DOE-HDBK-1130-98 Chg Notice 2, Radiological Worker Training

NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-98 October 1998 Change Notice No. 1 June 2001 Change Notice No. 2 December 2003 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice No. 1 DOE-HDBK-1130-98 June 2001 Radiological Worker Training An attachment to the Handbook was omitted. The same attachment is included in DOE-HDBK- 1131-98, General Employee Radiological Training. Accordingly, the reference in DOE-HDBK- 1130-98 will be changed to refer to the attachment included in DOE-HDBK-1131-98. Page/Section Change Part 1 of 3 Program Management Guide p. 16 / Evaluating Training Program Effectiveness Change last sentence of section to read: These guidelines are included as an attachment to the Program Management Guide to DOE-HDBK- 1131-98, General Employee Radiological Training. Change Notice No 2. DOE-HDBK-1130-98 December 2003 Page Change Cover Change Metric to Not Measurement Sensitive. iii Correct technical standards website address to: http://tis.eh.doe.gov/techstds/. Change "WordPerfect 8.0" to "WordPerfect 9.0". v of Program Management Guide Delete reference to Attachment 2 of Program Management Guide Organizational Relationships and Reporting Structure Change DOE Office of Worker Protection Programs and Hazards Management (DOE EH-52) to DOE Office of Worker Protection Policy and Programs (DOE EH-52). 16 of Program Management Guide Training Program Development/Change Requests Revise: All requests for program changes and revisions should be submitted to EH-52 using the DOE Technical Standard Program form “Document Improvement Proposal” F 1300.3. This form is available from the DOE Technical Standards Home Page - Maintenance of DOE Technical Standards TSPP-09). (See the Foreword of this document for website address). 19 of Program Management Guide Change - U.S. Department of Energy, Order 5480.20A, “Personnel Selection, Qualification, and Training Requirements For DOE Nuclear Facilities,” November, 1994. To - U.S. Department of Energy, Order 5480.20A, Ch. 1, “Personnel Selection, Qualification, and Training Requirements For DOE Nuclear Facilities,” 2001. 38 of Instructor's Guide 30 of Student’s Guide 1.b.2 Change - the DOE Radiological Control Technical Standards To - the DOE Radiological Control Technical Standard DOE-HDBK-1130-98 iii Foreword This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance.

This Handbook contains recommended training materials consistent with other DOE core radiological training materials. The training material consists of the following documents: Program Management Guide - This document contains detailed information on how to use the Handbook material. Instructor’s Guide - This document contains a lesson plan for instructor use, including notation of key points for inclusion of facility-specific information. Student’s Guide - This document contains student handout material and also should be augmented by facility-specific information. Please note that the Student Guide is not included in this draft document because the text is essentially a duplicate of the Instructor Guide without the instructor notes. The Student Guide will however, be included in the final version. This Handbook was produced in WordPerfect 9.0 and has been formatted for printing on an HP 4M (or higher) LaserJet printer. Copies of this Handbook may be obtained from either the DOE Radiation Safety Training Home Page Internet site (http://tis-nt.eh.doe.gov/wpphm/rst/rst.html) or the DOE Technical Standards Program Internet site (http://tis.eh.doe.gov/techstds/). Documents downloaded from the DOE Radiation Safety Training Home Page Internet site may be manipulated using the software noted above. DOE-HDBK-1130-98 iv This page intentionally left blank DOE-HDBK-1130-98 Part 1 of 3 Radiological Worker Training Program Management Guide Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1130-98 This page intentionally left blank. ii DOE-HDBK-1130-98 iii Course Developers Christine Liner Savannah River Site (Development Chairperson) Al Reeder Lockheed Martin Energy Systems Carolyn Owen Lawrence Livermore National Laboratory Dean Atchinson Brookhaven National Laboratory Brent Pearson Coleman Industries Roland Jean Sandia National Laboratories Karin Jessen Lockheed Martin Energy Systems Course Reviewers Technical Standards Managers U.S. Department of Energy Peter O’Connell U.S. Department of Energy Randy Sullivan ATL International, Inc. William Ulicny ATL International, Inc. We would also like to take this opportunity to recognize several individuals who provided significant contributions in developing previous revisions to DOE Radiological Worker Training material. Vicki Bogan Savannah River Site (Former) Michael Sanders Savannah River Site (Former) Pete Seilheimer Hanford Site Cindy Caldwell Hanford Site Chris Lesperance Hanford Site Gerald Eaton Hanford Site Doug Gabbard Fernald Environmental Restoration Management Company Rocky Barnum Pacific Northwest National Laboratory Thomas Clawson Idaho National Engineering and Environmental Laboratory Roger Raymond Idaho National Engineering and Environmental Laboratory Kathleen McIntyre Brookhaven National Laboratory Jim Allen Stanford Linear Accelerator Center Paula Trinoskey Lawrence Livermore National Laboratory DOE-HDBK-1130-98 iv This page intentionally left blank. DOE-HDBK-1130-98 v Table of Contents Page Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Purpose and Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Compliance with 10 CFR 835-Subpart J . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Goal of Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Organizational Relationships and Reporting Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

Training Program Descriptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Overview of Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Description of Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Radiological Fundamentals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Biological Effects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Radiation Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 ALARA Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Personnel Monitoring Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Radiological Access Controls and Postings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Radiological Emergencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Practical Factors for RW I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 High /Very High Radiation Area Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Practical Factors for High Radiation Areas . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Radiological Worker II . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Radioactive Contamination Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Practical Factors for RW II . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Specialized Radiological Worker Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Refresher Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Proficiency Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Retraining . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Instructor Training and Qualifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Training Program Material Development . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Training Material Presentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Training Certificates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Training Aids . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

Training Program Standards and Policies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Training Examinations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Lectures, Seminars, Training Exercises, etc. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 Delinquent Training/Failure Procedures and Policies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Exceptions and Waivers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Administration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Training Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Training Program Development/Change Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Audits (internal and external) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Evaluating Training Program Effectiveness . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 DOE-HDBK-1130-98 vi This page intentionally left blank. DOE-HDBK-1130-98 1 Introduction Purpose and Scope This guide describes the DOE Radiological Worker I and II (RW I and II) training programs. It includes standards and policies as well as recommendations for material development and program administration. It is intended for use by DOE contractors for the development of facility-specific radiological worker training. Compliance with 10 CFR 835-Subpart J The DOE core training materials for RW Training reflect the requirements identified in 10 CFR 835-Subpart J, “Radiation Safety Training” and recommendations identified in the DOE Implementation Guide G441.12, Radiation Safety Training, and in the DOE Radiological Control Technical Standard. When implemented in its entirety and supplemented as noted with appropriate facility-specific information, this handbook will generally meet the requirements of 10 CFR 835-Subpart J for radiological worker training. However, it is incumbent on management of each facility to review the content of this course against the radiological hazards present to ensure that the training content is appropriate to each individual’s prior training, anticipated and actual assignments, and degree of exposure to potential radiological hazards. Training described in this guide does not eliminate the need for additional training for facility-specific hazards. Notations throughout the program documents indicate the need for facility-specific information. If the noted section is not applicable to the facility, no information is required to be presented. The site Radiological Control Manager or designee should concur in facility-generated radiological training material. Continued Next Page Introduction (continued) DOE-HDBK-1130-98 2 Goal of Training Program The goal of the core training program is to provide a high level of knowledge and skills in radiological fundamentals for the radiological worker at all DOE facilities.

Organizational Relationships and Reporting Structure 1. DOE Office of Worker Protection Policy and Programs (DOE EH-52) is responsible for approving and maintaining the core training materials associated with the RW I and II training programs. 2. The establishment of a comprehensive and effective contractor site radiological control training program is the responsibility of line management and their subordinates. The training function may be performed by a separate training organization, but the responsibility for quality and effectiveness rests with line management. Training Program Description Next DOE-HDBK-1130-98 3 Training Program Descriptions Overview of Training Program Radiological Worker I Training is intended for radiological workers whose job assignments require unescorted access to Radiological Buffer Areas, Radiation Areas, or Radioactive Materials Areas. The RW I program consists of the core academic material plus the appropriate practical factors evaluation and lessons learned. The High/Very High Radiation (HR/VHR) Area module may be added to the Radiological Worker I course to give personnel unescorted entry into High Radiation Areas where contamination is not present. Radiological Worker II Training is intended for radiological workers whose job assignments involve unescorted entry to High Radiation Areas, Contamination Areas, High Contamination Areas and Airborne Radioactivity Areas. Further, workers who have potential contact with hot particles or use of gloveboxes with high contamination levels should complete Radiological Worker II training. The RW II program consists of the RW core academic material, the HR/VHR Area module (this may be deleted for certain sites, such as uranium mill tailings remediation projects, which do not have HR/VHR Areas), the Contamination Control module, the applicable practical factors evaluation, and lessons learned. Description of Programs Core Academic Material is approximately 8 hours in length but will vary dependent upon the amount of facility-specific material. RW Core Academic Training includes the following modules (1-7): Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 4 Radiological Fundamentals (Module 1) C Atomic Structure C Definitions and Units of Measure C The Four Basic Types of Ionizing Radiation C Units of Measure for Radiation Biological Effects (Module 2) C Sources of Radiation C Effects of Radiation on Cells C Acute and Chronic Radiation Dose C Prenatal Radiation Exposure C Risks in Perspective Radiation Limits (Module 3) C Basis for and Purpose of Radiation Dose Limits and Administrative Control Levels C Dose Limits and Administrative Control Levels C Worker Responsibilities Regarding Dose Limits ALARA Program (Module 4) C ALARA Program C Responsibilities for the ALARA Program C External and Internal Dose Reduction C Radioactive Waste Minimization Personnel Monitoring Programs (Module 5) C External Dosimetry C Internal Monitoring C Methods for Obtaining Radiation Dose Records Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 5 Radiological Access Controls and Postings (Module 6) C Radiological Work Permits C Radiological Postings C Areas an RW I Trained Person Can Enter C Areas an RW I Trained Person May Not Enter Radiological Emergencies (Module 7) C Emergency Alarms and Responses

C Radiological Emergency Situations C Considerations in Rescue and Recovery Operations Radiological Worker I Radiological Worker I training consists of the RW core academic material (Modules 1-7) plus the applicable practical factors (Module 10.1). Practical Factors for RW I (Module 10.1) The recommended evaluation for RW I consists of the following topics: C Review an Appropriate Radiological Work Permit (RWP) C Record the Appropriate Information on the RWP C Select and Wear Required Dosimeter(s) C Enter Simulated Area and Demonstrate ALARA Techniques C Monitor for Contamination (e.g., hand and foot monitoring on exiting RBA) C Respond to Emergency Situations or Abnormal Radiological Situations It may be necessary for an RW I qualified individual to enter an HR Area. If this becomes necessary, then the HR/VHR training should be presented, along with the applicable practical factors (Modules 10.1 and/or 10.2). Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 6 High/Very High Radiation Area Training (Module 8) The materials for the HR/VHR Area Module include the following: C High and Very High Radiation Area Definitions C Signs and Postings C Entry, Work In, and Exit from High Radiation Areas C Access Controls for High and Very High Radiation Areas Practical Factors for High Radiation Areas (Module 10.2) The recommended evaluation for RW I (High Radiation Area) consists of entry, work, and exit requirements: C Identify High Radiation Area signs C State special controls on RWP C State area radiation levels (with appropriate units) C State facility-specific administrative control levels C Select dosimetry in accordance with RWP C Wear dosimetry in accordance with procedures C Perform pre-operational checks (as appropriate) on survey meter and/or dose rate indicating device C Record appropriate information on RWP prior to entry C Verify current radiation survey prior to first entry C Enter only areas designated on RWP C Maximize distance from higher radiation areas C Do not loiter C State appropriate actions to take when a radiation area monitor alarms C Record appropriate information on RWP upon exit Radiological Worker II RW II Core Training is approximately 16 hours in length but will vary dependent on the amount of facility-specific material. RW II includes the core academic material modules (1 - 7), HR/VHR Area module (8), Contamination Control module (9), and RW II Practical Exercise module (10.3). Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 7 Radioactive Contamination Control (Module 9) The radioactive contamination control module includes the following topics: C Comparison of Ionizing Radiation and Radioactive Contamination C Types of Contamination C Sources of Radioactive Contamination C Contamination Control Methods C Contamination Monitoring Equipment C Decontamination C Types of Contamination Areas C Lessons Learned Practical Factors for RW II (Module 10.3) The recommended evaluation for RW II consists of the following topics: C Review an Appropriate Radiological Work Permit (RWP) C Record the Appropriate Information on the RWP C Select Required Dosimeter(s) and Protective Clothing C Don Protective Clothing and Dosimeter(s) C Enter Simulated Area and Demonstrate Contamination Control Practices C Remove Protective Clothing and Dosimeter(s) C Monitor for Contamination

C Respond to emergency situations or abnormal radiological situations Specialized Radiological Worker Training Specialized Radiological Worker Training should be completed for non- routine operations or work in areas with changing radiological conditions. This training is in addition to Radiological Worker II training and is required for personnel planning, preparing, and performing jobs that have the potential for high radiological consequences. Such jobs may Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 8 Specialized Radiological Worker Training (continued) involve special containment devices, the use of mockups, and ALARA considerations. In some cases, depending on facility-specific criteria, pre- job briefings provide an acceptable alternative to Specialized Radiological Worker Training. Individuals who install, inspect, or work in radiological containments shall be trained commensurate with their duties. Individuals that wear respiratory protection need to be medically qualified and wear the equipment as trained in accordance with OSHA standards and DOE requirements. This training is in addition to Radiological Worker II training Refresher Training Refresher training programs for RW I and II training may be implemented in the alternate year when full retraining is not completed or in response to observations or indications of poor radiological performance. Refresher training is intended to maintain and enhance the proficiency of the worker. The refresher training for RW I and II training should be documented. RW I and II refresher training may be accomplished through any available media. This may include video, handout, computer- based training or classroom training. RW I and II refresher training should include changes in requirements and lessons learned from operations and maintenance experience, and occurrence reporting for the site and across the DOE complex. The following topics may be included: C New procedures and changes to existing procedures C New equipment and changes or modifications to existing equipment or facilities C Lessons learned from facility operating experiences Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 9 Refresher Training (continued) C Lessons learned from industry operating experiences C Identified deficiencies from post training evaluations Proficiency Requirements In accordance with 10 CFR 835-Subpart J, each individual shall demonstrate knowledge of the radiation safety training topics established in § 835-Subpart J, commensurate with the hazards in the area and required controls, by successful completion of an examination and performance demonstrations prior to being permitted unescorted access to radiological areas and prior to performing unescorted assignments as a radiological worker. A written examination and a practical factors evaluation shall be used to demonstrate satisfactory completion of RW I, HR/VHR Area, and RW II training (10 CFR 835 - Subpart J). These exams may be combined into one exam if the training is presented as one training class. C The minimum passing score for any written examination should be 80%. C A minimum passing score on the practical evaluation should be 80%. C Computer-based and other electronic methods of examination are acceptable. Retraining In accordance with 10 CFR 835-Subpart J, RW retraining shall be provided

to individuals when there is a significant change to radiation protection policies and procedures that may affect the individual and at intervals not to exceed 24 months. The requirements of 10 CFR 835-Subpart J for examination apply. Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 10 Retraining (continued) Retraining should include selected fundamentals of the initial training with emphasis on seldom-used knowledge and skills. Retraining should be tailored to subjects for which trainee evaluations and experience indicate that special emphasis and depth of coverage is needed. A self-study method may be used, when possible, for retraining. A suggestion for a self-study method is to allow the workers to self study the training material; present any updates or changes, lessons learned, etc.; then allow the workers to take the examination and applicable practical exercise. Minimum requirements for RW I and RW II retraining should be successful completion of the written examination, practical exercise, and training on lessons learned/new procedures. Materials developed in support of retraining should be documented in accordance with 10 CFR 835.704 “Administrative Records.” Instructor Training and Qualifications All classroom instruction should be provided by instructors qualified in accordance with the contractor’s site instructor qualification program. Training staff (contractor and subcontractor, if used) should possess both technical knowledge and experience, and the developmental and instructional skills required to fulfill their assigned duties. 1. Training staff responsible for program management, supervision, and development should have and maintain the education, experience, and technical qualifications required for their jobs. Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 11 Instructor Training and Qualifications (continued) 2. Instructors should have the technical qualifications, which include adequate theory, practical knowledge, and experience for the subject matter that they are assigned to teach. 3. Methods should be in place at each contractor site to ensure that individual instructors meet and maintain position qualification requirements. 4. Subject matter experts, without instructor qualification, may provide training in their area of expertise. However, if these subject matter experts are to be permanent instructors, they should be trained as instructors in the next practical training cycle. Qualifications for trainers at nuclear facilities can be found in DOE Order 5480.20A, “Personnel Selection, Qualification, and Training Requirements for DOE Nuclear Facilities.” Training Program Material Development Next Page DOE-HDBK-1130-98 12 Training Program Material Development Training Material Presentation Training materials for the core programs consist of lesson plans and study guides. To ensure compliance with 10 CFR 835-Subpart J, facility- specific materials must be added to the core materials when necessary to adequately train individuals for facility-specific radiological hazards. Training Certificates A training certificate that identifies current training status of core training may be provided to qualified personnel. Each facility is responsible to administer and track the certificates. Facilities have the option of utilizing the certificates as proof of training.

