DOE-HDBK-1141-2008, Radiological Assessor Training

DOE-HDBK-1141-2008 August 2008 DOE HANDBOOK Radiological Assessor Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techs\ Foreword This Handbook describes an implementation process for training as recommended in Implementation Guide G441.1-1B, Radiation Protection Programs, March 2007, and as outlined in DOE- STD- 1098-99, CN1, March 2005, DOE Radiological Control (the 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 training required by Title 10 Code of Federal Regulations Part 835 Occupational Radiation Protection (10 CFR 835) and training recommended by the RCS. This training is intended for auditors and assessors to assist in meeting the training requirements of 10 CFR 835 for the conduct of audits and assessments of occupational radiation protection programs. While this Handbook addresses many requirements of 10 CFR 835 Subpart B, it must be supplemented with facility-specific information to achieve full compliance. This Handbook contains recommended training materials consistent with other DOE radiological safety training materials. The training material consists of the following five parts: Program Management Guide - This part contains detailed information on how to use the Handbook material. Instructor’s Guide - This part contains lesson plans for instructor use, including notation of key points for inclusion of facility-specific information. Overheads - This part contains overheads instructor use corresponding to the Instructor's Guide. Student’s Guide - This part contains student handout material and also should be augmented by facility-specific information. Handouts - This part contains several student handouts that provide supporting information for various modules. This training material is targeted for individuals with a basic knowledge of radiological protection concepts and provides material on how to conduct a radiological assessment. This Handbook was produced in Microsoft Word and has been formatted for printing on a HP 4M (or higher) LaserJet printer. Overheads were produced in Powerpoint. Copies of this Handbook may be obtained from either the DOE Radiation Safety Training Home Page Internet site (http://www.hss.energy.gov/healthsafety/wshp/radiation/RST/rstmater.htm) or the Technical Standards Internet site (http://www.hss.energy.gov/nuclearsafety/techstds). iii This page intentionally left blank. Part 1 of 5 Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide Office of Health, Safety & Security U.S. Department of Energy Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide ii This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide iii Table of Contents Page Introduction ................................................................................................................................... 1 Purpose and Scope .................................................................. 1

Compliance with 10 CFR 835-Subpart B ................................. 1 Goal of Training Program ......................................................... 2 Organizational Relationships and Reporting Structure ............ 2 Training Program Descriptions................................................................................................... 3 Overview of Training Program.................................................. 3 Prerequisites ............................................................................. 3 Proficiency Requirements......................................................... 4 Retraining.................................................................................. 5 Instructor Training and Qualifications....................................... 5 Training Program Material Development ................................................................................... 6 Training Material Presentation.................................................. 6 Training Certificates .................................................................. 7 Training Aids, References ........................................................ 7 Training Program Standards and Policies................................................................................. 8 Lectures, Seminars, Training Exercises, etc............................ 8 Delinquent Training/Failure ...................................................... 8 Exceptions and Waivers ........................................................... 8 Administration............................................................................................................................... 9 Training Records....................................................................... 9 Training Program Development/Change Requests ................. 9 Audits (internal and external).................................................... 9 Evaluating Training Program Effectiveness ........................... 10 References and Supporting Documents.................................................................................. 11 Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide iv This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 1 Introduction Purpose and Scope This handbook describes a Radiological Assessor Training program. It includes standards and policies as well as recommendations for material development and program administration. It is intended for use by DOE and DOE contractors for the development of facility- specific radiological assessor training. This material is intended for assessment of occupational radiation protection programs. This material does not address environmental radiation protection programs. Compliance with 10 CFR 835-Subpart B The DOE training materials for Radiological Assessor Training reflect the requirements identified in 10 CFR 835-Subpart B, Management and Administrative Requirements, and recommendations identified in the DOE Implementation Guide G441.1-1B, Radiation Protection Programs Guide, and in DOE-STD-1098-99, DOE Radiological Control Standard. When implemented in its entirety and supplemented as noted with appropriate facility-specific information, this handbook provides an acceptable method to meet the requirements of 10 CFR 835-Subpart B for training of individuals

(auditors and assessors) responsible for developing and implementing measures necessary for ensuring compliance with 10 CFR 835 (10 CFR 835.103). Radiological Assessor Training DOE-HDBK-1141-2001 Program Management Guide 2 However, it is incumbent on management of each facility to review the content of this handbook against the radiological hazards present to ensure that the training content is appropriate to each individual’s prior training, work assignments, and degree of exposure to potential radiological hazards. Training described in this handbook does not eliminate the need for additional training on 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 need be presented. The site Radiological Control Manager or designee should concur in facility- generated radiological training material. Goal of Training Program The goal of the training program is to provide a sufficient level of knowledge and skills in radiological assessment fundamentals commensurate with the assigned duties and potential radiological hazards encountered at DOE facilities using or possessing radioactive materials and/or radiation-producing devices. Organizational Relationships and Reporting Structure The DOE Office of Health, Safety and Security’s Office of Worker Safety and Health Policy (HS-11) is responsible for approving and maintaining the training materials. The establishment of a comprehensive and effective contractor site radiological control training program is the Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 3 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. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 4 Training Program Descriptions Overview of Training Program Radiological Assessor Training may be provided to individuals (auditors and assessors) responsible for developing and implementing measures necessary for ensuring compliance with 10 CFR 835 at a DOE site or facility. The terminal objective is that, upon completion of this training, individuals with appropriate education and experience may conduct audits, assessments, appraisals and surveillances of occupational radiation protection programs at a DOE site or facility in accordance with 10 CFR 835.103 and in meeting other quality assurance requirements. Prerequisites The material is targeted for individuals with a baseline knowledge of radiological protection concepts and provides material on how to conduct a radiological assessment. DOE has developed training materials for radiation protection concepts as part of the Department’s Technical Qualification Program. Students participating in the Radiological Assessors Training should be able to demonstrate competence of radiation protection concepts equivalent to the DOE Technical Qualification Program Topic Area Radiation Protection. The student Manual for the Radiation Protection Topic Area provides a good review of the competency topical expectations. DOE has also provided guidance on qualifications of radiological assessors in DOE STD-1107-97 Knowledge, Skills, and Abilities for Key Radiation Protection Positions

at DOE Facilities. Students should be capable of meeting Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 5 Proficiency Requirements this standard prior to conducting independent technical evaluations/assessments of radiation protection programs (i.e. evaluations beyond simple surveillances of radiation protection program implementation). In accordance with 10 CFR 835-Subpart B, each individual shall have appropriate education, training and skills to discharge their responsibilities for ensuring compliance with 10 CFR 835. Refer to DOE Order 5480.20A, Personnel Selection, Qualification, and Training Requirements for DOE Nuclear Facilities, for qualification requirements for technical staff (this category frequently includes radiological assessors). An examination or performance demonstration is recommended. Retraining Sites are encouraged to develop periodic training and retraining for radiological assessors and auditors. Retraining should focus on lessons learned and site specific events as necessary. Materials developed in support of training 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 Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 6 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. 2.Instructors should have the technical qualifications, including 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. DOE Order 5480.20A, Personnel Selection, Qualification, and Training Requirements for DOE Nuclear Facilities, discusses qualification requirements for instructors. DOE has also provided guidance on qualifications of radiological instructors in DOE STD-1107-97 Knowledge, Skills, and Abilities for Key Radiation Protection Positions at DOE Facilities. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 7 Training Program Material Development Training Material Presentation Training materials consist of lesson plans, overheads, student guides, and handouts. To ensure appropriate training, facility-specific materials must be added to the materials when necessary to adequately train individuals for facility-specific radiological hazards. For example, facility-specific modules may be added to cover such topical areas as: reactors, breeder reactors, spent fuel storage, radwaste burial, radwaste storage, high level waste storage, tank farms, reprocessing plants, and vitrification plants.

Conversely, modules with no applicability to a facility or site may be omitted (e.g., a tritium facility may want to omit modules on uranium and plutonium). It is estimated that this material could be presented in 44 hours. The Table of Contents in the Instructor's Guide provides a recommended breakdown of time per module. Training Certificates A training certificate that identifies the individual’s current training status may be provided to qualified personnel. Each facility is responsible for determining the training status of employees. Facilities have the option of utilizing a certificate as proof of training. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 8 Training Aids, References Facility-specific training aids should be developed at the facility to suit individual training styles. Each facility may add information, activities, and/or view graphs to enhance the program. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 9 Training Program Standards and Policies Lectures, Seminars, Training Exercises, etc. Delinquent Training/Failure Radiological assessor training is designed to be delivered in a classroom setting. An alternate delivery method may be implemented with computer-based training (CBT) equipment or web-based training (WBT) equipment. The presentation of training should include DOE developed materials and facility-specific information. Employees who are delinquent on initial training or retraining should lose their status of being qualified assessors or auditors until successful completion of the delinquent training requirement. Exceptions and Waivers Successful completion of the Radiological Assessor 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 B is the responsibility of the facility in which the individual will be conducting assessments. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 10 Administration Training Records Training records and course documentation shall meet the requirements of 10 CFR 835.704 Administrative Records. Training Program Development/Change Requests All requests for program changes and revisions that are generic in nature may be submitted using DOE F 1300.3 Document Improvement Proposal. A copy of DOE F 1300.3 and instructions are included at the end of this document. 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. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 11 Evaluating Training Program Effectiveness Verification of the effectiveness of Radiological Assessor Training should be accomplished by surveying a limited subset of former students in the workplace. This evaluation should include observation of practical applications and discussion of the course material. DOE/HSS has issued guidelines for evaluating the effectiveness of radiological training through the DOE Operations Offices and DOE Field Offices. These guidelines are available from the DOE Radiation Safety Training Home Page. (See the Foreword of this

document.) 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 programs. Radiological Assessor Training DOE-HDBK-1141-2008 Program Management Guide 12 References and Supporting Documents U.S. Department of Energy, DOE Order 5480.20 change 1, Personnel Selection, Qualification, and Training Requirements for DOE Nuclear Facilities, July 2001. U.S. Department of Energy, DOE STD-1098-99, Radiological Control, Reaffirmed December 2004. U.S. Department of Energy, DOE STD-1107-97, Knowledge, Skills, and Abilities for Key Radiation Protection Positions at DOE Facilities, January 1997. U.S. Department of Energy, 10 CFR 835, Occupational Radiation Protection, June 2007. Part 2 of 5 Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Office of Health, Safety and Security U.S. Department of Energy Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide ii This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide iii Table of Contents Regulatory Documents * (2).............................................................................Module1-1 10 CFR Part 835, Background and Focus (3)..................................................Module 2-1 Overview of the DOE Radiological Control Manual (3) ....................................Module 3-1 Elements of a Radiological Control Program (2) ..............................................Module 4-1 Technical Safety Requirements (2)..................................................................Module 5-1 Radiological Aspects of Uranium (2)................................................................Module 6-1 Radiological Aspects of Tritium (2) ..................................................................Module 7-1 Radiological Aspects of Plutonium (2) .............................................................Module 8-1 Radiological Work Permits (2)..........................................................................Module 9-1 Contamination Containment and Temporary Control Measures (1)...............Module 10-1 Radiological Work Site Mockup Demonstration (2)........................................Module 11-1 Radiation-Generating Devices (2)..................................................................Module 12-1 Radiological Aspects of Accelerators (2) .......................................................Module 13-1 Assessment Techniques (3) ..........................................................................Module 14-1 Planning and Conducting Assessments (3) ...................................................Module 15-1 Case Studies (2) ............................................................................................Module 16-1 Review and Critique of Findings and Improved Writing of Findings (2)..........Module 17-1 Compliance-Based Versus Performance-Based Evaluations (1)...................Module 18-1 Field Exercise Guidelines (4) .........................................................................Module 19-1 Course Summary (2 - with exam) ..................................................................Module 20-1 * (#) - Estimated time in hours Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide iv This page intentionally left blank.

Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Regulatory Documents Objectives: Upon completion of this training, the participant will be able to: 1. Identify the hierarchy of regulatory documents. 2. Define the purpose of 10 CFR Part 835. 3. Define the purpose of the DOE Radiological Control Standard. 4. Define the terms “shall” and “should” as used in the above documents. 5. Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites and facilities. Training Aids: Overhead Transparencies (OTs): OT 1.1 – OT 1.17 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Flip chart Markers Masking tape Student Materials: Student’s Guide References: U.S. Department of Energy, 10 CFR Part 820, Procedural Rules for DOE Nuclear Activities, 2007. U.S. Department of Energy, 10 CFR Part 835, Occupational Radiation Protection, 2007. U.S. Department of Energy, Radiological Control, DOE STD-1098-99, Reaffirmed December 2004. U.S. Department of Energy, Department of Energy Radiological Health and Safety Policy, DOE P 441.1, April 1996. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 2 I. Introduction II. DOE radiological health and safety A. Policy (some key points in summary) • Establish and maintain a system of regulatory policy and guidance. • Ensure appropriate training is developed and delivered and the technical competence of the DOE workforce. • Establish and maintain, from the lowest to the highest levels, line management involvement and accountability for Departmental radiological performance. • Ensure radiological measurements, analyses, worker monitoring results, and estimates of public exposures are accurate and appropriately made. • Conduct radiological operations in a manner that controls the spread of radioactive materials and reduces exposure to the work force and the general public and utilizes a process that seeks exposure level as low as reasonably achievable (ALARA). • Incorporate dose reduction, contamination reduction, and waste minimization features into the design of new facilities and significant modifications to existing facilities in the earliest planning stages. • Conduct oversight to ensure Departmental requirements are being complied with and appropriate radiological work practices are being implemented. Show OT 1.1 and OT 1.2. State objectives. Discuss that this is from DOE P 441.1 Show OT 1.3. Show OT 1.4. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 3 B. History DOE has provided numerous written standards for on-site radiological protection, the most recent regulation being 10 CFR Part 835, Occupational Radiation Protection, Amended June 2007. This regulation was preceded by: • DOE Notice 5480.6 of June 17, 1992, Radiological Control, which specified that the DOE Radiological Control Manual (DOE/EH- 0256T) would supersede DOE Order 5480.11. • DOE Order 5480.11, Radiation Protection for Occupational Workers. The purpose was to establish radiation protection standards and program requirements for DOE and DOE contractors for the protection of workers from ionizing radiation. The establishment of DOE radiological

protection standards did not start with these documents. A chronology of dose limits of DOE and its predecessor agencies, the Atomic Energy Commission (1946-1975) and the Energy Research and Development Administration (1975-1977), demonstrate a lowering of whole body dose limits over the last 50 years. In the establishment of these dose limits, DOE has followed recommendations of national and international radiological protection groups, notably the International Commission on Radiological Protection (ICRP) and the National Council on Radiation Protection and Measurements (NCRP). Show OT 1.5. Discuss that there are different limit which will be discussed later (e.g., whole body, lens of the eye, and skin). Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 4 C. Hierarchy of requirements Currently within DOE there are two parallel hierarchies of requirements: • Rules and/or regulations (these terms are used interchangeably in this training) • DOE Orders III. Rules and regulations In response to the enforcement authority in the Price-Anderson Amendments Act (PAAA) of 1988, DOE is converting its contractual requirement in orders to enforceable rules to enhance contractor accountability for safety. A. DOE enforcement of rules under PAAA 10 CFR Part 820 (effective on September 16, 1993) sets forth the procedures to implement the provisions of the PAAA. Part 820 requires contractors to comply with DOE Nuclear Safety Requirements. PAAA demands a “large stick” to enhance contractor accountability for safety. Rules provide authority for the assessment of civil and criminal penalties and thus provide the large stick. Show OT 1.6. Obj. 1 Identify the hierarchy of regulatory documents. Show OT 1.7. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 5 B. Penalties under Part 820 1. Civil penalties DOE may assess civil penalties against any person subject to Part 820, for violations of: • Codified rules in the CFR • Compliance orders • Any program or plan required by a rule or compliance order Note: Certain nonprofit educational institutions and other listed institutions are exempt from assessment of civil penalties. 2. Criminal penalties If a person subject to the Atomic Energy Act of 1954, as amended, or Nuclear Safety Requirements, has by action or omission knowingly and willfully violated, caused to be violated, attempted to violate, or conspired to violate any section of the Atomic Energy Act of 1954, as amended, or applicable DOE Nuclear Safety Requirements, the person shall be subject to criminal sanctions. 3. The “carrot and stick” approach DOE may provide monetary incentives in its management and operating (M&O) contracts for actions consistent with or exceeding requirements, and to penalize actions and activities that were not in compliance with requirements. Noncompliance with the Radiation Protection Program can subject a contractor to PAAA enforcement. There are provisions to mitigate penalties for self-identifying and reporting violations. Discuss site-specific monetary incentives. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 6 C. DOE Nuclear Safety Requirements DOE Nuclear Safety Requirements are the set of enforceable rules, regulations, or orders relating to nuclear safety that have been adopted by DOE (or by another agency if DOE specifically identifies it).

