6 CCR 1007-1
PART 16: RADIATION SAFETY REQUIREMENTS FOR WIRELINE SERVICE OPERATIONS AND SUBSURFACE TRACER STUDIES RADIATION SAFETY REQUIREMENTS FOR WIRELINE SERVICE OPERATIONS AND SUBSURFACE TRACER STUDIES
16.1 Purpose and Scope.
16.1.1 Authority. [Eff 04/01/2007]
Rules and regulations set forth herein are adopted pursuant to the provisions of Sections 25-1- 108, 25-1.5-101(1)(l), and 25-11-104, CRS. [Eff 04/01/2007]
16.1.2 Basis and Purpose. [Eff 04/01/2007]
A statement of basis and purpose accompanies this part and changes to this part. A copy may be obtained from the Department. [Eff 04/01/2007]
16.1.3 Scope. [Eff 04/01/2007]
The regulations in this part establish radiation safety requirements for using sources of radiation for wireline service operations including mineral-logging, radioactive markers, and subsurface tracer studies. [Eff 04/01/2007]
16.1.4 Applicability. [Eff 04/01/2007]
The regulations in this part apply to all applicants, licensees or registrants who use sources of radiation for wireline service operations including mineral-logging, radioactive markers, or subsurface tracer studies. The requirements of this part are in addition to, and not in substitution for, the requirements of Parts 1, 2, 3, 4, and 10 of these regulations. [Eff 04/01/2007]
16.1.5 Published Material Incorporated by Reference. [Eff 04/01/2007]
Published material incorporated in Part 16 by reference is available in accord with Part 1, Section 1.4. [Eff 04/01/2007]
16.2 Definitions.
As used in this part, these terms have the definitions set forth as follows. [Eff 04/01/2007] “Energy compensation source” (ECS) means a small sealed source, with an activity not exceeding 3.7 MBq (100 microcurie), used within a logging tool, or other tool components, to provide a reference standard to maintain the tool's calibration when in use. [Eff 04/01/2007] “Field station” means a facility where radioactive sources may be stored or used and from which equipment is dispatched to temporary jobsites. [Eff 04/01/2007] “Injection tool” means a device used for controlled subsurface injection of radioactive tracer material. [Eff 04/01/2007] “Irretrievable well-logging source” means any sealed source containing licensed material that is pulled off or not connected to the wireline that suspends the source in the well and for which all reasonable effort at recovery has been expended. [Eff 04/01/2007] “Logging assistant” means any individual who, under the personal supervision of a logging supervisor, handles sealed sources or tracers that are not in logging tools or shipping containers or who performs surveys required by 16.22. [Eff 04/01/2007] “Logging supervisor” means the individual who uses sources of radiation or provides personal supervision of the utilization of sources of radiation at the well site. [Eff 04/01/2007] “Logging tool” means a device used subsurface to perform well-logging. [Eff 04/01/2007] “Mineral logging” means any logging performed for the purpose of mineral exploration other than oil or gas. [Eff 04/01/2007] “Personal supervision” means guidance and instruction by the supervisor who is physically present at the jobsite and watching the performance of the operation in such proximity that contact can be maintained and immediate assistance given as required. [Eff 04/01/2007] “Radioactive marker” means radioactive material placed subsurface or on a structure intended for subsurface use for the purpose of depth determination or direction orientation. [Eff “Safety review” means a periodic review provided by the licensee for its employees on radiation safety aspects of well-logging, with opportunities for employees to ask safety questions. The review shall include, as appropriate, the results of internal inspections, new procedures or equipment, and accidents or errors that have been observed. [Eff 04/01/2007] “Source holder” means a housing or assembly into which a radioactive source is placed for the purpose of facilitating the handling and use of the source in well-logging operations. [Eff “Subsurface tracer study” means the release of a substance tagged with radioactive material for the purpose of tracing the movement or position of the tagged substance in the well-bore or adjacent formation. [Eff 04/01/2007] “Temporary jobsite” means a location where radioactive materials are present for the purpose of performing wireline service operations or subsurface tracer studies. [Eff 04/01/2007] “Tritium neutron generator target source” means a tritium source used within a neutron generator tube to produce neutrons for use in well-logging applications. [Eff 04/01/2007] “Uranium sinker bar” means a weight containing depleted uranium used to pull a logging tool down toward the bottom of a well. [Eff 04/01/2007] “Well-bore” means a drilled hole in which wireline service operations and subsurface tracer studies are performed. [Eff 04/01/2007] “Well-logging” means all operations involving the lowering and raising of measuring devices or tools which may contain sources of radiation into well-bores or cavities for the purpose of obtaining information about the well or adjacent formations. [Eff 04/01/2007] “Wireline” means a cable containing one or more electrical conductors which is used to lower and raise logging tools in the well-bore. [Eff 04/01/2007] “Wireline service operation” means any evaluation or mechanical service which is performed in the well-bore using devices on a wireline. [Eff 04/01/2007] PROHIBITION
16.4 Prohibition.
No licensee shall perform wireline service operations with a sealed source(s) unless, prior to commencement of the operation, the licensee has a written agreement with the well-operator, well-owner, drilling contractor, or land owner that: [Eff 04/01/2007] 16.4.1 In the event a sealed source is lodged downhole, a reasonable effort at recovery will be made; and [Eff 04/01/2007] 16.4.2 In the event a decision is made to abandon the sealed source downhole, the requirements of 16.25 and of any other State agency having applicable regulations shall be met. [Eff EQUIPMENT CONTROL
16.5 Limits on Levels of Radiation.
Sources of radiation shall be used, stored, and transported in such a manner that the transportation requirements of Part 17 and the dose limitation requirements of Part 4 of these regulations are met. [Eff 04/01/2007]
16.6 Storage Precautions.
16.6.1 Each source of radiation, except an accelerator, shall be provided with a storage or transport container. The container shall be provided with a lock, or tamper seal for calibration sources, to prevent unauthorized removal of, or exposure to, the source of radiation. [Eff 04/01/2007] 16.6.2 Sources of radiation shall be stored in a manner which will minimize danger from explosion or fire. [Eff 04/01/2007]
16.7 Transport Precautions.
Transport containers shall be physically secured to the transporting vehicle to prevent accidental loss, tampering, or unauthorized removal. [Eff 04/01/2007]
16.8 Radiation Survey Instruments.
16.8.1 The licensee or registrant shall keep a calibrated and operable radiation survey instrument capable of detecting beta and gamma radiation at each field station and temporary jobsite to make the radiation surveys required by this part and by Part 4 of these regulations. To satisfy this requirement, the radiation survey instrument must be capable of measuring 0.001 mSv (0.1 mrem) per hour through at least 0.5 mSv (50 mrem) per hour. [Eff 04/01/2007]
16.8.2 Each radiation survey instrument shall be calibrated: [Eff 04/01/2007]
16.8.2.1 At intervals not to exceed 6 months and after each instrument servicing; [Eff 04/01/2007] [Eff 04/01/2007] 16.8.2.2 For linear scale instruments, at two points located approximately 1/3 and 2/3 of full- scale on each scale; for logarithmic scale instruments, at midrange of each decade, and at two points of at least one decade; and for digital instruments, at appropriate points; and [Eff 04/01/2007] [Eff 04/01/2007] 16.8.2.3 So that accuracy within 20 percent of the true radiation level can be demonstrated on each scale. [Eff 04/01/2007] [Eff 04/01/2007] 16.8.3 Calibration records shall be maintained for a period of 2 years for inspection by the Department. [Eff 04/01/2007]