However, it should be noted that 10 CFR 835-Subpart J requires each facility to ensure radiological workers have adequate training for the hazards present. The training certificate from another DOE site does not, in itself, relieve the facility from ensuring the worker has had adequate training. It is appropriate for facilities to supplement a visiting radiological worker’s training with facility-specific training sufficient to ensure an adequate level of training for the hazards present. It may also be appropriate to confirm the adequacy of the worker’s training with a standard examination and practical evaluation. Training Aids Facility-specific training aids may be developed at the facility to suit individual training styles. Each facility may add information, activities, a glossary, and/or view graphs to enhance their program. Training Program Standards and Policies Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 13 Training Examinations Written examinations and/or computer-based training (CBT) examinations shall be used to demonstrate satisfactory completion of theoretical and classroom material for RW I and RW II. The examinations should: C Be completed with a minimum passing grade of 80%, C Cover material representative of the learning objectives from both core material and facility-specific material, C Be varied from class to class and within classes when the class size is large, C Not use true/false questions, and C Be acknowledged by trainee signature participation in a post- examination review. An example core examination question bank is available from DOE EH- 52. Each question in the examination bank should be numbered in accordance with the corresponding learning objective. All questions should consist of the multiple choice type question. The facility should develop an appropriate exam bank, and the DOE example questions may be used as a basis. Example questions may be used verbatim, but the order of answers should be changed. The DOE example exam bank is not held confidential. The facility exam bank should be held confidential in accordance with facility practices for exam confidentiality. The practice should ensure students do not have knowledge of specific answer keys. Rad Worker I Written Examination: The Rad Worker I exam is the responsibility of each facility and should consist of a minimum of thirty (30) questions. The remedial action for failure of this examination is the responsibility of each facility. HR/VHR Area Written Examinations: The HR/VHR Area exam is the responsibility of each facility and should consist of a minimum of five (5) questions. Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 14 Training Examinations (continued) The remedial action for failure of this examination is the responsibility of each facility. Rad Worker Written II Examinations: The Rad Worker II exam is the responsibility of each facility and should consist of a minimum of fifty (50) questions. The remedial action for failure of this examination is the responsibility of each facility. Initial challenge examinations may be appropriate for experienced radiological workers and those with current qualifications at another DOE facility. They should be designed to cover the core RW training core learning objectives only. Challenges should not apply to facility- specific topics. Each learning objective should be represented on the

challenge examination. Failure of a challenge examination should result in the attendance of a scheduled initial training session. Successful completion of the initial challenge examination does not exempt the employee from the facility-specific examination, practical factors evaluation, and training in lessons learned/new procedures. Practical Factors Evaluation: A practical factors evaluation should be used to demonstrate satisfactory completion skills for RW I, RW I HR/VHR Area, and RW II training. A minimum score of 80% should be attained for each practical factor evaluation. The criteria for a satisfactory score is outlined in the attachments to the Instructor’s Guide. Successful completion of the written examination should be a prerequisite for the practical evaluation. Lectures, Seminars, Training Exercises, etc. RW I and II core training programs are designed to be delivered in a classroom setting. An alternate delivery method may be implemented with CBT equipment. The presentation of RWT should include core materials and facility-specific information. In all cases, regardless of the setting or delivery method, examination requirements of 10 CFR 835- Subpart J shall be followed. Continued Next Page Training Program Standards and Policies (continued) DOE-HDBK-1130-98 15 Delinquent Training/Failure Procedures and Policies Radiological workers who are delinquent on retraining shall lose their Radiological Worker access status until successful completion of the delinquent training requirement. These workers shall not be allowed unescorted entry into associated radiological areas. Currently trained radiological workers who fail a challenge or retraining exam shall lose their training status until successful completion of the examination and practical factors evaluation. These workers should not be allowed unescorted entry into associated controlled/radiological areas. Exceptions and Waivers Successful completion of the core courses for RW I, RW I HR/VHR Area, and RW II training at one DOE site may be recognized by other DOE sites. However, the determination as to the adequacy of training as required by 10 CFR 835-Subpart J is the responsibility of the facility. It may be appropriate to accept this training as the basis for a challenge exam covering generic topics. However, this training may not adequately cover facility-specific topics. Administration Next DOE-HDBK-1130-98 16 Administration Training Records Training records and course documentation shall meet the requirements of 10 CFR 835.704 “Administration Records.” Training Program Development/Change Requests All requests for program changes and revisions should be submitted to EH-52 using the DOE Technical Standard Program form “Document Improvement Proposal” F 1300.3. This form is available from the DOE Technical Standards Home Page - Maintenance of DOE Technical Standards TSPP-09). (See the Foreword of this document for website address). Audits (internal and external) Internal verification of training effectiveness may be accomplished through senior instructor or supervisor observation of practical applications and discussions of course material. Results should be documented and maintained by the organization responsible for Radiological Control Training. The RW I, RW I HR/VHR Area, and RW II core training program materials and processes will be evaluated on a periodic basis by DOE-

HQ. The evaluation should include a comparison of program elements with applicable industry standards and requirements. Evaluating Training Program Effectiveness Verification of the effectiveness of Radiological Control training should be accomplished by surveying a limited subset of former students in the workplace. This evaluation should include observation of practical applications, discussion of the course material, and may include an associated written examination. DOE/EH has issued guidelines for evaluating the effectiveness of radiological training through the DOE Operations Offices and DOE Field Offices. Continued Next Page Administration (continued) DOE-HDBK-1130-98 17 Evaluating Training Program Effectiveness (continued) These guidelines are included as an attachment to the Program Management Guide to DOE-HDBK-1131-98, General Employee Radiological Training. For additional guidance, refer to DOE STD 1070-94, “Guide for Evaluation of Nuclear Facility Training Programs.” The guidelines contained in these documents are relevant for the establishment and implementation of post-training evaluation and retention testing programs. In response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 91-6, DOE committed to develop an implementation plan to upgrade radiation protection programs at DOE defense nuclear facilities. The implementation plan detailed DOE’s plans to develop and implement radiation protection post-training evaluation and retention testing programs. Post-training evaluations will be used to identify opportunities for improving course materials, upgrading instruction methods and techniques, and the need for additional training. Retention testing will indicate when individual performance or testing fails to meet expectations. Corrective actions for deficiencies identified in retention testing will be incorporated in the individual’s development plan and the site’s training program on an appropriate schedule. In addition, Article 613.7 of the DOE Radiological Control Standard states that sites should implement a training effectiveness verification program. This program, which is in addition to performance evaluations routinely performed by the site’s training department, is to verify the effectiveness of radiological control training by surveying a limited subset of former students in the workplace. This recommendation applies to both DOE defense nuclear facilities and DOE facilities not classified as defense nuclear facilities. Continued Next Page Administration (continued) DOE-HDBK-1130-98 18 Evaluating Training Program Effectiveness (continued) Per DOE’s commitment to DNFSB, it is expected that all defense nuclear facilities will implement these or equivalent programs. DOE facilities not classified as defense nuclear facilities should also strive to implement such programs. Line management should monitor progress of program implementation. The guidance contained in DOE STD-1070-94 is not meant to be prescriptive. Training organizations should review this guidance and determine its applicability, taking into consideration the existence of similar programs already in place at their facility. Forward evaluation results indicating a possible need to revise core training programs to EH-52 using the “Request for Change to DOE Core Training Materials” form. References Next DOE-HDBK-1130-98 19 References

1. Cohen, Bernard L., “Catalog of Risks Extended and Updated,” Health Physics, the Radiation Protection Journal, Vol. 61, 1991. 2. “Investigation Report C-337-A, Contamination Incident at the Paducah Gaseous Diffusion Plant on August 23, 1991,” September 1991. 3. NCRP, “Ionizing Radiation Exposure of the Population of the United States,” Report No. 93. 4. ORAU 88/H-99, “Guide to Good Practice in Radiation Protection Training.” 5. Travis, E. L., “Primer of Medical Radiobiology,” 1989. 6. U.S. Department of Energy, “Implementation Guidance for Use with 10 CFR 835, Occupational Radiation Protection,” 1998. 7. U.S. Department of Energy, DOE Radiological Control Standard, 1998. 8. U.S. Department of Energy, “Occupational Radiation Protection,” 10 CFR 835, 1998. 9. U.S. Department of Energy, “Reproductive Health: Effects of Chemical and Radiation on Fertility and the Unborn Child,” Lawrence Livermore National Laboratory, February 1, 1984. 10. U.S. Department of Energy, Order 5480.20A, Ch. 1, “Personnel Selection, Qualification, and Training Requirements For DOE Nuclear Facilities,” November, 2001. 11. U.S. Department of Health, Education and Welfare, Radiological Health Handbook, January 1970. 12. U.S. Nuclear Regulatory Commission, “Instruction Concerning Prenatal Radiation Exposure,” U.S. NRC Regulatory Guide 8.13, December 1987. 13. U.S. Nuclear Regulatory Commission, “Instruction Concerning Risks From Occupational Radiation Exposure,” U.S. NRC Regulatory Guide 8.29, Version I, February 1997. 14. Wallace, Susan S., and Robert B. Painter, Editors., “Ionizing Radiation Damage to DNA: Molecular Aspects,” UCLA Symposia on Molecular and Cellular Biology, New Series, Vol. 136, Wiley-Liss, N.Y. 1990. DOE-HDBK-1130-98 20 This page intentionally left blank. DOE-HDBK-1130-98 (Part 2 of 3) Radiological Worker Training Instructor’s Guide Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide ii This page intentionally left blank. DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide iii Course Developers Christine Liner Savannah River Site Al Reeder Lockheed Martin Energy Systems Carolyn Owen Lawrence Livermore National Laboratory Dean Atchinson Brookhaven National Laboratory Brent Pearson Coleman Industries Roland Jean Sandia National Laboratories Karin Jessen Lockheed Martin Energy Systems Course Reviewers Technical Standards Managers U.S. Department of Energy Peter O’Connell U.S. Department of Energy Randy Sullivan ATL International, Inc. William Ulicny ATL International, Inc. We would also like to take this opportunity to recognize several individuals who provided significant contributions in developing previous revisions to DOE Radiological Worker Training material. Vicki Bogan Savannah River Site (Former) Michael Sanders Savannah River Site (Former) Pete Seilheimer Hanford Site Cindy Caldwell Hanford Site Chris Lesperance Hanford Site Gerald Eaton Hanford Site Doug Gabbard Fernald Environmental Restoration Management Company Rocky Barnum Pacific Northwest National Laboratory Thomas Clawson Idaho National Engineering and Environmental Laboratory Roger Raymond Idaho National Engineering and Environmental Laboratory Kathleen McIntyre Brookhaven National Laboratory Jim Allen Stanford Linear Accelerator Center Paula Trinoskey Lawrence Livermore National Laboratory DOE-HDBK-1130-98

Radiological Worker Training Instructor’s Guide iv This page intentionally left blank. DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide v Table of Contents Page Training Program Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xi A. DOE Course Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xi B. Overview of Courses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xii C. Evaluation Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xiii D. Documentation of Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xiv E. Periodic Training and Refresher Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xiv MODULE 1: RADIOLOGICAL FUNDAMENTALS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Instructional Aids . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 A. Atomic Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 B. Definitions and Units of Measure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 C. The Four Basic Types of Ionizing Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 D. Units of Measure for Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 MODULE 2: BIOLOGICAL EFFECTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Instructional Aids . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18

I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 A. Sources of Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 B. Effects of Radiation on Cells . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 C. Acute and Chronic Radiation Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 D. Prenatal Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 E. Risks in Perspective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 MODULE 3: RADIATION LIMITS AND ADMINISTRATIVE CONTROL LEVELS . . . . . . . . . . . . . . . 35 DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide vi Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 A. Basis for and Purpose of Radiation Dose Equivalent Limits and Administrative Control Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 B. Dose Equivalent Limits and Administrative Control Levels . . . . . . . . . . . . . . . . . . . . . . 37 C. Worker Responsibilities Regarding Dose Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40

III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 MODULE 4: ALARA PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 A. ALARA Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 B. Responsibilities for the ALARA Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 C. External and Internal Radiation Dose Reduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 D. Radioactive Waste Minimization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 MODULE 5: PERSONNEL MONITORING PROGRAMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52

II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 A. External Dosimetry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 B. Internal Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 C. Methods for Obtaining Radiation Dose Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide vii IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 MODULE 6: RADIOLOGICAL ACCESS CONTROLS AND POSTINGS . . . . . . . . . . . . . . . . . . . . . . . 56 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 A. Radiological Work Permits (RWPs) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 B. Radiological Postings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 C. Areas a RW I Trained Person Can Enter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 D. Areas a RW I Trained Person May Not Enter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71 MODULE 7: RADIOLOGICAL EMERGENCIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72

I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 A. Emergency Alarms and Responses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 B. Radiological Emergency Situations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 74 C. Considerations in Rescue and Recovery Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76 MODULE 8: HIGH/VERY HIGH RADIATION AREA TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 A. High and Very High Radiation Area Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 B. Signs and Postings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79 DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide viii C. Entry, Work In, and Exit from High Radiation Areas . . . . . . . . . . . . . . . . . . . . . . . . . . 80 D. Access Controls for High and Very High Radiation Areas . . . . . . . . . . . . . . . . . . . . . . . 82 E. Access to VHRAs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83

MODULE 9: RADIOACTIVE CONTAMINATION CONTROL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 84 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 84 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 84 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 84 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 A. Comparison of Ionizing Radiation and Radioactive Contamination . . . . . . . . . . . . . . . . . 85 B. Types of Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86 C. Radioactive Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 87 D. Contamination Control Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89 E. Contamination Monitoring Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 F. Decontamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 G. Types of Contamination Areas . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 H. Lessons Learned . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 97 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 MODULE 10.1: PRACTICAL FACTORS FOR RADIOLOGICAL WORKER I . . . . . . . . . . . . . . . . . . . . 99 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101

II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 A. Review an Appropriate Radiological Work Permit . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 B. Record the Appropriate Information on the RWP . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 C. Select and Wear Required Dosimeter(s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 102 D. Enter Simulated Area and Demonstrate ALARA Techniques . . . . . . . . . . . . . . . . . . . . 102 E. Monitor for Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 A. Review Evaluation Rules/Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 B. Review Pass/Fail Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105 DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide ix C. Provide Students With Necessary Documentation/ Materials for Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105 MODULE 10.2: PRACTICAL FACTORS FOR HIGH RADIATION AREAS . . . . . . . . . . . . . . . . . . . . 106 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 107 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 107 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 107 C. Objectives Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 107 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 A. Identify High Radiation Area Signs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 B. State Special Controls on RWP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 C. State Area Radiation Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 D. State Facility-Specific Administrative Control Levels . . . . . . . . . . . . . . . . . . . . . . . . . 108 E. Select Dosimetry in Accordance with RWP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 F. Wear Dosimetry in Accordance with Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 G. Perform Pre-Operational Checks on Survey Meter or Dose Rate