Compliance orders are issued by the Secretary. They identify a situation that violates, potentially violates, or otherwise is inconsistent with the: • Atomic Energy Act of 1954, as amended • Nuclear statutes • Nuclear Safety Requirements Compliance orders: • Mandate a remedy or other action • States the reason for the remedy or other action D. 10 CFR Part 835 On December 14, 1993, DOE published a final rule in the Federal Register (58 FR 65458) Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection (10 CFR 835). On November 4, 1998 an amendment to 10 CFR 835 was published in the Federal Register (63 FR 59663). On June 8, 2007 an amendment to 10 CFR 835 was published in the Federal Register (72 FR 31904). The purpose of 10 CFR 835 is the codification of radiological protection requirements. It contains “shall” statements, which are legally binding. It also contains: • Prescriptive language Show OT 1.8. Obj. 2 Define the purpose of 10 CFR Part 835. Define prescriptive language. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 7 • Added emphasis on ALARA • Requirements for a Radiation Protection Program (RPP) • Federal law • Criminal and civil penalties for violations E. Radiation Protection Program (10 CFR Part 835) Each site, under Part 835, must submit a written Radiation Protection Program (RPP). The RPP requires careful consideration because noncompliance may subject a contractor to PAAA enforcement F. Guidance documents for 10 CFR Part 835 Two types of regulatory guidance documents have been developed: • Guidance for implementing the provisions of 10 CFR Part 835. • Guidance providing technical positions. The above are available through the DOE HS-11 website at: http://www.hss.energy.gov/healthsafety/wshp/radiation/ Unlike the requirements specifically set forth in 10 CFR Part 835, the provisions in guidance documents are not mandatory. They are intended solely to describe the rationale for, and the objectives of, regulatory requirements and/or to identify acceptable methods for implementing regulatory requirements. Show OT 1.9. Show OT 1.10. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 8 Failure to follow a guidance document does not in itself indicate noncompliance with a specific requirement of the rule. A finding of noncompliance is found for a failure to satisfy the regulatory requirement. Following a guidance document in the prescribed manner will ordinarily create a presumption of compliance with a related regulatory requirement. 1. Technical guidance Technical guidance describes and disseminates technical methods and techniques for fulfilling implementation and, in turn, the requirements in 10 CFR Part 835. Examples of this guidance are DOE Technical Standards and DOE Radiological Control Technical Positions (RCTPs). 2. Implementation guides (IGs) Implementation guidance is intended to identify and make available to DOE contractors basic program elements and acceptable methods for implementing specific provisions of the final rule. Thirteen implementation guides have been condensed into one G441.1-1B, March 7, 2007. G. Relationship between 10 CFR Part 835 and 10 CFR Part 20 10 CFR Part 20 is the occupational radiological regulation issued by the Nuclear Regulatory Commission (NRC). The question of consistency among federal

agencies in their occupational radiological protection regulations became a major point of discussion during the rule making process. Refer students to website for RCTPs: Insert appropriate URL Review RCTPs and discuss as applicable to the site. Refer students to website for IGs: Insert appropriate URL Show OT 1.11. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 9 While agreeing with the goal of consistency, DOE believes that it must promulgate its own regulations because of the unique nature and diversity of radiological activities within the DOE complex. The final rule allows DOE to establish more rigorous requirements in areas of particular concern. Overall 10 CFR Part 835 has many similarities as 10 CFR Part 20. IV. DOE STD Radiological Control and Orders A. Radiological Control In January 1992, a memorandum was sent to the heads of DOE elements involved in managing radiological programs. In the memorandum, the Secretary directed a series of initiatives to enhance the conduct of radiological operations within the Department of Energy. Also in this memo, the Assistant Secretary of Environment, Safety and Health was directed to develop a comprehensive and definitive radiological control manual. The DOE Radiological Control Manual was developed to meet that directive and was approved by the Secretary and promulgated with DOE Notice 5480.6, Radiological Control, in July 1992. After the issuance of 10 CFR 835 as a final rule in December 1993, DOE Notice N441.1, Radiological Protection for DOE Activities, was issued on 9-30-95. This cancelled the notice which made the Radiological Control Manual a requirements document. However, the notice stated that "cancelled orders that are incorporated by reference in a contract shall remain in effect until the contract is modified to delete the reference. N441.1 also retained some of the radiation protection requirements from the Radiological Control Manual that were not included in 10 CFR 835. Show OT 1.12. Obj. 3 Define the purpose of the DOE Radiological Control Standard. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 10 In July, 1999, the Radiological Control Manual was replaced by the standard, DOE-STD-1098- 99, Radiological Control. Many DOE sites contractually must still adhere to the provisions of either the Radiological Control Manual or the Radiological Control Standard. Subsequent to the 1998 amendment to 10 CFR 835, the effective date of N441.1 has passed. The DOE Radiological Control Standard is not regulatory in nature. It is a guidance document that describes DOE’s policy and expectations for an excellent radiological control program. 1. Implementation If a site fully implements a provision of the DOE Radiological Control Standard, the user will have most likely complied with any related statutory, regulatory, or contractual requirements. Users are cautioned that they must review the source document (10 CFR 835) to ensure compliance. 2. Enforceability When incorporated into contracts, the provisions of the DOE Radiological Control Standard or Manual are binding requirements. If portions of the Site-Specific Radiological Control Manual are incorporated in the RPP under Part 835 and approved by DOE, they are also binding. B. The Site-Specific Radiological Control Manual • The DOE Radiological Control Standard states that a Site-Specific Radiological Control Manual should be written and followed.

. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 11 C. Relationship between 10 CFR Part 835 and the DOE Radiological Control Standard 1. Compliance • The Office of Enforcement and Investigation (HS-40) will enforce 10 CFR Part 835. It can assess fines and penalties. • The Program Offices will audit for both compliance with 10 CFR 835 and contractual agreements including the DOE Radiological Control Standard or Manual, Orders, etc. Results of these audits can affect the contractor’s award fee. 2. What if there are conflicts? 10 CFR Part 835 takes precedence over requirements of the DOE Radiological Control Standard and orders. It is unlikely that there will be a conflicting requirement between the two documents, although one document may have a requirement that is not addressed in the other. Show OT 1.13. What is the relationship between Part 835 and the DOE Radiological Control Standard regarding compliance issues? Show OT 1.14. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 12 It is planned that all requirements for nuclear safety will be incorporated into rules. 3. “Shall” and “should” statements • 10 CFR Part 835 contains “shall” statements. “Shall” statements in Part 835 are legally binding. Processes for exemption relief from Part 835 are set forth in Subpart E to Part 820. If relief is requested from provisions of Part 835, the exemption must be considered and granted, if appropriate, by the Chief Health, Safety and Security Officer (HS-1). • The use of “should” in the DOE Radiological Control Standard recognizes that there may be site- or facility-specific attributes that warrant special treatment. It also recognizes that literal compliance with the elements and requirements of the provision may not achieve the desired level of radiological control performance. Obj. 4 Define the terms “shall” and “should” as used in the above documents. Refer students to website for exemption decisions: http://tis.eh.doe.gov/whs/rhmwp/e xemption.html Review exemption decisions and discuss as applicable to the site. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 13 D. DOE Standards DOE has developed several technical standards for occupational radiation protection. Depending on the site-specific application, some standards are required to be followed. For example, sites which need to monitor individual external exposures to ionizing radiation need to follow the DOE Laboratory Accreditation Program (DOELAP) standards. Other standards may be incorporated by reference in the site RPP. Other standards provide technical guidance on specific applications, but adherence to the standard may not be required. Prior to conducting an assessment, the site requirements documents must be reviewed to determine applicable requirements. Show OT 1.15. Refer students to website for technical standards: Insert appropriate URL Radiation protection standards are also on: Insert appropriate URL Review standards and discuss as applicable to the site. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 14 V. Defense Nuclear Facilities Safety Board A. Establishment The Atomic Energy Act of 1954 was amended by adding Chapter 21, Defense Nuclear Facilities Safety Board (DNFSB). This amendment established an independent board in the executive branch to provide oversight of some DOE operations at DOE facilities and sites.

B. Members The DNFSB consists of five members appointed by the President with consent of the Senate. The Board shall: • Review and evaluate standards • Investigate any event or practice at a DOE defense nuclear facility that the Board determines has adversely affected or may adversely affect public health and safety. The Board may: • Establish reporting requirements for the Secretary of Energy By evaluating how well DOE meets its objectives, the DNFSB helps DOE achieve and maintain excellence in radiological protection. C. Secretary of Energy The Secretary of Energy shall fully cooperate with the Board. Obj. 7 Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites and facilities. Show OT 1.16. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 15 D. DNFSB Recommendations DNFSB provides DOE with recommendations for improving safety at DOE defense nuclear facilities. Examples include: DNFSB Recommendation 91-6 dealt with radiological protection concerns throughout the DOE defense nuclear facilities complex, and identified several actions to be taken by the Department to improve radiological protection performance. DNFSB Recommendation 92-7 dealt with training and qualification at DOE sites and facilities. DNFSB Recommendation 98-1 dealt with resolution of internal audit findings. DNFSB Recommendation 99-1 dealt with safe storage of fissionable materials. Implementation of DOE and site commitments made in response to DNFSB recommendations are areas to review during an assessment. Show OT 1.17. Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor's Guide Module 1 - 16 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: 10 CFR Part 835, Background and Focus Objectives: Upon completion of this training, the participant will be able to: 1. Describe the contents of 10 CFR Part 835. 2. Identify the site requirements of 10 CFR Part 835. Training Aids: Overhead Transparencies (OTs): OT 2.1 – OT 2.32 (may be supplemented or substituted with updated or site-specific information) Handout - “Dosimetric Quantities in 10 CFR Part 835” Equipment Needs: Overhead projector Screen Student Materials: Student’s Guide Handout - “Dosimetric Quantities in 10 CFR Part 835” 10 CFR 835 Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 2 References: U.S. Department of Energy, 10 CFR Part 820, Procedural Rules for DOE Nuclear Facilities, 2007. U.S. Department of Energy, 10 CFR Part 835, Occupational Radiation Protection, 2007. U.S. Department of Energy, Order 5400.5, Radiation Protection of the Public and the Environment, 1990. U.S. Department of Energy, DOE STD-1107-97 Knowledge, Skills, and Abilities for Key Radiation Protection Positions at DOE Facilities, Reaffirmed June 2005. U.S. Department of Energy, DOE G 441.1-1B, Radiation Protection Programs Guide, March 2007. U.S. Department of Energy, DOE O 231.1-1A, Change 2, Environment, Safety and Health Reporting, 2004. U.S. Department of Energy, DOE M 231.1-1A, Change 2, Environment, Safety and Health Reporting Manual, 2004. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide

Module 2 - 1 I. Introduction This module provides an overview of many of the provisions of 10 CFR 835. For completeness, individuals should always reference back to 10 CFR 835 for the complete text. II. Outline of 10 CFR Part 835 Part 835 is the codification of radiological protection requirements. Part 835 contains 14 subparts and five appendices. The outline consists of the following subparts: A — General Provisions B — Management and Administrative Requirements C — Standards for Internal and External Exposure D — Reserved E — Monitoring of Individuals and Areas F — Entry Control Program G — Posting and Labeling H — Records I — Reports to Individuals J — Radiation Safety Training K — Design and Control L — Radioactive Contamination Control M — Sealed Radioactive Source Control N — Emergency Exposure Situations Under 10 CFR Part 835, each site must submit a Radiation Protection Program (RPP). Part 835 helps to ensure that DOE facilities are operated in a manner such that occupational radiological exposure to workers is maintained within acceptable limits and as low as is reasonably achievable (ALARA). Show OT 2.1. Emphasize that this lesson is an overview of major areas of 10 CFR Part 835. Not every provision is addressed in this module 10 CFR 835 should be reviewed in its entirety to ensure compliance. Provide copies of 10 CFR 835 for reference. State objectives. Show OT 2.2. Obj. 1 Describe the contents of 10 CFR Part 835. Show OT 2.3. Obj. 2 Identify the site requirements of 10 CFR Part 835. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 2 A. Subpart A - General Provisions Subpart A contains the scope of the rule. The rule in this part establishes radiological protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of DOE activities. It also includes activities excluded from the provisions of the rule. Activities that are excluded include the following (summarized): • Activities regulated through a license by the Nuclear Regulatory Commission (NRC) or a state under an agreement with the NRC. • Activities conducted under the authority of the Director, Naval Nuclear Propulsion Program. • Specified activities conducted under the Nuclear Explosives and Weapons Surety Program. • Radioactive material transportation. • DOE activities in other countries with acceptable radiation protection program. • Background radiation. Occupational doses received as a result of excluded activities and radioactive material transportation, as listed above, shall be considered when determining compliance with the occupational dose limits (835.202 and 835.207), and with the limits for the embryo/fetus (835.206). Subpart A also addresses: • Definitions • Radiological units (Curie, rad, roentgen, rem, and multiples) Show OT 2.4. Discuss radioactive material transportation definition. Show OT 2.5. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 3 B. Subpart B - Management and Administrative Requirements The RPP shall: • Include formal plans and measures for applying the ALARA process to occupational exposures. • Specify the existing and/or anticipated operational task. • Address, but not be limited to, each requirement in Part 835. • Include plans, schedules, and other measures for achieving compliance. DOE may direct or make modifications to an

RPP. An initial RPP or update shall be considered approved 180 days after its submission unless rejected by DOE at an earlier date. Internal Audits (10 CFR 835.102) Internal audits of the radiation protection program, including examination of program content and implementation, shall be conducted through a process that ensures that all functional elements are reviewed no less frequently than every 36 months. This training material and DOE G 441.1-1B, Radiation Protection Programs Guide, provide guidance on DOE's expectations. Show OT 2.6. Discuss again DOE's series of Implementation Guides and their purpose. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 4 Education, Training and Skills (10 CFR 835.103) Individuals responsible for developing and implementing measures necessary for ensuring compliance with the requirements of this part shall have the appropriate education, training, and skills to discharge these responsibilities. DOE STD-1107-97, Reaffirmed June 2005, Knowledge, Skills, and Abilities for Key Radiation Protection Positions at DOE Facilities, provides guidance on DOE's expectations. Written Procedures (10 CFR 835.104) Written procedures are required, as necessary, to ensure compliance with 835, commensurate with radiological hazards and education, training and skills of exposed individuals. C. Subpart C - Standards for Internal and External Exposure This subpart addresses limits for: • General employees (occupational) • Embryos/fetus of declared pregnant worker (i.e., A woman who has voluntarily declared to her employer, in writing, her pregnancy for the purpose of being subject to the occupational dose limits to the embryo/fetus. This declaration may be revoked, in writing, at any time by the declared pregnant worker.) • Occupationally exposed minors • General public in a controlled area It also addresses: • Planned special exposures • Nonuniform exposures of the skin • Concentrations of radioactive material in air Show OT 2.7. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 5 1. Summary of dose limits 10 CFR Part 835 employs the rem unit for several different physical quantities. For information about these quantities refer participants to page 1 of handouts, “Dosimetric Quantities in 10 CFR Part 835.” Show OT 2.8 and OT 2.9. Exposed Individual Annual Limit General Employee: Whole Body (internal and external) (TED) 5.0 rem General Employee: Lens of Eye (ED) 15.0 rem General Employee: Extremity (below elbow and knees) and skin (SED) 50.0 rem General Employee: Any Organ or Tissue (other than lens of eye) (DED + CED) 50.0 rem Declared Pregnant Worker: Embryo/Fetus (gestation period) (ED) 0.5 rem Occupationally Exposed Minors (under age 18): (TED) 0.1 rem * Members of the Public in Controlled Areas: (TED) 0.1 rem • And 10% of other general employee limits. 2. Planned special exposures (PSEs) It is acknowledged that unusual conditions can arise in which higher-than-normal doses can be justified. In these well-planned, well- controlled, and highly infrequent and unusual conditions operating management would be permitted to allow specified individual doses exceeding the occupational limit, such as 5 rem per year. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 6 The term "unusual conditions" is made clear by specifying that alternatives which would preclude exposures higher than the prescribed dose limits must be either unavailable or impractical.