16.9 Leak Testing of Sealed Sources.
16.9.1 Requirements. [Eff 04/01/2007]
Each licensee using sealed sources of radioactive material shall have the sources tested for leakage. Records of leak test results shall be kept in units of becquerel (Bq) (or microcurie, µCi) and maintained for inspection by the Department for 6 months after the next required leak test is performed or until transfer or disposal of the sealed source. [Eff 04/01/2007]
16.9.2 Method of Testing. [Eff 04/01/2007]
16.9.2.1 Tests for leakage shall be performed using a leak test kit or method approved by the Department, the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State. [Eff 04/01/2007] [Eff 04/01/2007] 16.9.2.2 The test sample shall be taken from the nearest accessible point to the surface of the sealed source where contamination is likely to accumulate. [Eff 04/01/2007] [Eff 16.9.2.3 The test sample shall be analyzed for radioactive contamination. [Eff 04/01/2007] [Eff 16.9.2.4 The analysis shall be capable of detecting the presence of 185 Bq (0.005 microcurie) of radioactive material on the test sample and must be performed by a person specifically approved by the Department, the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State to perform the analysis. [Eff 04/01/2007] [Eff 04/01/2007]
16.9.3 Interval of Testing. [Eff 04/01/2007]
16.9.3.1 Each sealed source of radioactive material (except an energy compensation source (ECS)) shall be tested at intervals not to exceed 6 months. In the absence of a certificate from a transferor indicating that a test has been made within 6 months prior to the transfer, the sealed source shall not be used until tested. [Eff 04/01/2007] [Eff 16.9.3.2 Each ECS that is not exempt from testing in accordance with 16.9.5 must be tested at intervals not to exceed 3 years. In the absence of a certificate from a transferor indicating that a test has been made within the 3 years prior to the transfer, the ECS shall not be used until tested. [Eff 04/01/2007] [Eff 04/01/2007]
16.9.4 Leaking or Contaminated Sources. [Eff 04/01/2007]
If, for any reason, it is suspected that a sealed source may be leaking, it shall be removed from service immediately and tested for leakage as soon as practical. [Eff 04/01/2007] 16.9.4.1 If the test reveals the presence of 185 Bq (0.005 microcurie) or more of removable radioactive material, the licensee shall immediately withdraw the source from use and shall cause it to be decontaminated and repaired, or disposed of, by a licensee authorized by the Department, U.S. Nuclear Regulatory Commission, Agreement State, or a Licensing State to perform these functions. [Eff 04/01/2007] [Eff 04/01/2007] 16.9.4.2 The licensee shall check the equipment associated with the leaking source for radioactive contamination and, if contaminated, have it decontaminated or disposed of by a licensee authorized by the Department, U.S. Nuclear Regulatory Commission, Agreement State, or a Licensing State to perform these functions. [Eff 04/01/2007] [Eff 16.9.4.3 A report describing the equipment involved, the test results, and the corrective action taken shall be filed with the Department within 5 days of receiving the test results. [Eff 04/01/2007] [Eff 04/01/2007]
16.9.5 Exemptions. [Eff 04/01/2007]
The following sources are exempted from the periodic leak test requirements of 16.9.1 through 16.9.4: [Eff 04/01/2007]
16.9.5.1 Hydrogen-3 (tritium) sources; [Eff 04/01/2007] [Eff 04/01/2007]
16.9.5.2 Sources of radioactive material with a half-life of 30 days or less; [Eff 04/01/2007] [Eff 16.9.5.3 Sealed sources of radioactive material in gaseous form; [Eff 04/01/2007] [Eff 16.9.5.4 Sources of beta- or gamma-emitting radioactive material with an activity of 3.7 MBq (100 microcurie) or less; and [Eff 04/01/2007] [Eff 04/01/2007] 16.9.5.5 Sources of alpha-emitting radioactive material with an activity of 0.37 MBq (10 microcurie) or less. [Eff 04/01/2007] [Eff 04/01/2007]
16.10 Quarterly Inventory.
16.10.1 Each licensee or registrant shall conduct a quarterly physical inventory to account for all sources of radiation. [Eff 04/01/2007] 16.10.2 Records of inventories shall be maintained for 2 years from the date of the inventory for inspection by the Department and shall include the quantities and kinds of sources of radiation, the location where sources of radiation are assigned, the date of the inventory, and the name of the individual conducting the inventory. [Eff 04/01/2007]
16.11 Utilization Records.
16.11.1 Each licensee or registrant shall maintain current records, which shall be kept available for inspection by the Department for 2 years from the date of the recorded event. [Eff 04/01/2007] 16.11.2 The records shall show the following information for each source of radiation: [Eff 04/01/2007] 16.11.2.1 Make, model number, and a serial number or a description of each source of radiation used; [Eff 04/01/2007] [Eff 04/01/2007] 16.11.2.2 The identity of the well-logging supervisor or field unit to whom assigned; and [Eff 04/01/2007] [Eff 04/01/2007] 16.11.2.3 Locations where used and dates of use. [Eff 04/01/2007] [Eff 04/01/2007] 16.11.3 In the case of tracer materials and radioactive markers, the utilization record shall indicate the radionuclide and activity used in a particular well. [Eff 04/01/2007] 16.12 Design, Performance, and Certification Criteria for Sealed Sources Used in Downhole Operations.
16.12.1 Each sealed source, except energy compensation sources (ECS) and those containing radioactive material in gaseous form, used in downhole operations and manufactured after December 30, 1986, shall be certified by the manufacturer, or other testing organization acceptable to the Department, to meet the following minimum criteria: [Eff 04/01/2007] 16.12.1.1 Be of doubly encapsulated construction; [Eff 04/01/2007] [Eff 04/01/2007] 16.12.1.2 Contain radioactive material whose chemical and physical forms are as insoluble and non-dispersible as practical; and [Eff 04/01/2007] [Eff 04/01/2007] 16.12.1.3 Satisfies the requirements of 16.12.3.1, 16.12.3.2, or 16.12.3.3, as appropriate. [Eff 04/01/2007] [Eff 04/01/2007] 16.12.2 For sealed sources, except those containing radioactive material in gaseous form, acquired after December 30, 1986, in the absence of a certificate from a transferor certifying that an individual sealed source meets the requirements of 16.12.1, the sealed source shall not be put into use until such determinations and testing have been performed. [Eff 04/01/2007] 16.12.3 Each sealed source, except energy compensation sources (ECS) and those containing radioactive material in gaseous form, used in downhole operations after December 30, 1986, shall be certified by the manufacturer, or other testing organization acceptable to the Department, as meeting the sealed source performance requirements for oil well-logging: [Eff 04/01/2007] 16.12.3.1 For a sealed source manufactured on or before July 14, 1989, a licensee may use the sealed source, for use in well logging applications, if it meets the requirements of United States Of America Standards Institute (USASI) N5.10-1968, “Classification of Sealed Radioactive Sources” (1968), or the requirements in 16.12.3.2 or 16.12.3.3. [Eff 04/01/2007] [Eff 04/01/2007] 16.12.3.2 For a sealed source manufactured after July 14, 1989, a licensee may use the sealed source, for use in well logging applications, if it meets the oil well logging requirements of American National Standards Institute / Health Physics Society (ANSI/HPS) N43.6-1997, “Sealed Radioactive Sources Classification” (November 1997). [Eff 04/01/2007] [Eff 16.12.3.3 For a sealed source manufactured after July 14, 1989, a licensee may use the sealed source, for use in well logging applications, if the sealed source's prototype has been tested and found to maintain its integrity after each of the following tests: [Eff 04/01/2007] [Eff 04/01/2007]
16.12.4 Certification documents shall be maintained for inspection by the Department for a period of 2 years after source disposal. If the source is abandoned downhole, the certification documents shall be maintained until the Department authorizes disposition. [Eff 04/01/2007] 16.12.5 Use of an energy compensation source (ECS) is subject to this part, except that if the ECS is contained within a logging tool, or other tool components, and contains quantities of licensed material not exceeding 3.7 MBq (100 microcurie), the ECS is only subject to the requirements: [Eff 04/01/2007] 16.12.5.1 Of 16.9, 16.10 and 16.11 for well logging applications with a surface casing for protecting fresh water aquifers; or [Eff 04/01/2007] [Eff 04/01/2007] 16.12.5.2 Of 16.9, 16.10, 16.11, 16.12 and 16.25 for well logging applications without a surface casing for protecting fresh water aquifers. [Eff 04/01/2007] [Eff 04/01/2007] 16.12.6 Use of a tritium neutron generation target source is subject to this part, except the requirements: [Eff 04/01/2007] 16.12.6.1 Of 16.12 and 16.25 do not apply for use of a tritium neutron generation target source containing quantities not exceeding 1,110 MBq (30 curie) and in a well with a surface casing for protecting fresh water aquifers; and [Eff 04/01/2007] [Eff 04/01/2007] 16.12.6.2 Of 16.12 do not apply for use of a tritium neutron generation target source containing quantities exceeding 1,110 MBq (30 curie) or in a well without a surface casing for protecting fresh water aquifers. [Eff 04/01/2007] [Eff 04/01/2007]
