DOE-HDBK-1141-2001 Module 4-7, Radiological Assessor Training - Instructor's Guide Module 4-7

Radiological Assessor Training DOE-HDBK-1141-2001 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, 1993. U.S. Department of Energy, 10 CFR Part 835, Occupational Radiation Protection, 1993. Radiological Assessor Training DOE-HDBK-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 Instructor�s Guide Module 4�8 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2001 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-1141-2001 Instructor�s Guide Module 5�2 References: U.S. Department of Energy, Order 5480.22, Change 2, Technical Safety Requirements, 1996. U.S. Department of Energy, Order 5480.23, Change 1, Nuclear Safety Analysis Reports, 1993. Federal Register, Department of Energy 10 CFR 830, Nuclear Safety Management, October 10, 2000, Vol.65, No. 196, 60292. U.S. Department of Energy, Order 232.1A, Occurrence Reporting and Processing of Operations Information, 1997. U.S. Department of Energy, Operation Procedure Identifying, Reporting, and Tracking Nuclear Safety Noncompliances, June 1998. Radiological Assessor Training DOE-HDBK-1141-2001 Instructor�s Guide Module 5�3 I. Introduction II. Purpose of DOE Order 5480.22 The intended purpose of DOE Order 5480.22, Technical Safety Requirements, is �to clearly state the requirements to have Technical Safety Requirements (TSRs) prepared for DOE nuclear facilities and to delineate the criteria, content, scope, format, approval process, and reporting requirements of these documents and revisions thereof.� 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 requires contractors to develop and submit TSRs to DOE for approval by April 10, 2003. In the interim, contractors are required to meet existing safety bases, including TSRs. 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-1141-2001 Instructor�s Guide Module 5�4 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-1141-2001 Instructor�s Guide Module 5�5 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-1141-2001 Instructor�s Guide Module 5�6 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-1141-2001 Instructor�s Guide Module 5�7 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 232.1A) Occurrence Reporting and Processing of Operations Information, July, 1997 • Categorization � Emergencies � Unusual Occurrences � Off-Normal Occurrences • 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-1141-2001 Instructor�s Guide Module 5�8 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 and Investigation (EH-10). 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-1141-2001 Instructor�s Guide Module 5�9 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-1141-2001 Instructor�s Guide Module 5�10 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2001 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 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, 2000. U.S. Department of Energy, DOE-STD-1121-99, Internal Dosimetry, 1999. U.S. Department of Energy, DOE-HDBK-1113-98, Radiological Safety Training for Uranium Facilities, 1998. U.S. Department of Energy, DOE-STD-1098-99, Radiological Control, 1999. 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-1141-2001 Instructor�s Guide Module 6�2 I. Introduction The guidance in DOE-STD-1136-2000, Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities, 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 Radiological Assessor Training DOE-HDBK-1141-2001 Instructor�s Guide Module 6�3 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-1141-2001 Instructor�s Guide Module 6�4 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-1141-2001 Instructor�s Guide Module 6�5 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, exposure rate 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-1141-2001 Instructor�s Guide Module 6�6 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-1141-2001 Instructor�s Guide Module 6�7 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, 1998. 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, gloves, and shoe covers. No personal outer clothing should be permitted under coveralls. For inspections or visits, lab coats, gloves, and shoe covers may be permissible. 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-1141-2001 Instructor�s Guide Module 6�8 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-1141-2001 Instructor�s Guide Module 6�9 B. Gamma radiation Gamma radiation is normally not the controlling factor at uranium facilities. However, significant 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-1141-2001 Instructor�s Guide Module 6�10 DOE-STD-1121-99, Internal Dosimetry, 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-1121-99, Internal Dosimetry. 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-1141-2001 Instructor�s Guide Module 6�11 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-1141-2001 Instructor�s Guide Module 6�12 This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2001 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-1141-2001 Instructor�s Guide Module 7�2 Student Materials: Student�s Guide References: U.S. Department of Energy, DOE-STD-1121-99, Internal Dosimetry, 1999. U.S. Department of Energy, DOE-HDBK-1129-99, DOE Handbook Tritium Handling and Safe Storage, 1999. U.S. Department of Energy, DOE-HDBK-1105-96, Radiological Training for Tritium Facilities, 1996. U.S. Department of Energy, DOE-HDBK-1079-94, Primer on Tritium Safe Handling Practices, 1994. U.S. Department of Energy, Radiological Control Programs for Special Tritium Compounds, Draft, DOE-OSCH-0002, 2001. U.S. Department of Energy, Radiological Control Technical Position, RCTP 99 - 02, Acceptable Approach for Developing Air Concentration Values for Controlling Exposures to Tritiated Particulate Aerosols and Organically-Bound Tritium, 1999. 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-1141-2001 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-1141-2001 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-1141-2001 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 99 - 02, Acceptable Approach for Developing Air Concentration Values for Controlling Exposures to Tritiated Particulate Aerosols and Organically-Bound Tritium. DOE has also developed a technical standard, now in draft, Radiological Control Programs for Special Tritium Compounds, DOE-OSCH-0002. Obj. 1 Describe the radiological properties of tritium. Show OT 7.5. Review Radiological Control Technical Position, RCTP 99 - 02, Acceptable Approach for Developing Air Concentration Values for Controlling Exposures to Tritiated Particulate Aerosols and Organically-Bound Tritium v Review Radiological Control Programs for Special Tritium Compounds, DOE-OSCH-0002 Radiological Assessor Training DOE-HDBK-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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-1141-2001 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. Part 2 - Instructor's Guide