10 CFR 835.204 specifies requirements for annual and lifetime dose from PSEs. It also specifies requirements for determining previous individual exposures prior to allowing a PSE. Every PSE must be approved in advance by DOE and requires the informed consent of the employee involved. 3. Concentration of radioactive material in air Appendices A and C contain the derived air concentration (DAC) values used in the control of occupational exposure to airborne radioactive material. DACs are listed in appendices A and C of 10 CFR 835. For intakes (appendix A), they are the airborne concentration that equals the annual limit on intake (ALI) divided by the volume of air breathed by an average worker for a working year of 2000 hours (assuming a breathing volume of 2400 m3). The ALI is the smaller value of intake of a given radionuclide in a year by a standardized man that would result in a CED of 5 rems or a HT,50 of 50 rems to any individual organ or tissue. Show OT 2.10. Show OT 2.11. Define DAC in terms of dose equivalent. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 7 Appendix C contains DACs for controlling external dose from being immersed in a cloud of airborne radioactive material. Estimation of internal dose shall be based on bioassay data rather than air concentration values unless bioassay data are: • Unavailable (e.g., radon or very short lived radioisotopes) • Less accurate than internal dose estimates based on representative air concentration values • Inadequate E. Subpart D - Reserved Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 8 E. Subpart E - Monitoring of Individuals and Areas This subpart addresses: • General requirements • Instrumentation • Individual monitoring - external • Individual monitoring - internal • Air monitoring • Receipt of packages containing radioactive material 1. General requirements (10 CFR 835.401) Monitoring of individuals and areas shall be performed to: • Demonstrate compliance with Part 835. • Document radiological conditions. • Detect changes in the radiological conditions. • Detect the gradual buildup of radioactive material. • Verify the effectiveness of engineering and process controls in containing radioactive material and reducing radiation exposure. • Identify and control potential sources of individual exposure to radiation and/or radioactive material. Show OT 2.12. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 9 2. Instrumentation Instruments and equipment used for monitoring and contamination control shall be: • Periodically maintained and calibrated on an established frequency. • Appropriate for the type(s), levels, and energies of the radiation(s) encountered. • Appropriate for existing environmental conditions. • Routinely tested for operability. 3. Individual monitoring - external (10 CFR 835.402) For the purpose of monitoring individual exposure to external radiation, personnel dosimetry shall be provided to and used by: • Radiological Workers likely to receive: – An effective dose to the whole body of 0.1 rem (100 mrem) or more in a year – A shallow equivalent dose to the skin or to any extremity of 5 rem or more in a year – A lens of the eye equivalent dose of 1.5 rem or more in a year • Declared Pregnant Workers who are likely to receive from external sources an equivalent dose to the embryo/fetus in excess of 10 percent of the applicable limit.

Show OT 2.13. Show OT 2.14. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 10 • Members of the public in a controlled area and occupationally exposed minors likely to receive, in one year, from external sources, a dose in excess of 50 percent of the applicable limits. • Individuals entering a High or Very High Radiation Area. DOE Laboratory Accreditation for Personnel Dosimetry is required for external dose monitoring programs implemented to demonstrate compliance with 10 CFR 835. 4. Individual monitoring - internal (10 CFR 835.402) Internal dose evaluation programs (including routine bioassay programs) shall be conducted for: • Radiological Workers who, under typical conditions, are likely to receive 0.1 rem or more committed effective dose from all occupational radionuclide intakes in a year. • Declared Pregnant Workers likely to receive an intake or intakes resulting in an equivalent dose to the embryo/fetus in excess of 10 percent of the limit. • Members of the public in a controlled area and occupationally exposed minors who are likely to receive a committed effective dose in excess of 50 percent of the limit from all intakes in a year. Show OT 2.15. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 11 DOE Laboratory Accreditation for Radiobioassay is required for internal dose monitoring programs implemented to demonstrate compliance with 10 CFR 835. 5. Air monitoring (10 CFR 835.403) Measurements of radioactivity concentrations in the ambient air of the workplace shall be performed as follows: • Air sampling shall be performed in occupied areas where an individual is likely to receive an exposure of 40 DAC- hrs or more in a year (i.e. an annual intake of 2 percent or more of the specific ALI value) for the mixture of isotopes. • Samples shall be taken as necessary to characterize the levels or concentration of airborne radioactive material when respirators are worn for radiation protection purposes. • Real-time air monitoring shall be performed when there is a need to alert potentially exposed individuals to unexpected increases in airborne radioactivity levels such that immediate action is necessary in order to minimize or stop inhalation exposures. Compliance due date 1-1-02. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 12 6. Receipt of Packages Containing Radioactive Material (10 CFR 835.405) Establishes requirements to monitor certain types of packages and sets a time limit of not later than 8 hours after the beginning of the working day following receipt of the package. F. Subpart F - Entry Control Program (10 CFR 835.501) Subpart F addresses entry into: • Radiological Areas • High Radiation Areas • Very High Radiation Areas 1. Radiological Areas The degree of control shall be commensurate with existing and potential radiological hazards within the area. Show OT 2.16. Show OT 2.17. Discuss different types of radiological areas. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 13 One or more of the following methods shall be used to ensure control: • Signs and barricades • Control devices on entrances • Conspicuous visual and/or audible alarms • Locked entrance ways • Administrative controls “No control(s) shall be installed at any radiological area exit that would prevent rapid evacuation of personnel under emergency conditions.”

2. High Radiation Areas A High Radiation Area is an area where radiation levels exist such that an individual could exceed a deep equivalent dose to the whole body of 0.1 rem in any one hour at 30 centimeters from the source or from any surface that the radiation penetrates. If an individual receives a deep equivalent dose exceeding 1.0 rem in an hour (at 30 cm), a High Radiation Area shall have one or more of the following: • A control device that prevents entry to the area when high radiation levels exist or that, upon entry, causes the radiation level to be reduced below that level that defines a High Radiation Area. • A device that functions automatically to prevent use or operation of the radiation source or field while individuals are in the area. Show OT 2.18. Show OT 2.19. Show OT 2.20. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 14 • A control device that energizes a conspicuous visible or audible alarm signal so that the individual entering the High Radiation Area and the supervisor of the activity are made aware of the entry. • Entryways that are locked. During periods when access to the area is required, positive control over each entry is maintained. • Continuous direct or electronic surveillance that is capable of preventing unauthorized entry. • A control device generating audible and visual alarm signals to alert personnel in the area before use or operation of the radiation source and in sufficient time to permit evacuation of the area or activation of a secondary control device that will prevent use or operation of the source. 3. Very High Radiation Areas A Very High Radiation Area is an area in which an individual could receive a dose in excess of 500 rad in one hour at 1 meter from the radiation source or from any surface that the radiation penetrates. In addition to the requirements for a High Radiation Area, additional measures shall be implemented to ensure individuals are not able to gain unauthorized access to Very High Radiation Areas. “No control(s) shall be established in a High or Very High Radiation Area that would prevent rapid evacuation of personnel.” Show OT 2.21. Show OT 2.22. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 15 G. Subpart G - Posting and Labeling Subpart G addresses the general requirements for signs: • Yellow background • Black or magenta radiation symbol • Clear and conspicuous signs In addition, Subpart G addresses specific posting requirements for: • Controlled Areas • Radiation Areas • High Radiation Areas • Very High Radiation Areas • Airborne Radioactivity Areas • Contamination Areas • High Contamination Areas • Radioactive Material Areas This subpart also addresses exceptions to posting and labeling. H. Subpart H - Records Subpart H addresses requirements for records documenting compliance with Part 835 and with the Radiation Protection Program. Records that are specifically required include those necessary to demonstrate compliance with the ALARA provisions of the rule. Show OT 2.23. Discuss posting and labeling exceptions. Show OT 2.24. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 16 10 CFR 835 also requires that certain records be maintained, including records of: • Individual monitoring • Sealed source inventory and control • Results of surveys for the release of material and equipment

• Results of specified monitoring for radiation and radioactive material • Maintenance and calibration of radiation monitoring instruments • Internal audits Each individual’s training as a general employee and as a Radiological Worker must be recorded. Where appropriate, demonstration and documentation of proficiency is required. Refer to 10 CFR 835 Subpart H for a complete listing of required records. DOE M 231.1-2, Change 2, Environment, Safety and Health Reporting Manual specifies radiation protection reporting requirements that may be applicable to the site or facility being assessed. I. Subpart I - Reports to Individuals (10 CFR 835.801) Subpart I addresses reports to individuals and their accessibility to reports, including: Discuss applicability of O 231.1 to the site or facility. Show OT 2.25. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 17 On an annual basis, each DOE or DOE contractor-operated site or facility must provide each individual monitored for occupational exposure a radiation dose report of his/her occupational exposure at that site or facility. Upon the request from an individual terminating employment, records of exposure shall be provided to that individual as soon as the data are available, but not later than 90 days after termination. A written estimate of the radiation dose received by that employee based on available information shall be provided at the time of termination, if requested. J. Subpart J - Radiation Safety Training This subpart addresses radiation safety training. The tailored approach to training requirements are based on: • Unescorted access to or receiving occupational dose in controlled areas (e.g., General Employees) • Unescorted access to radiological areas or unescorted assignment as Radiological Workers Requirements of Part 835 include: • Verification by examination for certain training (e.g., Radiological Worker Training) • Intervals of training not to exceed twenty four months • List of topics which must be included in training • Provisions for limited use of escorts in lieu of training Show OT 2.26. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 18 K. Subpart K - Design and Control Subpart K addresses added emphasis on facility and equipment design and administrative controls to maintain radiological exposures ALARA. 1. Facility design and modifications (10 CFR 835.1001) During the design of new facilities or modification of old facilities, the following objectives shall be adopted: • Optimal methods shall be used to assure ALARA • Maintain exposure levels below an average of 0.5 mrem/hr • Avoid release of radioactivity to the workplace atmosphere • The design or modification of a facility and the selection of materials shall include features that facilitate operations, maintenance, decontamination, and decommissioning Show OT 2.27. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 19 2. Workplace controls (10 CFR 835.1003) During routine operations, the combination of physical design features and administrative control shall provide that: • The anticipated occupational dose to general employees shall not exceed the limits • The ALARA process is utilized for personnel exposures to ionizing radiation L. Subpart L - Radioactive Contamination Control 1. Control of material and equipment This section addresses the requirements for

release of materials and equipment from radiological areas to controlled areas. Releases to uncontrolled areas are addressed in DOE O 5400.5. Some of the provisions: • Specifies conditions for material and equipment in contamination areas (CAs), high contamination areas (HCAs), and airborne radioactivity areas (ARAs) to be released to a controlled area • Addresses movement of material and equipment with removable surface contamination, on-site from one radiological area for immediate placement in another radiological area • Specifies conditions for material and equipment with fixed contamination to be released for use in controlled areas outside of radiological areas Show OT 2.28. Show OT 2.29. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 20 Control of Areas (10 CFR 835.1102) addresses • Prevention of inadvertent transfer or removal of contamination to locations outside radiological areas under normal conditions • Where contamination levels exceed values in Appendix D, the area is controlled commensurate with hazards • Areas with fixed contamination exceeding radioactivity values may be located outside radiological areas, provided certain controls, conditions, or provisions are met • Personnel monitoring for contamination upon exiting CAs, HCAs, or ARAs • Use of protective clothing in CAs and HCAs M. Subpart M - Sealed Radioactive Source Control Sealed radioactive sources shall be used, handled and stored in a manner commensurate with the hazard. Specifies values (Appendix E) for sources which must be inventoried and leak tested at intervals not to exceed six months. N. Subpart N - Emergency Exposure Situations This subpart addresses: • Employees who have exceeded dose limits as result of authorized emergency exposure • Nuclear accident dosimetry Show OT 2.30. Show OT 2.31. Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 21 Individuals whose occupational exposures have exceeded any limits as a result of an authorized emergency exposure may be permitted to return to work provided that certain conditions are met. Nuclear accident dosimetry Nuclear accident dosimetry involves installations possessing sufficient quantities of fissile material to constitute a critical mass, and shall include; • Method to conduct initial screening of personnel involved • Method and equipment for analysis of biological materials • A system of fixed nuclear accident dosimeter units • Personal nuclear accident dosimeters Show OT 2.32. Summarize lesson. Review objectives. Ask for questions. T T Radiological Assessor Training DOE-HDBK-1141- 2008 Instructor’s Guide Module 2 - 22 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Overview of the DOE Radiological Control Standard Objectives: Upon completion of this lesson, the participant will be able to: 1. Describe the managerial responsibilities in the DOE Radiological Control Standard. 2. Describe the contents of the DOE Radiological Control Standard. Training Aids: Overhead Transparencies (OTs): OT 3.1 – OT 3.12 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Student Materials: Student’s Guide References: U.S. Department of Energy, DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004.

U.S. Department of Energy, O 440.1B, Worker Protection Program for DOE (Including the National Nuclear Security Agency) Federal Employees, May 2007. Module 2 Page 0 I. Introduction II. DOE Radiological Control Standard The DOE Radiological Control Standard is written for line management. It is designed to assist line managers in fulfilling their duties and responsibilities for implementing an occupational radiation protection program. It is also designed to assist site/facility workers in having the information they need to be responsible for their own radiological exposures and to help ensure that the controls are in place to eliminate any releases, unplanned exposures or uptake, and to apply ALARA principles. The emphasis is on teamwork and support from line management. The Radiological Control Standard may be considered as an occupational radiation protection good practices document. Individual sites may have contractual commitments to implement sections of the standard. III. Chapter 1, Excellence in Radiological Control This chapter defines the roles of DOE and the contractors in achieving the goal of radiological control excellence. It consists of the following five sections: • DOE Radiological Control Standard • Leadership in Radiological Control • Improving Radiological Control Performance • Contractor Radiological Control Organization • DOE Management Show OT 3.1. State objectives. Obj. 1 Describe the managerial responsibilities in the DOE Radiological Control Standard. Discuss site commitments to follow the Radiological Control Standard or Manual. Emphasize the need to review site requirements documents prior to conducting an assessment. Show OT 3.2. Obj. 2 Describe the contents of the DOE Radiological Control Standard. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 1 A. DOE Radiological Control Standard The contractor is responsible for implementing an occupational radiation protection program. To assist this effort, they may develop a Site Radiological Control Standard Implementation Plan. The Site-Specific Radiological Control Standard, which is developed from the Implementation Plan, does not require DOE approval. B. Leadership in Radiological Control Commitment of senior management to radiological control is defined in this section of the Standard. The responsibilities and accountability of each individual for ALARA and radiological excellence is emphasized. Worker responsibilities and the concepts of conduct of radiological operations are clearly defined. C. Improving Radiological Control Performance The use of critiques as a management tool, rather than as a method to “fix blame” or “shoot the messenger,” and the importance of real root cause identification are emphasized. Over 20 radiological performance indicators are identified that are tools designed to assist managers in focusing their priorities and attention on radiological control performance. D. Contractor Radiological Control Organization This section discusses the contractor’s radiological control organization and the qualifications of the Radiological Control Manager. Show OT 3.3. Show OT 3.4. Show OT 3.5. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 2 E. DOE Management This section discusses the roles and responsibilities of DOE management for providing guidance and performance evaluation of radiological control programs.