16.13 Labeling.
16.13.1 Each source, source holder, or logging tool containing radioactive material shall bear a durable, legible, and clearly visible marking or label, which has, as a minimum, the standard radiation caution symbol, without the conventional color requirement, and the following wording: [Eff DANGER* – RADIOACTIVE [Eff 04/01/2007] *or “CAUTION” [Eff 04/01/2007] This labeling shall be on the smallest component transported as a separate piece of equipment. [Eff 04/01/2007] 16.13.2 Each transport container shall have permanently attached to it a durable, legible, and clearly visible label which has, as a minimum, the standard radiation caution symbol and the following wording: [Eff 04/01/2007] DANGER*- RADIOACTIVE [Eff 04/01/2007] NOTIFY CIVIL AUTHORITIES [OR NAME OF COMPANY] [Eff 04/01/2007] *or “CAUTION” [Eff 04/01/2007] 16.13.3 The licensee may use a uranium sinker bar in well logging applications only if it is legibly impressed with the following wording: [Eff 04/01/2007] CAUTION--RADIOACTIVE--DEPLETED URANIUM [Eff 04/01/2007] and [Eff 04/01/2007] NOTIFY CIVIL AUTHORITIES [OR COMPANY NAME] IF FOUND [Eff 04/01/2007]
16.14 Inspection and Maintenance.
16.14.1 Each licensee or registrant shall conduct, at intervals not to exceed 6 months, a program of inspection and maintenance of source holders, logging tools, source handling tools, storage containers, transport containers, and injection tools to assure proper labeling and physical condition. [Eff 04/01/2007] 16.14.2 If any inspection conducted pursuant to 16.14.1 reveals damage to labeling or components critical to radiation safety, the device shall be removed from service until repairs have been made. [Eff 04/01/2007] 16.14.3 If a sealed source is stuck in the source holder, the licensee shall not perform any operation, such as drilling, cutting, or chiseling, on the source holder unless the licensee is specifically approved by the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State to perform this operation. [Eff 04/01/2007] 16.14.4 The repair, opening, or modification of any sealed source shall be performed only by persons specifically authorized to do so by the Department, the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State. [Eff 04/01/2007] 16.14.5 Records of inspection and maintenance shall be maintained for a period of 2 years for inspection by the Department. [Eff 04/01/2007] REQUIREMENTS FOR PERSONNEL SAFETY
16.15 Training Requirements.
16.15.1 No licensee or registrant shall permit any individual to act as a logging supervisor as defined in this part until such individual has: [Eff 04/01/2007] 16.15.1.1 Received, in a course recognized by the Department, the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State, instruction in the subjects outlined in Appendix 16A and demonstrated an understanding thereof; [Eff 04/01/2007] [Eff 04/01/2007] 16.15.1.2 Read and received instruction in the regulations contained in this part and the applicable sections of Parts 1, 4, and 10 of these regulations or their equivalent, conditions of appropriate license or certificate of registration, and the licensee's or registrant's operating and emergency procedures, and demonstrated an understanding thereof; and [Eff 04/01/2007] [Eff 04/01/2007] 16.15.1.3 Demonstrated competence to use sources of radiation, related handling tools, and radiation survey instruments which will be used on the job. [Eff 04/01/2007] [Eff 16.15.2 No licensee or registrant shall permit any individual to assist in the handling of sources of radiation until such individual has: [Eff 04/01/2007] 16.15.2.1 Read or received instruction in the licensee's or registrant's operating and emergency procedures and demonstrated an understanding thereof; and [Eff 04/01/2007] [Eff 16.15.2.2 Demonstrated competence to use, under the personal supervision of the logging supervisor, the sources of radiation, related handling tools, and radiation survey instruments which will be used on the job. [Eff 04/01/2007] [Eff 04/01/2007] 16.15.3 The licensee shall provide safety reviews for logging supervisors and logging assistants at least once during each calendar year. [Eff 04/01/2007] 16.15.4 The licensee or registrant shall maintain employee training records for inspection by the Department for 2 years following termination of the individual's employment. [Eff 04/01/2007]
16.16 Operating and Emergency Procedures.
The licensee's or registrant's operating and emergency procedures shall include instructions in at least the following: [Eff 04/01/2007] 16.16.1 Handling and use of sources of radiation to be employed so that no individual is likely to be exposed to radiation doses in excess of the standards established in Part 4 of these regulations; [Eff 04/01/2007] 16.16.2 Methods and occasions for conducting radiation surveys; [Eff 04/01/2007] 16.16.3 Methods and occasions for locking and securing sources of radiation; [Eff 04/01/2007] 16.16.4 Personnel monitoring and the use of personnel monitoring equipment; [Eff 04/01/2007] 16.16.5 Transportation to temporary jobsites and field stations, including the packaging and placing of sources of radiation in vehicles, placarding of vehicles, and securing sources of radiation during transportation; [Eff 04/01/2007] 16.16.6 Minimizing exposure of individuals in the event of an accident; [Eff 04/01/2007] 16.16.7 Procedure for notifying proper personnel in the event of an accident; [Eff 04/01/2007]
16.16.8 Maintenance of records; [Eff 04/01/2007]
16.16.9 Use, inspection and maintenance of source holders, logging tools, source handling tools, storage containers, transport containers, and injection tools; [Eff 04/01/2007] 16.16.10 Procedure to be followed in the event a sealed source is lodged downhole; [Eff 04/01/2007] 16.16.11 Procedures to be used for picking up, receiving, and opening packages containing radioactive material; [Eff 04/01/2007] 16.16.12 For the use of tracers, decontamination of the environment, equipment, and personnel; [Eff 16.16.13 Maintenance of records generated by logging personnel at temporary jobsites; [Eff 16.16.14 Notifying proper persons in the event of an accident; and [Eff 04/01/2007] 16.16.15 Actions to be taken if a sealed source is ruptured, including actions to prevent the spread of contamination and minimize inhalation and ingestion of radioactive material and actions to obtain suitable radiation survey instruments as required by 16.8. [Eff 04/01/2007]