Indicating Device . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 H. Record Appropriate Information on RWP Prior to Entry . . . . . . . . . . . . . . . . . . . . . . . 108 I. Verify Current Radiation Survey Prior to First Entry . . . . . . . . . . . . . . . . . . . . . . . . . 108 J. Enter Only Areas Designated on RWP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 K. Maximize Distance from Higher Radiation Areas . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 L. Do Not Loiter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 M. State Appropriate Actions to Take When a Radiation Area Monitor Alarms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 N. Record Appropriate Information on RWP upon Exit . . . . . . . . . . . . . . . . . . . . . . . . . . 109 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109 A. Review Evaluation Rules/Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109 B. Review Pass/Fail Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109 C. Provide Students With Necessary Documentation/ Materials for Evaluation . . . . . . . . . 109 MODULE 10.3: PRACTICAL FACTORS FOR RADIOLOGICAL WORKER II . . . . . . . . . . . . . . . . . . 111 Terminal Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 Enabling Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 Instructional Aids: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 I. MODULE INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 A. Self Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 B. Module Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 C. Introduce Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 D. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 113 II. MODULE OUTLINE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 113 A. Review an appropriate Radiological Work Permit (RWP) . . . . . . . . . . . . . . . . . . . . . . 113 B. Record the Appropriate Information on the RWP sign in sheet . . . . . . . . . . . . . . . . . . 113 DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide x C. Select Required Dosimeter(s) and Protective Clothing . . . . . . . . . . . . . . . . . . . . . . . . 114 D. Don Protective Clothing and Dosimeter(s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 114 E. Enter Simulated Area and Demonstrate Contamination Control and ALARA Techniques . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 115

F. Remove Protective Clothing and Dosimeter(s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 116 G. Monitor for Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 116 III. SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 IV. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 A. Review Evaluation Rules/Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 B. Review Pass/Fail Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 118 C. Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 118 ATTACHMENT 1 - Instructions for Evaluators . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 120 I. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 120 II. SET-UP PRACTICAL FACTORS MOCK-UP AREA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 120 III. ESTABLISH SCORING CRITERIA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 121 IV. CONDUCTING EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 124 ATTACHMENT 2 - Sample Grading Checklist for RW II . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 129 ATTACHMENT 3 - Sample Job Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 130 ATTACHMENT 4 - Sample Survey Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131 ATTACHMENT 5 - Sample Questions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 132 DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide xi Training Program Overview DOE Radiological Health and Safety (DOE P 441.1) Safety Policy. “It is the policy of the Department of Energy to conduct its radiological operations in a manner that ensures the health and safety of all its employees, contractors, and the general public. In achieving this objective, the Department shall ensure that radiation exposures to its workers and the public and releases of radioactivity to the environment are maintained below regulatory limits and deliberate efforts are taken to further reduce exposures and releases as low as reasonably achievable. The Department is fully committed to implementing a radiological control program of the highest quality that consistently reflects this policy.” In meeting this policy, the Department shall: “Ensure personnel responsible for performing radiological work activities are appropriately trained. Standards shall be established to ensure the technical competency of the Department’s workforce, as appropriate, through implementation of radiological training and professional development programs.” A. DOE Course Design The DOE training material for radiological workers consists of four areas. 1. Core Academics (Modules 1-7) This area includes modules 1 through 7. These modules discuss the theory that a worker should know to work safely around radiological hazards.

The core academics are recommended for radiological workers whose job assignments limit required unescorted access to Radiological Buffer Areas, Radiation Areas, and Radioactive Material Areas. 2. High/Very High Radiation Area (Module 8) This module should be added to the core academics for personnel whose job assignments require unescorted entry into High Radiation Areas where contamination is not present or whose job assignments require work near High/Very High Radiation Areas. DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide xii 3. Contamination Control (Module 9) This module is recommended for workers who require unescorted access to Contamination, High Contamination, and/or Airborne Radioactivity Areas. 4. Practical Factors Evaluations (Module 10) This module contains generic practical exercises that provide hands-on experience for the worker. These exercises are for the levels of training needed by different radiological workers. B. Overview of Courses The DOE training material can be divided into the following levels of radiological worker training: 1. Radiological Worker I (RW I) Training This course contains the core academics and the appropriate practical factors. This training is for radiological workers whose job assignments require access to Radiological Buffer Areas and Radiation Areas. RW I training is also suggested for unescorted entry into Radioactive Material Areas containing either sealed radioactive sources or radioactive material labeled in accordance with 10 CFR 835. RW I training alone does not prepare the worker to work around higher radiation levels or with contaminated materials. It is suggested that RW I tasks be limited to inspections, tours, and activities that involve work on nonradiological systems. 2. Radiological Worker I Training with High/Very High Radiation Area Training This course contains the core academics, the High/Very High Radiation Area (HR/VHR) module, and the appropriate practical factors. The HR/VHR Area lesson plan may be added to the RW I course to give personnel unescorted entry into High Radiation Areas where contamination is not a concern. DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide xiii Figure 1 Three Levels of Radiological Worker Training with Associated Training Requirements 3. Radiological Worker II (RW II) Training This course consists of the core academics, the High/Very High Radiation Area module, the Contamination Control module, and the appropriate practical factors. This training is recommended for the radiological worker whose job assignments involve unescorted entry into High Radiation Areas, Contamination Areas, High Contamination Areas, and Airborne Radioactivity Areas. Further, workers who have potential contact with hot particles or use gloveboxes with high contamination levels should complete RW II training. RW II training prepares the worker to work around higher radiation levels and with contaminated materials normally associated with radiological facilities/activities. C. Evaluation Criteria At the completion of the applicable course, the participant must successfully complete a written exam and a practical evaluation to be considered to have successfully completed the training. Successful completion of the written exam should be a prerequisite for the practical factors evaluation. DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide xiv 1. Written Examination

Successful completion of the written examination typically requires a minimum passing score of 80 percent or equivalent. The written exam is based on the objectives in the theory portion of the course (Modules 1-7). 2. Practical Factors Evaluation Successful completion of the practical factors evaluation typically requires a minimum score of 80 percent or equivalent. The practical factors evaluation includes entry into a simulated controlled work environment. This evaluation is based on the application of the theory portion of the applicable course (Modules 1-7). D. Documentation of Training (Insert facility-specific information.) E. Periodic Training and Refresher Training 1. Training Training is required at intervals not to exceed every 24 months. 2. Refresher Training Refresher training should be conducted in the off year when periodic training is not due. DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide xv Figure 2 Evaluation Overview Diagram DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide xvi This page intentionally left blank. DOE-HDBK-1130-98 Radiological Worker Training Instructor’s Guide 1 Course Title: Radiological Worker Training (Core Academics) DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 2 Module 1: Radiological Fundamentals Terminal Objective: Given various radiological concepts, the participant will be able to define the fundamentals of radiation, radioactive material, and radioactive contamination in accordance with the approved lesson materials. Enabling Objectives: The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 Identify the three basic particles of an atom. EO2 Define radioactive material, radioactivity, radioactive half-life, and radioactive contamination. EO3 Identify the units used to measure radioactivity and contamination. EO4 Define ionization and ionizing radiation. EO5 Distinguish between ionizing radiation and non-ionizing radiation. EO6 Identify the four basic types of ionizing radiation and the following for each type: a. Physical characteristics b. Range c. Shielding d. Biological hazard(s) e. Sources at the site EO7 Identify the units used to measure radiation. EO8 Convert rem to millirem and millirem to rem. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 3 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview Nuclear science is truly a product of the 20th century. This module will discuss several nuclear science topics at a basic level appropriate for the radiological worker. These concepts are necessary for the worker to understand the nature of radiation and its potential effect on health. The topics covered include basic particles of the atom, types of radiation, and the definition of units used to measure radiation. C. Objectives Review D. Introduction This module introduces the worker to basic radiological fundamentals and terms that are common in the DOE complex. After learning the fundamentals of radiation, radioactive material, and radioactive contamination, the worker will build from the basic to the more in-depth concepts presented in the other modules. Post information in room. Have students introduce themselves: name, background

DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 4 II. MODULE OUTLINE A. Atomic Structure 1. The basic unit of matter is the atom. The three basic particles of the atom are protons, neutrons, and electrons. The central portion of the atom is the nucleus. The nucleus consists of protons and neutrons. Electrons orbit the nucleus—similar to the way planets orbit our sun. EO1 Identify the three basic particles of an atom. a. Protons 1) Protons are located in the nucleus of the atom. 2) Protons have a positive electrical charge. 3) The number of protons in the nucleus determines the element. (Optional) Insert diagram of the atom. Have students label the three basic particles. b. Neutrons 1) Neutrons are located in the nucleus of the atom. 2) Neutrons have no electrical charge. 3) Atoms of the same element have the same number of protons, but can have a different number of neutrons. 4) Atoms which have the same number of protons but different numbers of neutrons are called isotopes. NOTE: Common notation for describing isotopes is to list the atomic symbol for an element followed by its atomic weight. The atomic weight is the sum of protons and neutrons. For example, tritium has 1 proton and 2 neutrons, and is denoted as H- 3. 5) Isotopes have the same chemical properties; however, the nuclear properties can be quite different. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 5 c. Electrons 1) Electrons are in orbit around the nucleus of an atom. 2) Electrons have a negative electrical charge. 3) This negative charge is equal in magnitude to the proton’s positive charge. Table 1-1 Basic Particles 3 Basic Particles Location Charge Comments Protons Nucleus + (positive) Number of protons determines the element. If the number of protons changes, the element changes. Neutrons Nucleus No Charge Atoms of the same element have the same number of protons, but can have a different number of neutrons. This is called an isotope. Electrons Orbit nucleus - (negative) This negative charge is equal in magnitude to the proton’s positive charge. 2. Stable and unstable atoms Only certain combinations of neutrons and protons result in stable atoms. a. If there are too many or too few neutrons for a given number of protons, the nucleus will not be stable. b. The unstable atom will try to become stable by giving off excess energy. This energy is in the form of particles or rays (radiation). These unstable atoms are known as radioactive atoms. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 6 3. Charge of the atom The number of electrons and protons determines the overall electrical charge of the atom. The term “ion” is used to define atoms or groups of atoms that have a net positive or negative electrical charge. Optional: Insert diagram that illustrates the different charges. a. No charge (neutral) If the number of electrons equals the number of protons, the atom is electrically neutral. This atom does not have a net electrical charge. b. Positive charge (+) If there are more protons than electrons, the atom is positively charged. c. Negative charge (-) If there are more electrons than protons, the atom is negatively charged. B. Definitions and Units of Measure 1. Radioactive material EO2 Define radioactive material. Radioactive material is any material containing unstable atoms that emit radiation.

Give facility-specific examples of radioactive isotopes at the site. 2. Radioactivity Radioactivity is the process of unstable (or radioactive) atoms becoming stable. This is done by emitting radiation. This process over a period of time is referred to as radioactive decay. A disintegration is a single atom undergoing radioactive decay. EO2 Define radioactivity. Give example of radioactive decay. 3. Radioactivity units Radioactivity is measured in the number of disintegrations radioactive material undergoes in a certain period of time. a. Disintegrations per minute (dpm) b. Disintegrations per second (dps) c. Curie (Ci) EO3 Identify the units used to measure radioactivity and contamination. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 7 One curie equals: C 2,200,000,000,000 disintegrations per minute (2.2x1012 dpm), or C 37,000,000,000 disintegrations per second (3.7x1010 dps), or C 1,000,000 microcuries (1x106 µCi). 4. Radioactive half-life Radioactive half-life is the time it takes for one half of the radioactive atoms present to decay. EO2 Define radioactive half-life. 5. Radioactive contamination Radioactive contamination is radioactive material that is uncontained and in an unwanted place. (There are certain places where radioactive material is intended to be.) EO2 Define radioactive contamination. Contamination is measured per unit area or volume. • dpm/100 cm2 • µCi/ml • µCi/g. EO3 Identify the units used to measure radioactivity and contamination. 6. Ionization Ionization is the process of removing electrons from neutral atoms. a. Electrons will be removed from an atom if enough energy is supplied. The remaining atom has a positive (+) charge. The ionized atoms may affect chemical processes in cells. The ionizations may affect the cell’s ability to function normally. b. The positively charged atom and the negatively charged electron are called an “ion pair.” c. Ionization should not be confused with radiation. Ions (or ion pairs) produced as a result of the interaction of radiation with an atom allow the detection of radiation. EO4 Define ionization. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 8 7. Ionizing radiation Ionizing radiation is energy (particles or rays) emitted from radioactive atoms, and some devices, that can cause ionization. Examples of devices that emit ionizing radiation are X-ray machines, accelerators, and fluoroscopes. a. It is important to note that exposure to ionizing radiation does not necessarily result in contamination of the worker. EO4 Define ionizing radiation. b. Radiation is a type of energy, and contamination is radioactive material that is uncontained and in an unwanted place. 8. Non-ionizing radiation a. Electromagnetic radiation that doesn’t have enough energy to ionize an atom is called “non-ionizing radiation.” EO5 Distinguish between ionizing radiation and non- ionizing radiation. b. Examples of non-ionizing radiation are radar waves, microwaves, and visible light. C. The Four Basic Types of Ionizing Radiation The four basic types of ionizing radiation of concern in the DOE complex are alpha particles, beta particles, gamma or X rays, and neutrons. 1. Alpha particles a. Physical characteristics 1) The alpha particle has a large mass and consists of two protons, two neutrons, and no electrons. 2) It is a highly charged particle (charge of plus two) that is emitted from the nucleus of an atom.

EO6 Identify the four basic types of ionizing radiation and the following for each: a. Physical characteristics b. Range c. Shielding d. Biological hazards e. Sources 3) The positive charge causes the alpha particle (+) to strip electrons (-) from nearby atoms as it passes through the material, thus ionizing these atoms. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 9 b. Range 1) The alpha particle deposits a large amount of energy in a short distance of travel. 2) This large energy deposit limits the penetrating ability of the alpha particle to a very short distance. 3) Range in air is about 1-2 inches. c. Shielding Most alpha particles are stopped by a few centimeters of air, a sheet of paper, or the dead layer (outer layer) of skin. d. Biological hazards 1) Alpha particles are not considered an external radiation hazard. This is because they are easily stopped by the dead layer of skin. 2) Internally, the source of the alpha radiation is in close contact with body tissue and can deposit large amounts of energy in a small volume of living body tissue. e. Sources (Insert facility-specific information.) DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 10 Table 1-2 Alpha Particles Physical Characteristics • Large mass (2 protons, 2 neutrons, 0 electrons). • +2 charge. Range • Very short (about 1-2 inches in air). • Deposits large amount of energy in a short distance of travel. Shielding • Few centimeters of air. • Sheet of paper. • Dead layer of skin (outer layer). Biological Hazards • No external hazard (dead layer of skin will stop alpha particles). • Internally, the source of alpha radiation is in close contact with body tissue. It can deposit large amounts of energy in a small amount of body tissue. Sources Insert facility-specific information. 2. Beta particles a. Physical characteristics 1) The beta particle has a small mass and is positively or negatively charged. Positively charged beta particles are called positrons and have an electrical charge of plus one. Negatively charged beta particles are high-energy electrons and have an electrical charge of minus one. 2) A negatively charged beta particle is physically identical to an electron. EO6 Identify the four basic types of ionizing radiation and the following for each type: a. Physical characteristics b. Range c. Shielding d. Biological hazards e. Sources 3) The beta particle ionizes target atoms due to the force between itself and the electrons of the atom. Both have a charge of minus one. b. Range 1) Because of its charge, the beta particle has a limited penetrating ability. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 11 2) The range in air of beta particles depends on the energy of the beta particle. In the case of tritium (H-3), the range is only an inch; in the case of phosphorous-32 (P-32) or strontium-90 (Sr-90), the range is 20 feet in air. c. Shielding Beta particles are typically shielded by plastic, glass, or safety glasses. d. Biological hazards 1) If ingested or inhaled, a beta emitter can be an internal hazard when the source of the beta radiation is in close contact with body tissue and can deposit energy in a small volume of living body tissue. 2) Externally, beta particles are potentially hazardous to the skin and eyes. 3) Provide facility-specific information on the additional risks or concerns from high-energy beta sources (e.g., P-32, Y-90), as appropriate.