IV. Chapter 2, Radiological Standards This chapter deals with administrative control dose limits, contamination control and control levels, and posting. A. Administrative Control Levels (ACLs) and Dose Limits Lifetime control levels and dose limits for Radiological Workers, members of the public, embryos/fetuses, and special control levels are discussed in this section. For most facilities an ACL of 500 millirem or less will be challenging for Radiological Workers. Individual occupational doses, in rem, should be kept below the individual's age in years. B. Contamination Control and Control Levels In this section, personnel contamination control, removable and fixed contamination control levels, and airborne radioactivity control levels are given. C. Posting Posting requirements are presented in this section and include several non-regulatory areas including: Radiological Buffer Areas, Underground Radioactive Material Areas, and Soil Contamination Areas. Show OT 3.6. Discuss site specific ACLs and other limits. Discuss non-regulatory posting used at the site. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 3 V. Chapter 3, Conduct of Radiological Work The planning of radiological work, work preparation (e.g., Radiological Work Permits), and the requirements for the entry to and exit from the various types of controlled areas are contained in this chapter. Also covered are: radiological work performance, the aspects of radiological work in different operations with radiation-generating equipment, and construction and restoration projects. A. Planning Radiological Work This section emphasizes that the conduct of radiological work is a line responsibility. Worker responsibility, along with systematic planning, provides the necessary information for safe radiological work. Of fundamental importance is the requirement to plan work with an emphasis on ALARA principles. B. Work Preparation In this section, the Radiological Work Permit (RWP) is discussed. This chapter states that the RWP is the key to any particular radiological operation, and preplanning is essential. C. Entry and Exit Requirements The minimum requirements for entry into and exit from defined radiological areas and other non-regulatory areas are discussed in this section. Show OT 3.7. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 4 D. Radiological Work Controls This section discusses radiological work as a team effort involving the Radiological Workers, their supervisors, and Radiological Control personnel. The DOE Radiological Control Standard discusses stop-radiological work authority for Radiological Control Technicians (RCTs), their supervisors, line supervision, and workers through their supervisors because of: • Inadequate radiological controls • Radiological controls not being implemented • A radiological control hold point not being satisfied DOE O 440.1B, May 2007, Worker Protection Program for DOE (Including National Nuclear Security Administration)Federal Employees specifies that individuals have the authority to stop work due to hazardous conditions. This stop work authority is not limited to just radiological hazards. Workers may "stop work when they discover employee exposures to imminent danger conditions or other serious hazards." Contractors are required to have procedures addressing stop work authority. E. Evaluation of Performance

Evaluation of performance, critiques, post job reviews, and lessons learned are discussed in this section. Discuss that, per O 440.1A, stop work authority is not limited to radiological hazards. Show OT 3.8. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 5 F. Special Applications This section examines the special aspects for the control of radiological work when working with the following: • Plutonium • Uranium • Tritium • Accelerators • Radiation Generating Devices G. Radiological Design Criteria This section addresses design objectives for design of new facilities and modification of existing facilities. VI. Chapter 4, Radioactive Materials The requirements for labeling, storage, control, release, and transportation of radioactive materials, and the control of radioactive sources, are discussed in this chapter. This chapter also deals with the management of solid and liquid radioactive wastes, and airborne radioactivity. Support activities such as personnel protective clothing and equipment, laundry, decontamination and vacuum cleaners, and portable air-handling equipment are also discussed. VII. Chapter 5, Radiological Health Support Operations This chapter discusses the requirements for external dosimetry, internal dosimetry, a respiratory protection program, the handling of contaminated personnel, radiological monitoring and surveys, and instrumentation and calibration. Show OT 3.9. Show OT 3.10. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 6 VIII. Chapter 6, Training and Qualification The requirements that ensure personnel have the training and qualifications needed to safely work in and around radiological areas and to maintain their own doses and those of others (ALARA) are discussed in this chapter. A. General Radiological Training Within these sections, training and qualification standards are discussed for: • General Employees • Radiological Workers I and II • Radiological Control Technicians and Supervisors B. Other Radiological Training This section addresses training and qualification for: • Managers/supervisors • ALARA training for: – Engineers – Schedulers – Procedure writers • Radiological control personnel – Dosimetry technicians – Instrument technicians – Medical personnel – Records clerk – Whole body counter technicians – Laboratory personnel • Radiographers • Radiation-generating device operators • Emergency response personnel Show OT 3.11. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 7 C. Training for Special Applications This section addresses training for the following facilities: • Plutonium • Uranium • Tritium • Accelerators IV. Chapter 7, Radiological Records The requirements for employee and visitor records, radiological control procedures (policies, procedures, Radiological Work Permits (RWPs), ALARA, and quality assurance records), radiological surveys, instrumentation and calibration records, records management, and radiological reporting are presented in this section. Show OT 3.12. Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 3 - 8 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Elements of a Radiological Control Program

Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify factors that influence the scope and magnitude of a Radiological Control Program at any nuclear facility. 2. Identify typical elements of a Radiological Control Program. Training Aids: Overhead Transparencies (OTs): OT 4.1 – OT 4.5 (may be supplemented or substituted with updated or site-specific information) Handouts - “List of Radiological Control Program Elements” “Elements of a Radiological Control Program” Equipment Needs: Overhead projector Screen Flip chart Markers Masking tape Student Materials: Student’s Guide References: U.S. Department of Energy, 10 CFR Part 820, Procedural Rules for DOE Nuclear Facilities, 2007. U.S. Department of Energy, 10 CFR Part 835, Occupational Radiation Protection, 2007. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 2 I. Introduction II. Radiological Control Program A. Overall program The Radiological Control Program consists of the commitments, policies, and procedures that are administered by a site or facility to meet the EH Health and Safety Policy. The Radiation Protection Program required by 10 CFR Part 835 is an element of the overall Radiological Control Program. The Radiological Control Program should address the following: • Requirements • Responsibilities • Programs/procedures • Assessments B. Size of the program Radiological Control Programs vary in size. There are several factors that may affect the magnitude of a Radiological Control Program. The specific mission, types and quantities of radioactive material, and the radiation- generating devices that will be used at the site are just a few. Show OT 4.1. State objectives. Show OT 4.2. Obj. 1 Identify factors that influence the scope and magnitude of a Radiological Control Program at any nuclear facility. • What to do? • Who does it? • How is it done? • Is it being done, and how well? Ask participants what factors may affect program size–list on flip chart. Encourage participants to write responses in their Student’s Guide. Responses should include the following: • The specific facility mission Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 3 III. Elements of a radiological control program A. Requirements • The radiation-generating devices at the site • The types and quantities of radioactive materials in use at the site • The physical and chemical forms of the radioactive materials in use at the site • The physical location of the site in relation to the population centers • The size of the work force • The age of the facility • The original facility design criteria Ask participants how a site would determine what had to be included in their program. Encourage participants to write responses in their student’s guide. Responses should include: • Hazard assessment/ characterization • Requirements/ commitments – Contract – RPP (10 CFR Part 835) – Other federal regulations – State regulations – Site RadCon Manual Implementation Plan – Orders – Other Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 4 B. Responsibilities C. Programs/procedures Ask participants how a site should address and document these responsibilities. Responses should include: • Organization and administration – Upper management commitment • Personnel training and qualification

Ask participants what type of subprograms should be included or what areas should be addressed in the responsibilities. Responses should include: • Work controls (engineered, administrative, personal protective equipment) • Posting and labeling • Entry controls • Radioactive materials controls • Criticality controls • Radiation-generating devices • Contamination controls • Respiratory protection • ALARA Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 5 D. Assessments • Dosimetry – External – Internal • Instrumentation and alarms • Monitoring – Workplace – Environmental – Air • Radioactive waste management • Transportation and receipt of radioactive material • Emergency response • Reporting • Records Ask participants what types of subprograms should be established to monitor and improve program performance. Responses should include: • Internal audits and investigations • Trend analysis • Performance indicators Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 6 IV. List of Radiological Control Program Elements • Organization and administration • Personnel training and qualification • Quality assurance • ALARA • Radiological Work Control – Procedures – Radiological Work Permits • Posting and labeling • Radioactive material control – Source control – Release of materials – Receipt and transportation • Radiation-generating devices – Sealed source – X-ray machines • Entry control • Contamination control • Instrumentation/alarms • Monitoring – Workplace – Effluent – Environmental Show OT 4.3. Obj. 2 Identify typical elements of a Radiological Control Program. Refer participants to page 4 of handouts, “List of Radiological Control Program Elements,” which has different element names, but similar functions. Show OT 4.4. Show OT 4.5. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 7 • Dosimetry – External – Internal - Program management (e.g., staffing, technical basis, procedures, quality assurance) - Individual monitoring (e.g., air monitoring, contamination monitoring, bioassay) - Internal dose evaluation • Respiratory protection • Facility specific features – Uranium – Plutonium – Tritium – Accelerators • Radioactive waste management • Emergency response • Records • Assessments/performance indicators Refer participants to page 10 of handouts, “Elements of a Radiological Control Program.” These provide a more detailed listing/breakdown of elements. As time allows, review selected elements. Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 4 – 8 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Technical Safety Requirements Objectives: Upon completion of this lesson, the participant will be able to: 1. Describe the purpose of DOE Order 5480.22 and its relationship to 10 CFR 830.205. 2. Describe the purpose of Technical Safety Requirements (TSRs) in regard to facility operations/activities. 3. Identify the source(s) of information required to develop reasonable and appropriate TSRs. 4. Describe the responsibilities for the development and use of TSRs. 5. List the criteria for identifying problems in meeting TSRs.

6. List areas in TSRs which could be reviewed as part of a radiological assessment. Training Aids: Overhead Transparencies (OTs): OT 5.1 – OT 5.13 (may be supplemented or Substituted with updated or Site-specific information) Handouts - “Typical Safety Analysis Report (SAR) Contents” “Technical Safety Requirement (TSR) Format and Content” Equipment Needs: Overhead projector Screen Flip chart Markers Masking tape Student Materials: Student’s Guide Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 2 References: U.S. Department of Energy, 10 CFR 830, Nuclear Safety Management, 2000. U.S. Department of Energy, Operation Procedure Identifying, Reporting, and Tracking Nuclear Safety Noncompliances, June 1998. I. Introduction II. Purpose of 10 CFR 830.205 On October 10, 2000 an Interim final rule was published in the Federal Register for 10 CFR 830, "Nuclear Safety Management". The Interim Final Rule was effective December 11, 2000, and codifies requirements for TSRs in 10 CFR 830.205. The new rule required contractors to develop and submit TSRs to DOE for approval by April 10, 2003. TSRs are a critical element in the overall DOE safety program. A. Definitions (Paragraph 6) • Technical Safety Requirements are those requirements that define the conditions, safe boundaries, and the management or administrative controls necessary to ensure the safe operation of nuclear facilities and to reduce the potential risk to the public and facility workers from uncontrolled releases of radioactive materials or from radiation exposure due to inadvertent criticality. Technical Safety Requirements consist of safety limits, operating limits, surveillance requirements, administrative controls, use and application instructions, and the bases thereof. • A controlled document is content maintained uniformly among the copies by an Administrative Control System (paragraph 6, Item e). Show OT 5.1 and OT 5.2. State objectives. Obj. 1 Describe the purpose of DOE Order 5480.22 and its relationship to 10 CFR 830.205. This material may need to be updated to reflect final implementation guidance for 10 CFR 830 when it is finalized. Show OT 5.3. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 3 Basis: Summary statements of the reasons for the operating limits and associated surveillance requirements. It shows how the numerical value, condition, or the surveillance fulfills the purpose from the safety documentation. B. Policy (Paragraph 7) It is the policy of the Department that nuclear facilities operate Cognizant Secretarial Officer (CSO)-approved Technical Safety Requirements, which prescribe the bounds for safe operation of these facilities in order to protect the health and safety of the public and reduce risk to workers. The TSRs constitute a contract between the operating contractor and DOE management of the methods that will be utilized or constraints to be applied to minimize the potential risk of operating the proposed facility or conducting the proposed activity. NOTE: TSRs apply to actions by specific facility personnel and their commitments to responsible DOE managers. The Technical Safety Requirements document is to be a controlled document. TSRs are not based upon maintaining worker doses below some acceptable level following an uncontrolled release of hazardous material or inadvertent criticality; rather, the risk to workers is reduced through controls that reduce the likelihood and potential impact of such events.

Show OT 5.4. Obj. 2 Describe the purpose of Technical Safety Requirements (TSRs) in regard to facility operations/activities. Show OT 5.5. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 4 C. Source for bases (justification) of TSRs In the development of limits, set-points, staffing requirements, and other parameters for input into the individual TSRs, the facility/operation- specific Safety Analysis Report (SAR), particularly the accident analyses contained therein, is normally the primary basis. The limitations that are included in the TSRs should be derived from the facility-specific safety analysis, which considers all credible accidents. This includes the most significant possible releases of radioactive and hazardous materials, criticality scenarios, and the accidental releases expected during the life of the facility. Careful and thorough examination of these accident analyses will provide values for defining the operational limits necessary to ensure that facility operations do not occur outside the bounds assumed in the analyses. Such an examination will also identify parameters and operating conditions that should be limited in order to reduce, provide warning of, and mitigate the uncontrolled releases of hazardous materials and to prevent inadvertent criticality. Examples of requirements expected to be developed include: • Operating limits for principal process parameters • Technical and administrative conditions that must be met • Availability of safety equipment and systems • Critical functions of instrumentation and controls Obj. 3 Identify the source(s) of information required to develop reasonable and appropriate TSRs. Show OT 5.6. SAR text of interest • Principal Safety Criteria • Accident Analysis • Deviation of TSRs Show OT 5.7. Show OT 5.8. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 5 Operations within the boundaries of the resulting requirements will provide reasonable assurance that the nuclear facility will not: • Threaten the health and safety of the public • Pose an undue risk to workers from the uncontrolled releases of radioactive or other hazardous materials and inadvertent criticality For facilities that do not have an approved SAR, the technical input into the TSRs must be derived from existing documents/analyses that specifically demonstrate the limiting conditions that the facility is expected to experience during normal operations and potential accident conditions. In order to serve as the basis for the TSRs, these studies must systematically evaluate: • All potential off-normal conditions that could occur during the life of the facility • What could be considered design basis accidents D. Responsibilities for TSRs • Prepare → Contractor • Review → DOE Field Office • Approve → CSO Refer participants to page 24 of handouts, “Typical Safety Analysis Report (SAR) Contents.” Show OT 5.9. Show OT 5.10. Obj. 4 Describe the responsibilities for the development and use of TSRs. Refer participants to page 26 of handouts, “Technical Safety Requirement (TSR) Format and Content.” Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 6 E. Identification of violations Violations of a TSR occur as the result of four circumstances: • Exceeding a Safety Limit (SL)

• Failing to take the necessary actions within the required time limit following: – Exceeding a Limit Control Setting (LCS) – Failing to meet Limiting Conditions for Operations (LCO) – Failing to successfully meet a Surveillance Requirement (SR) • Failing to perform a surveillance within the required time limit • Failing to comply with an Administrative Control (AC) requirement As stated previously, compliance with TSRs is required by 10 CFR 830.205, violations may be enforceable under PAAA. F. Reporting Requirements (DOE Order 231.1A,Change 1 A, Chg 1) Occurrence Reporting and Processing of Operations Information, June 2004 • Categorization – Operational Emergency – Significance Category 1 - 4 • Notification • Follow-up notification • Occurrence Report preparation TSR ACs may impose additional facility- or operations-specific reporting requirements, which must also be carefully and fully followed. Show OT 5.11. Note that the violation relates to failure to comply with an Action Statement. The actions required to be taken when LCSs are exceeded, or when operations outside an LCO occur, are intended to provide compensatory protection for the same safety concerns for which the limit was established. Thus, exceeding the limit by itself is not considered a violation but is a reportable event as an Off-Normal Occurrence. Obj. 5 List the criteria for identifying problems in meeting TSRs. Show OT 5.12. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 7 Violations of TSRs may need to be reported as part of the Noncompliance Tracking System (NTS). For guidance on NTS reports, refer to Operation Procedure Identifying, Reporting, and Tracking Nuclear Safety Noncompliances, June 1998, prepared by the DOE Office of Enforcement (HS - 40). G. Ancillary guidance The TSR document shall be kept current at all times so that it reflects the facility as it exists and is analyzed in the SAR. The TSR must be approved prior to changes in the facility or facility practices. TSRs should be written in a clear and concise manner, in language that is understandable by those in the facility operating organization. The TSR should not contain excessive details that belong more appropriately in the SAR. The scope and content of TSRs are to be limited to only the most critical nuclear safety areas. This serves to make TSR Documents more useful for controlling facility safety. H. Radiological Assessment of TSR Compliance TSRs typically specify requirements for several areas that may be reviewed as part of a radiological assessment. These areas include: Area monitors: Criticality monitors Area Radiation Monitors Air Monitors (i.e., real time air monitors, fixed head air samplers) TSRs are the primary source of the more important safety requirements that are imposed upon any facility operations/activities. The bases for the TSRs can be found in the Safety Analysis Report, principally in the chapters on Safety Criteria and Accident Analysis. Obj. 6 List areas in TSRs which could be reviewed as part of a radiological assessment Show OT 5.13. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 8 Surveillance requirements for area monitors HEPA ventilation systems and their surveillances Shift Staffing Facility staff qualification, training and retraining Audits and reviews Summarize lesson. Review objectives. Ask for questions.

Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 5 – 9 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Aspects of Uranium Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify the radiological properties of uranium. 2. Describe the toxicological properties and behavior of uranium. 3. Identify appropriate instrumentation, measurement techniques, and special radiological survey methods for uranium. 4. Describe personnel protection requirements, external dose control techniques, and internal dose control techniques. 5. Describe special controls and considerations required for uranium operations. Training Aids: Overhead Transparencies (OTs): OT 6.1 – OT 6.11 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Flip chart Markers Masking tape Student Materials: Student’s Guide Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 2 References: ICRP Publication 30, Limits for Intakes of Radionuclides by Workers, 1979. U.S. Department of Energy, DOE-STD-1136-2000, Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities, 2004. U.S. Department of Energy, DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003. U.S. Department of Energy, DOE-HDBK-1113-98, Radiological Safety Training for Uranium Facilities, Reaffirmation May 2005. U.S. Department of Energy, DOE-STD-1098-99 Chg 1, Radiological Control, March 2005. U.S. Environmental Protection Agency, Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration, and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, EPA-520/1-88-020, 1988. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 3 I. Introduction The guidance in DOE-STD-1136-2000, Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities, 2004 should be reviewed in detail prior to conducting an assessment of uranium facilities. The following is a brief overview of the radiological aspects of uranium. II. Radiological aspects of uranium A. Radiological properties of uranium Fifteen radioisotopes exist, but the three of most concern to the uranium industry are: Uranium-238: 99.7% abundant in natural uranium; half-life = 4.5 billion yrs, specific activity = 3.3 E-7 Ci/g Uranium-235: 0.72% abundant; half-life = 710 million yrs, specific activity = 2.1 E-6 Ci/g Uranium-234: 0.006% abundant; half-life = 247 thousand yrs, specific activity = 6.2 E-3 Ci/g Enriched uranium has a higher content of Uranium-235 than found in nature. Typical enrichment values are: • 2%-3% Uranium-235: power reactor grade fuel • >90% Uranium-235: weapons grade material Show OT 6.1 and OT 6.2. State objectives. Show OT 6.3. Obj. 1 Identify the radiological properties of uranium. Review DOE-STD-1136-2000, Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities, 2004. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 4 Specialized reactor fuel may have enrichments other than those listed above. The uranium byproduct of enrichment is reduced in Uranium-235 content and is called depleted uranium. Its typical composition is as follows:

• 99.75% Uranium-238 • 0.20% Uranium-235 • 0.0007% Uranium-234 As a result of the differences in specific activities, Uranium-234 may account for a significant fraction, or even the majority, of the radioactivity for enriched uranium. For example, for 3% enriched uranium (i.e., 3% Uranium-235), the Uranium-234 (with an abundance of 0.03%) would have approximately 6 times the activity as Uranium-238 and approximately 30 times the activity as Uranium-235. Uranium-238 and Uranium-234 are part of the uranium decay series, while Uranium-235 is part of the actinium series. Therefore, following chemical separation, decay products will continue to grow in. The most significant of these are Thorium-234 and Protactinium-234m from the uranium series and Thorium-231 from the actinium series. Other small amounts of radioactive material may be present as the result of reprocessing uranium. These include Neptunium, Plutonium, Technetium-99, and other radioisotopes of uranium, including Uranium-232 and Uranium-236. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 5 B. Radioisotopes The primary radioisotopes of uranium are all long-lived alpha-emitters. The specific activity (Ci/g) of uranium increases as enrichment increases; therefore, enriched uranium is a more serious radiation hazard. In most uranium facilities, the inhalation hazard from alpha particles released in the respiratory tract is the predominant radiological hazard associated with the alpha emitting uranium isotopes. In addition, uranium decay products are primarily beta-emitters. For external exposure, the major concern is the high-energy beta particle from Protactinium-234m (2.29 MeV). As a result of beta radiation, the typical contact dose with a block of uranium is approximately 200 mrad/hr. Trace contaminants such as Technetium-99 and Uranium-232 may result in additional external radiation dose when present. As a result of the alpha-neutron reaction, casks of enriched uranium hexafluoride may also emit neutrons. Typical dose rates are on the order of a few mrem/hr. Show OT 6.4. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 6 C. Criticality Uranium-235 and Uranium-233 are both fissile materials; therefore, facilities handling enriched uranium and/or Uranium-233 have the potential for criticality accidents, generating large amounts of neutron and gamma radiation. D. Toxicological properties of uranium Uranium is a heavy metal poison and is toxic in much the same way lead or mercury is. For soluble compounds of low enrichments (< 5% Uranium-235), the toxic properties of uranium override the radiological hazards. The kidney is the primary organ of concern. For insoluble compounds of any enrichment or all compounds of highly enriched uranium, the radiological hazards are limiting. III. Detection, measurement, and survey techniques A. Monitoring program A radiation protection monitoring program in a uranium facility must ensure the detection of typical ionizing radiations over wide energy ranges. To detect alpha radiation from the uranium isotopes surveys using photon-sensitive portable and fixed alpha detectors such, as zinc sulfide or gas proportional counters, should be used. Appropriate beta detection instrumentation should be available to measure decay products such as Protactinium-234m. If Technetium-99 is suspected, special low-energy beta particle detection equipment should be available.

Obj. 2 Describe the toxicological properties and behavior of uranium. See Table 2-13 of DOE-STD-1136-2000 Show OT 6.5. Obj. 3 Identify appropriate instrumentation, measurement techniques, and special radiological survey methods for uranium. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 7 If large quantities of uranium hexafluoride are present, appropriate neutron survey instruments should be available to measure the neutron radiation. If the facility contains enriched uranium and/or Uranium-233, appropriate criticality safety alarm systems shall be in place and appropriate neutron and gamma survey instruments available. Continuous air monitors (CAMs), sample extraction lines that go to CAMs, and continuous radiation dose monitors should be placed outside glove boxes and fume hoods. B. Survey Techniques Monitoring practices include, but are not limited to, the following: • Contamination surveys of the workplace • Release surveys • External exposure surveys • Airborne contamination surveys • Routine surveillance by a Radiological Control Technician All work areas must be monitored for contamination levels on a regularly scheduled basis. The frequency of such surveys will depend on the potential for dispensability of the radioactive material. During these routine surveys, all work enclosures, work surfaces, floors, and equipment within the workplace should be surveyed. Show OT 6.6. C. Workplace characterization At the time a program is established, measurements of external dose should be made Show OT 6.7. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 8 at all locations where it occurs to delineate the levels involved (workplace characterization). Additional measurements should be made at the same frequency as the contamination surveys to identify the buildup of uranium in HEPA filters and glove boxes. Airborne contamination surveys should be performed for: • Prompt detection of airborne contamination for worker protection • Personnel dose assessment • Monitoring of trends within the workplace • Special studies IV. Personnel protection requirements Workers in uranium facilities need to be appropriately trained on the hazards. DOE has developed DOE-HDBK-1113-98, Radiological Safety Training for Uranium Facilities, Reaffirmation May 2005. This handbook provides DOE's guidance on expectations for training of uranium workers. A. Personnel air sampling The use of personnel air sampling programs should be considered in monitoring individual Radiological Workers. B. Protective clothing As a minimum, personnel who perform operations in controlled areas should wear coveralls – protective clothing is required in contamination areas, not controlled areas. No personal outer clothing should be permitted under coveralls. For inspections or visits, lab Show OT 6.8. Obj. 4 Describe personnel protection requirements, external dose control techniques, and internal dose control techniques. Review DOE-HDBK-1113-98, Radiological Safety Training for Uranium Facilities, 1998. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 9 coats, gloves, and shoe covers may be permissible. Protective clothing should be removed at the

step-off pad, and personnel monitoring for contamination shall be performed. If this is not practical, strict control of the movement of personnel shall be maintained from the step-off pad to a location where protective clothing can be removed. Personnel wearing protective clothing shall not be allowed to mingle with individuals wearing personal street clothing. Protective clothing shall not be allowed in uncontrolled areas such as offices, lunchrooms, or control rooms. C. Respiratory protection Respiratory protection should be readily available. Respiratory protective equipment should be used for all bag-out operations, bag and glove changes, and any situation involving a potential or actual breach of confinement. V. External dose control A. Beta radiation Beta radiation is usually the dominant external radiation hazard in work with unshielded forms of uranium. The primary concern is Protactinium-234m, though other radionuclides may be present. Particular care should be taken in operations such as melting and casting, where decay products could be separated and concentrated. Appropriate measurements should be made of the material and appropriate extremity dosimetry worn by workers handling the material. Show OT 6.9. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 10 B. Gamma radiation Gamma radiation is normally not the controlling factor at uranium facilities. However, gamma fields can exist in areas where large quantities of uranium are stored. Appropriate actions including time, distance, and shielding considerations should be taken to maintain radiation doses ALARA. C. Neutron radiation Neutron radiation from enriched uranium fluoride compounds should also be considered in determining potential external radiation hazards. VI. Internal dose control Intakes In most uranium facilities, the primary radiological hazard is the potential for internal intakes of uranium. This hazard must be controlled by appropriate facility and equipment design, contamination control procedures, and protective clothing. Inhalation is the primary route of concern. Uranium transported from the lungs is deposited in the bone (22%), kidney (12%), or other tissues (12%), or excreted (54%), according to International Commission on Radiological Protection (ICRP) Publication 30. Control must be verified by a bioassay program. Urinalysis is the most common technique, but fecal analysis and in vivo monitoring may also be appropriate. Show OT 6.10. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 11 DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003, provides technical guidance on internal dosimetry programs, including evaluation of occupational internal doses from exposure to radon and thoron. This standard should be reviewed prior to conducting assessments of internal dosimetry programs. VII.Special controls and considerations at uranium operations A. Criticality alarm systems (gamma or neutron) shall be provided in each area where an accidental criticality is possible. Site requirements documents relating to criticality alarms should be reviewed prior to the assessment, if applicable. These requirements may include: ANSI/ANS 8.1, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors; ANSI/ANS 8.3 Criticality Accident Alarm Systems; ANSI/ANS 8.7, Nuclear Criticality Safety in the Storage of Fissile Materials; ANSI/ANS 8.15, Nuclear Criticality Control of Special Actinide Elements; and ANSI/ANS 8.19, ANS Administrative Procedures for Nuclear Criticality.

B. All DOE facilities that possess sufficient quantities and kinds of fissile material to constitute a potentially critical mass shall provide nuclear accident dosimetry (fixed and personal). The number of dosimeters needed and their placement will depend on the nature of the operation, structural design of the facility, and accessibility of areas to personnel. An analysis of the dosimeters and their placement should be conducted and documented. Review DOE-STD-1121-98, Internal Dosimetry. Reaffirmation May 2003 Show OT 6.11. Obj. 5 Describe special controls and considerations required for uranium operations. Reference 10 CFR 835.1304. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 6 – 12 C. Uranium metal in finely divided form is pyrophoric; therefore, any grinding or milling operations must be carefully conducted to avoid fires. Uranium hexafluoride is commonly found in many uranium operations. This material is a solid at room temperatures but volatilizes readily at elevated temperatures. As a gas, it is extremely hazardous, forming hydrofluoric acid when it comes in contact with water. Operations involving uranium hexafluoride must be conducted very carefully to prevent release of the gas. D. External radiation hazards from uranium are primarily associated with decay products; therefore, operations in which the decay products can separate and concentrate must be monitored carefully. For example, crucibles used to melt depleted uranium and casks used to ship uranium hexafluoride are sometimes more radioactive after they are emptied than when they are full. The reason is that the decay products are left in the emptying process and are no longer self-shielded by the uranium. Summarize lesson. Review objectives. Answer questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Aspects of Tritium Objectives: Upon completion of this lesson, the participant will be able to: 1. Describe the radiological properties of tritium. 2. Identify personnel protection requirements and dose control techniques. 3. Identify the biological effects of internally deposited tritium. 4. Describe appropriate instrumentation, measurement techniques, and special radiological survey methods for tritium. 5. Identify special controls and considerations required for the use of tritium. Training Aids: Overhead Transparencies (OTs): OT 7.1 – OT 7.14 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Flip chart Markers Masking tape Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 2 Student Materials: Student’s Guide References: U.S. Department of Energy, DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003. U.S. Department of Energy, DOE-HDBK-1129-99, DOE Handbook Tritium Handling and Safe Storage, Reaffirmation 2007. U.S. Department of Energy, DOE-HDBK-1105-96, Radiological Training for Tritium Facilities, Reaffirmation 2002. U.S. Department of Energy, DOE-HDBK-1079-94, Primer on Tritium Safe Handling Practices, 1994. U.S. Department of Energy, Radiological Control Technical Position, RCTP 01 - 02, Acceptable Approaches for Developing Air Concentration Values for Controlling Exposures to Special Tritium Compounds, 2001.

U.S. Environmental Protection Agency, Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration, and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, EPA-520/1-88-020, 1988. ICRP Publication 30, Limits for Intakes of Radionuclides by Workers, 1979. ICRP Publication 66, Human Respiratory Tract Model for Radiological Protection, 1994. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 3 I. Introduction II. Radiological aspects of tritium A. There are three primary sources of tritium. These are: 1. Environmental sources - Reactions between cosmic rays and the upper atmosphere 14N + 1n � 3H + 12C 2H + 2H � 3H + 1H 2. By-product of power reactors • Ternary fission - A fission event resulting in fission fragments, one of which is tritium. Occurrence typically has a 0.1% yield. B-10 (n, 2 alpha) 3H Li-7 (n, n alpha) 3H 3. DOE production of tritium (Hanford, Savannah River reactors) is by the following reaction: 6Li + 1n � 3H + alpha Show OT 7.1 and OT 7.2. State objectives. Show OT 7.3. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 4 B. Chemical and radiological properties of tritium 1. Chemical forms • Elemental tritium (tritium gas, HT, DT, T2) • Tritiated water (tritium oxide, HTO, DTO, T2O) • Special tritium compounds (STCs): created by intentional combination of tritium with the desired materials or by inadvertent contamination of a material that has been subjected to the presence of tritium for a period of time. These are classified in a number of ways, depending on their host material (metal or organic), rate of tritium release (stable or unstable), and physical form (particulate or non-particulate). They include: - Organically bound tritium (OBT); the main types of OBT encountered in the DOE complex are solvents, oils, and solid particulates (e.g., plastics, nylon, and organic dust forms). - Particulates; stable or insoluble forms are referred to as stable tritiated particulates (STPs). Show OT 7.4. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 5 2. Radiological properties • 3H � 3He + beta minus and anti-neutrino • Emax = 18.6 keV, Eavg = 5.69 keV • Half-life = 12.32 years • Specific activity = 9619 Ci/gram • ALIwater = 3000 MBq = 8 E4 µCi (inhalation and ingestion) • DACwater = 0.8 MBq/m3 = 2 E-5 µCi/cm3 • DACelemental = 2 E4 MBq/m3 = 0.5 µCi/cm3 • f1 = 1 • Committed dose equivalent per unit intake = 1.73 E-11 Sv/Bq = 6.4 E-2 mrem/µCi • DACelemental/DACwater = 25,000 In addition, DOE has issued guidance on radiological protection for special tritiated compounds in Radiological Control Technical Position, RCTP 0 1 - 02, Acceptable Approaches for Developing Air Concentration Values for Controlling Exposures to Special Tritium Compounds. DOE has also issued RCTP 06-01, Acceptable Approaches for Developing Sealed Radioactive Sources and Posting and Labeling Requirements for Special Tritium Compounds (STCs). DOE has also developed a technical standard, Radiological Control Programs for Special Tritium Compounds, DOE- HDBK-1184-2004, Change Notice 1 May 2006. Obj. 1 Describe the radiological properties of tritium. Show OT 7.5.