16.17 Personnel Monitoring.
16.17.1 No licensee or registrant shall permit any individual to act as a logging supervisor or to assist in the handling of sources of radiation unless each such individual wears, at all times during the handling of such sources, a personnel dosimeter that is processed and evaluated by an accredited National Voluntary Laboratory Accreditation Program (NVLAP) processor. [Eff 16.7.1.1 Each personnel dosimeter shall be assigned to and worn by only one individual. [Eff 04/01/2007] [Eff 04/01/2007] 16.7.1.2 Film badges must be replaced at least monthly. Other types of personnel dosimeter must be replaced at least quarterly. [Eff 04/01/2007] [Eff 04/01/2007] 16.7.1.3 After replacement, each personnel dosimeter must be promptly processed. [Eff 04/01/2007] [Eff 04/01/2007] 16.17.2 Personnel monitoring records shall be maintained for inspection until the Department authorizes disposition. [Eff 04/01/2007] PRECAUTIONARY PROCEDURES IN LOGGING AND SUBSURFACE TRACER OPERATIONS
16.18 Security.
During each logging or tracer application, the logging supervisor or other designated employee shall maintain direct surveillance of the operation to protect against unauthorized or unnecessary entry into a restricted area, as defined in Part 1 of these regulations. [Eff 04/01/2007]
16.19 Handling Tools.
The licensee shall provide and require the use of tools that will assure remote handling of sealed sources other than low-activity calibration sources. [Eff 04/01/2007]
16.20 Subsurface Tracer Studies.
16.20.1 Protective gloves and other appropriate protective clothing and equipment shall be used by all personnel handling radioactive tracer material. Precautions shall be taken to avoid ingestion or inhalation of radioactive material. [Eff 04/01/2007] 16.20.2 No licensee shall cause the injection of radioactive material into potable aquifers without prior written authorization from the Department and any other appropriate State agency. [Eff
16.21 Particle Accelerators.
No licensee or registrant shall permit aboveground testing of particle accelerators, designed for use in well-logging, which results in the production of radiation, except in areas or facilities controlled or shielded so that the requirements of 4.6 and 4.14 of these regulations, as applicable, are met. [Eff 04/01/2007] RADIATION SURVEYS AND RECORDS
16.22 Radiation Surveys.
16.22.1 Radiation surveys or calculations shall be made and recorded for each area where radioactive materials are stored. [Eff 04/01/2007] 16.22.2 Radiation surveys or calculations shall be made and recorded for the radiation levels in occupied positions and on the exterior of each vehicle used to transport radioactive material. Such surveys and calculations shall include each source of radiation or combination of sources to be transported in the vehicle. [Eff 04/01/2007] 16.22.3 If the sealed source assembly is removed from the logging tool before departing the jobsite, the logging tool detector shall be energized, or a survey meter used, to assure that the logging tool is free of contamination. [Eff 04/01/2007] 16.22.4 Radiation surveys shall be made and recorded at the jobsite or wellhead for each tracer operation, except those using hydrogen-3, carbon-14, and sulfur-35. These surveys shall include measurements of radiation levels before and after the operation. [Eff 04/01/2007] 16.22.5 Records required pursuant to 16.22.1 through 16.22.4 shall include the dates, the identification of individual(s) making the survey, the identification of survey instrument(s) used, and an exact description of the location of the survey. Records of these surveys shall be maintained for inspection by the Department for 2 years after completion of the survey. [Eff 04/01/2007]
16.23 Documents and Records Required at Field Stations.
Each licensee or registrant shall maintain, for inspection by the Department, the following documents and records for the specific devices and sources used at the field station: [Eff 16.23.1 Appropriate license, certificate of registration, or equivalent document(s); [Eff 04/01/2007]
16.23.2 Operating and emergency procedures; [Eff 04/01/2007]
16.23.3 Applicable regulations; [Eff 04/01/2007]
16.23.4 Records of the latest survey instrument calibrations pursuant to 16.8; [Eff 04/01/2007] 16.23.5 Records of the latest leak test results pursuant to 16.9; [Eff 04/01/2007] 16.23.6 Records of quarterly inventories required pursuant to 16.10; [Eff 04/01/2007]
16.23.7 Utilization records required pursuant to 16.11; [Eff 04/01/2007]
16.23.8 Records of inspection and maintenance required pursuant to 16.14; [Eff 04/01/2007]
16.23.9 Survey records required pursuant to 16.22; and [Eff 04/01/2007]
16.23.10 Training records required pursuant to 16.15. [Eff 04/01/2007]
16.24 Documents and Records Required at Temporary Jobsites.
Each licensee or registrant conducting operations at a temporary jobsite shall have the following documents and records available at that site for inspection by the Department: [Eff 04/01/2007]
16.24.1 Operating and emergency procedures; [Eff 04/01/2007]
16.24.2 Survey records required pursuant to 16.22 for the period of operation at the site; [Eff 16.24.3 Evidence of current calibration for the radiation survey instruments in use at the site; [Eff 16.24.4 When operating in the State under reciprocity, a copy of the appropriate license, certificate of registration, or equivalent document(s); and [Eff 04/01/2007] 16.24.5 Shipping papers for the transportation of radioactive material. [Eff 04/01/2007] NOTIFICATION
