than 100 E.Q.. of a radioisotope or exposure to greater than permissable doses of radiation are evaluated to determine whether decontamination procedures and/or medical examination should be carried out; and to advise the CNSC of such incidents as required, f) to ascertain the requirements for personnel monitoring, approve the use of radiation detection instruments, and administer a centralized TLD and neutron monitor record keeping system, g) to approve according to CNSC standards, all proposed radiation laboratories, h) supervise the leak testing of all large sealed sources as required by CNSC regulations, i) to ensure that general advice on radiation hazards and protection is available to Permit Holders, j) to present an annual report of the Radiation Safety Programme, to the Joint Health and Safety Committee, the Vice-President (Academic) and the CNSC, k) to conduct formal inspections and periodic spot-checks of laboratories and approved radioisotope locations to ensure compliance with permit conditions, licence conditions, Radiation Safety Manual procedures and policies, and CNSC Regulations. An inspection checklist shall be used which covers areas of Personnel, Dosimetry, Handling and Contamination Control, Security Signage Inventory and Disposal,. This form reflects the requirements of the GN, NS, RP regulations and NSC act. l) to maintain files on all active projects. These shall include inventories of all radioactive sources under a Permit Holder s control. Such files shall be considered active until all of the radioactive sources have been accounted for, either by disposal or by safe storage; m) to give final approval of all purchase orders for radioactive materials or radiationemitting devices in accordance with the specifications of authorized projects; n) to advise local Fire Department authorities of locations where radioactive materials are stored or used; o) to serve as the CNSC s contact on licencing matters. The RSO will be responsible for providing the CNSC with all information required for maintenance and renewal of the consolidated radioisotope licence. p) The RSO shall make any and all reports to the CNSC as defined and required by the Canadian Nuclear Safety Act section 27, the General Nuclear Safety Regulations Sections 15 and 29, Radiation Protection Regulations Sections 15, 16, and 17, Nuclear Substance and Radiation Devices Regulations (section 38) and the Packaging and Transportation regulations Sections 19 and 20. q) In the event of personnel contamination, from a spill exceeding 110 exemption quantities of an isotope the RSO will inform the CNSC of the incident as per Section 16 of the Radiation Protection Regulations and as per CNSC Info-0743, Spills Procedures.

18 3.0 TRAINING AND AUTHORIZATION 3.1 RADIATION SAFETY TRAINING 18 All personnel who may be exposed to ionizing radiation as a result of their employment must be instructed in advance regarding related radiation hazards and appropriate radiation safety procedures. Permit Holders and Permit Users are required to complete the Trent University Radiation Safety Course before they will be authorized to work with radioactive materials or radiation-emitting devices at Trent University. In addition, Permit Holders and Permit Users are required to retrain every three years. Customized radiation safety courses are offered by the Radiation Safety Officer (RSO) through the Office of the Dean of Arts and Science (Science). They follow the CNSC regulatory guides: Radiation Safety in Educational, Medical and Research Institutions, and Radiation Safety Training for Radioisotope, Medical Accelerator and Transportation Workers (Regulatory Guide G-121, C-200 E). The RSO will issue Radiation Safety Course certificates to applicants who have successfully completed the Radiation Safety Course. Records of the names of all people who have completed the Radiation Safety Course will be kept on file by the RSO. For more information, or to register for the Radiation Safety Course contact Chris Williams at ext. 7061, CWilliams@Trentu.ca or visit the Laboratory Safety Page. 3.2 APPLICATION FOR RADIOISOTOPE USE PERMITS AND PROJECT AUTHORIZATION Prior to possessing or using radioactive material or radiation-emitting devices, authorization must be obtained from the Radiation Safety Officer. Qualified Applicants (see Section 2.3, Permit Holders) may complete an Application for Radioisotope Permit and forward the application to the Radiation Safety Officer. A copy of the application form is illustrated in Appendix 2. Research projects which will be using open sources are also required to submit a radiation contamination monitoring plan which includes a map of the room in which the work will be performed, radioactive work areas and monitoring locations (see Contamination Monitoring Section 6.1.3). When approved, the application will be assigned a number and a permit will be returned to the applicant (Appendix 3). The conditions of approval will be indicated on the permit. The Radiation Safety Program at Trent requires that work with radioactive substances or equipment must be authorized. Work with radioisotopes of quantities less than the EQ are exempt from the authorization process provided the total quantity of isotope purchased throughout a year is less than 3 EQ and that the possession limit of 1 EQ is not exceeded. An Exemption Quantity (E.Q.) is the quantity listed in Schedule 1, Part 1, of the Canadian Nuclear Safety Commission Regulations. Sources less than exempt quantities are licence exempt according to the Regulations. Exempt quantities for some commonly used radioisotopes can be found in Appendix 4. The quantity and radiotoxicity of radioactive material required relative to the Annual Limit on Intake (ALI) (Appendix 4) determine the manner in which approval is given: a) for unsealed radioisotopes where the quantity does not exceed 5 ALI for the isotope listed