Review Radiological Control Technical Position, RCTP 01 - 02, Acceptable Approaches for Developing Air Concentration Values for Controlling Exposures to Special Tritium Compounds. Rev Review Radiological Control Programs for Special Tritium Compounds, DOE- HDBK-1184-2004 Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 6 C. Potential exposure pathways of tritium Dose pathways and biological effects • Inhalation – Elemental tritium (tritium gas) - Limiting condition is exposure to the lung – Approximately 0.005% of HT inhaled is converted to HTO prior to exhalation – Nearly 100% of inhaled HTO is incorporated into body fluids/tissues. • Ingestion – Tritiated water • Assumed to be instantaneous • Biological half-life is normally ten days, but may be reduced by a factor or two-three with increased fluid intake • Skin absorption of HTO through intact skin ≈50% of that inhaled. For different modes of entry of STCs: – STPs behave with the characteristics of the particle to which they are attached. - Soluble OBT distributes throughout the body causing a whole body dose. Insoluble OBT can be taken into the body by inhalation when in particulate form. Airborne droplets of insoluble components of oils may be treated as stable particulates. Show OT 7.6. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 7 D. General sources of tritium releases 1. Gaseous releases - ventilation exhaust systems 2. Liquid wastes • Aqueous • Organic (e.g., oils) 3. Solid wastes • Contaminated wastes • Treatment residues E. Exposure controls for tritium The personnel protection requirements for tritium include: • Airborne contamination controls • Surface contamination controls 1. Airborne controls • Differential room pressure zones • Dilution ventilation • Room-air detritiation systems • Local exhaust ventilation Show OT 7.7. Show OT 7.8. Obj. 2 Identify personnel protection requirements and dose control techniques. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 8 2. Contamination controls • Good housekeeping • Good work practices 3. Personnel protective equipment • Air supplied respirators • Protective clothing F. Metabolism of tritium The tritium beta lacks sufficient energy to penetrate the dead cell layer in skin. Therefore, it is of little consequence as an external hazard. The beta particles can produce Bremsstrahlung radiation when they interact with matter, although the tritium Bremsstrahlung is extremely low energy. It is remotely possible that the Bremsstrahlung exposure could become significant around materials with very high specific activities and little or no shielding. Tritium can deliver a radiation dose if it gets inside the body. Modes of entry include: • Inhalation • Ingestion • Absorption 1. Inhalation Tritium gas (HT) is only slightly incorporated into the body when inhaled. Approximately 0.005% of HT inhaled is converted to tritiated water prior to being exhaled. Depending upon the rate at which HT converts to HTO in vivo, it is possible that some dissolved HT may be excreted in urine. Obj. 3 Identify the biological effects of internally deposited tritium. Show OT 7.9. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 9

Tritiated water (HTO) is much more radiologically hazardous than tritium gas. Inhaled HTO enters the body through the lung fluids with 100% efficiency, and mixes rapidly with body water. Nearly 100% of tritiated water (HTO) inhaled is incorporated into body fluids and tissues. 2. Ingestion Ingested HTO is assumed to be completely and instantaneously absorbed from the gastrointestinal tract and mixes rapidly with the body fluids so that following ingestion, the concentration in sweat, sputum, urine, blood, perspiration and expired water vapor is the same. 3. Absorption There is negligible skin absorption for tritium gas. Some HT can be absorbed through the skin from contact with surface contamination. This uptake is probably in the form of HTO, resulting from the oxidation of HT. Some tritium may be retained in the skin in the form of organics, presumably resulting from exchange reactions with HT on or in the skin. HTO can be readily absorbed through the skin. It will be uniformly distributed in all biological fluids within one to two hours. Most exposures are to HTO, which rapidly enters the body water via absorption through the lungs and/or skin. A small amount of HT can dissolve in lung fluids, convert to HTO, and enter the body fluids. Exposures to HTO are approximately 10,000 to 25,000 times more hazardous than exposure to HT. HTO has an effective half-life in the body in the range of 4 to 18 days, with a mean effective half-life of about 9 or 10 days. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 10 Most tritium leaves the body either in urine or through evaporation from the lungs and skin. The dose commitment from an uptake of one curie of HTO is approximately 63 rem. For the above 3 discussed modes of entry: STPs and insoluble components of tritiated oils behave with the characteristics of the particle to which they are attached. For dose calculations for STPs, ICRP Publication 66 uses absorption types; slow, medium, and fast (S, M, F). These are used in place of the lung retention classes (day, week, and year; D, W, Y) used in ICRP Publication 30. Depending on the absorption type of the compound, the dose per intake will be different than HTO. For example: The air concentration value (which could be used in assessing dose per intake) for Type S STP is 10 times more restrictive than HTO, while the air concentration value for Type F STP is 5 times less restrictive than HTO. Soluble OBTs act somewhat similar to HTO, however a larger percentage of nuclear transformations occur in the stomach. The dose per intake is approximately twice that of HTO. Skin absorption is also a valid intake pathway for tritiated oil components and solvent OBT. G. Methods of tritium containment 1. Primary - Process equipment and piping 2. Secondary • Glove boxes • Temporary vented enclosures Review Types S, M, F Show OT 7.10. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 11 3. Tertiary - Room and associated ventilation systems • Effluent recovery systems • Emergency containment systems H. Airborne tritium controls 1. Differential room pressure zones - The air ventilation system plays a key role in controlling the spread of contamination. In addition to providing the necessary humidity and temperature control for a building, differential pressure zones should be established within a building to ensure that the air flows from areas with lower hazardous contamination potential to areas with more hazardous contamination potential.

2. Dilution ventilation - Dilution ventilation is the once-through flow technique of exchanging outside air for inside air for comfort and basic contamination control. 3. Room-air detritiation systems - Such a system uses tritium monitors located in the room exhaust to activate (close) fast acting dampers. The dampers then route the exhaust through a special oxidation/drying system and return the air to the room. 3. Local exhaust ventilation - The primary advantage of local exhaust ventilation techniques is the removal of airborne tritium, regardless of its evolution rate or chemical or physical form. In addition, these techniques use relatively low flow rates compared to normal ventilation requirements. Show OT 7.11. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 12 I. Measurement techniques for tritium 1. Air monitoring - Fixed and portable ionization chambers most widely used. 2. Differential monitoring - Separate monitoring of HT and HTO components through the use of bubblers in conjunction with desiccants or catalysts. 3. Discrete sampling - Samples collected with a bubbler or “cold finger” type sampler, then later analyzed by liquid scintillation counting techniques. 4. Process monitoring • Stack, room, hood, glove box • Mass spectroscopy, gas chromatography, calorimetry 5. Surface monitoring • Difficult to measure directly due to low- energy emission • May have some success with thin window GM (pancake style probe), thin window sodium iodine, or gas flow proportional counters • Smears taken for loose contamination, and measured by dissolution and analysis by liquid scintillation counting techniques 6. Liquid Monitoring - Liquid scintillation counting techniques Show OT 7.12. Obj. 4 Describe appropriate instrumentation, measurement techniques, and special radiological survey methods for tritium. Flow-through ionization chambers Typical example - TRITON radioactive gas monitors Explain how the ionization chamber works. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 13 J. Bioassay program for tritium workers An adequate bioassay program for tritium workers would test for chronic and acute exposure. 1. Chronic exposure - Periodic urinanalysis for tritium (daily to biweekly identified in Tritium Good Practices Manual) 2. Acute exposure • Wait one to two hours. • Void bladder. • Collect sample as soon as possible thereafter. • Continue to collect daily to determine individual half-life. Dose from exposure to STCs may need to be assessed based on air monitoring results, see RCTP 99-02. DOE-STD-1121-99, Internal Dosimetry, 1999, provides guidance on internal dosimetry programs including monitoring and assessing dose from tritium. K. Tritium effluent recovery systems 1. Purpose - Reduce tritium available for release 2. Method - Tritium gas converted to HTO and ultimately a stable waste form Show OT 7.13. Obj. 5 Identify special controls and considerations required for the use of tritium. Review DOE-STD-1121-99, Internal Dosimetry, 1999, for tritium applications. Show OT 7.14. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 7 – 14 L. Inventory control and accountability for tritium 1. Nuclear materials, including tritium, need to be controlled and have material accountability. 2. Appendix D to the Tritium Good Practices Manual discusses inventory control and defines it to consist of:

• Measurements • Measurement controls • Determination of holdup in systems • Development of predictors • Establishment of accounting practices Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Aspects of Plutonium Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify the radiological properties of plutonium. 2. Identify the biological effects of plutonium. 3. Identify special controls and considerations required for plutonium operations. 4. Describe appropriate instruments, measurement techniques, and special radiological survey methods for plutonium. 5. Describe personnel protection requirements and dose control techniques for plutonium. Training Aids: Overhead Transparencies (OTs): OT 8.1 – OT 8.12 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Student Materials: Student’s Guide Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 2 References: American National Standards Institute, ANSI/ANS, Criticality Accident Alarm Systems, 1986. American National Standards Institute, ANSI/ANS 8.1, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors, 1983. American National Standards Institute, ANSI/ANS 8.19, ANS Administrative Procedures for Nuclear, 1984. ICRP Publication 30 Part 4, Limits for Intakes of Radionuclides by Workers: an Addendum, 1988. U.S. Department of Energy, DOE-STD-1128-98, Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities, Change Notice 2, December 2006. U.S. Department of Energy, DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003. U.S. Department of Energy, DOE-STD-1098-99, Radiological Control, Change Notice 1, March 2005 U.S. Department of Energy, Radiological Control Technical Position 2001-01, Questions and Answers Concerning Acceptable Approaches to Implementing Bioassay Program Requirements, January 2001. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 3 I. Introduction The guidance in DOE-STD-1128-98, Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities, Change Notice 2 December 2006 should be reviewed in detail prior to conducting an assessment of plutonium facilities. The following is a brief overview of the radiological aspects of plutonium. II. Background Plutonium was first synthesized in the winter of 1940- 41 by a team of scientists at the University of California. Its potential use in weapons was quickly identified, and much of the effort of the Manhattan Project was in the production of sizable quantities of plutonium. Other uses for plutonium include use as: • Reactor fuel • Heat sources in thermoelectric generators to power satellites • Components in portable neutron sources Plutonium is a silvery-white metal that readily oxidizes to a dull gray color. It can be found in a variety of physical and chemical forms. Several of the chemical forms (including the pure metal) are pyrophoric, so care must be exercised in handling the material. Because of the pyrophoric nature of plutonium and its alloys, the preferred form for storing, shipping, and handling is as plutonium oxide. III. Radiological properties of plutonium

A. Isotopes There are 15 isotopes of plutonium, all radioactive, beginning with Plutonium-232 and ending with Plutonium-246. The radioisotopes of primary interest are Plutonium-238, Plutonium- 239, and Plutonium-240, all of which are primarily alpha-emitters. Show OT 8.1 and OT 8.2. State objectives. Review DOE-STD-1128-98, Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities Change Notice 2 December 2006. Pyrophoric = able to ignite spontaneously Obj. 1 Identify the radiological Properties of plutonium. Show OT 8.3. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 4 1. Plutonium-238 (half-life = 87.7 yrs) is most commonly used as a heat source in thermoelectric generators. Because of its heat production, care must be taken in handling gram or larger quantities, as it could melt plastic or ignite other materials. 2. Plutonium-239 (half-life = 24,000 yrs) is the primary component of plutonium reactor fuel (>85%) and weapons grade plutonium (>90%), with Plutonium-240 (half-life = 6,560 yrs) constituting most of the remainder in both cases. 3. Plutonium radioisotopes emit relatively few high-energy gamma rays, so kilogram quantities can often be processed without serious gamma dose problems. However, small amounts of some radioisotopes or decay products can increase external dose. For example, Plutonium-241 decays by beta emission to Americium-241, which emits a 60- keV gamma ray. This can be a significant source of dose to hands in glove boxes. 4. Neutron dose rates from spontaneous fission and from alpha-neutron reactions with light elements may be significant (e.g., 1 kg of Pu-F4 (Pu-238) would have a contact neutron dose equivalent rate of 4800 rem/hr). B. Biological effects of internally deposited plutonium The primary hazards from the most common chemical form of plutonium (PuO2) are inhalation and ingestion. This chemical form is relatively insoluble. Therefore, uptake through the gastroin- testinal (GI) system following an ingestion is small. Inhaled plutonium can remain in the lungs for a considerable time before being removed through the lymph system. Show OT 8.4. Obj. 2 Identify the biological effects of plutonium. . Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 5 Plutonium is difficult to remove from the body. The primary method is through the administration of chelating agents as soon after the intake as possible. Trained medical personnel are needed to administer chelating agents. The plutonium that enters the systemic system is mostly translocated to the liver and the bone (as is discussed in the following section). Accordingly, development of cancer in these organs and in the lungs are of particular interest in evaluating long-term effects from intakes of plutonium. C. Survey techniques A radiation protection program in a plutonium facility shall ensure the detection of all types of radiation (i.e., alpha, beta, gamma, x-ray, and neutron) over large energy ranges. Alpha- sensitive instruments are necessary for most contamination control surveys. Continuous air monitors (CAMs), sample extraction lines that go to CAMs, and continuous radiation dose monitors should be placed outside the glove boxes and hoods. Neutron surveys become important when

processing tens of grams of Plutonium-238 or hundreds of grams of mixed isotopes of plutonium, particularly compounds (i.e., PuO2, PuF4). The neutron survey is important in instances where photon shields, such as leaded glass, are used. Such shields normally stop all of the charged particles, most of the low-energy photons, and essentially none of the neutrons. Under these circumstances, neutron radiation is likely to be the major contributor to whole body dose. Exposure rate surveys are normally conducted with photon-sensitive instruments with known energy responses for photons with energies ≥ 10 keV. Show OT 8.5. Obj. 3 Identify special controls and considerations required for plutonium operations. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 6 Monitoring practices include, but are not limited to, the following: • Contamination surveys of the workplace • Release surveys • External exposure rate surveys • Airborne radioactivity surveys (both real time (CAMs) and historical (fixed air head)) • Routine surveillance by a Radiological Control Technician All workplaces shall be monitored for contamination levels on a regularly scheduled basis. The frequency of such surveys will depend on the potential for dispensability of the radioactive material. As a minimum, all gloves, work surfaces, floors, and equipment within the workplace should be surveyed. Airborne radioactivity surveys should be performed for: • Prompt detection of airborne contaminants for worker protection • Personnel dose assessment • Monitoring of trends within the workplace • Special studies Intakes In most plutonium facilities, the primary radiological hazard is the potential for internal intakes of plutonium. This hazard must be controlled by appropriate facility and equipment design, contamination control procedures, and protective clothing/equipment. Show OT 8.6. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 7 Plutonium transferred from the initial entry site is assumed to be translocated to the liver (45%) and the bone (45). Retention half-life in the liver is 20 yrs and in the bone is 50 yrs, according to International Commission on Radiological Protection (ICRP) Publication 30. Control must be verified by a bioassay program. Urinalysis is the most common technique, but fecal analysis and in vivo monitoring may also be appropriate. DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003 provides technical guidance on internal dosimetry programs, including enhanced workplace monitoring for instances where there is a technology shortfall, such as for plutonium. This standard should be reviewed prior to conducting assessments of internal dosimetry programs. The standard also discusses appropriate evaluation of bioassay results. D. Monitoring instruments DOE-STD-1128-98, Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities, Change Notice 2 December 2006 has additional guidance on monitoring instrumentation. Facilities that deal with unencapsulated plutonium should have continuously operating effluent monitors to determine whether or not plutonium is being released to the environment. Per ICRP Publication 48, studies have indicated an average partitioning of plutonium between liver and bone of 30% and 50%. However, due to high individual variability, use of the 45% liver and 45% bone partitioning is still recommended.