16.25 Notification of Incidents, Abandonment, and Lost Sources.
16.25.1 Notification of incidents and sources lost in other than downhole logging operations shall be made in accordance with appropriate provisions of 4.52 of these regulations. [Eff 04/01/2007] 16.25.2 Whenever a sealed source or device containing radioactive material is lodged downhole, the licensee shall: [Eff 04/01/2007] 16.25.2.1 Monitor at the surface for the presence of radioactive contamination with a radiation survey instrument or logging tool during logging tool recovery operations; and [Eff 04/01/2007] [Eff 04/01/2007] 16.25.2.2 Notify the Department immediately by telephone and subsequently within 30 days by confirmatory letter if the licensee knows or has reason to believe that a sealed source has been ruptured. This letter shall identify the well or other location, describe the magnitude and extent of the escape of radioactive material, assess the consequences of the rupture, and explain efforts being planned or taken to mitigate these consequences. [Eff 04/01/2007] [Eff 04/01/2007] 16.25.3 When it becomes apparent that efforts to recover the radioactive source will not be successful, the licensee shall: [Eff 04/01/2007] 16.25.3.1 Advise the well operator of the regulations of the Department regarding abandonment and an appropriate method of abandonment, which shall include: [Eff 04/01/2007] [Eff
16.25.3.2 Notify the Department by telephone, giving the circumstances that resulted in the inability to retrieve the source; and [Eff 04/01/2007] [Eff 04/01/2007]
16.25.3.3 File a written report with the Department within 30 days of the abandonment. The licensee shall send a copy of the report to the appropriate State agency that issued permits or otherwise approved of the drilling operation. The report shall contain the following information: [Eff 04/01/2007] [Eff 04/01/2007]
16.25.4 Whenever a sealed source containing radioactive material is abandoned downhole, the licensee shall provide a means to prevent inadvertent intrusion on the source, unless the source is not accessible to any subsequent drilling operations, and shall provide a permanent plaque 1 for posting the well or well-bore. This plaque shall: [Eff 04/01/2007] 1 An example of a suggested plaque is shown in Appendix 16B. [Eff 04/01/2007] 16.25.4.1 Be constructed of long-lasting material, such as stainless steel, brass, bronze, or monel; [Eff 04/01/2007] [Eff 04/01/2007] 16.25.4.2 Be mounted at the surface of the well, unless the mounting of the plaque is not practical; [Eff 04/01/2007] [Eff 04/01/2007] 16.25.4.3 Be at least 17 cm (7 inches) square and 3 mm (1/8 th inch) thick; and [Eff 04/01/2007] [Eff 04/01/2007] 16.25.4.4 Contain the following information engraved on its face: [Eff 04/01/2007] [Eff
16.25.5 The licensee shall immediately notify the Department by telephone and subsequently by confirming letter if the licensee knows or has reason to believe that radioactive material has been lost in or to an underground potable aquifer. Such notice shall designate the well location and shall describe the magnitude and extent of loss of radioactive material, assess the consequences of such loss, and explain efforts planned or being taken to mitigate these consequences. [Eff PART 16, APPENDIX 16A:
SUBJECTS TO BE INCLUDED IN TRAINING COURSES FOR LOGGING SUPERVISORS 16A.1 Fundamentals of Radiation Safety [Eff 04/01/2007] 16A.1.1 Characteristics of radiation [Eff 04/01/2007] 16A.1.2 Units of radiation dose and quantity of radioactivity [Eff 04/01/2007] 16A.1.3 Significance of radiation dose [Eff 04/01/2007]
EXAMPLE OF PLAQUE FOR IDENTIFYING WELLS CONTAINING SEALED SOURCES CONTAINING RADIOACTIVE MATERIAL ABANDONED DOWNHOLE The size of the plaque should be convenient for use on active or inactive wells, for example, a 7-inch square. Letter size of the word “CAUTION” should be approximately twice the letter size of the rest of the information, for example, 1/2-inch and 1/4-inch letter size, respectively. [Eff 04/01/2007] PART 17 : TRANSPORTATION OF RADIOACTIVE MATERIAL TRANSPORTATION OF RADIOACTIVE MATERIAL RH 17.1 Purpose and Scope.
The regulations in this part establish requirements for packaging, preparation for shipment, and transportation of radioactive material and apply to any person who transports radioactive material or delivers radioactive material to a carrier for transport. RH 17.2 Definitions.
As used in this part, the following definitions apply:
“Carrier” means a person engaged in the transportation of passengers or property by land or water as a common, contract, or private carrier, or by civil aircraft. “Closed transport vehicle” means a transport vehicle equipped with a securely attached exterior enclosure that during normal transportation restricts the access of unauthorized persons to the cargo space containing the radioactive material. The enclosure may be either temporary or permanent but shall limit access from top, sides, and ends. In the case of packaged materials, it may be of the “see-through” type.
“Exclusive use” means the sole use by a single consignor of a conveyance for which all initial, intermediate, and final loading and unloading are carried out in accordance with the direction of the consignor or consignee. The consignor and the carrier must ensure that any loading or unloading is performed by personnel having radiological training and resources appropriate for safe handling of the consignment. The consignor must issue specific instructions, in writing, for maintenance of exclusive use shipment controls, and include them with the shipping paper information provided to the carrier by the consignor.
“Fissile material” means plutonium-238, plutonium-239, plutonium-241, uranium-233, and uranium-235, or any combination of these radionuclides. Unirradiated natural uranium and depleted uranium, and natural uranium or depleted uranium that has been irradiated in thermal reactors only, are not included in this definition. 1 1 Department jurisdiction extends only to “special nuclear material in quantities not sufficient to form a critical mass” as defined in Part 1 of these regulations.
“Fissile material package” means a fissile material packaging together with its fissile material contents.
“Low specific activity (LSA) material” means radioactive material that satisfies the descriptions and limits set forth below. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. LSA material must be in one of three groups:
(1) LSA-I .
(2) LSA-II .
(3) LSA-III . Solids (e.g., consolidated wastes, activated materials) in which:
“Regulations of the U.S. Department of Transportation” means the regulations in 49 CFR Parts 100–189 and Parts 390–397.
“Regulations of the U.S. Nuclear Regulatory Commission” means the regulations in 10 CFR 71 for purposes of this Part.
“Specific activity” of a radionuclide means the radioactivity of a radionuclide per unit mass of that nuclide. The specific activity of a material in which the radionuclide is essentially uniformly distributed is the radioactivity per unit mass of the material. “State” means a State of the United States, the District of Columbia, the Commonwealth of Puerto Rico, the Virgin Islands, Guam, American Samoa, and the Commonwealth of the Northern Mariana Islands.
“Surface contaminated object” (SCO) means a solid object that is not itself classed as radioactive material, but which has radioactive material distributed on any of its surfaces. SCO must be in one of two groups with surface activity not exceeding the following limits:
1. SCO-I: a solid object on which:
2. SCO-II: a solid object on which the limits for SCO-I are exceeded and on which:
“Transport index” means the dimensionless number, rounded up the next tenth, placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation. The transport index is the number expressing the maximum radiation level at 1 meter (3.3 feet) from the external surface of the package in millisievert (mSv) per hour multiplied by 100 (equivalent to the maximum radiation level in millirem per hour at 1 meter). “Type A quantity” means a quantity of radioactive material, the aggregate radioactivity of which does not exceed A for special form radioactive material or A for normal form radioactive 1 2 material, where A and A are given in Appendix A of this Part 17 or may be determined by 1 2 procedures described in Appendix A of this Part 17.
“Type A package” means a packaging that, together with its radioactive contents limited to A or A as appropriate, meets the requirements of 49 CFR 173.410 and 173.412 and is designed to retain the integrity of containment and shielding under normal conditions of transport as demonstrated by the tests set forth in 173.465 or 173.466, as appropriate. “Type B package” means a Type B packaging together with its radioactive contents. 2 2 A Type B package design is designated as B(U) or B(M). B(U) refers to the need for unilateral approval of international shipments; B(M) refers to the need for multilateral approval. There is no distinction made in how packages with these designations may be used in domestic transportation. To determine their distinction for international transportation, refer to 49 CFR Part 173. A Type B package approved prior to September 6, 1983 was designated only as Type B. Limitations on its use are specified in RH 17.8. “Type B packaging” means a packaging designed to retain the integrity of containment and shielding when subjected to the normal conditions of transport and hypothetical accident test conditions set forth 10 CFR Part 71.
“Type B quantity” means a quantity of radioactive material greater than a Type A quantity. General Regulatory Provisions RH 17.3 Requirement for License.
No person shall transport radioactive material or deliver radioactive material to a carrier for transport except as authorized in a general or specific license issued by the Department or as exempted in RH 17.4.
RH 17.4 Exemptions.
17.4.1 Common and contract carriers, freight forwarders, and warehouse workers which are subject to the requirements of the U.S. Department of Transportation in 49 CFR 170 through 189 or the U.S. Postal Service in the Postal Service Manual (Domestic Mail Manual), are exempt from the requirements of this part to the extent that they transport or store radioactive material in the regular course of their carriage for others or storage incident thereto. Common and contract carriers who are not subject to the requirements of the U.S. Department of Transportation or U.S. Postal Service are subject to RH 17.3 and other applicable requirements of these regulations.