e. Sources (Insert facility-specific information.) Table 1-3 Beta Particles Physical Characteristic s • Small mass. • -1 charge or + 1 charge. Range • Short distance (one inch to 20 feet). Shielding • Plastic. • Glass. • Safety glasses. Biological Hazard • Internal hazard (this is due to short range). • Externally, may be hazardous to skin and eyes. Sources Insert facility-specific information. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 12 3. Gamma rays/X rays a. Physical characteristics 1) Gamma/X-ray radiation is an electromagnetic wave (electromagnetic radiation) or photon and has no mass and no electrical charge. 2) Gamma rays are very similar to X rays. The difference between gamma rays and X rays is that gamma rays originate inside the nucleus and X rays originate in the electron orbits outside the nucleus. 3) Gamma/X-ray radiation can ionize as a result of direct interactions with orbital electrons. EO6 Identify the four basic types of ionizing radiation and the following for each type: a. Physical characteristics b. Range c. Shielding d. Biological hazards e. Sources b. Range 1) Because gamma/X-ray radiation has no charge and no mass, it has very high penetrating ability. 2) The range in air is very far. It will easily go several hundred feet. c. Shielding Gamma/X-ray radiation is best shielded by very dense materials, such as lead. Water or concrete, although not as effective as the same thickness as lead, are also commonly used, especially if the thickness of shielding is not limiting. d. Biological hazards Gamma/X-ray radiation can result in radiation exposure to the whole body. e. Sources (Insert facility-specific information.) DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 13 Table 1-4 Gamma Rays/X-Rays Physical Characteristic s • No mass. • No charge. • Electromagnetic wave or photon. • Similar (difference is the place of origin). Range • Range in air is very far. • It will easily go several hundred feet. • Very high penetrating power since it has no mass and no charge. Shielding • Concrete. • Water. • Lead. Biological Hazard • Whole body exposure. • The hazard may be external and/or internal. This depends on whether the source is inside or outside the body. Sources Insert facility-specific information. 4. Neutrons a. Physical characteristics 1) Neutron radiation consists of neutrons that are ejected from the nucleus. 2) A neutron has mass, but no electrical charge. EO6 Identify the four basic types of ionizing radiation and the following for each type: a. Physical characteristics b. Range c. Shielding d. Biological hazards e. Sources 3) An interaction can occur as the result of a collision between a neutron and a nucleus. The nucleus recoils due to the energy imparted by the neutron and ionizes other atoms. This is called “secondary ionization.” 4) Neutrons may also be absorbed by a nucleus. This is called neutron activation. A charged particle or gamma ray may be emitted as a result of this interaction. The emitted radiation can cause ionization in other atoms. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 14 b. Range 1) Because of the lack of a charge, neutrons have a relatively high penetrating ability and are difficult to stop. 2) The range in air is very far. Like gamma rays, they can easily travel several hundred feet in air. c. Shielding

Neutron radiation is best shielded by materials with a high hydrogen content such as water, concrete, or plastic. d. Biological hazards Neutrons are a whole body hazard due to their high penetrating ability. e. Sources (Insert facility-specific information.) Table 1-5 Neutrons Physical Characteristic s • No charge. • Has mass. Range • Range in air is very far. • Easily can go several hundred feet. • High penetrating power due to lack of charge (difficult to stop). Shielding • Water. • Concrete. • Plastic (high hydrogen content). Biological Hazard • Whole body exposure. • The hazard is generally external. Sources Insert facility-specific information. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 15 D. Units of Measure for Radiation 1. Roentgen (R) a. Is a unit for measuring external exposure. b. Defined only for effect on air. c. Applies only to gamma and X rays. d. Does not relate biological effects of radiation to the human body. e. 1 R (Roentgen) = 1000 milliroentgen (mR). EO7 Identify the units used to measure radiation. 2. Rad (Radiation absorbed dose) a. A unit for measuring absorbed dose in any material. Absorbed dose results from energy being deposited by the radiation. b. Is defined for any material. c. Applies to all types of radiation. d. Does not take into account the potential effect that different types of radiation have on the body. e. 1 rad = 1000 millirad (mrad). 3. Rem (Roentgen equivalent man) a. A unit for measuring dose equivalence. b. Is the most commonly used unit. c. Pertains to the human body. d. Takes into account the energy absorbed (dose) and the biological effect on the body due to the different types of radiation. The Quality Factor (QF) is used as a multiplier to reflect the relative amount of biological damage caused by the same amount of energy deposited in cells by the different types of ionizing radiation. Rem = rad x QF. DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 16 Quality Factors: alpha = 20 beta = 1 gamma/x-ray = 1 neutron = 2-11 (depending on the energy) e. 1 rem = 1,000 millirem (mrem). EO8 Convert rem to millirem and millirem to rem. 4. Radiation dose and dose rate a. Radiation dose rate is the dose per time. b. Example: 1) Radiation dose rate = dose/time. 2) Radiation dose equivalent rate = mrem/hr. 3) Radiation absorbed dose rate = mrad/hr. Table 1-6 Radiation Units Roentgen (R) Rad (Radiation Absorbed Dose) Rem (Roentgen Equivalent Man) Unit for measuring exposure. Unit for measuring absorbed dose in any material. Unit for measuring dose equivalence (most commonly used unit). Defined only for effect on air. Defined for any material. Pertains to human body. Applies only to gamma and X-ray radiation. Applies to all types of radiation. Applies to all types of radiation. Does not relate biological effects of radiation to the human body. Does not take into account the potential effect that different types of radiation have on the body. Takes into account the energy absorbed (dose) and the biological effect on the body due to the different types of radiation. Equal doses of different types of radiation (as measured in rad) can cause different levels of damage to the body (measured in rem). DOE-HDBK-1130-98 Module 1: Radiological Fundamentals Instructor’s Notes 17 III. SUMMARY (Insert facility-specific information.) IV. EVALUATION

(Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 2: Biological Effects Instructor’s Notes 18 Module 2: Biological Effects Terminal Objective: Given various radiation doses and sources of radiation, identify natural and manmade sources of radiation and the biological risks associated with radiation dose in accordance with lesson materials. Enabling Objectives: The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 Identify the major sources of natural background and manmade radiation. EO2 Identify the average annual dose to the general population from natural background and manmade sources of radiation. EO3 State the method by which radiation causes damage to cells. EO4 Identify the possible effects of radiation on cells. EO5 Define the terms “acute dose” and “chronic dose.” EO6 State examples of chronic radiation dose. EO7 Define the terms “somatic effect” and “heritable effect.” EO8 State the potential effects associated with prenatal radiation dose. EO9 Compare the biological risks from chronic radiation doses to health risks workers are subjected to in industry and daily life. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 19 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview The fact that ionizing radiation produces biological damage has been known for many years. We have gained most of our knowledge of these effects since World War II. In this module, we will discuss the potential for biological effects and risks due to ionizing radiation and put these potential risks into perspective when compared to other occupations and daily activities. With this information, it is hoped that employees will develop a healthy respect for radiation rather than fear or disregard. C. Objectives Review D. Introduction We know more about the biological effects of ionizing radiation than most other environmental factors. Rather than just being able to base our information on animal studies, we have a large body of information available regarding exposures to humans. There are four major groups of people that have been exposed to significant levels of radiation. The first group includes early radiation workers, such as radiologists. These workers received large doses of radiation before the biological effects were recognized. Since that time, standards have been developed to protect workers. The second group is the more than 250,000 survivors of the atomic bombs dropped at Hiroshima and Nagasaki. Some of these survivors received doses estimated to be in excess of 50,000 mrem. The third group includes individuals who have been involved in radiation accidents. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 20 The fourth and largest group of individuals are patients who have undergone radiation therapy for cancer and other diseases. II. MODULE OUTLINE A. Sources of Radiation We live in a radioactive world and always have. In fact, the majority of us will be exposed to more ionizing radiation from natural background radiation than from our jobs. Introduce objectives 1. Natural sources There are several sources of radiation that occur naturally. The radiation emitted from these sources is identical to the radiation that results from manmade sources.

EO1 Identify the major sources of natural background and manmade radiation. The four major sources of naturally occurring radiation exposures are: • Cosmic radiation • Sources in the earth’s crust, also referred to as terrestrial radiation • Sources in the human body, also referred to as internal sources • Radon a. Cosmic radiation (total average dose ~ 28 mrem/yr) 1) Cosmic radiation comes from the sun and outer space. It consists of positively charged particles and gamma radiation. 2) At sea level, the average annual cosmic radiation dose is about 26 mrem. 3) At higher elevations, the amount of atmosphere shielding cosmic rays decreases; therefore, the dose increases. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 21 b. Sources in earth’s crust (terrestrial) (total average dose ~ 28 mrem/yr) There are natural sources of radiation in the ground (i.e., rocks and soil). 1) Some of the contributors to terrestrial sources are the natural radioactive elements radium, uranium, and thorium. 2) Many areas have elevated levels of terrestrial radiation due to increased concentrations of uranium or thorium in the soil. c. Internal (total average dose ~40 mrem/yr) 1) The food we eat and the water we drink contain trace amounts of natural radioactive materials. 2) These naturally occurring radioactive materials deposit in our bodies and cause internal exposure to radiation. 3) Some naturally occurring radioactive isotopes include Sodium-24 (Na-24), Carbon-14 (C-14), Argon-41 (Ar-41), and Potassium-40 (K-40). Most of our internal exposure comes from K-40. d. Radon (total average dose ~ 200 mrem/yr) 1) Radon comes from the radioactive decay of uranium, which is naturally present in the soil. 2) Radon is a gas. It can travel through the soil and enter through building foundation cracks. The greatest concentrations of indoor radon are found in basements. 3) Radon emits alpha radiation. It presents a hazard only when taken into the body (e.g., when inhaled). Review characteristics of alpha radiation. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 22 2. Manmade sources The difference between manmade sources of radiation and naturally occurring sources is the origin of the source. E01 Identify the major sources of natural background and manmade radiation. The four top sources of manmade radiation exposures are: • Tobacco products • Medical radiation • Building materials • Domestic water supply a. Tobacco products (total average dose ~1300 mrem/yr for smokers) b. Medical radiation sources (total average dose ~ 54 mrem/yr) 1) X rays (total average dose ~ 40mrem/yr) a) X rays are similar to gamma rays; however, they originate outside the nucleus. b) A typical radiation dose from a chest X ray is about 10 mrem. 2) Diagnosis and therapy (total average dose ~14 mrem/yr) In addition to X rays, radioactive materials and radioactive sources are used in medicine for diagnosis and therapy. c. Building materials (total average dose ~7 mrem/yr) d. Domestic water supply (total average dose ~5 mrem/yr) DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 23 e. Other minor contributors Other contributors to dose include consumer products, industrial sources, and atmospheric testing of nuclear weapons. Discuss: It has been more than 20 years since atmospheric testing has been conducted. 3. Average annual dose

The average annual total effective dose equivalent to the general population (non-smokers) from naturally occurring and manmade sources is about 360 mrem. EO2 Identify the average annual dose to the general population from natural background and manmade sources of radiation. B. Effects of Radiation on Cells The human body is made up of many organ systems. Each system is made up of tissues. Specialized cells make up tissues. Ionizing radiation can potentially affect the normal function of cells. 1. Biological effects begin with the ionization of atoms a. The method by which radiation causes damage to human cells is by ionization of atoms in the cells. Atoms make up the cells that make up the tissues of the body. Any potential radiation damage begins with damage to atoms. b. A cell is made up of two principal parts, the body of the cell and the nucleus. The nucleus is like the brain of the cell. EO3 State the method by which radiation causes damage to cells. Review the four types of ionizing radiation. c. When ionizing radiation hits a cell, it may strike a vital part of the cell like the nucleus or a less vital part of the cell, like the cytoplasm. 2. Cell sensitivity Some cells are more sensitive than others to environmental factors such as viruses, toxins, and ionizing radiation. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 24 a. Actively dividing and non-specialized cells 1) Cells in our bodies that are actively dividing are more sensitive to ionizing radiation. 2) Cells that are rapidly dividing include blood- forming cells, the cells that line our intestinal tract, hair follicles, and cells that form sperm. b. Less actively dividing and more specialized cells Cells that divide at a slower rate or are more specialized (such as brain cells or muscle cells) are not as sensitive to damage by ionizing radiation. 3. Possible effects of radiation on cells Several things can happen when a cell is exposed to ionizing radiation. The following are possible effects of radiation on cells. EO4 Identify the possible effects of radiation on cells. a. There is no damage b. Cells repair the damage and operate normally 1) The body of most cells is made up primarily of water. When ionizing radiation hits a cell, it is most likely to interact with the water in the cell. One of the byproducts of radiation- induced ionization of water is hydrogen peroxide. Hydrogen peroxide can damage cell atomic structures. 2) Ionizing radiation can also hit the nucleus of the cell. The nucleus contains the vital parts of the cell, such as chromosomes. The chromosomes determine cell function. When chromosomes duplicate themselves, the chromosomes transfer their information to new cells. Radiation may cause a change in the chromosome that does not affect the cell. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 25 3) Damage to chromosomes and other cell structures can be repaired. In fact, our bodies repair a very large number of chromosome breaks every day (References 7 and 10). c. Cells are damaged and operate abnormally 1) Cell damage may not be repaired or may be incompletely repaired. In that case, the cell may not be able to function properly. 2) It is possible that a chromosome in the cell nucleus could be damaged but not be repaired correctly. If the cell continues to reproduce, this is called a mutation and may result in cancer. d. Cells die as a result of the damage

At any given moment, thousands of our cells die and are replaced by normal functioning cells. However, the radiation damage to a cell may be so extensive that the cell dies prematurely. C. Acute and Chronic Radiation Dose Potential biological effects depend on how much and how fast a radiation dose is received. Radiation doses can be grouped into two categories: acute and chronic dose. 1. Acute radiation doses a. High doses of radiation received in a short period of time are called acute doses. The body’s cell repair mechanisms are not as effective for damage caused by an acute dose. EO5 Define the terms “acute dose” and “chronic dose.” b. After an acute dose to the whole body DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 26 After an acute dose, damaged cells will be replaced by new cells and the body will repair itself, although this may take a number of months. Only in extreme cases, such as with the Chernobyl firefighters (500 rem), would the dose be so high as to make recovery unlikely. c. Acute doses to only part of the body 1) X-ray machines It is possible that radiation exposure may be limited to a part of the body, such as the hands. There have been accidents, particularly with X-ray machines, in which individuals have exposed their fingers to part of the intense radiation beam. In some of these cases, individuals have received doses of millions of mrem to their fingers, and some individuals have lost their finger or fingers. It is important for individuals who work with X-ray or similar equipment to be trained in the safe use of this equipment. 2) Radiation therapy a) Radiation therapy patients receive high doses of radiation in a short period of time, but generally only to a small portion of the body (not a whole body dose). Reference 5. b) The skin and limited tissue of these patients may receive significant doses, but doses to the region of a tumor are many times higher. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 27 c) Ionizing radiation is used to treat cancer in these patients because cancer cells are rapidly dividing and therefore sensitive to ionizing radiation. Some of the side effects of people undergoing radiation therapy are hair loss, nausea, and tiredness. d. Probability of a large acute dose What is important to understand is that it takes a large acute dose of radiation before any physical effect is seen. These acute doses have occurred in Hiroshima/Nagasaki, and in a few radiation accidents, including Chernobyl. The possibility of a radiological worker receiving a large acute dose of ionizing radiation on the job is extremely low. Typically, radioactive materials are handled in small quantities that do not produce a large amount of radiation. Where there is a potential for larger exposures, many safety features are required. 2. Chronic radiation doses A chronic radiation dose is typically a small amount of radiation received over a long period of time. An example of a chronic dose is the dose we receive from natural background every day of our lives. The body’s cell repair mechanisms are better able to repair a chronic dose than an acute dose. EO5 Define the terms “acute dose” and “chronic dose.” EO6 State examples of chronic radiation dose. a. The body has time to repair damage because a smaller percentage of the cells need repair at any given time. b. The body also has time to replace dead or non- functioning cells with new, healthy cells.

DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 28 3. Biological effects of radiation exposure Somatic effects refer to the effects radiation has on the individual receiving the dose. Genetic effects refer to mutations due to radiation damage to the DNA of a cell. When this change is in the DNA of parental reproductive cells, it is called a heritable effect. a. Somatic Effects Somatic effects can best be described in terms of prompt and delayed effects as discussed below. EO7 Define the term “heritable effect.” 1) Prompt Effects Although rare in the nuclear industry, large doses are typically acute radiation doses representing serious overexposures. The biological effects of large acute doses are as follows: Table 2-1 Prompt Biological Effects Dose (rem) Effect 0-25 None detectable through symptoms or routine blood tests. 25-100 Changes in blood. 100-300 Nausea, anorexia. 300-600 Diarrhea, hemorrhage, and possible death Effects are dependent on medical intervention and the individual. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 29 2) Delayed Effects Delayed effects may result from either a single large acute overexposure or from continuing low-level chronic exposure. Cancer in its various forms is the most important potential delayed effect of radiation exposure. Other effects noted include cataracts, life shortening and, for individuals exposed in the womb, lower IQ test scores. b. Heritable Effects A heritable effect is a physical mutation or trait that is passed on to offspring. In the case of heritable effects, the parental individual has experienced damage to some genetic material in the reproductive cells and has passed the damaged genetic material onto offspring. 1) Heritable effects from radiation have never been observed in humans but are considered possible. They have been observed in studies of plants and animals. 2) Heritable effects have not been found in the 77,000 Japanese children born to the survivors of Hiroshima and Nagasaki (these are children who were conceived after the atom bomb -- i.e., heritable effects). Studies have followed these children, their children, and their grandchildren. 4. Factors affecting biological damage due to exposure to radiation a. Total dose In general, the greater the dose, the greater the potential for biological effects. b. Dose rate (how fast) The faster the dose is delivered, the less time the body has to repair itself. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 30 c. Type of radiation For example, internally deposited alpha emitters are more damaging than beta or gamma emitters for the same energy deposited. d. Area of the body that receives a dose In general, the larger the area of the body that receives a dose, the greater the biological effect. Extremities are less sensitive than blood forming and other critical organs. That is why the annual dose limit for extremities is higher than for a whole body dose that irradiates internal organs. e. Cell sensitivity The most sensitive cells are those that are rapidly dividing. Examples include blood cells, hair follicles, and the cells lining the gastrointestinal tract. f. Individual sensitivity Some individuals are more sensitive to environmental factors such as ionizing radiation. The developing embryo/fetus is the most sensitive, and children are more sensitive than adults.

In general, the human body becomes relatively less sensitive to ionizing radiation with increasing age. The exception is that elderly people are more sensitive than middle-aged adults due to the inability to repair damage as quickly (less efficient cell repair mechanisms). DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 31 D. Prenatal Radiation Exposure Although no effects were seen in Japanese children conceived after the atomic bomb, there were effects seen in some children who were in the womb when exposed to the atomic bomb radiation at Hiroshima and Nagasaki. Some of these children were born with a slightly smaller head size, lower average birth weight, and increased incidence of mental retardation. Some later showed lower IQ test scores and slower scholastic development, smaller physical size, and increased incidence of behavioral problems. EO8 State the potential effects associated with prenatal radiation dose. 1. Sensitivity of the fetus Embryo/fetal cells are rapidly dividing, which makes them sensitive to many environmental factors including ionizing radiation. The embryo/fetus is most susceptible to developing adverse health effects if exposed during the time period of 8 - 15 weeks after conception. 2. Factors for potential effects associated with prenatal exposures Many chemical and physical (environmental) factors are suspected of causing or known to have caused damage to a fetus, especially early in the pregnancy. Radiation, alcohol consumption, exposure to lead, and heat, such as from hot tubs, are only a few such factors. E. Risks in Perspective Current radiation protection standards and practices are based on the premise that any radiation dose, no matter how small, can result in health effects such as cancer. Further, it is assumed that these effects are produced in direct proportion to the dose received (i.e., doubling the radiation dose results in a doubling of the risk of the effect). These two assumptions lead to a dose-response relationship, often referred to as the linear, no-threshold model, for limiting health effects at very low radiation dose levels. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 32 However, it should be noted that this is a conservative assumption made in the absence of more conclusive evidence. Health effects (primarily cancer) have been observed in humans only at doses in excess of 10 rem delivered at high dose rates. Below this dose, estimation of adverse health effects is speculative. Risk estimates that are used to predict health effects in exposed individuals or populations are based on epidemiological studies of well-defined populations (e.g., the Japanese survivors of the atomic bombings in 1945 and medical patients) exposed to relatively high doses delivered at high dose rates. It is generally accepted that studies have not demonstrated adverse health effects in individuals exposed to small doses (less than 10 rem) delivered over a period of many years. 1. Risk from exposures to ionizing radiation a. No increases in cancer have been observed in individuals who receive a dose of ionizing radiation at occupational levels. The possibility of cancer induction cannot be dismissed even though an increase in cancers has not been observed. Risk estimates have been derived from studies of individuals who have been exposed to high levels of radiation.

b. The risk of cancer induction from radiation exposure can be put into perspective. This can be done by comparing it to the normal rate of cancer death in today’s society. The current rate of cancer death among Americans is about 20 percent. Taken from a personal perspective, each of us has about 20 chances in 100 of dying of cancer. A radiological worker who receives 25,000 mrem over a working life increases his/her risk of cancer by 1 percent, or has about 21 chances in 100 of dying of cancer. A 25,000 mrem dose is a fairly large dose over the course of a working lifetime. The average annual dose to DOE workers is less than 100 mrem, which leads to a working lifetime dose (40 years assumed) of no more than approximately 4,000 mrem. Review: There are many other causes of cancer, not just radiation. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 33 2. Comparison of risks a. Table 2-2 compares the estimated days of life expectancy lost as a result of exposure to radiation and other health risks. The following information is intended to put the potential risk of radiation into perspective when compared to other occupations and daily activities. Table 2-2 Estimated Loss of Life Expectancy from Health Risks EO9 Compare the biological risks from chronic radiation doses to the health risks workers are subjected to in industry and daily life. Health Risk Estimated Loss of Life Expectancy Smoking 20 cigarettes a day 6 years Overweight (by 15%) 2 years Alcohol consumption (U.S. average) 1 year Agricultural accidents 320 days Construction accidents 227 days Auto accidents 207 days Home accidents 74 days Occupational radiation dose (1 rem/y), from age 18-65 (47 rem total) 51 days All natural hazards (earthquakes, lightning, flood) 7 days Medical radiation 6 days References 1 and 12 of the PMG. The estimates in Table 2-2 indicate that the health risks from occupational radiation doses are smaller than the risks associated with normal day-to-day activities that we have grown to accept. b. Acceptance of a risk: 1) is a personal matter. 2) requires a good deal of informed judgment. c. The risks associated with occupational radiation doses are generally considered acceptable as compared to other occupational risks by most scientific groups who have studied them. There are some scientific groups who claim that the risk is too high. DOE continues to fund and review worker health studies to address these concerns. DOE-HDBK-1130-98 Module 2 Biological Effects Instructor’s Notes 34 III. SUMMARY In summary, the estimated risk associated with occupation radiation dose is similar to other routine occupational risks and much less than some risks widely accepted in society. The risk of work in a radiation environment is considered within the normal occupational risk tolerance by national and international scientific groups. However, acceptance of risk is an individual matter and is best made with accurate information. A radiological worker should understand the risk of working in a nuclear environment in relation to the risks of daily life and the risks presented by work in other professions. The intent of this module is to give you the facts about radiation exposure risks and provide you with an opportunity to ask questions about radiation risk. It is hoped that understanding radiation risk and risk in general will help you to develop an informed and healthy respect for radiation, and that your understanding will eliminate excessive fear of or indifference to radiation.

IV. EVALUATION (Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 3: Radiation Limits and Administrative Control Limits Instructor’s Notes 35 Module 3: Radiation Limits and Administrative Control Levels Terminal Objective: Given various time frames and different parts of the body, identify the applicable DOE dose limits, DOE administrative control levels, and facility-specific administrative control levels in accordance with the lesson material. Enabling Objectives: The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 State the purposes of administrative control levels. EO2 Identify the DOE radiation dose limits, DOE recommended administrative control level, and the facility administrative control level. EO3 State the site policy concerning prenatal radiation exposure. EO4 Identify the employee’s responsibilities concerning radiation dose limits and administrative control levels. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 3: Radiation Limits and Administrative Control Levels Instructor’s Notes 36 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview This module will address DOE dose limits and administrative control levels. C. Objectives Review Introduce objectives. D. Introduction DOE limits and administrative control levels have been established for the purpose of restricting occupational radiation exposures to levels of acceptable risk. II. MODULE OUTLINE A. Basis for and Purpose of Radiation Dose Equivalent Limits and Administrative Control Levels 1. Basis for DOE dose limits a. DOE has established radiation dose equivalent limits for general workers. These limits are based on guidance from national and international scientific groups and government agencies, such as: 1) International Commission on Radiological Protection (ICRP) 2) National Council on Radiation Protection and Measurements (NCRP) 3) U.S. Environmental Protection Agency (EPA) b. The radiation protection standards for all DOE workers are described in 10 CFR 835, “Occupational Radiation Protection.” These regulations apply to DOE, its contractors, and persons utilizing or working in DOE facilities and include dose equivalent limits. DOE-HDBK-1130-98 Module 3: Radiation Limits and Administrative Control Levels Instructor’s Notes 37 2. Facility administrative control levels for general employees The facility administrative control levels for workers are lower than the DOE limits and are set to: EO1 State the purpose of administrative control levels. a. Ensure the DOE limits and control levels are not exceeded. b. Help reduce individual and total worker population radiation dose (collective dose). B. Dose Equivalent Limits and Administrative Control Levels EO2 Identify the DOE radiation dose limits and facility administrative controls levels. Table 3-7 Dose Equivalent Limits and Controls (Optional -- leave chart blank and have student complete chart.)DOE Dose Equivalent Limit rem/year DOE Recommendations rem/year Facility Administrative Control Level rem/year Whole body 5 2 facility-specific Extremity 50 N/A facility-specific Skin & other organs 50 N/A facility-specific Lens of the eye 15 N/A facility-specific Member of the public

0.1 N/A facility-specific Declared pregnant worker 0.5/gestation period N/A facility-specific NOTE: 1) The chart is based on limits and control levels for routine conditions. The limits and control levels are also based on the sum of internal and external dose. External dose is from sources outside the body. Internal dose is from sources inside the body. 2) The internal dose reported in a given calendar year is actually the projected dose the individual will receive over the next 50 years from intakes in that calendar year. Radioactive material may be inhaled, ingested, or absorbed through the skin or open wound. DOE-HDBK-1130-98 Module 3: Radiation Limits and Administrative Control Levels Instructor’s Notes 38 1. Whole body a. Definition The whole body extends from the top of the head down to just below the elbow and just below the knee. This is the location of most of the blood- producing and vital organs. b. Limit and control levels The DOE whole body dose equivalent limit is based on the sum of internal and external dose. 1) DOE radiation dose equivalent limit during routine conditions is 5 rem/year. 2) Because DOE’s objective is to maintain personnel radiation dose well below the regulatory limits, the DOE Radiological Control Technical Standard recommends a DOE administrative control level during routine conditions of 2 rem/year. 3) Facility administrative control level. (Insert facility-specific information.) 2. Extremities a. Definition Extremities include the hands and arms below the elbow, and the feet and legs below the knees. b. Limit and control level Extremities can withstand a much larger dose than the whole body because there are no major blood- producing organs located here. 1) DOE radiation dose equivalent limit for extremities is 50 rem/year. 2) Facility administrative control levels. (Insert facility-specific information.) 3. Skin and other organs a. DOE radiation dose equivalent limit for skin and other organs is 50 rem/year. DOE-HDBK-1130-98 Module 3: Radiation Limits and Administrative Control Levels Instructor’s Notes 39 b. Facility administrative control level (Insert facility-specific information.) 4. Lens of the eye a. DOE radiation dose equivalent limit for lens of the eye is 15 rem/year. b. Facility administrative control level. (Insert facility-specific information.) 5. Declared pregnant worker: Embryo/fetus After a female worker voluntarily notifies her employer in writing that she is pregnant, she is considered a declared pregnant worker. For the purposes of radiological protection of the fetus/embryo, DOE requires a special limit for dose to the fetus/embryo. In addition, the DOE RCS recommends that the employer provide the option of a mutually agreeable assignment of work tasks, with no loss of pay or promotional opportunity, such that further occupational radiation exposure is unlikely. C This declaration may be revoked, in writing, at anytime by the declared pregnant worker. b. DOE limit For a declared pregnant worker who continues working as a radiological worker, the following radiation dose limit will apply. 1) The dose equivalent limit for the embryo/fetus (during the entire gestation period) is 500 mrem. a) Measures must be taken to avoid substantial variation above the uniform exposure rate necessary to meet the 500 mrem limit for the gestation period. b) The DOE RCS recommends that efforts be made to avoid exceeding 50 mrem/month to the embryo/fetus of the declared pregnant worker.

DOE-HDBK-1130-98 Module 3: Radiation Limits and Administrative Control Levels Instructor’s Notes 40 2) If the dose equivalent to the embryo/fetus is determined to have already exceeded 500 mrem when a worker notifies her employer of her pregnancy, the worker shall not be assigned to tasks where additional occupational radiation exposure is likely during the remainder of the pregnancy. b. Site policy (Insert facility-specific information.) c. Facility administrative control level (Insert facility-specific information.) EO3 State the site policy concerning prenatal radiation exposure. 6. Members of the public a. DOE radiation dose equivalent limit is 100 mrem/year. b. Facility administrative control levels (Insert facility-specific information.) C. Worker Responsibilities Regarding Dose Limits 1. It is each employee’s responsibility to comply with DOE dose limits and facility administrative control levels. 2. If you suspect that dose limits or administrative control levels are being approached or exceeded, you should notify your supervisor immediately. EO4 Identify the employee’s responsibilities concerning radiation dose limits and administrative control levels. 3. (Insert facility-specific information.) III. SUMMARY (Insert Site Summary.) IV. EVALUATION (Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 41 Module 4: ALARA Program Terminal Objective: Given different radiological conditions, identify the techniques for minimizing exposure to radiation and radioactive material in accordance with lesson materials. Enabling Objectives: The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 State the ALARA concept. EO2 State the DOE/Site management policy for the ALARA program. EO3 Identify the responsibilities of management, the Radiological Control Organization, and the radiological worker in the ALARA Program. EO4 Identify methods for reducing external and internal radiation dose. EO5 State the pathways by which radioactive material can enter the body. EO6 Identify methods a radiological worker can use to minimize radioactive waste. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 42 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview This module is designed to inform the student of the concept of ALARA (As Low As Reasonably Achievable). This module discusses radiation hazards. Methods for reducing both external and internal doses from radiation and radioactive material are also discussed. C. Objectives Review Introduce objectives. D. Introduction DOE establishes dose limits and administrative control levels for general employees. However, radiological workers and their management strive to keep radiation dose well below these limits. Radiological workers should always try to maintain their radiation dose As Low As Reasonably Achievable (ALARA). II. MODULE OUTLINE A. ALARA Program ALARA stands for As Low As Reasonably Achievable. ALARA is an approach to radiation safety that strives to manage and control doses (both individual and collective) to the work force and the general public to as low as is reasonable taking into account social, technical, economic, practical, and public policy considerations.

1. ALARA concept a. ALARA stands for As Low As Reasonably Achievable. EO1 State the ALARA concept. b. Because some risk, however small, exists from any radiation dose, all doses should be kept ALARA. ALARA includes reducing both internal and external radiation dose. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 43 c. The ALARA concept is an integral part of all site activities that involve the use of sources of ionizing radiation. d. ALARA is the responsibility of all employees. 2. DOE Management Policy for the ALARA program Personal radiation exposure shall be maintained As Low As Reasonably Achievable. Radiation exposure to the work force and public shall be controlled such that: EO2 State the DOE/Site management policy for the ALARA program. • Radiation doses are well below regulatory limits. • There is no radiation exposure without an overall benefit. 3. Site policy (Insert facility-specific information.) B. Responsibilities for the ALARA Program The individual radiological worker is ultimately responsible for maintaining his/her radiation dose ALARA. However, management and Radiological Control personnel also play an important role in the ALARA program. The following are some of the responsibilities of the three groups: EO3 Identify the responsibilities of Management, the Radiological Control Organization, and the radiological worker in the ALARA Program. 1. Management (Insert facility-specific information.) 2. Radiological Control Organization (Insert facility-specific information.) 3. Radiological workers Each radiological worker is expected to demonstrate responsibility and accountability. This is accomplished through an informed, disciplined, and cautious attitude toward radiation and radioactivity. (Insert facility-specific information.) DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 44 C. External and Internal Radiation Dose Reduction Engineering controls should be the primary method to control exposure (e.g., enclosed hoods). Administrative controls is the next method to control exposures (e.g., postings). Personnel protective equipment is the last method (e.g., respirators). 1. Basic protective measures used to minimize external dose include: • Minimizing time in radiation areas • Maximizing the distance from a source of radiation • Using shielding whenever possible • Reducing the amount of radioactive material (source reduction) a. Methods for minimizing time Reducing the time spent in a field of radiation will lower the dose received by the workers. EO4 Identify methods for reducing external and internal radiation dose. 1) Plan and discuss the task thoroughly prior to entering the area. Use only the number of workers actually required to do the job. 2) Have all necessary tools present before entering the area. 3) Use mock-ups and practice runs that duplicate work conditions. 4) Take the most direct route to the job site if possible and practical. 5) Never loiter in an area controlled for radiological purposes. 6) Work efficiently and swiftly. 7) Do the job right the first time. 8) Perform as much work outside the area as possible. When practical, remove parts or components to areas with lower dose rates to perform work. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 45 9) Do not exceed stay times. In some cases, the Radiological Control Organization may limit the amount of time a worker may stay in an area due to various reasons. This is known as “stay time.” If you have been assigned a stay time, do not exceed this time.