19 19 in Column 1 of Appendix 3, immediate conditional approval may be given. b) for unsealed radioisotopes where the quantity will exceed 5 ALI, written approval must be obtained from the CNSC through the RSO. c) sealed sources or radiation devices containing sealed sources or radiation emitting devices will be assessed on a case by case basis and may require CNSC approval. If any changes are to be made to a previously authorized project, the Permit Holder must apply in writing to the Radiation Safety Officer for an amendment to the project prior to instituting the changes. Permits are normally valid for one year. Permit Holders are required to submit to the Radiation Safety Officer a brief summary of their work over the past year involving radioisotopes (see section 2.3 and Appendix 1). The summary should include, the amount of radioisotopes purchased, a brief description of the work performed and, if they are continuing their work, a brief description of what they anticipate they will be doing over the next year (this is not an extensive description but rather a summary). Permit Holders who wish to renew their permit for another year should contact the Radiation Safety Officer by the end of November of each year. 4.0 ACQUISITION AND RECEIVING RADIOACTIVE SUBSTANCES AND EQUIPMENT All acquisitions of radioactive material must be authorized by the Radiation Safety Officer. Vendors of radioactive prescribed substances and equipment require a letter of authorization from the Radiation Safety Officer at the University prior to fulfilling any request to purchase. Only CNSC certified equipment may be purchased and used in Canada. Permit Holders who wish to purchase radioisotopes are required to inform the RSO prior to placing the order for the substance. Upon receipt of the order a copy of the packing slip indicating the supplier, the activity, and the name of the person who placed the order, must be given to the RSO within 2 days. Failure to do so will result in a loss of ordering privileges. Only Permit Holders are permitted to purchase radioactive prescribed substances. A Permit Holder may delegate this responsibility to a Permit User provided that the individual has been sufficiently trained, and this delegation is in writing with a copy of the letter to be sent to the RSO. All purchase requests should be consistent with the conditions of the Permit. Purchase requests that are consistent with the Permits will be authorized without delay. The Radiation Safety Officer will contact Permit Holders to discuss and clarify purchase requests that are inconsistent with the conditions of the permits. Ongoing, regular purchases of radioisotopes may be authorized in advance through the RSO. Contact the RSO for more information. Permit Holders must ensure that the purchase of any new radioactive substance will not result in an increase the amount of material possessed such that the possession limits of the permit are exceeded. This can result when orders are placed in advance of using up all the existing stock. Radioactive materials may not be assigned or transferred to the possession of any unauthorized person, nor used for any purpose in any place other than that originally authorized, without prior approval of the RSO.

20 RECEIPT OF RADIOACTIVE SUBSTANCES The procedure for receiving packages is outlined in the Information Document Radioisotope Safety Identifying and Opening Radioactive Packages (INFO-0426/Revision 1). This poster can be obtained from the RSO. The recommended procedure for opening packages which contain unsealed radioactive material is as follows: 1. Wear a lab coat and disposable gloves while handling the package. 2. If an appropriate survey meter is available, monitor the radiation fields around the package and compare with the units stated on the package. Note any discrepancies. 3. If the material is volatile (unbound iodine, tritium, radioactive gases, etc) or in powder form, place the package in a fume hood. 4. Open the outer package and check for possible damage to the contents, broken seals or discoloration of packing materials. If the contents appear to be damaged, isolate the package to prevent further contamination and notify the RSO. 5. If no damage is evident, remove the inner package or primary container, check for damage and wipe test the container. If contamination is detected, monitor all packaging and if appropriate, all areas coming into contact with the package for contamination. Contain the contamination, decontaminate and dipose in accordance with the conditions of the radioisotope licence. 6. Avoid unnecessary direct contact with unshielded containers. 7. Verify the radioisotope, the activity, and other details with the information on the packing slip and with the purchase order. Log the radioisotope, activity, date received and any anomalies in the inventory record. 8. Report all anomalies (radiation levels in excess of the package labelling, incorrect transport index, contamination, leakage, short or wrong shipment) to the project supervisor or RSO. Note: The Transportation of Dangerous Goods Act requires that all persons, shipping or receiving radioactive substances be certified under the act. Contact the RSO for details. 5.0 INVENTORY AND STORAGE OF RADIOISOTOPES Permit Holders are required to establish cradle-to-grave documentation for all radioisotopes acquired under their permit. Cradle to grave means that documentation exists which tracks the substance from the time it arrives on-site, through all aspects of its use and up to and including its final disposal. Records of all radioisotope purchases and inventories must be maintained upto-date and available for inspection in the areas where the radioisotopes are used or stored. Each inventory should be able to trace each container or source from the date and location of delivery to the date and location of disposal or transfer. A recommended format for inventory records is presented in Appendix 5. Permit Holders should establish procedures that are in keeping with the ALARA Principle: When using or storing radioisotopes or radiation-emitting devices radiation exposure/dose must be kept As Low As Reasonably Achievable. At a minimum the following directions must be followed.