17.4.2 Any licensee is exempt from the requirements of this part to the extent that the licensee delivers to a carrier for transport a package containing radioactive material having a specific activity not greater than 70 Bq/g (0.002 microcurie per gram).
RH 17.5 Transportation of Licensed Material.
17.5.1 Each licensee who transports licensed material outside the site of usage, as specified in the Department license, or where transport is on public highways, or who delivers licensed material to a carrier for transport, shall:
17.5.1.1 Comply with the applicable requirements, appropriate to the mode of transport, of the regulations of the U.S. Department of Transportation, particularly the regulations of U.S. Department of transportation in the following areas:
17.5.1.2 The licensee shall also comply with applicable U.S. Department of Transportation regulations pertaining to the following modes of transportation:
17.5.1.3 Assure that any special instructions needed to safely open the package are sent to or have been made available to the consignee.
17.5.2 If, for any reason, the regulations of the U.S. Department of Transportation are not applicable to a shipment of licensed material, the licensee shall conform to the standards and requirements of 49 CFR Parts 170 through 189 appropriate to the mode of transport to the same extent as if the shipment was subject to the regulations.
General Licenses RH 17.6 General Licenses for Carriers.
17.6.1 A general license is hereby issued to any common or contract carrier not exempt under RH 17.4 to receive, possess, transport, and store radioactive material in the regular course of their carriage for others or storage incident thereto, provided the transportation and storage is in accordance with the applicable requirements, appropriate to the mode of transport, of the U.S. Department of Transportation insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting. 3 17.6.2 A general license is hereby issued to any private carrier to transport radioactive material, provided the transportation is in accordance with the applicable requirements, appropriate to the mode of transport, of the U.S. Department of Transportation insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting. 3 3 Notification of an incident shall be filed with, or made to, the Department as prescribed in 49 CFR, regardless of and in addition to the notification made to the U.S. Department of Transportation or other agencies.
17.6.3 Persons who transport radioactive material pursuant to the general licenses in RH 17.6.1 or 17.6.2 are exempt from the requirements of Parts 4 and 10 of these regulations to the extent that they transport radioactive material.
RH 17.7 General License: Nuclear Regulatory Commission-Approved Packages.
17.7.1 A general license is hereby issued to any licensee of the Department to transport, or to deliver to a carrier for transport, licensed material in a package for which a license, certificate of compliance, or other approval has been issued by the Nuclear Regulatory Commission.
17.7.2 This general license applies only to a licensee who:
17.7.2.1 Has a copy of the specific license, certificate of compliance, or other approval by the Nuclear Regulatory Commission of the package and has the drawings and other documents referenced in the approval relating to the use and maintenance of the packaging and to the action to be taken prior to shipment;
17.7.2.2 Complies with the terms and conditions of the license, certificate, or other approval by the Nuclear Regulatory Commission, as applicable, and the applicable requirements of this Part 17;
17.7.2.3 Prior to the licensee's first use of the package, has registered with the Nuclear Regulatory Commission; and
17.7.2.4 Has a quality assurance program required by RH 17.20.
17.7.3 The general license in RH 17.7.1 applies only when the package approval authorizes use of the package under this general license.
17.7.4 For a Type B or fissile material package, the design of which was approved by Nuclear Regulatory Commission before April 1, 1996, the general license is subject to additional restrictions of RH 17.8.
RH 17.8 General License: Previously Approved Type B Packages.
17.8.1 A Type B package previously approved by the Nuclear Regulatory Commission, but not designated as B(U) or B(M) in the Nuclear Regulatory Commission certificate of compliance, may be used under the general license of RH 17.7 with the following additional conditions:
17.8.1.1 Fabrication of the packaging was satisfactorily completed before August 31, 1986, as demonstrated by application of its model number in accordance with Nuclear Regulatory Commission regulations at 10 CFR 71.85(c);
17.8.1.2 A package used for a shipment to a location outside the United States is subject to multilateral approval, as defined in U.S. Department of Transportation regulations at 49 CFR 173.403; and 17.8.1.3 A serial number which uniquely identifies each packaging which conforms to the approved design is assigned to, and legibly and durably marked on, the outside of each packaging.
17.8.2 A Type B(U) package, a Type B(M) package, a low specific activity (LSA) material package or a fissile material package, previously approved by the nuclear regulatory commission but without the designation “-85” in the identification number of the Nuclear Regulatory Commission certificate of compliance, may be used under the general license of RH 17.8 with the following additional conditions:
17.8.2.1 Fabrication of the package is satisfactorily completed by April 1, 1999, as demonstrated by application of its model number in accordance with Nuclear Regulatory Commission regulations at 10 CFR 71.85(c);
17.8.2.2 A package used for a shipment to a location outside the United States is subject to multilateral approval except approved under special arrangement in accordance with U.S. Department of Transportation regulations at 49 CFR 173.403; and 17.8.2.3 A serial number that uniquely identifies each packaging which conforms to the approved design is assigned to, and legibly and durably marked on, the outside of each packaging.
RH 17.9 General License: U.S. Department of Transportation Specification Container.
17.9.1 A general license is issued to any licensee of the Department to transport, or to deliver to a carrier for transport, licensed material in a specification container for fissile material or for a Type B quantity of radioactive material as specified in 49 CFR Parts 173 and 178.
17.9.2 This general license applies only to a licensee who:
17.9.2.1 Has a copy of the specification;
17.9.2.2 Complies with the terms and conditions of the specification and the applicable requirements of this Part 17; and
17.9.2.3 Has a quality assurance program required by 17.20.
17.9.3 The general license in RH 17.9.1 is subject to the limitation that the specification container may not be used for a shipment to a location outside the United States except by multilateral approval as defined in 49 CFR 173.403.
RH 17.10 General License: Use of Foreign Approved Package.
17.10.1 A general license is issued to any licensee of the Department to transport, or to deliver to a carrier for transport, licensed material in a package the design of which has been approved in a foreign national competent authority certificate and revalidated by the U.S. Department of Transportation as meeting the applicable requirements of 49 CFR 171.12.
17.10.2 This general license applies only to international shipments.
17.10.3 This general license applies only to a licensee who:
17.10.3.1 Has a copy of the applicable certificate, the revalidation, and the drawings and other documents referenced in the certificate relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment;
17.10.3.2 Complies with the terms and conditions of the certificate and revalidation, and with the applicable requirements of this Part 17; and 17.10.3.3 Has a quality assurance program approved by the Nuclear Regulatory Commission. RH 17.11 General License: Fissile Material, Limited Quantity per Package.
17.11.1 A general license is hereby issued to any licensee to transport fissile material, or to deliver fissile material to a carrier for transport, if the material is shipped in accordance with this section.
17.11.2 This general license applies only when a package contains no more than a Type A quantity of radioactive material, including only one of the following:
17.11.2.1 Up to 40 grams of uranium-235; or
17.11.2.2 Up to 30 grams of uranium-233; or
17.11.2.3 Up to 25 grams of the fissile radionuclides of plutonium, except that for encapsulated plutonium-beryllium neutron sources in special form, an A quantity of plutonium may be present; or 17.11.2.4 A combination of fissile radionuclides in which the sum of the ratios of the amount of each radionuclide to the corresponding maximum amount in RH 17.11.2.1, 17.11.2.2, and
17.11.3 For packages where fissile material is mixed with substances having an average hydrogen density greater than water, this general license applies only when a package contains no more than a type a quantity of radioactive material, including only one of the following:
17.11.3.1 Up to 29 grams of uranium-235; or
17.11.3.2 Up to 18 grams of uranium-233; or
17.11.3.3 Up to 18 grams of the fissile radionuclides of plutonium; or
17.11.3.4 A combination of fissile radionuclides in which the sum of the ratios of the amount of each radionuclide to the corresponding maximum amount in RH 17.11.3.1, 17.11.3.2, and
17.11.4 Except as specified in RH 17.11.4.2, this general license applies only when all of the following requirements are met:
17.11.4.1 A package containing fissile radionuclides is labeled with a transport index not less than the number given by the following equation:
where the package contains x grams of uranium-235, y grams of uranium-233, and z grams of the fissile radionuclides of plutonium;
17.11.4.2 For a package in which the only fissile material is encapsulated plutonium-beryllium neutron sources in special form, the transport index based on criticality considerations may be taken as 0.025 times the number of grams of the fissile radionuclides of plutonium.