Review DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003. Discuss technology shortfall - routine bioassay cannot reliably detect exposures of 100 millirem. Show OT 8.7. Obj. 4 Describe appropriate instruments, measurement techniques, and special radiological survey methods for plutonium. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 8 Criticality alarm systems (gamma or neutron) should be provided in each area where an accidental criticality is possible. E. Sources of external dose External dose control for plutonium is primarily concerned with photon dose rates from handling plutonium in a glove box and from the neutron dose rate from some mixtures of plutonium. While significant high-energy penetrating photons are not commonly associated with plutonium, low- energy photons (x- and gamma-rays) can create significant dose rate problems to extremities. This is particularly a concern when large amounts of Plutonium-238, Plutonium-241, or Americium-241 (from the decay of Plutonium-241) are present. Neutrons can also represent a potentially significant dose due to spontaneous fission (alpha, neutron) reactions or neutron induced fission. The neutron dose is largely determined by the radioisotope and other materials near the source. F. Control of external dose External dose control is accomplished with traditional dose reduction techniques: • Time (minimize) • Distance (maximize) • Shielding (use as needed) Other work practices, including good housekeeping and specialized tool and equipment design, can reduce external dose, as well. Show OT 8.8. Show OT 8.9. Long-handled tongs, for example. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 9 G. Techniques for internal dose control The confinement system is a series of physical barriers that, together with a ventilation system, minimizes the potential for release of radioactive material into work areas and the environment under normal and abnormal conditions, thereby minimizing internal dose. Generally, three confinement systems are used to achieve the confinement system objectives at plutonium handling facilities. They consist of the following: • Primary confinement is provided by piping, tanks, glove boxes, encapsulating material, and the like, and any off-gas system that controls effluent from within the primary confinement. It provides confinement of the area immediately surrounding the hazardous material. • Secondary confinement is provided by the walls, floor, roof, and associated ventilation exhaust systems of the cell or enclosure surrounding the process material or equipment. Except in the case of glove box operations, the area inside this barrier is usually unoccupied; it provides protection for operating personnel. • Tertiary confinement is provided by the walls, floor, roof, and associated ventilation exhaust system of the facility. It provides a final barrier against release of hazardous material to the environment. Show OT 8.10. The term “containment” is also used for “confinement.” Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 10 Different devices may be used to confine and control radioactive material. The selection of the appropriate device will depend on the quantity of material, its form, and the operations to be performed. Fume hoods may be used for some operations

with plutonium, depending on the quantity and dispersability of the material. In general, plutonium fume hood operations shall be limited to wet chemistry processes and less than 100 mg of plutonium. Higher levels of plutonium are generally handled in glove boxes. Care should be taken in the design of the glove box to ensure confinement of the material and any fire. Ventilation may also be employed to confine plutonium, although it usually is used in conjunction with other measures. H. Personnel protection Workers in plutonium facilities need to be appropriately trained on the hazards. DOE has developed Radiological Safety Training for Plutonium Facilities, DOE-HDBK-1145-2001, Reaffirmation January 2007. This document provides DOE's guidance on expectations for training of plutonium workers. The use of personal air sampling programs should be considered to monitor individual workers for exposure to airborne plutonium. Section 4.4.4 of DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003 discusses use of breathing zone or personal air monitoring when there is a technology shortfall (i.e., the derived investigation level is less than the minimum detectable activity). Technology shortfalls are common for routine plutonium bioassay programs. Show OT 8.11. Obj. 5 Describe personnel protection requirements and dose control techniques for plutonium. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 8 – 11 In addition, DOE has issued guidance on use of air monitoring results when there is a technology shortfall in Radiological Control Technical Position (RCTP) 2001-01, Questions and Answers Concerning Acceptable Approaches to Implementing Bioassay Program Requirements. In part, RCTP 2001-01 states that, when there is a technology shortfall for bioassay and air monitoring results indicate exposures greater than 100 millirem in a year are likely, one should assess dose based on the air monitoring results. As a minimum, personnel who perform operations in controlled areas should wear coveralls and shoe covers. For inspections or visits, lab coats and shoe covers may be permissible. When contaminated wet areas are to be entered, water- repellent (plastic or rubber) clothing shall be worn. No personal outer clothing should be permitted under coveralls. Hands should be protected by a minimum of two barriers; for example, at least one pair of surgeon’s gloves and one pair of rubber gloves should be worn. Protective clothing should be removed at the step- off pad, and personnel monitoring for contamination shall be performed. Respiratory protection equipment shall be readily available. Respiratory protection equipment should be used for all bag-out operations, bag and glove changes, and any situation involving a potential or actual breach of confinement. Protection, in the form of air-purifying or atmosphere-supplying respirators, shall be used whenever concentrations of radionuclides in the air are likely to exceed the applicable DACs. I. Inventory control and accountability requirements Real-time or near real-time accountability systems should be incorporated if possible. Review Radiological Control Technical Position 2001-01, Questions and Answers Concerning Acceptable Approaches to Implementing Bioassay Program Requirements DAC = Derived Air Concentration, a 10 CFR 835 limit for airborne radioactivity. Show OT 8.12. Radiological Assessor Training DOE-HDBK-1141-2008

Instructor’s Guide Module 8 – 12 J. Criticality safety considerations Criticality alarm systems (gamma or neutron) shall be provided in each area where an accidental criticality is possible. Criticality safety requirements may include: ANSI/ANS 8.3-1986, Criticality Accident Alarm Systems; ANSI/ANS 8.1-1983, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors; and ANSI/ANS 8.19-1984, ANS Administrative Procedures for Nuclear Criticality. It is important to review site requirements documents prior to conducting the assessment. All DOE facilities that possess sufficient quantities and kinds of fissile material to potentially constitute a critical mass shall provide nuclear accident dosimetry. Reference 10 CFR 835.1304. Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 9 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Work Permits Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify types of job hazards that are not addressed by Radiological Work Permits (RWPs). 2. Describe the two basic types of RWPs. 3. Determine the types of jobs that may and may not be worked under the controls imposed by RWPs. 4. Identify typical time limits for the two basic types of RWPs. 5. List essential elements of an effective RWP. 6. List RWP program elements that may be included in a radiological assessment. Training Aids: Overhead Transparencies (OTs): OT 9.1 – OT 9.11 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Student Materials: Student’s Guide References: U.S. Department of Energy, DOE-STD-1098-99, Radiological Control, Change Notice 1, March 2005. U.S. Department of Energy, 10 CFR Part 835, Occupational Radiation Protection, Amended June 2007. U.S. Department of Energy, Order 440.1-1A, Worker Protection Program for DOE (Including the National Nuclear Security Administration) Federal Employees Guide for Use with DOE O 440.1B March 2007. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 9 – 2 I. Introduction 10 CFR Part 835.501(d) requires written authorizations to control entry and perform work in radiological areas, commensurate with the radiological hazards. DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004, Chapter 3, Part 2, provides guidance on DOE's expectations for such written authorizations. These written authorizations may take a variety of forms tailored to the work processes involved. Often, the form will be that of a Radiological Work Permit (RWP), discussed in detail below. II. Radiological Work Permits (RWPs) A. Purpose The RWP is designed to document the radiological conditions and associated controls in a work area. The RWP should be integrated with other work authorizations that address safety and health issues, such as those for industrial safety and hygiene, welding, and confined space entry. Articles 311 and 312 of DOE-STD-1098-99 provide guidance on preparing work control procedures consistent with the principles of Integrated Safety Management. This includes use of multidiciplinary teams to prepare work control procedures for tasks involving significant types of hazards and referring to U.S. Department of Energy, Order 440.1-1A, Worker Protection Program for DOE (Including the National Nuclear Security Administration) Federal Employees Guide for Use with DOE O 440.1B March 2007.

B. Typical RWP process 1. Requester submits an RWP request form. Show OT 9.1 and OT 9.2. State objectives. Review Chp 3, Part 2 of DOE- STD-1098-99, Radiological Control, Reaffirmed December 2004. Obj. 1 Identify types of job hazards that are not addressed by Radiological Work Permits (RWPs). Show OT 9.3. The process may be different at your site or facility. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 9 – 3 2. Radiological Control Supervisor accepts form, collects additional job information as necessary, and assures that completion of appropriate radiological surveys to be performed in the work area. 3. Radiological Control Technicians, or other appropriately trained and authorized personnel, perform surveys, analyze samples, and report results. 4. RWP controls are established based on the results of the surveys. 5. Radiological Control personnel, in consultation with relevant technical staff, complete, distribute and implement the RWP. 6. Radiological Workers and Radiological Control personnel review completed RWP, prior to start of job, during pre-job briefs, and/or ALARA reviews. 7. Radiological Worker/Supervisor advises Radiological Control personnel when job is complete (so RWP can be terminated). 8. Radiological Control personnel maintain surveys and RWP documentation. C. Types of RWPs There are two basic types of Radiological Work Permits: • Job-specific RWP • General RWP The job-specific permit is used for jobs which present a greater potential for significant radiation dose, airborne radioactivity, or spread of contamination, and which involve “hands on” work. Show OT 9.4. Show OT 9.5. Obj. 2 Describe the two basic types of RWPs. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 9 – 4 Examples of jobs that would likely require job- specific RWPs include those where work is: • Performed with detailed, specific, written work procedures, approved in advance by Radiological Control personnel Obj. 3 Determine the types of jobs that may and may not be worked under the controls imposed by RWPs. • “Hands-on” work performed infrequently on radiological systems (e.g., valve replacement in process buildings) • Performed in areas in which the radiological conditions have no history of remaining stable The general RWP typically is used for jobs with less potential for health physics concerns and for routine, repetitive jobs that do not involve “hands on” work. Examples of jobs that may be worked under a general RWP include: • Routine tours, inspections, inventories, valve lineups, equipment tagouts, surveys, and equipment operation. • Work routinely performed on nonradiological systems (e.g., fire protection systems in shut- down process buildings). • Routine operations involving radioactive material for which the radiological conditions have a history of remaining stable. Keep in mind that there may be a need for other (nonradiological) permits or authorizations to safely perform these jobs. For example permits may be needed to address nonradiological hazards, such as: electrical, confined space, asbestos, hazardous materials, respiratory protection, fire, heavy equipment and scaffolding. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 9 – 5 D. Time limits The job-specific RWP usually remains in effect only for the duration of the job (typically less than 30 days).

The general RWP typically is approved for a period of time of one year or less. Show OT 9.6. Obj. 4 Identify typical time limits for the two basic types of RWPs. E. Elements of an RWP include: • Description of work (detailed) • Radiological conditions (contamination, airborne, radiation levels) in the work area • Dosimetry (TLD badge, self-reading dosimetry, special dosimetry) requirements • Requirements for a pre-job briefing, if necessary • Radiological Control Technician coverage (start of job, continuous, intermittent) • Training requirements to work in the area • Protective clothing requirements • Respiratory protection equipment requirements • Stay time requirements • Radiological conditions that may limit work or void the RWP • Special dose reduction (ALARA) or contamination reducing measures to be considered Show OT 9.7. Obj. 5 List essential elements of an effective RWP. “Valve work” is not a detailed work description. Briefings are needed most for elevated radiation or contamination levels: workers in High Contamination Areas need briefings more than workers in Contamination Areas. Show OT 9.8. Discuss stay time, accidents, and alarms. Discuss staff rotation, alarming dosimetry, planning, and shielding. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 9 – 6 • Special personnel contamination monitoring requirements • Work document number (if used) • Unique RWP identification number • Date of permit issue and expiration date • Signatures of Radiological Worker and supervisor (attesting to their understanding of RWP requirements and agreement to follow) and Radiological Control staff Show OT 9.9. If time allows, show examples of contemporary RWPs, highlighting required information and radiological controls. F. RWP Elements for Radiological Assessment The following are RWP program elements which may be reviewed as part of a radiological assessment: • RWPs appropriately required for activities and areas • Completeness of information on RWPs • Adequacy of radiological surveys to support RWP • Worker adherence to RWP requirements • RWP appropriately reviewed and approved • Adequacy of worker monitoring (TLDs, bioassay, air monitoring RCT coverage) specified on RWP • ALARA considerations included in RWP • RWP program implemented in accordance with written procedures Obj. 6 List RWP program elements that may be included in a radiological assessment. Show OT 9.10. Show OT 9.11. Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 9 – 7 Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 10 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Contamination Containment and Temporary Control Measures Objectives: Upon completion of this lesson, the participant will be able to: 1. Describe what temporary engineered radiological controls can be used to reduce or eliminate contamination spread. 2. Describe why engineered and administrative controls are needed. Training Aids: Overhead Transparencies (OTs): OT 10.1 – OT 10.5 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Student Materials: Student’s Guide References: U.S. Department of Energy, DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004.

U.S. Department of Energy, 10 CFR Part 835, Occupational Radiation Protection, Amended June 2007. U.S. Department of Energy, DOE-STD-1121-98, Internal Dosimetry, Reaffirmation May 2003. U.S. Department of Energy, Radiological Control Technical Position 2001-01, Questions and Answers Concerning Acceptable Approaches to Implementing Bioassay Program Requirements, 2001. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 10 – 2 I. Introduction 10 CFR Part 835, Occupational Radiation Protection, specifies contamination control requirements in Subpart L. Chapters 3 and 4 of DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004 provides guidance on meeting the requirements and additional information for implementing an effective contamination control program. All of these documents should be reviewed prior to conducting an assessment. II. Contamination containment and temporary control measures Minimization of internal dose The minimization and control of internal dose should be conducted in accordance with the following hierarchy of controls: 1. Engineered controls, including containment of radioactive material at the source wherever applicable, should be the primary method of minimizing airborne radioactivity and internal dose to workers. Engineered controls are devices such as glove boxes, glove bags, portable filtration units, and containment tents. They should be used to prevent worker inhalation of radionuclides. Portable and fixed/permanent shielding using dense materials (lead) or portable plastic interlocking fluid filled containers are also engineered features, used to minimize external radiation dose. Show OT 10.1. State objectives. Review 10 CFR Part 835, Occupational Radiation Protection DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004 Show OT 10.2. Obj. 1 Describe what temporary engineered radiological controls can be used to reduce or eliminate contamination spread. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 10 – 3 The use of these devices reduces the spread of contamination, cleanup time, and decontamination costs. These measures help maintain doses ALARA. In addition, they can reduce the need for respirators and the impact on work in nearby areas. Engineered controls should be used in accordance with technical instructions, proper training, and effective administrative controls Site-specific manuals should contain generic instructions on the design, controls, training, and use of engineered controls. 2. Administrative controls, including access restrictions and the use of specific work practices designed to minimize airborne contamination, should be used as the secondary method to minimize worker internal dose. Obj. 2 Describe why engineered and administrative controls are needed. Show OT 10.3. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 10 – 4 3. Only when engineered and administrative controls have been applied and the potential for airborne radioactivity still exists, should personnel protective equipment, including use of respiratory protection, be considered. Chapter 3 of DOE-STD-1098-99 discusses: Access controls for Contamination Areas Controlling the spread of contamination Monitoring for contamination. Appendix 3 C, Contamination Control Practices, includes recommended selection of protective clothing, and a recommended sequence for donning and doffing.

Use of respiratory protection should be considered under the following conditions: • Entry into posted Airborne Radioactivity Areas • During breach of contaminated systems or components • Work in areas or on equipment with removable contamination levels greater than 100 times the values in Table 2-2 of DOE-STD-1098-99 • During work on contaminated or activated surfaces with the potential to generate airborne radioactivity The selection of respiratory protection equipment should include consideration of worker safety, comfort, and efficiency. The use of positive pressure respiratory protection devices is recommended wherever practicable to alleviate fatigue and increase comfort. Show OT 10.4. Air-supplied respirators, for example Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 10 – 5 Respirators can provide adequate protection for workers in an airborne radioactivity environment, but engineered controls may be more practical. By using engineered controls instead of respirators, the worker is not subjected to the stresses created by wearing a respirator. It is more difficult to breath and communicate when wearing a respirator. Vision is impaired, and the respirator is not comfortable. Productivity can therefore be improved by using engineered features instead of respirators. To minimize intakes of radioactive material by personnel, smoking, eating, or chewing shall not be permitted in Contamination, High Contamination, Airborne Radioactivity Areas, or Radiological Buffer Areas established for contamination control purposes. Contamination should be contained at its source. The principle is to prevent contamination spread from occurring. The most effective methods based on sound ALARA principles should be used. All controls should be documented and clearly controlled by RWPs. Respirators may be appropriate for simple, straightforward jobs. In specific situations the use of respiratory protection may be contraindicated due to physical limitations or the potential for significantly increased external dose. Show OT 10.5. Example: Work in high radiation fields and airborne radioactivity. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 10 – 6 In such situations, written authorization should be obtained from the line organization manager and the Radiological Control Manager prior to incurring internal dose. Specific justification of the need to accept the dose, including a description of measures taken to mitigate the intake of airborne radioactivity, should be documented as part of the radiological work documentation. The use of personal air sampling programs should be considered to monitor individual workers for exposure to airborne radioactive material, especially when the use of respiratory protection is contraindicated. This is particularly important when there is a bioassay program technology shortfall (i.e., the derived investigation level is less than the minimum detectable activity). Section 4.4.4 of DOE-STD-1121-98, Internal Dosimetry, discusses use of breathing zone or personal air monitoring. In addition, DOE has issued guidance on use of air monitoring results when there is a technology shortfall in Radiological Control Technical Position (RCTP) 2001-01, Questions and Answers Concerning Acceptable Approaches to Implementing Bioassay Program Requirements.