21 Permit Holders shall: 21 a) ensure that when in storage radioactive nuclear substances or radiation devices are accessible only to authorized personnel, b) ensure that the dose rate at any occupied location outside the storage area, room or enclosure resulting from the substances or devices in storage does not exceed 2.5 Sv/h, and c) have measures in place to ensure that the dose limits in the Radiation Protection Regulations are not exceeded as a result of the substances or devices in storage. Radioactive material shall be kept or stored in a manner that: a) provides adequate radiation shielding recognizing the ALARA (As Low As Reasonably Achievable) principle; and b) provides adequate protection against theft, fire, explosion, flooding or accidental breakage of primary storage containers. c) provides that rooms that contain radioactive material shall remain locked when the room is not occupied. Every Permit Holder who stores a nuclear substance shall post and keep posted, in a readily visible location at the place where the nuclear substance is stored, a legible sign that indicates that, in case of emergency, contact the security office at Security has the protocol for initiating the accident procedure. More information on how to meet the requirement to keep all exposures as low as reasonably achievable can be obtained from the CNSC Regulatory Guide G129(e). 5.1 TRANSPORTATION OF RADIOACTIVE MATERIALS The packaging and labelling of radioactive shipments are governed by the CNSC s Packaging and Transport of Nuclear Substances Regulations and Transportation Dangerous Goods Act. No radioactive materials shall be shipped or transported from Trent University without the written authorization of the RSO. Contact the RSO, for more information. In-house transportation of radioactive materials requires that the material be placed on a cart or other device to either increase the distance between the user and the material or ensure appropriate levels of shielding are present in order to minimize the radiation exposure. 5.2 Transfer of Radioactive Material Transfers of radioactive material are not permitted between internal permit holders without the express written consent of the RSO. The RSO will examine, the purpose of the transfer, inventory records, validity of request, urgency and ensure that the recipient

22 22 of the transfer has a valid permit and the controls in place in advance of authorizing the transfer. Transfers of radioactive material for use externally to Trent university are rare, but when they come up, again express written authorization by the RSO is required. The RSO will ensure that the recipient s RSO is made aware of the request, that the recipient is authorized to possess, use and dispose of the material, and that all packaging and transport regulations are met prior to authorizing the transfer. The RSO will also ensure that internal inventories are updated and that there is written documentation from the recipient that they accept the transfer. 6.0 GENERAL WORK PROCEDURES The following guidelines for working with radioisotopes must be followed. a) Radioactive materials or radiation-emitting devices shall only be used by persons authorized by the RSO and identified in a permit or a list of qualified, trained personnel. This list shall be posted in the radiation work area. b) Radioactive materials or radiation-emitting devices shall only be used in those radioisotope laboratories authorized by the RSO and identified by a permit. c) A copy of the permit shall be posted in every radioisotope laboratory. d) A copy of the Trent University Radioisotope Licence shall be posted in every radioisotope laboratory. e) A copy of the Radiation Safety Manual shall be available to all persons who work with radioisotopes or radiation-emitting devices. f) An up-to-date inventory of all radioactive materials shall be maintained at all times. The quantity of radioactive material used or stored in a laboratory shall not exceed that specified on the radioisotope permit issued by the RSO. g) Radiation surveys and monitoring shall be undertaken and records maintained as outlined in section 6.1. h) A suitable radiation monitor should be available during the course of work with ionizing radiation. i) Disposal of radioactive wastes shall be undertaken and records maintained as outlined in section 7.0. j) Permit Holders are required to complete and submit an annual report (appendix 1) to the RSO within 14 days of the end of the calendar year. k) All laboratories approved for radioactive work will display the required information and notification posters. As part of the permitting process, signage is required on all labs which contain radioactive material that states Rayonnement Danger- Radiation and the 24 hr Campus Security emergency phone number (It also contains the trefoil symbol). All labs are required to post this sign on the outer door to a lab In addition all basic labs must post the INFO , INFO -0744, INFO-0743 posters in the lab. These will be supplied to them (this is stated specifically on the permit issued to the permit holder. Signage will be checked as part of the inspection process.