17.11.4.3 In all cases, the transport index must be rounded up to one decimal place and shall not exceed 10.0.
17.11.4.4 Except for the beryllium contained within the special form plutonium-beryllium sources authorized in rh 17.11.2, beryllium, graphite, or hydrogenous material enriched in deuterium is not present in quantities exceeding 0.1% of the fissile material mass.
17.11.4.5 The licensee has a quality assurance program approved by the nuclear regulatory commission.
RH 17.12 General License: Fissile Material, Limited Moderator per Package.
17.12.1 A general license is hereby issued to any licensee to transport fissile material, or to deliver fissile material to a carrier for transport, if the material is shipped in accordance with this section.
17.12.2 This general license applies only when all of the following requirements are met.
17.12.2.1 The package contains no more than a Type A quantity of radioactive material.
17.12.2.2 Neither beryllium nor hydrogenous material enriched in deuterium is present.
17.12.2.3 The total mass of graphite present does not exceed 7.7 times the total mass of uranium-235 plus plutonium.
17.12.2.4 Substances having a higher hydrogen density than water, for example certain hydrocarbon oils, are not present, except that polyethylene may be used for packing or wrapping.
17.12.2.5 Uranium-233 is not present, and the amount of plutonium does not exceed 1 percent of the amount of uranium-235.
17.12.2.6 The amount of uranium-235 is limited as follows:
17.12.2.7 The transport index of each package based on criticality considerations is taken as 10 times the number of grams of uranium-235 in the package divided by the maximum allowable number of grams per package in accordance with Table 1 or 2 of this section as applicable.
TABLE 1: PERMISSIBLE MASS OF URANIUM-235 PER FISSILE MATERIAL PACKAGE [NONUNIFORM DISTRIBUTION] Uranium enrichment in Permissible maximum weight percent of grams of uranium-235 uranium-235 not per package exceeding 24 40 20 42 15 45 11 48 10 51
9.5 52
9 54
8.5 55
8 57
7.5 59
7 60
6.5 62
6 65
5.5 68
5 72
4.5 76
4 80
3.5 88
3 100
2.5 120
2 164
1.5 272
1.35 320
1 680 *
0.92 1200 *
* Pursuant to the Department's agreement with the Nuclear Regulatory Commission, jurisdiction extends only to 350 grams of uranium-235.
TABLE 2: PERMISSIBLE MASS OF URANIUM-235 PER FISSILE MATERIAL PACKAGE [UNIFORM DISTRIBUTION] Uranium enrichment in Permissible maximum weight percent of grams of uranium-235 uranium-235 not per package exceeding 4 84
3.5 92
3 112
2.5 148
2 240
1.5 560 *
1.35 800*
* Pursuant to the Department's agreement with the Nuclear Regulatory Commission, jurisdiction extends only to 350 grams of uranium-235.
Operating Controls and Procedures RH 17.13 Fissile Material: Assumptions as to Unknown Properties of Fissile Material. When the isotopic abundance, mass, concentration, degree of irradiation, degree of moderation, or other pertinent property of fissile material in any package is not known, the licensee shall package the fissile material as if the unknown properties had credible values that would cause the maximum neutron multiplication.
RH 17.14 Preliminary Determinations.
Prior to the first use of any packaging for the shipment of radioactive material:
17.14.1 The licensee shall ascertain that there are no defects which could significantly reduce the effectiveness of the packaging;
17.14.2 Where the maximum normal operating pressure will exceed 35 kilopascal (5 pounds per square inch) gauge, the licensee shall test the containment systems at an internal pressure at least 50 percent higher than the maximum normal operating pressure to verify the capability of that system to maintain its structural integrity at that pressure;
17.14.3 The licensee shall determine that the packaging has been fabricated in accordance with the design approved by the Nuclear Regulatory Commission; and 17.14.4 The licensee shall conspicuously and durably mark the packaging with its model number, serial number, gross weight, and a package identification number as assigned by the Nuclear Regulatory Commission.
RH 17.15 Routine Determinations.
Prior to each shipment of licensed material, the licensee shall determine that:
17.15.1 The package is proper for the contents to be shipped;
17.15.2 The package is in unimpaired physical condition except for superficial defects such as marks or dents;
17.15.3 Each closure device of the packaging, including any required gasket, is properly installed and secured and free of defects;
17.15.4 Any system for containing liquid is adequately sealed and has adequate space or other specified provision for expansion of the liquid;
17.15.5 Any pressure relief device is operable and set in accordance with written procedures;
17.15.6 The package has been loaded and closed in accordance with written procedures;
17.15.7 Any structural part of the package which could be used to lift or tie down the package during transport is rendered inoperable for the purpose unless it satisfies design requirements specified in 10 CFR 71.45;
17.15.8 The level of non-fixed (removable) radioactive contamination on the external surfaces of each package offered for shipment is as low as reasonably achievable.
17.15.8.1 The level of non-fixed (removable) radioactive contamination may be determined by wiping an area of 300 square centimeters of the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the wiping material. Sufficient measurements must be taken in the most appropriate locations to yield a representative assessment of the removable contamination levels. Except as provided in RH 17.15.8.2, the amount of radioactivity measured on any single wiping material, when averaged over the surface wiped, must not exceed the limits given in Table 3 below at any time during transport. Other methods of assessment of equal or greater efficiency may be used. When other methods are used, the detection efficiency of the method used must be taken in account and in no case may the removable contamination on the external surfaces of the package exceed 10 times the limits listed in Table 3.
17.15.8.2 In the case of packages transported as exclusive use shipments by rail or highway only, the non-fixed (removable) radioactive contamination at any time during transport must not exceed 10 times the levels prescribed in RH 17.15.8.1. The levels at the beginning of transport must not exceed the levels in RH 17.15.8.1.
17.15.9 External radiation levels around the package and around the vehicle, if applicable will not exceed 2 mSv/h (200 millirems per hour) at any point on the external surface of the package at any time during transportation. The transport index shall not exceed 10.0; TABLE 3: NON-FIXED (REMOVABLE) EXTERNAL RADIOACTIVE CONTAMINATION WIPE LIMITS . Maximum Permissible Maximum Permissible Maximum Permissible Limits Limits Limits Contaminant Bq/cm2 2 2 uCi/cm dpm/cm Beta and gamma emitters 0.4 -5 22 and low toxicity alpha emitters All other alpha emitting 0.04 -6 2.2 radionuclides 17.15.10 For a package transported in exclusive use by rail, highway or water, radiation levels external to the package may exceed the limits specified in RH 17.15.9 but shall not exceed any of the following:
17.15.10.1 2 mSv/h (200 millirems per hour) on the accessible external surface of the package unless the following conditions are met, in which case the limit is 10 mSv/h (1000 millirems per hour);
17.15.10.2 2 mSv/h (200 millirems per hour) at any point on the outer surface of the vehicle, including the upper and lower surfaces, or, in the case of a flat-bed style vehicle, with a personnel barrier * , at any point on the vertical planes projected from the outer edges of the vehicle, on the upper surface of the load (or enclosure, if used), and on the lower external surface of the vehicle;
* A flat-bed style vehicle with a personnel barrier shall have radiation levels determined at vertical planes. If no personnel barrier is in place, the package cannot exceed 2 mSv/h (200 millirems per hour) at any accessible surface.