10) (Insert facility-specific information.) b. Methods for maximizing distance from sources of radiation The worker should stay as far away as possible from the source of radiation. EO4 Identify methods for reducing external and internal radiation dose. 1) Stay as far away from radiation sources as practical given the task assignment. For point sources (such as valves and hot spots), the dose rate follows a principle called the inverse square law. This law states that if you double the distance, the dose rate falls to 1/4 of the original dose rate. If you triple the distance, the dose rate falls to 1/9 of the original dose rate. Dose RateA= Dose RateB x Distance2 A Distance2 B 2) Be familiar with radiological conditions in the area. 3) During work delays, move to lower dose rate areas. 4) Use remote handling devices when possible. 5) (Insert facility-specific information.) c. Proper uses of shielding Shielding reduces the amount of radiation dose to the worker. Different materials shield a worker from the different types of radiation. EO4 Identify methods for reducing external and internal radiation dose. 1) Take advantage of permanent shielding, such as non-radiological equipment/structures. 2) Use shielded containments when available. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 46 3) Wear safety glasses/goggles to protect your eyes from beta radiation, when applicable. 4) Temporary shielding (e.g., lead or concrete blocks) can only be installed when proper procedures are used. 5) Temporary shielding will be marked or labeled with wording such as “Temporary Shielding - Do Not Remove Without Permission from Radiological Control.” 6) Once temporary shielding is installed, it cannot be removed without proper authorization. • When evaluating the use of shielding, the estimated dose saved is compared to the estimated dose incurred during shield installation and removal. 7) (Insert facility-specific information.) d. Source Reduction Source reduction is another method of reducing radiation doses. Source reduction often involves procedures such as flushing radioactive systems, decontamination, and removal of contaminated items. This is done to reduce the amount of radioactive materials present in/on a system because these materials can add to radiation levels in an area. 2. Internal radiation dose reduction a. Pathways Internal dose is a result of radioactive materials being taken into the body. Radioactive material can enter the body through one or more of the following pathways: EO5 State the pathways through which radioactive material can enter the body. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 47 1) Inhalation 2) Ingestion 3) Absorption through the skin 4) Absorption through wounds This information excludes exposure from natural internal sources of radioactivity that is discussed in Unit 305. b. Methods to reduce internal radiation dose Reducing the potential for radioactive materials to enter the body is important. As previously stated, install or use engineering controls followed by administrative controls as the primary methods to control internal exposure. PPE is the last choice for controlling internal exposure. In addition, the following are methods the worker can use. EO4 Identify methods for reducing external and internal radiation dose. 1) Wear respirators properly when required. Respirators should only be used by personnel qualified to wear them.

2) Report all wounds or cuts (including scratches and scabs) to the appropriate facility-specific organization before entering any area controlled for radiological purposes. (Discuss reporting wounds or cuts with facility-specific information.) 3) Comply with the requirements of the controlling work documents. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 48 4) Do not eat, drink, smoke, or chew in Radioactive Materials Areas, Contamination Areas, High Contamination Areas, or Airborne Radioactivity Areas, as dispersible radioactive materials may be present. 5) (Insert facility-specific information.) 3. Lessons Learned Review lessons learned from your site or other sites to demonstrate what may be learned from mistakes leading to excessive personnel exposures. (Insert facility-specific information.) D. Radioactive Waste Minimization One of the potential consequences of working with radioactive materials is the generation of radioactive waste. This radioactive waste must be properly disposed. Examples of radioactive waste include: • Paper • Gloves • Glassware • Rags • Brooms, mops The ALARA concept also applies to minimizing radioactive waste. This will reduce personnel exposure associated with the handling, packaging, storing, and disposing of radioactive waste. This will also reduce the resultant costs. It is very important for each radiological worker to minimize the amount of radioactive waste generated. 1. Methods to minimize radioactive waste The following information identifies methods to minimize radioactive waste. a. Minimize the materials used for radiological work. EO6 Identify methods a radiological worker can use to minimize radioactive waste. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 49 1) Take only the tools and materials you need for the job into areas controlled for radiological purposes. This is especially important for contamination areas. 2) Unpack equipment and tools in a clean area. This will help to avoid bringing unnecessary material to the job site. This material can become radioactive waste if it is contaminated. 3) Use tools and equipment that are identified for radiological work when possible. (Add facility-specific information about where such tools are stored.) 4) Use only the materials required to clean the area. An excessive amount of bags, rags, and solvent adds to radioactive waste. 5) Sleeve, or otherwise protect with a covering such as plastic, clean materials brought into contaminated areas. 6) (Insert facility-specific information.) b. Separate radioactive waste from nonradioactive waste. 1) Place radioactive waste in the containers identified for radioactive waste. Do not place radioactive waste in nonradioactive waste containers. 2) Do not throw nonradioactive waste, or radioactive material that may be reused, into radioactive waste containers. 3) (Insert facility-specific information.) c. Separate compactible material from noncompactible material. d. Minimize the amount of mixed waste generated. Mixed waste is waste that contains both radioactive and hazardous materials. DOE-HDBK-1130-98 Module 4: ALARA Program Instructor’s Notes 50 e. Use good housekeeping techniques. f. (Insert facility-specific information.) III. SUMMARY This module addressed key points for the implementation and success of the Site’s ALARA Program. Responsibilities for all employees and methods to achieve the ALARA concepts were also discussed.

IV. EVALUATION (Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 5: Personnel Monitoring Programs Instructor’s Notes 51 Module 5: Personnel Monitoring Programs Terminal Objective: Given different personnel monitoring programs, identify the purpose, types, and worker responsibilities for each in accordance with lesson material. Enabling Objectives: The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 State the purpose and worker responsibilities for each of the external dosimeter devices used at the site. EO2 State the purpose and worker responsibilities for each type of internal monitoring method used at the site. EO3 State the methods for obtaining radiation dose records. EO4 Identify worker responsibilities for reporting radiation dose received from other sites and from medical applications. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 5: Personnel Monitoring Programs Instructor’s Notes 52 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview The various types of personnel monitoring devices and the employee’s responsibilities concerning each will be discussed. C. Objectives Review Introduce objectives. D. Introduction External exposure results from radiation that comes from radioactive material outside of the body. A “personnel dosimeter” is a device used to measure external dose. Internal dose is radiation that comes from radioactive material within the body. The whole body counter, chest counter, and bioassay sampling are methods for measuring internal dose. Personnel monitoring for radiation dose involves assessing exposure due to external sources and internal sources. II. MODULE OUTLINE A. External Dosimetry A personnel dosimeter is a device used to measure radiation dose. Different types of external dosimeters may be used. Radiological Control personnel determine which type(s) are needed. The following information identifies the different types used at this facility. 1. Purpose (Insert facility-specific information to describe purpose, and basic operation of each type.) EO1 State the purpose and worker responsibility for each of the external dosimeter devices used at the site. 2. Worker responsibilities for external dosimetry include the following: DOE-HDBK-1130-98 Module 5: Personnel Monitoring Programs Instructor’s Notes 53 a. Wear dosimeters when required. Radiological Control personnel identify the requirements. Check signs and radiological work permits (RWPs) for the requirements. b. Wear dosimeters properly. 1) Primary dosimeters should be worn on the chest area. This area is on or between the neck and the waist. Radiological control procedures or work authorizations may also identify proper placement. 2) Supplement dosimeters are worn in accordance with site policy. This includes pocket, electronic dosimeters, extremity dosimetry, or multiple dosimeter sets. c. Take proper actions if dosimeter is lost, damaged, contaminated, or off-scale. If in an area controlled for radiological purposes, take the following actions: 1) Place work activities in a safe condition. 2) Alert others. 3) Immediately exit the area. 4) Notify radiological control personnel.

d. Store the dosimeter in the proper storage location. e. Return dosimeters for processing as directed. Personnel that fail to return dosimeters may be restricted from continued radiological work. Discuss facility-specific policy for storage of dosimeters. f. Dosimeters issued from the permanent work site cannot be worn at another site. g. (Insert facility-specific information.) DOE-HDBK-1130-98 Module 5: Personnel Monitoring Programs Instructor’s Notes 54 B. Internal Monitoring Whole body counters, chest counters, and/or bioassay samples may be used to monitor radioactive material in the human body. In some cases, the locations of radioactive material may be determined. An internal dose estimate may be performed based on these measurements. 1. Purpose of each type of internal monitoring. (Insert facility-specific information.) 2. Worker responsibilities (Insert facility-specific information.) C. Methods for Obtaining Radiation Dose Records EO2 State the purpose and work responsibilities for each type of internal monitoring method used at the site. 1. Individuals who are monitored for exposure at DOE facilities have the right to request reports of that exposure as follows: EO3 State the method for obtaining radiation dose records. a. Upon the request from an individual terminating employment, records of radiation dose shall be provided by the DOE facility within 90 days. If requested, a written estimate of radiation exposure received by the terminating employee shall be provided at the time of termination. b. Each individual required to be monitored for radiation exposure at a DOE facility shall receive a report of that exposure on an annual basis. c. Detailed information concerning any individual’s dose shall be made available to the individual upon request of that individual. d. When a DOE contractor is required to report to the Department, pursuant to Departmental requirements for occurrence reporting and processing, any exposure of an individual to radiation and/or radioactive material, or planned special exposure, the contractor shall also provide that individual with a report on his/her exposure data included therein. Such a report shall be transmitted at a time not later than the transmittal to the Department. DOE-HDBK-1130-98 Module 5: Personnel Monitoring Programs Instructor’s Notes 55 2. Reporting radiation dose received from other facilities and medical applications a. Notify Radiological Control personnel prior to and following any radiation dose received at another facility so that dose records can be updated. EO4 Identify worker responsibilities for reporting radiation dose received from other sites and from medical applications. b. Notify Radiological Control of medical radioactive applications. This does not include routine medical and dental X rays. This does include therapeutic and diagnostic radio- pharmaceuticals. (Insert facility-specific information.) III. SUMMARY (Insert facility-specific information.) IV. EVALUATION (Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 56 Module 6: Radiological Access Controls and Postings Terminal Objective: Given an area controlled for radiological purposes, the participant will be able to enter and exit the area in accordance with radiological access controls and postings. Enabling Objectives:

The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 State the purpose of and information found on Radiological Work Permits (RWPs). EO2 Identify the worker’s responsibilities in using Radiological Work Permits. EO3 Identify the colors and symbol used on radiological postings. EO4 State the radiological and disciplinary consequences of disregarding radiological postings, signs, and labels. EO5 Define the areas controlled for radiological purposes. EO6 Identify the minimum or recommended requirements for entering, working in, and exiting: a. Radiological Buffer Areas b. Radiation Areas c. Radioactive Material Areas d. Underground Radioactive Material Areas e. Soil Contamination Areas f. Fixed Contamination Areas EO7 Identify the areas a Radiological Worker I trained person may enter. EO8 Identify the purpose and use of personnel contamination monitors. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 57 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview Radiological Work Permits (RWP) used to control access into areas controlled for radiological purposes will be addressed. In addition, radiological requirements for working in these areas will be presented. C. Objectives Review Introduce objectives. D. Introduction The previous modules discussed some important radiological topics from a theoretical perspective. The current module will discuss the application of this theory to control radiological work in a safe but efficient manner. II. MODULE OUTLINE A. Radiological Work Permits (RWPs) 1. Purpose of RWPs RWPs may be used to establish radiological controls for entry into areas controlled for radiological purposes. They serve to: a. Inform workers of area radiological conditions. b. Inform workers of entry requirements. EO1 State the purpose of and information found on Radiological Work Permits (RWPs). c. Provide a record relating radiation doses to specific work activities. 2. Types of RWPs The type of RWP used will depend on the radiological conditions in the area. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 58 a. General Radiological Work Permit 1) This should be used to control routine or repetitive activities such as tours and inspections or minor work activities in areas with well characterized, stable radiological conditions. 2) General RWPs should not be approved for periods longer than 1 year. 3) Examples of use (Insert facility-specific information.) b. Job-specific radiological work permit 1) This should be used to control nonroutine operations or work in areas with changing radiological conditions. 2) It should only remain in effect for the duration of a particular job. 3) Examples of use (Insert facility-specific information.) c. An alternate formal mechanism, such as written procedures, experiment authorizations, or other written authorization, may be used in lieu of an RWP. The alternate method should include the elements of an RWP. 3. Information found on the RWP The RWP should include the following information: a. Description of work. b. Work area radiological conditions This information may also be determined from area radiological survey maps/diagrams or the radiological posting for that area.

c. Dosimetry requirements. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 59 d. Pre-job briefing requirements. Pre-job briefings generally consist of discussions among workers and supervisor(s) concerning various radiological aspects of the job. The purpose of the briefings should be to discuss radiological exposure and appropriate actions for unplanned situations. e. Required level of training for entry. f. Protective clothing/equipment requirements. g. Radiological Control coverage requirements and stay time controls, as applicable. h. Limiting radiological condition that may void the permit. i. Special dose or contamination reduction. considerations. j. Special personnel frisking considerations. k. Technical work document to be used, as applicable. l. Date of issue and expiration. m. Authorizing signatures and unique identifying designation or number. 4. Responsibilities of the worker when using an RWP a. Workers must read and comply with the RWP requirements. b. Workers must acknowledge they have read, understood, and agreed to comply with the RWP prior to entering the area and after any revision to the RWP. This is done by signature or through electronic means. EO2 Identify the worker’s responsibilities in using Radiological Work Permits. c. Radiological Control or a supervisor should be contacted prior to work if the RWP appears to be incorrect or is difficult to understand. d. Do not make substitutions for specified requirements. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 60 e. Report to Radiological Control personnel if radiological controls are not adequate or are not being followed. B. Radiological Postings 1. Radiological postings are used to: a. Alert personnel to the presence of radiation and radioactive materials. b. Aid in minimizing personnel dose. c. Prevent the spread of contamination. In addition, 10 CFR 835 - Subpart F specifies requirements for personnel entry controls for HR and VHR Areas. 2. Posting requirements a. Areas and materials controlled for radiological purposes will be designated with a magenta or black standard three-bladed radiological warning symbol (trefoil) on a yellow background. EO3 Identify the colors and symbol used on radiological postings. b. Fixed barriers such as walls, rope, tape, or chain will designate the boundaries of posted areas. Where possible, the barriers will be yellow and magenta in color. c. The barriers should be placed to clearly mark the boundary of the radiological areas. d. Entrance points to radiologically controlled areas should have signs or postings stating the entry requirements, such as “Personnel Dosimeters, RWP and Respirator Required.” e. In some cases, more than one radiological condition may be present. The area shall be posted to include all of the radiological conditions that are present. See 10 CFR 835.603. f. In areas of ongoing work activities, the dose rate and contamination levels (or ranges of each) may be included in postings. g. The posting will be placed where it is clearly visible to personnel. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 61 3. Responsibilities of the worker a. Before entering an area controlled for radiological purposes, read all of the signs. Since radiological conditions can change, the signs will also be changed to reflect the new conditions. A sign or posting that you saw one day may be replaced with a new one the next day.