23 Classification of rooms: 23 1) basic-level if the quantity does not exceed 5 ALI, 2) intermediate-level if the quantity used does not exceed 50 ALI, 3) high-level if the quantity does not exceed 500 ALI, 4) containment-level if the quantity exceeds 500 ALI, or 5) special purpose if approved in writing by the Commission or a person authorized by the Commission. l) All laboratories in which radiation emitting substances are present shall have posted at each entrance to that laboratory a sign with the radiation warning symbol (trefoil) and the words Radioactive Laboratory. m) Cupboards, cabinets, refrigerators and other containers used to store active materials in the radioisotope laboratory must be identified with a radiation warning label. n) Primary storage containers must be identified with a radiation warning symbol and the words Radioactive and information regarding the name, quantity, date of measurement and the form of the nuclear substance contained within. Labelling is not required for temporary use of the containers within. Labelling is not required for containers such as beakers, flasks and test tubes which are used temporarily while the responsible individual is present. o) All equipment containing radioactive isotope sources must be identified with a radiation warning symbol and a notice saying DO NOT MOVE - CNSC Licence permits use of this equipment only in Room #. Any change in location must be approved in advance by the Radiation Safety Officer. p) Appropriate radiation warning labels are required on all X-ray and other ionizing radiation-producing devices. q) There shall be no smoking, eating, drinking or storage of food in any area containing radioactive material. r) There shall be no mouth pipetting of solutions. s) Whenever practical, the user should perform a trial experiment using stable or low activity material to establish the adequacy of the procedures and equipment. t) Before the start of an operation on a source of radioactive material, radiation levels will be measured. Handling tongs or a suitable remote handling device must be used for handling any source or container which emits, at contact, a dose rate in excess of 2 msv/hr. u) In the course of operations that might produce airborne contamination (eg. boiling, evaporating, sanding or grinding), work shall be carried out in a fume hood. v) A glove box shall be used for work involving exemption quantities or more, of dry radioactive powdered material. w) When hand or clothing contamination is possible, protective gloves and clothing shall be worn; employees should not work with radioactive materials if they have open cuts or abrasions. x) After handling open radioactive material, hands shall be washed before leaving the laboratory and clothes, shoes and hands shall be monitored for contamination. y) Whenever possible, work with radioactive material should be carried out in trays lined with disposable absorbent material;

24 24 z) Objects and equipment used in work with radioactive material should not be used for other purposes and must be surveyed for contamination prior to removal from the laboratory. aa) Containers used for storage of radioactive waste (solid and liquid) shall be labelled with the radiation warning symbol and the words Radioactive Waste- Caution 6.1 RADIATION SURVEYS AND MONITORING Exposure Levels: Every Permit Holder shall implement a radiation protection program and shall, as part of that program; a) keep the amount of exposure to ionizing radiation at the lowest reasonable level (ALARA) through the implementation of; i) management control over work practices, ii) personnel qualification and training, iii) control of occupational and public exposure to radiation, and iv) planning for unusual situations; and b) ascertain the quantity and concentration of any nuclear substance released as a result of the licensed activity; i) by direct measurement as a result of monitoring, or ii) if the time and resources required for direct measurement as a result of monitoring outweigh the usefulness of ascertaining the quantity and concentration using that method, by estimating them. To accomplish this each Permit holder should establish appropriate dose monitoring and contamination monitoring programs as well as emergency procedures for their lab Dose Monitoring Programs: (CNSC Radiation Protection Regulations) Dose monitoring programs are used to determine the effective and equivalent dose as a result of exposure to ionizing radiation. Permit holders shall establish proper dose monitoring procedures which will be capable of ensuring that the Trent limits (Table 2, column 4) are measurable. If the use of a dosimetry service is determined as the best method of ensuring this, it should be coordinated through the RSO. If a dosimetry service is deemed impractical then recording direct measurement of doses through the use of a calibrated dose rate meter is acceptable. A dosimetry service is mandatory for those operations where an individual has a reasonable chance of receiving an effective dose of 5 msv per year. It is recommended that for classes or projects where exposure to ionizing radiation will occur over an extended period of time (months-years) a dosimetry service be used. Dosimetry services must be certified by the CNSC. The exposure from sources of radiation shall normally be controlled in such a way as to provide assurance that no individual or user, except a Nuclear Energy Worker (NEW), shall receive an