In part, RCTP 2001-01 states that, when there is a technology shortfall for bioassay and air monitoring results indicate exposures greater than 100 millirem in a year are likely, one should assess dose based on the air monitoring results. Review Radiological Control Technical Position 2001-01, Questions and Answers Concerning Acceptable Approaches to Implementing Bioassay Program Requirements Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Work Site Mockup Demonstration Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify poor radiological work practices, in and around a mock radiological work site. 2. Inspect a typical contamination containment (glove bag). 3. Develop field assessment notes to support findings (hands-on exercise). Training Aids: Overhead Transparencies (OTs): OT 11.1 (may be supplemented or substituted with updated or site-specific information) Materials needed for this exercise are listed on the following pages. Student Materials: Student’s Guide References: U.S. Department of Energy, DOE-STD-1098-99, Radiological Control, Reaffirmation December 2004. Radiological Work Site Mockup Demonstration Checklist for Module 11 The exercise is a mock-up demonstration that is performed by the instructors to give the participants an opportunity to assess and identify poor radiological work practices. The participants should be instructed to identify and make notes of the poor radiological practices during the demonstration. After the demonstration, ask the participants to: • Identify poor radiological practices • Make recommendations for improvement Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 2 Radiological Work Site Mockup Demonstration Checklist for Module 11 (continued) Description of Mock-up Demonstration Area The area is intended to simulate an actual, posted area where radiological work is performed. White plastic PVC pipes and junctions are used to create a support structure for a heavyweight clear plastic contamination containment (glove bag). The glove bag measures approximately 2 ft wide x 2 ft high x 3 ft long. The glove bag has four glove ports, which allow the installation of four sets of heavy rubber gloves for Radiological Workers #1 and #2. The bag is suspended from the PVC pipes by “bungee” cords. Inside the glove bag is a valve, with two shutoff valves installed on both sides. The valves are installed on PVC pipe, which penetrates the glove bag. The penetrations are taped, to ensure a good seal. Normally a polyethylene (poly) bottle would be connected to the glove bag, to collect any liquid released inside the bag. In this exercise, the poly bottle is intentionally not installed. Radiological rope barrier and standard signs (which intentionally contain improper wording or incorrect color combinations) surround the posted area, which measures about 15 ft x 15 ft square. One exit, with step-off pad, is provided, through which the actors enter the area. Directly beneath the glove bag is a simulated area of high radiation called a “hot spot,” with a standard label filled-in to indicate the dose rate. A yellow lead blanket is provided to cover (shield) the “hot spot.”

The simulated job, which is controlled by a Radiological Work Permit (RWP), is valve removal by Radiological Workers #1 and #2, supported by a Radiological Control (DOE RadCon) Technician, a Quality Inspector, and a DOE Representative. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 3 Radiological Work Site Mockup Demonstration Checklist for Module 11 (continued) Supplies and Equipment for Mock Exercise This item is needed: To: rubber mallet install and dismantle PVC pipe support standard screwdriver tighten glove hose clamps pipe wrench tighten valve connections "hot spot" blank labels enter field information on dose rates "bogus'" radiological signs (RADIATION AREA signs with incorrect wording and/or colors) simulate erroneous posting of radiological area step-off pad simulate radiological area exit razor knife cut glove penetrations into bag yellow tape seal valve-to-glove bag surfaces yellow lead blanket shield "hot spots" yellow poly bottle stage in background, outside radiological area stanchions ("rad rope") simulate radiological area boundaries office trash can serve as a "prop" Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 4 Radiological Work Site Mockup Demonstration Checklist for Module 11 (continued) Setup for Mock Exercise Complete the following tasks prior to the implementation of the mock-up exercise: q Install PVC containment supports, pipe with valve and glove bag. q Place a tear in one finger of a glove attached to a glove bag (large enough to stick a finger through). q Open both isolation (green-handled) valves. q Prepare a "hot spot" label and write "500 mrem/hr" on the label. q Stick label onto mock hot spot and place yellow lead blanket over it. q String yellow and magenta poly rope through stanchions to establish mock radiological area. q Place defective signs (wrong color or wording) onto the rope; for example, “Radiation Zone.” q Place poly bottle in background (5 ft behind containment supports). q Place a yellow plastic waste bag just outside the radiological area. q Prepare RWP for this job showing High Radiation Area, Radiological Buffer Area, thermoluminescent dosimeters (TLDs) and pocket dosimeters, continuous Radiological Control Technician coverage, and pre-job briefing required (instructor reviews with the class members in an earlier session). q Brief players before mock exercise (see Module 11 of Instructor’s Guide). q Dress players (include “maternity padding” for DOE Representative). q Paint simulated cut on right hand of Worker 2. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 5 I. Introduction II. Mockup demonstration Show OT 11.1. State objectives. Refer to previous pages for instructions on setting up for the mockup demonstration. A. Storyboard Ask participants to observe the demonstration and watch for poor radiological work practices. Encourage participants to write down poor work practices in their student’s guide for discussion after demonstration. Player(s) Action Dialogue Workers #1 and #2 Approach posted radiological area. Worker #2 Chews gum and rubs the open cut on his hand. Worker #1 Worker #2 Asks Worker #2: Replies: "Do you have the RWP?" "I thought you had it." Worker #2 Asks Worker #1: "Where is that RadCon Technician?" Worker #1 Replies: "I haven't seen him." Worker #1

Pulls out his pocket dosimeter, raps it on the pipe, and reads it. Asks Worker #2: "Where is your dosimeter?" Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 6 Player(s) Action Dialogue Worker #2 Replies: "I'll just use your reading." Worker #1 Asks Worker #2: "Are you ready to get started?" Worker #2 Replies: Takes a sip from his soft drink and places the cup on the floor. "In a minute..." Workers #1 and #2 Enter radiological area. Engage in small talk: what happened over the weekend, hunting, children. Worker #2 Sticks used chewing gum to pipe support. Notices green isolation valves are open. Calls out to Worker #1: “Hey, these valves are open.” Worker #1 Replies to Worker #2: “So, close them.” Worker #2 Closes only one valve. Comments to Worker #1: “I wish we had been trained to work on this valve. It sure would be easier if we knew what we were doing and had received a pre-job briefing.” Worker #1 Replies: Sticks finger through a hole in a torn glove bag. “No big deal, we can wing it.” Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 7 Player(s) Action Dialogue Worker #1 Works a short minute. Asks Worker 2: “Have you seen the replacement valve?” Worker #2 Points to the valve outside the area and replies: Leaves the area to get the replacement valve. “It’s over there, I’ll get it.” Worker #1 Loiters in area, close to “hot spot.” RadCon Technician Enters the scene and walks around the area, but does not provide much assistance to the workers. Demonstrate his contamination survey instrument (with a pancake probe). DOE Representative and Quality Inspector Enter the area and engage in small talk with Worker #1. Worker #1 Resumes work. DOE Representative Relocates lead blanket, then sits over “hot spot.” Worker #2 Returns with replacement valve and knocks over his soft drink. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 8 Player(s) Action Dialogue Worker #1 Worker #2 Worker #1 Worker #2 Continues working. Shakes hands because they have become wet. Complains: Turns to Worker #2 and replies: Shuts the valve off. “Hey, there is rusty water in this glove bag.” “Well, shut the valve.” Worker #1 Opens the glove bag's zipper and places the replacement valve in the bottom of the glove bag. Quality Inspector Worker #2 Quality Inspector Complains: Reaches into his pocket and offers the Quality Inspector a stick of gum. Replies: Takes the gum. “My mouth is sure dry.” “Would you like a stick of gum.” “Sure, thanks.” Quality Inspector Moves the poly bottle into area and sits on it. Quality Inspector Worker #2 Quality Inspector Reaches into area to “help” Workers #1 and #2 with the job. Asks the Quality Inspector: Replies: “How many of these jobs have you done?” “None, I’m new. Matter of fact, I’m scheduled for GERT next Tuesday.” Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 9 Player(s) Action Dialogue Worker #1 and Worker #2 Worker #1 Remove the defective valve. Look around for the bag to place the valve in. Complains: “Where’s the bag to put this thing in?” RadCon Technician Leaves the controlled area. Returns with the yellow bag and prepares to receive the defective valve from Workers #1 and #2. Worker #2 Fumbles about and misses the yellow bag, dropping the valve on the floor. “OOPS” RadCon Technician

Picks up the valve and puts it into the plastic bag, laying it on the floor. He leaves the area without monitoring Quality Inspector Worker #1 Quality Inspector Drops his pen into the area of the spill. Picks up the pen and hands it to the Quality Inspector. Accepts the pen and does not request it to be monitored or decontaminated. Quality Inspector and DOE Representative Leave the area. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 10 Player(s) Action Dialogue Worker #1 Worker #2 Worker #2 Asks Worker #2: Replies: Places lead blanket over the spill. “What should we do about the spill?” “It’s almost breaktime. RadCon will take care of it later.” Worker #1 Picks up bagged valve and throws it into a nearby trash can. Workers #1 and #2 Leave the area. B. Deliberate errors from mock exercise • Workers #1 and #2 are dressed differently for the same job • Protective clothing worn by Worker #1 is not taped at wrists, ankles • Bearded Worker #1 wearing respirator • Half-face respirator used (type not recommended for radioactive materials) • Wrong (yellow) canisters installed in mask • Worker #2 chews gum • No RWP copy at work site • No RadCon Technician present (RWP calls for continuous coverage) • Worker #1 abuses pocket dosimeter • Worker #2 has no pocket dosimeter • Quality Inspector, RadCon Technician, and DOE Representative have no TLD badges • Worker #2 drinks soft drink in area • Green isolation valves not closed prior to beginning work • No pre-job briefing (based on dialogue) • No training for this job (based on dialogue) • Torn glove (glove bag not inspected for integrity prior to job start) • No corrective action to torn glove Ask participants to identify errors observed during the demonstration. Encourage participants to write down the errors in their student’s guide, then discuss each of the errors. 0 Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 11 • Replacement valve not taken into area • Worker #1 loiters in high radiation area while #2 gets replacement valve • RadCon Technician not actively involved in job assistance • RadCon Technician does not have proper survey instrument for measuring radiation levels • DOE Representative moves lead blanket without replacing it to original position • DOE Representative (pregnant) sits over unshielded hot spot • Worker #2 has open cut on hand • Worker #2 creates liquid spill (knocks over soft drink) • Inappropriate response to spill (covers with lead blanket, no notice to RadCon) • Quality Inspector is given gum in area and chews it • Poly bottle not installed for glove bag • Quality Inspector is in area without having received General Employee Radiological Training (GERT) • No yellow plastic bag in area to receive old valve dropped onto floor • Worker #2 drops old valve onto floor (creating another spill) • RadCon Technician does no monitoring after valve dropped onto floor • Quality Inspector drops pen into contamination and there is no monitoring or decontamination of the pen • Worker #1 puts used, contaminated valve into ordinary trash can NOTE: Participants will detect other errors that are not listed. Summarize lesson. Review objectives. Ask for questions. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 11 – 12 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide

Module 12 – 1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiation-Generating Devices Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify radiation-generating devices. 2. Describe the basic components of an x-ray machine. 3. Identify the most common use of x-rays. 4. Identify the potential hazards associated with x-rays. 5. Identify the most common use of sealed gamma ray sources and the potential hazards. 6. Identify the most common use of beta and neutron sources and the potential hazards. Training Aids: Overhead Transparencies (OTs): OT 12.1 – OT 12.11 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen Student Materials: Student’s Guide Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 12 – 2 References: U.S. Department of Energy, DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004. U.S. Department of Energy, 10 CFR Part 835, Occupational Radiation Protection, Amended June 2007. ANSI N43.2-1989a, Radiation Safety for X-ray Diffraction and Fluorescence Analysis Equipment, 1989. ANSI N43.3-1993, Installations Using Non-Medical X-ray and Sealed Gamma Ray Sources Energies up to 10 MeV, 1993. U.S. Nuclear Regulatory Commission, 10 CFR Part 34, Licenses for Radiography and Radiation Safety Requirements for Radiographic Operations, 1992. Update to DOE G 441.1-1B, Radiation Protection Programs for Use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection. Section 7.0 Radiation Generating Devices. Section 15.0 Sealed Radioactive Source Accountability and Control. U.S. Department of Energy, DOE HDBK-1109-97, Radiological Safety Training for Radiation-Producing (X-Ray) Devices, Reaffirmation January 2007. Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 12 – 3 I. Introduction Update to DOE G 441.1-1B, Radiation Protection Programs for Use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection. Section 7.0 Radiation Generating Devices, includes provisions for exposure to ionizing radiation from DOE activities. Included in the 10 CFR 835 definition of a radiological worker is "operation of radiation producing devices". 10 CFR 835 also specifies requirements for sealed radioactive sources. II. DOE Guidance Update to DOE G 441.1-1B, Radiation Protection Programs for Use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection. Section 7.0 Radiation Generating Devices, provides guidance on DOE's expectations for controlling exposure from radiation generating devices (RGD). The IG includes a definition of a RGD as "a collective term for devices which produce ionizing radiation including, certain sealed radioactive sources, small particle accelerators used for single purpose applications which produce ionizing radiation (e.g., radiography), and electron generating devices that produce x-rays incidentally." For sealed radioactive sources, refer to DOE Update to DOE G 441.1-1B, Radiation Protection Programs for Use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection, Section 15.0 Sealed Radioactive Source Accountability and Control. Article 365 of DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004 provides additional guidance, including the use of ANSI N43.3, ANSI N43.2, and 10 CFR Part 34 for meeting its requirements covering RGDs.

DOE HDBK-1109-97, Radiological Safety Training for Radiation-Producing (X-Ray) Devices, provides guidance on DOE's expectations for radiation safety training for individuals using RGDs. Show OT 12.1 and OT 12.2. State objectives. Review 10 CFR 835 radiological worker definition. Show OT 12.3. Review Update to DOE G 441.1-1B, Radiation Protection Programs for Use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection, Section 7.0 Radiation Generating Devices. Show OT 12.4. Obj. 1 Identify radiation generating devices. Update to DOE G 441.1-1B, Radiation Protection Programs for Use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection, Section 15.0 Sealed Radioactive Source Accountability and Control. Review DOE-STD-1098-99, Radiological Control, Reaffirmed December 2004 (Article 365). Review DOE HDBK-1109-97, Radiological Safety Training for Radiation-Producing (X-Ray) Devices Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 12 – 4 III. X-ray machines A. Components X-ray devices have been in existence for about 100 years. Although there are many different designs of x-ray machines, they all have the same basic components. These include a source of electrons, an electrical potential difference to accelerate the electrons, and an anode, or target for the accelerated electrons to strike. Usually, the source of electrons in an x-ray machine is a thin wire filament from which electrons are emitted when it is heated by a large electrical current. Controlling the current through the filament, then, becomes a way to control the number of electrons available for acceleration. The electrical potential difference between the cathode (filament) and the anode (or target) is the force that accelerates the electrons. The larger the potential difference, the more kinetic energy the electrons will acquire. The potential difference is measured in units of kilovolts (kV). The energy of the electrons is measured in units of kilo electron volts (keV), with one electron volt being the amount of energy required to move one electron through a potential difference of one volt. The accelerated electrons then strike the anode (or target). The target may consist of various materials, depending on the purpose and design of the x-ray tube. X-ray production is most efficient in high atomic number targets, like tungsten. Show OT 12.5. Obj. 2 Describe the basic components of an x-ray machine. The number of electrons moving across the x-ray tube, or the tube current, is adjusted on the x-ray machine control panel with the milliAmpere (mA) control. In some x-ray machines, the mA may be fixed, and not adjustable by the operator. Electrons interact in the target by one of the following mechanisms: • Excitation • Ionization • Bremsstrahlung Radiological Assessor Training DOE-HDBK-1141-2008 Instructor’s Guide Module 12 – 5 When electrons strike and excite target atoms, the kinetic energy of the electrons is deposited in the target as heat. When electrons ionize target atoms, characteristic x-rays will be emitted as electrons from outer shells fill vacancies created by ejected electrons. B. X-ray energy spectrum The energy of the x-ray photons coming out of the x-ray machine is of interest to the users of the machine. The typical energy spectrum from an x-ray machine consists of the characteristi