EO2 Identify the worker’s responsibilities in using Radiological Work Permits. b. Obey any posted, written or oral requirements including “Exit,” “Evacuate,” “Hold Point,” or “Stop Work Orders.” These requirements may be included in RWPs and work procedures, and may come from Radiological Control personnel at the job site. 1) Hold points are specific times noted in a procedure, work permit, etc., where work must stop for Radiological Control or other evaluations. 2) Stop Work Orders are usually a result of: a) Inadequate radiological controls b) Failure to implement radiological controls c) Radiological hold point not being observed d) Changing or unexpected conditions. c. Report unusual conditions such as leaks, spills, or alarming area monitors to the Radiological Control personnel. d. Be aware of changing radiological conditions. Be aware that others’ activities may change the radiological conditions in your area. e. If any type of material used to identify a radiological hazard is found outside an area controlled for radiological purposes, it should be reported to Radiological Control personnel immediately. 4. Consequences of disregarding radiological postings, signs, and labels EO4 State the radiological and disciplinary consequences of disregarding radiological postings, signs, and labels. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 62 a. It is each worker’s responsibility to read and comply with all the information identified on radiological postings, signs, and labels. b. Disregarding any of these or removing/relocating them without permission can lead to: 1) Unnecessary or excessive radiation dose . 2) Personnel contamination. 3) Disciplinary actions such as formal reprimand, suspension, or even termination. C. Areas a RW I Trained Person Can Enter The level of training a radiological worker has successfully completed determines the types of areas he/she can enter. EO7 Identify the areas a Radiological Worker I- trained person may enter. 1. Radiological Buffer Areas (RBAs) RBAs are intermediate areas which DOE RCS recommends be established to prevent the spread of radioactive contamination and to protect personnel from radiation exposure. This area designation is not required by 10 CFR 835 and its use may vary from site to site. EO5 Define the areas controlled for radiological purposes. a. Posting Recommendations: “CAUTION, RADIOLOGICAL BUFFER AREA” b. Recommended requirements for unescorted entry should include: 1) Appropriate training, such as Radiological Worker I Training. EO6 Identify the minimum or recommended requirements for entering, working in, and exiting Radiological Buffer Areas. 2) Personnel dosimetry, as appropriate. 3) (Insert facility-specific information.) c. Recommended requirements for working in RBA (Insert facility-specific information.) DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 63 d. Recommended requirements for exiting an RBA: Personnel exiting a RBA containing a Contamination Area, High Contamination Area, or Airborne Radioactivity Area should, at a minimum, perform a hand and foot frisk. 1) General guidelines for handheld monitoring using a hand-held radioactive contamination survey instrument include the following: E08 Identify the purpose and use of personnel contamination methods. a) Verify the instrument is on, set to the proper scale, and within the calibration date.

b) Verify instrument response and source check. c) Ensure the audible function of the instrument is on and can be heard. d) Determine the instrument background. (Insert facility-specific information concerning acceptable background rates). e) Survey hands before picking up the probe. f) Hold the probe approximately ½" from the surface being surveyed for beta/gamma and ¼" for alpha radiation. g) Move probe slowly over the surface, approximately 2" per second. h) If the count rate increases during frisking, pause for 5 to 10 seconds over the area to provide adequate time for instrument response. 2) Alarm response for hand-held survey instrument a) If contamination is indicated, remain in the area and notify the Radiological Control personnel. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 64 b) Minimize cross contamination. For example, put a glove on a contaminated hand while waiting for the Radiological Control personnel to arrive. 3) Portal monitors (Insert facility-specific information.) 2. Radiation Areas (RAs) RAs are any areas accessible to individuals in which radiation levels could result in an individual’s receiving a deep dose equivalent in excess of 5 mrem/hr. This is established based on dose rates at 30 cm from the source of radiation. a. Posting Requirements: “CAUTION, RADIATION AREA” Additionally, the posting may state: “Personnel Dosimetry Required for Entry” b. Minimum requirements for unescorted entry should be: 1) Appropriate training, such as Radiological Worker I Training. 2) Personnel dosimeter. 3) Worker’s signature on the RWP, as applicable. 4) (Insert facility-specific information.) E05 Define the areas controlled for radiological purposes. E06 Identify the minimum or recommended requirements for entering, working in, and exiting Radiation Areas. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 65 c. Minimum requirements for working in an RA 1) Don’t loiter in the area. 2) Follow proper emergency response to abnormal situations. 3) Avoid hot spots. Hot spots are localized sources of radiation or radioactive material normally within facility piping or equipment. The radiation levels of hot spots exceed the general area radiation level by more than a factor of 5 and are greater than 100 mrem per hour on contact. Posting: “Caution, Hot Spot” 4) (Insert facility-specific information.) d. Minimum requirements for exiting a RA: 1) Observe posted exit requirements 2) Sign-out on RWP or equivalent, as applicable 3) Insert facility-specific information 3. Radioactive Materials Area (RMA) RMA means an area, accessible to individuals, in which items or containers of radioactive material exist and the total activity of rad-material exceeds ten times the applicable value provided in 10 CFR 835 Appendix E. EO5 Define the areas controlled for radiological purposes. a. Radioactive material may consist of equipment, components, or materials that have been exposed to contamination or have been activated. Sealed or unsealed radioactive sources are also included. b. Radioactive material may be stored in drums, boxes, etc., and will be marked appropriately. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 66 c. Posting Requirements: “CAUTION, RADIOACTIVE MATERIAL(S)” d. Exceptions to posting requirements.

1) Areas may be excepted from the posting requirements for periods of less than 8 continuous hours when placed under continuous observation and control of an individual knowledgeable of, and empowered to implement, required access and exposure control measures. See 10 CFR 835.604 2) The following areas may be excepted from the radioactive material area posting requirements: a) Areas posted Radiation Area, High Radiation Area, Very High Radiation Area, Airborne Radioactivity Area, Contamination Area, or High Contamination Area b) Areas in which each item or container of radioactive material is clearly and adequately labeled in accordance with 10 CFR 835 such that individuals entering the area are made aware of the hazard. c) The radioactive material consists solely of structures or installed components which have been activated. d) Areas containing only packages received from radioactive material transportation labeled and in a non-degraded condition need not be posted in accordance with 10 CFR 835 until the packages are surveyed. e. Minimum requirements for unescorted entry should include: DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 67 1) Appropriate training, such as Radiological Worker I Training. 2) For entry into Radioactive Material Areas where whole body dose rates exceed 5 mrem/hour, the Radiation Area entry requirements will apply. EO6 Identify the minimum or recommended requirements for entering, working in, and exiting Radioactive Materials Areas. 3) For entry into Radioactive Material Areas where removable contamination levels exceed the specified DOE limits, the Contamination Area entry requirements will apply. 4) (Insert facility-specific information.) Show sign. f. Minimum requirements for working in an RMA (Insert facility-specific information.) g. Minimum requirements for exiting an RMA (Insert facility-specific information.) 4. Fixed Contamination Area (Recommended) This area designation is recommended by the DOE RCS. It may be an area or equipment that contains radioactive material that cannot be easily removed from surfaces by nondestructive means, such as wiping, brushing, or laundering. This type of area designation is not required by 10 CFR 835 and its use may vary from site to site. EO5 Define the areas controlled for radiological purposes. EO6 Identify the minimum or recommended requirements for entering, working in, and exiting Fixed Contamination Areas. a. Recommended Posting: “CAUTION, FIXED CONTAMINATION” b. Contact the Radiological Control Organization for entry and exit requirements. c. (Insert facility-specific information.) Show sign. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 68 5. Soil Contamination Areas (for work that doesn’t disturb the soil) (Recommended) This area designation is recommended by the DOE RCS. It contains surface soil or subsurface contamination levels that exceed the recommended DOE limits. This type of area designation is not required by 10 CFR 835 and its use may vary from site to site. EO5 Define the areas controlled for radiological purposes. a. Posting: “CAUTION, SOIL CONTAMINATION AREA” b. Contact the Radiological Control Organization for entry and exit requirements. c. (Insert facility-specific information.) EO6 Identify the minimum or recommended requirements for entering, working in.,and exiting Soil Contamination Areas. Show sign.

6. Underground Radioactive Materials Areas (URMAS) (when an individual is not likely to receive a dose of >0.1 rem in a year) (Recommended) URMAS are area designations recommended by the DOE RCS. They are established to indicate the presence of underground items that contain radioactive materials such as pipelines, radioactive cribs, covered ponds, inactive burial grounds, and covered spills. This type of area designation is not required by 10 CFR 835, and its use may vary from site to site. EO5 Define the areas controlled for radiological purposes. a. Posting: “UNDERGROUND RADIOACTIVE MATERIALS” Show sign. Special instructions such as, "Consult with Radiological Control Organization before Digging" or "Subsurface Contamination Exists" may be included. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 69 b. General requirements: 1) An Underground Radioactive Materials Area may be exempt from the general entry and exit requirements if individual doses do not exceed 100 mrem in a year. EO6 Identify the minimum or recommended requirements for entering, working in, and exiting Underground Radioactive Material Areas. 2) Contact the Radiological Control Organization prior to entry. c. (Insert facility-specific information.) D. Areas a RW I Trained Person May Not Enter 1. High Radiation Areas (HRAs) HRA is any area accessible to individuals in which radiation levels could result in an individual receiving a deep dose equivalent in excess of 100 mrem/hr at 30 centimeters from the source. a. Posting Requirements: “CAUTION or DANGER, HIGH RADIATION AREA” Additionally, the posting may state: “Personnel Dosimetry Required for Entry” Show sign. b. Unescorted entry into this area requires appropriate training, such as RW II or RW I with the High Radiation Area training module. 2. Very High Radiation Areas (VHRs) A VHR is any area accessible to individuals in which radiation levels could result in an individual receiving an absorbed dose in excess of 500 rad/hr at 1 meter from the source of radiation. a. Posting Requirements: “GRAVE DANGER, VERY HIGH RADIATION AREA” Show sign. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 70 3. Contamination Areas (CAs) CAs are those areas, accessible to individuals, in which removable contamination levels are greater than 1 time but less than or equal to 100 times the specified limits in Appendix D of 10 CFR 835. a. Posting Requirements: “CAUTION, CONTAMINATION AREA” b. Unescorted entry into this area requires appropriate training, such as RW II training. 4. High Contamination Areas (HCAs) An HCA is an area, accessible to individuals, in which removable contamination levels are 100 times or more the specified limits in Appendix D of 10 CFR 835. a. Posting Requirements: “CAUTION or DANGER, HIGH CONTAMINATION AREA” Show sign. Additionally, the posting may state: “RWP REQUIRED FOR ENTRY” b. Unescorted entry into this area requires appropriate training, such as RW II training. 5. Airborne Radioactivity Areas (ARAs) ARAs are those areas, accessible to individuals, where the concentration of airborne radioactivity, above natural background, exceeds or is likely to exceed the specified limits in 10 CFR 835. a. Posting Requirements: “CAUTION or DANGER AIRBORNE RADIOACTIVITY AREA” Additionally, the posting may state: “RWP REQUIRED FOR ENTRY” Show sign.

b. Unescorted entry into this area requires appropriate training, such as RW II training. DOE-HDBK-1130-98 Module 6: Radiological Access Controls and Postings Instructor’s Notes 71 III. SUMMARY (Insert facility-specific information.) IV. EVALUATION (Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 7: Radiological Emergencies Instructor’s Notes 72 Module 7: Radiological Emergencies Terminal Objective: Given a radiological emergency or alarm, identify the appropriate responses in accordance with approved lesson materials. Enabling Objectives: The participant will be able to SELECT the correct response from a group of responses to verify his/her ability to: EO1 State the purpose and types of emergency alarms. EO2 Identify the correct responses to emergencies and alarms. EO3 State the possible consequences of disregarding radiological alarms. EO4 State the site administrative emergency radiation dose guidelines. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 7: Radiological Emergencies Instructor’s Notes 73 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview This module discusses off-normal and emergency situations and the appropriate response to each. Radiological alarms associated with monitoring equipment will also be discussed. C. Objectives Review Introduce objectives. D. Introduction Monitoring systems are used to warn personnel when off-normal radiological conditions exist. Radiological workers must become familiar with these alarms and know the response to each. These responses will help to minimize exposure and personal contamination during off- normal conditions. II. MODULE OUTLINE A. Emergency Alarms and Responses Equipment that monitors radiation dose rates and airborne contamination levels is placed throughout DOE radiological facilities. It is essential for radiological workers to recognize the equipment and the associated alarms and know the appropriate response. EO1 State the purpose and types of emergency alarms. 1. Area Radiation Monitors C Types and purpose C Operational check (if appropriate) C Alarms C Appropriate response (Insert facility-specific information.) DOE-HDBK-1130-98 Module 7: Radiological Emergencies Instructor’s Notes 74 2. Airborne Contamination Monitors C Types and purpose C Operational check (if appropriate) C Alarms C Appropriate response (Insert facility-specific information.) EO2 Identify the correct responses to emergencies and alarms. 3. Disregard for Radiological Alarms Disregarding any of these radiological alarms may lead to: EO3 State the possible consequences of disregarding radiological alarms. C Possible excessive radiation dose C Unnecessary spread of contamination C Unnecessary personal contamination C Disciplinary action B. Radiological Emergency Situations Working in a radiological environment requires more precautionary measures than performing the same job in a nonradiological setting. If an emergency arises during radiological work, response actions may be necessary to ensure personnel safety. 1. Personnel injuries in areas controlled for radiological purposes. (Insert facility-specific information.) EO2 Identify the correct responses to emergencies and/or alarms.

2. Situations that require immediate exit from an area controlled for radiological purpose. (Insert facility-specific information.) 3. An accidental breach of a radioactive system or spill of radioactive material a. For radioactive spills involving highly toxic chemicals, workers should immediately exit the area without attempting to stop or secure the spill. They should then promptly notify Industrial Hygiene or the Hazardous Material team and Radiological Control personnel. DOE-HDBK-1130-98 Module 7: Radiological Emergencies Instructor’s Notes 75 b. For other spills: C Stop or secure the operation causing the spill, if it can be done safely C Warn others in the area and notify Radiological Control personnel C Isolate the spill area, if possible C Minimize individual exposure and contamination C Secure unfiltered ventilation (fan, open windows, etc.) C. Considerations in Rescue and Recovery Operations 1. In extremely rare cases, emergency exposure to high levels of radiation may be necessary. This is done to rescue personnel or protect major property. 2. Rescue and recovery operations that involve radiological hazards can be very complex. 3. The type of response to these operations is generally left up to the official in charge of the emergency situation. The official’s judgment is guided by many variables that include determining the risk versus the benefit of an action and deciding how best to implement the action. 4. No individual shall be required to perform a rescue action that might involve substantial personal risk. All personnel selected to provide emergency response shall be trained commensurate with the hazards in the area and required controls. They shall be briefed beforehand on the known or anticipated hazards to which they shall be subjected. 5. The DOE guidelines for control of Emergency Exposure are as follows: DOE-HDBK-1130-98 Module 7: Radiological Emergencies Instructor’s Notes 76 Table 7-1 Guidelines for Control of Emergency Exposures Dose limit1 (whole body) Activity performed Conditions 5 rem 10 rem 25 rem All activities Protecting major property. Lifesaving or protection of large populations. Where lower dose limit is not practicable. >25 rem Lifesaving or protection of large populations. Only on a voluntary basis to personnel fully aware of the risks involved. 1The lens of the eye dose guideline is three times the listed values. The shallow dose guideline to the skin of the whole body and the extremities is 10 times the listed values. These doses are in addition to and accounted for separately from the doses received under the limits in §§835.202 and 835.205. 6. Site administrative emergency dose guidelines for rescue and recovery operations. (Insert facility-specific information.) EO4 State the site administrative emergency radiation dose guidelines. III. SUMMARY (Insert facility-specific information.) IV. EVALUATION (Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 8: High/Very High Radiation Area Training Instructor’s Notes 77 Module 8: High/Very High Radiation Area Training Prerequisite: Core Academics (Modules 1-7) Terminal Objective: Given a High or Very High Radiation area sign, define the area and identify the requirements for entry to High Radiation Areas in accordance with the lesson material. Enabling Objectives:

The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 Define “High Radiation Area” and “Very High Radiation Area.” EO2 Identify sources and locations that may produce High Radiation Areas and Very High Radiation Areas at the site. EO3 State the minimum requirements for entering, working in, and exiting High Radiation Areas. EO4 State the administrative and physical controls for access to High Radiation Areas. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 8: High/Very High Radiation Area Training Instructor’s Notes 78 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview This module discusses information regarding entry, work in, and control of High Radiation Areas and the materials and systems that can emit high radiation levels. C. Objectives Review Introduce objectives. D. Introduction 1. The High Radiation Area lesson plan familiarizes the participant with requirements for entry, work in, and exit from High Radiation Areas. 2. Radiological Worker Modules 1-7 (core academic material) are a prerequisite for this module. If prerequisite requirements are met, this module may be taught alone. II. MODULE OUTLINE A. High and Very High Radiation Area Definitions 1. High Radiation Area A High Radiation Area is any area, accessible to individuals, in which radiation levels could result in an individual receiving a deep dose equivalent in excess of 0.1 rem (100 mrem), but less than or equal to 500 rad in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. EO1 Define High Radiation Area and Very High Radiation Area. 30 cm is approximately = to 1 foot (11.81 inches) 2. Very High Radiation Area A Very High Radiation Area is any area, accessible to individuals, in which radiation levels could result in an individual receiving an absorbed dose in excess of 500 rads in one hour at 1 meter from a radiation source or from any surface that the radiation penetrates. 1m is slightly more than 1 yard (39.37 inches) DOE-HDBK-1130-98 Module 8: High/Very High Radiation Area Training Instructor’s Notes 79 B. Signs and Postings 1. High Radiation Area High Radiation Areas will be posted with a standard radiation symbol colored magenta (or black) on a yellow background, reading: “CAUTION” or “DANGER HIGH RADIATION AREA” Additionally the posting may state: “Personnel Dosimeter, Supplemental Dosimeters, and RWP Required for Entry” Show sign. 2. Very High Radiation Area Very High Radiation Areas will be posted with a standard radiation symbol colored magenta (or black) on a yellow background, reading: “GRAVE DANGER, VERY HIGH RADIATION AREA” Show sign. Additionally the posting may state: “Special Controls Required for Entry” Some HRAs and VHRAs only exist when machinery is energized, such as radiation producing devices. For example, a posting could be: “High Radiation Area When Warning Light is On” “Controlled Area When Warning Light is Off” 3. Radiation sources (Insert facility-specific information on radiation sources that can produce High/Very High Radiation Areas and the location of each.) EO2 Identify sources and locations that may produce High Radiation Areas and Very High Radiation Areas. DOE-HDBK-1130-98 Module 8: High/Very High Radiation Area Training Instructor’s Notes

80 Table 8-1 High and Very High Radiation Area Definitions and sources (Objectives EO1 and EO2) Sign Definition Sources Insert HRA sign > 100 mrem in 1 hour This is taken at 30 centimeters from the source of radiation or any surface that the radiation penetrates. (Insert facility- specific sources and locations.) Insert VHRA sign > 500 rad in 1 hour This is taken at 100 centimeters from the source of radiation, or any surface that the radiation penetrates. (Insert facility- specific sources and locations.) C. Entry, Work In, and Exit from High Radiation Areas 1. Minimum requirements for entering HRAs EO3 State the minimum requirements for entering HRAs. a. Appropriate training (e.g., Radiological Worker I Training plus High Radiation Area Training or Radiological Worker II Training). b. Worker signature on the appropriate Radiological Work Permit (RWP). c. Personnel and supplemental dosimeter. d. Survey meter(s) or dose rate indicating device available at the work area (may be required for certain jobs). Workers need to receive proper training prior to using a dose rate indicating device. e. Access control. f. A radiation survey prior to first entry. g. Notification of operations personnel. h. Additional requirements where dose rates are greater than 1 rem in an hour. These should include: DOE-HDBK-1130-98 Module 8: High/Very High Radiation Area Training Instructor’s Notes 81 1) Determination of worker’s current dose. 2) Pre-job briefing, as applicable. 3) Review and determination by the RCO regarding the level of RC technician coverage. 4) Access Points secured by control devices. Required by 10 CFR 835. i. Additional measures to ensure personnel are not able to gain unauthorized or inadvertent access to Very High Radiation Areas. j. (Insert facility-specific information.) 2. Minimum requirements for working in HRAs a. Don’t loiter. b. Practice ALARA. c. (Insert facility-specific information.) EO3 State the minimum requirements for working in HRAs. 3. Minimum requirements for exiting HRAs No controls shall be established in a Radiological Area that would prevent rapid evacuation of personnel. a. Sign out on RWP, as applicable. b. (Insert facility-specific information.) EO3 State the minimum requirements for exiting HRAs. DOE-HDBK-1130-98 Module 8: High/Very High Radiation Area Training Instructor’s Notes 82 D. Access Controls for High and Very High Radiation Areas There are different controls that are used to prevent the inadvertent entry or unauthorized access into Radiological Areas. The following identifies administrative and physical controls that are used for HRAs. 1. Administrative controls The following are administrative controls that may be used to control access to HRAs. These are used in addition to physical controls. a. Formal radiological reviews. EO4 State the administrative and physical controls for access to HRAs. b. RWPs. c. Pre-job briefings. d. Procedures. e. Postings. f. Administrative control levels (ACLs). g. (Insert facility-specific information.) 2. Physical controls One or more of the following features should be used for each entrance or access point to an HRA and shall be used for HRAs >1 rem in any one hour. It should be noted again that no controls shall be established in an HRA or VHRA that would prevent rapid evacuation of personnel. EO4 State the administrative and physical controls for access to HRAs.

a. A control device that prevents entry or upon entry causes the radiation level to be reduced below that level defining an HRA. b. An automatic device that prevents use or operation of the radiation source. c. A control device that energizes a visible or audible alarm. d. Entryways that are locked. Maintain positive control over each entry. DOE-HDBK-1130-98 Module 8: High/Very High Radiation Area Training Instructor’s Notes 83 e. Continuous direct or electronic surveillance. f. (Insert facility-specific information.) 3. Consequences of violating radiological signs or postings, or bypassing physical access controls: a. Equipment damage. b. Personnel injury. c. Excessive and unplanned personnel exposure. d. Disciplinary action. E. Access to VHRAs Due to the extremely high dose rates in a VHRA, personnel access to these areas needs to be strictly monitored and controlled. Additional training would be required, as well as enhanced monitoring. III. SUMMARY (Insert facility-specific information.) IV. EVALUATION (Insert facility-specific information.) Refer to RWT Program Management Guide for evaluation guidance. DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 84 Module 9: Radioactive Contamination Control Prerequisites: Core Academics - (Modules 1-7) Terminal Objective: Given different types of radioactive contamination, identify the methods used to control the spread of radioactive contamination in accordance with lesson material. Enabling Objectives: The participant will be able to select the correct response from a group of responses to verify his/her ability to: EO1 Define fixed, removable, and airborne contamination. EO2 State sources of radioactive contamination. EO3 State the appropriate response to a spill of radioactive material. EO4 Identify methods used to control radioactive contamination. EO5 Identify the proper use of protective clothing. EO6 Identify the purpose and use of personnel contamination monitors. EO7 Identify the normal methods used for decontamination. EO8 Define “Contamination,” “High Contamination,” and “Airborne Radioactivity Areas.” EO9 Identify the minimum requirements for entering, working in, and exiting Contamination, High Contamination, and Airborne Radioactivity Areas. Instructional Aids: 1. Student Guide 2. Transparencies 3. Activities (as applicable) 4. Self-check quizzes (as applicable) DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 85 I. MODULE INTRODUCTION A. Self Introduction 1. Name 2. Phone Number 3. Background B. Module Overview This module is designed to inform the worker about radioactive contamination and discuss methods used to control the spread of contamination. C. Objectives Review Introduce objectives. D. Introduction Contamination control is one of the important aspects of radiological protection. Using proper contamination control practices helps to ensure a safe working environment. It is important for all employees to recognize potential sources of contamination and to use appropriate contamination control methods. II. MODULE OUTLINE A. Comparison of Ionizing Radiation and Radioactive Contamination 1. Ionizing radiation Energy (particles or rays) emitted from radioactive atoms or generated from machines such as X-ray machines that can cause ionization (e.g., gamma rays, X rays, beta particles, and other particles capable of ionizing atoms). DOE-HDBK-1130-98

Module 9: Radioactive Contamination Control Instructor’s Notes 86 2. Radioactive contamination Radioactive material is material that contains radioactive atoms. When radioactive material is properly contained, it still emits radiation and may be an external dose hazard, but it is not a contamination hazard. When radioactive material escapes its container, it is then referred to as radioactive contamination. 3. Radiation is energy; contamination is a material. B. Types of Contamination Radioactive contamination can be fixed, removable, or airborne. EO1 Define fixed, removable, and airborne contamination. 1. Fixed contamination is contamination that cannot be easily removed from surfaces. a. It cannot be removed by casual contact. b. It may be released when the surface is disturbed (buffing, grinding, using volatile liquids for cleaning, etc.). c. Over time it may “weep,” leach, or otherwise become loose or removable. 2. Removable contamination is contamination that can easily be removed from surfaces. Any object that comes in contact with it may become contaminated. a. It may be transferred by casual contact, wiping, brushing, or washing. b. Air movement across removable contamination could cause the contamination to become airborne. 3. Airborne contamination is contamination suspended in air. DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 87 Table 9-1 Types of Radioactive Contamination Types Definitions (Objective EO1) Fixed Contamination Cannot be removed by casual contact. It may be released when the surface is disturbed (buffing, grinding, using volatile liquids for cleaning, etc.). Over time, may become loose or removable. Removable Contamination May be transferred by casual contact. Any object that makes contact with it may in turn become contaminated. Air movement across removable contamination may cause the contamination to become airborne. Airborne Contamination Airborne contamination is contamination suspended in the air. C. Radioactive Contamination Radiological work is required in areas and in systems that are contaminated by design (e.g., maintenance of valves in radioactive fluid systems). EO2 State sources of radioactive contamination. Regardless of the precautions taken, radioactive material will sometimes contaminate objects, areas, and people. 1. Sources The following are some sources of radioactive contamination. a. Leaks or breaks in radioactive fluid systems. b. Leaks or breaks in air-handling systems for radioactive areas. c. Airborne contamination depositing on surfaces. d. Leaks or tears in radioactive material containers such as barrels, plastic bags or boxes. DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 88 e. Another common cause of contamination is sloppy work practices. These may lead to contamination of tools, equipment, and workers. Examples include: 1) Opening radioactive systems without proper controls. 2) Poor housekeeping in contaminated areas. 3) Excessive motion or movement in areas of higher contamination. 4) Improper usage of step-off pads and change areas. 5) Violation of contamination control ropes and boundaries. f. Hot particles: Small, sometimes microscopic pieces of highly radioactive material may escape containment. These pieces are known as “hot particles.” 1) Hot particles may be present when contaminated systems leak or are opened. These particles may also be present when machining, cutting, or grinding is performed on highly radioactive materials.

2) Hot particles can cause a high, localized radiation dose in a short period of time if they remain in contact with skin. 2. Indicators of possible contamination: Radiological workers should be aware of potential radioactive contamination problems. Potential contamination problems should be reported to the Radiological Controls Organization. Examples include: a. Leaks, spills, or standing water that is possibly from a radioactive fluid system. b. Damaged or leaking radioactive material containers. c. Open radioactive systems with no observable controls. DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 89 d. Dust/dirt accumulations in radioactive contamination areas. e. Torn or damaged tents and glove bags or containments on radioactive systems. 3. Radiological worker response to a spill of radioactive material Each of the examples listed above may be a spill of radioactive material. Here is the minimum response to a spill of radioactive material: EO3 State the appropriate response to a spill of radioactive material. a. Stop or secure the operation causing the spill, if qualified. b. Warn others in the area. c. Isolate the area. d. Minimize exposure to radiation and contamination. e. Secure unfiltered ventilation. f. Notify Radiological Control personnel. D. Contamination Control Methods Every radiological worker should perform work in such a manner as to minimize the generation of radioactive contamination and confine the spread of radioactive contamination to the smallest area possible. By controlling contamination, the worker minimizes the potential for internal exposure, and personnel contamination can be minimized. Examples of methods used to control the spread of radioactive contamination follow: 1. Prevention A sound maintenance program can prevent many radioactive material releases. EO4 Identify the methods used to control radioactive contamination. a. Establish a solid routine maintenance program for operating systems to minimize failures and leaks that lead to contamination. b. Repair leaks as soon as identified to prevent a more serious problem. c. Establish adequate work controls before starting jobs. DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 90 d. During pre-job briefings, discuss measures that will help reduce or prevent contamination spread. The agreed upon measures should be implemented by workers at the job site. e. Change protective gear (e.g., gloves) as necessary (typically as directed by Radiological Control personnel) to prevent cross-contamination. f. Stage areas to prevent contamination spread from work activities. 1) Cover work area to minimize cleanup afterward. 2) Cover piping/equipment below a work area to prevent dripping contamination onto cleaner areas. 3) Cap contaminated pipes or systems when not in use. g. Prepare tools and equipment to prevent contamination. 1) Bag or sleeve hoses and lines to prevent contamination. 2) Minimize the equipment and tools taken into and out of contamination areas. 3) Cover/tape tools or equipment used during the job to minimize decontamination after the job (i.e., taping up a screwdriver before use). h. Use good housekeeping practices; clean up during and after jobs. “Good Housekeeping” is a prime factor in an effective contamination control program. Each radiological worker should keep his/her work area neat and clean to control the spread of contamination.

DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 91 i. Use standard contamination control procedures as established by the Radiological Control Organization. 1) Do not violate contamination area ropes or barricades. 2) Frisk materials out of contamination areas as directed by site procedures. 3) Use change areas and step-off pads as directed. 4) Do not pass items out of contamination areas without following site procedures. 5) Be alert for potential violations to contamination control procedures. j. Ensure ventilation systems are operating as designed (i.e., no unauthorized modifications). k. Radiological workers should always ensure that the proper entry, exit, and equipment control procedures are used to avoid the spread of contamination. Comply with procedures!! 2. Engineering controls a. Ventilation EO4 Identify methods used to control radioactive contamination. 1) Systems and temporary spot ventilation (e.g., temporary enclosures with HEPA filters) are designed to maintain airflow from areas of least contamination to areas of most contamination (e.g., clean to contaminated to highly contaminated areas). 2) A slight negative pressure is maintained on buildings/rooms/enclosures where potential contamination exists. 3) High efficiency particulate air (HEPA) filters are used to remove radioactive particles from the air. HEPA - High Efficiency Particulate Air filter. DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 92 b. Containment Permanent and temporary containments are used for contamination control. Examples include vessels, pipes, cells, glovebags, gloveboxes, tents, huts, and plastic coverings. 3. Personal Protective Measures Sometimes engineering controls cannot eliminate contamination. Personnel protective measures, such as protective clothing and respiratory equipment, will be used at this point. a. Protective clothing EO5 Identify the proper use of protective clothing. 1) Protective clothing is required for entering areas containing contamination and airborne radioactivity levels above specified limits to prevent personnel contamination. 2) The amount and type of protective clothing required is dependent on work area radiological conditions and nature of the job. 3) Personal effects such as watches, rings, jewelry, etc., should not be worn. 4) Full protective clothing generally consists of: a) Coveralls. b) Cotton liners. c) Rubber gloves. d) Shoe covers. e) Rubber overshoes. f) Hood. NOTE: Cotton glove liners may be worn inside rubber gloves for comfort, but should not be worn alone or considered as a layer of protection against contamination. DOE-HDBK-1130-98 Module 9: Radioactive Contamination Control Instructor’s Notes 93 5) Proper use of protective clothing a) Inspect protective clothing for rips, tears, or holes prior to use. If you find damaged protective clothing, discard properly. b) Supplemental and multiple dosimeters should be worn as prescribed by the Radiological Control Organization. c) After donning protective clothing, proceed directly from the dress-out area to the work area. d) Avoid getting coveralls wet. Wet coveralls provide a means for contamination to reach the skin/clothing. e) Contact Radiological Control personnel if clothing becomes ripped, wet, or otherwise compromised. b. Respiratory protection equipment This is used to prevent the inhalation of radioactive materials. This training course DOES NOT qualify