17.15.10.3 0.1 mSv/h (10 millirems per hour) at any point 2 meters from the vertical planes represented by the outer lateral surfaces of the vehicle, or, in the case of a flat-bed style vehicle, at any point 2 meters from the vertical planes projected from the outer edges of the vehicle; and 17.15.10.4 0.02 mSv/h (2 millirems per hour) in any normally occupied positions of the vehicle, except that this provision does not apply to private motor carriers when persons occupying these positions are provided with special health supervision, personnel radiation exposure monitoring devices, and training in accordance with RH 10.3 of these regulations; and 17.15.11 A package must be prepared for transport so that in still air at 100 degrees Fahrenheit (38 degrees Celsius) and in the shade, no accessible surface of a package would have a temperature exceeding 122 degrees Fahrenheit (50 degrees Celsius) in a nonexclusive use shipment or 180 degrees Fahrenheit (82 degrees Celsius) in an exclusive use shipment. Accessible package surface temperatures shall not exceed these limits at any time during transportation.
17.15.12 A package may not incorporate a feature intended to allow continuous venting during transport.
17.15.13 “Beforedelivery of a package to a carrier for transport, the licensee shall ensure that any special instructions needed to safely open the package have been sent to, or otherwise made available to, the consignee for the consignee's use in accordance with 4.32.5.2.” RH 17.16 Air Transport of Plutonium.
Notwithstanding the provisions of any general licenses and notwithstanding any exemptions stated directly in this part or included indirectly by citation of the U.S. Department of Transportation regulations, as may be applicable, the licensee shall assure that plutonium in any form is not transported by air, or delivered to a carrier for air transport, unless:
17.16.1 The plutonium is contained in a medical device designed for individual human application; or 17.16.2 The plutonium is contained in a material in which the specific activity is not greater than 70 Bq/g (0.002 microcuries per gram) of material and in which the radioactivity is essentially uniformly distributed; or 17.16.3 The plutonium is shipped in a single package containing no more than an A quantity of plutonium in any isotope or form and is shipped in accordance with RH 17.5; or 17.16.4 The plutonium is shipped in a package specifically authorized (in the certificate of compliance issued by the Nuclear Regulatory Commission for that package) for the shipment of plutonium by air and the licensee requires, through special arrangement with the carrier, compliance with 49 CFR 175.704, the U.S. Department of Transportation regulations applicable to the air transport of plutonium.
RH 17.17 Shipment Records.
Each licensee shall maintain, for a period of 2 years after shipment, a record of each shipment of licensed material not exempt under RH 17.4 showing, where applicable:
17.17.1 Identification of the packaging by model number and serial number;
17.17.2 Verification that the packaging, as shipped, had no significant defect;
17.17.3 Volume and identification of coolant;
17.17.4 Type and quantity of licensed material in each package, and the total quantity of each shipment;
17.17.5 Date of the shipment;
17.17.6 Name and address of the transferee;
17.17.7 Address to which the shipment was made; and
17.17.8 Results of the determinations required by RH 17.15 and by the conditions of the package approval.
RH 17.18 Reports.
The licensee shall report to the Department within 30 days:
17.18.1 Any instance in which there is significant reduction in the effectiveness of any packaging during use; and 17.18.2 Details of any defects with safety significance in the packaging after first use, with the means employed to repair the defects and prevent their recurrence; or 17.18.3 Instances in which the conditions of approval in the certificate of compliance were not observed in making a shipment.
RH 17.19 Advance Notification of Transport of Nuclear Waste.
17.19.1 Prior to the transport of any nuclear waste outside of the confines of the licensee's facility or other place of use or storage, or prior to the delivery of any nuclear waste to a carrier for transport, each licensee shall provide advance notification of such transport to the governor, or governor's designee, 4 of each state through which the waste will be transported. 4 A list of the mailing addresses of the governors and governors' designees is available upon request from the Director, Office of State Programs, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555. The list will be published annually in the Federal Register on or about June 30 to reflect any changes in information.
17.19.2 Advance notification is required only when:
17.19.2.1 The nuclear waste is required to be in Type B packaging for transportation;
17.19.2.2 The nuclear waste is being transported into, within, or through, a state enroute to a disposal facility or to a collection point for transport to a disposal facility; and 17.19.2.3 The quantity of licensed material in a single package exceeds any one of the following:
17.19.3 Each advance notification required by RH 17.19.1 shall contain the following information:
17.19.3.1 The name, address, and telephone number of the shipper, carrier, and receiver of the shipment;
17.19.3.2 A description of the nuclear waste contained in the shipment as required by 49 CFR
17.19.3.3 The point of origin of the shipment and the 7-day period during which departure of the shipment is estimated to occur;
17.19.3.4 The 7-day period during which arrival of the shipment at state boundaries is estimated to occur;
17.19.3.5 The destination of the shipment, and the 7-day period during which arrival of the shipment is estimated to occur; and 17.19.3.6 A point of contact with a telephone number for current shipment information.
17.19.4 The notification required by RH 17.19.1 shall be made in writing to the office of each appropriate governor, or governor's designee, and to the Department. A notification delivered by mail must be postmarked at least 7 days before the beginning of the 7-day period during which departure of the shipment is estimated to occur. A notification delivered by messenger must reach the office of the governor, or governor's designee, at least 4 days before the beginning of the 7-day period during which departure of the shipment is estimated to occur. A copy of the notification shall be retained by the licensee for 3 years.
17.19.5 The licensee shall notify each appropriate governor, or governor's designee, and the Department of any changes to schedule information provided pursuant to RH 17.19.1. Such notification shall be by telephone to a responsible individual in the office of the governor, or governor's designee, of the appropriate state or states. The licensee shall maintain for 3 years a record of the name of the individual contacted.
17.19.6 Each licensee who cancels a nuclear waste shipment, for which advance notification has been sent, shall send a cancellation notice to the governor, or governor's designee, of each appropriate state and to the Department. A copy of the notice shall be retained by the licensee for 3 years. Quality Assurance RH 17.20 Quality Assurance Reguirements.
17.20.1 Unless otherwise authorized by the agency, each licensee shall establish, maintain, and execute a quality assurance program to verify by procedures such as checking, auditing, and inspection that deficiencies, deviations, and defective material and equipment relating to the shipment of packages containing radioactive material are promptly identified and corrected.
17.20.2 The licensee shall identify the material and components to be covered by the quality assurance program.
17.20.3 Each licensee shall document the quality assurance program by written procedures or instructions and shall carry out the program in accordance with those procedures throughout the period during which packaging is used.
17.20.4 Prior to the use of any package for the shipment of radioactive material, each licensee shall obtain approval by the Department of its quality assurance program.
17.20.5 The licensee shall maintain sufficient written records to demonstrate compliance with the quality assurance program. Records of quality assurance pertaining to the use of a package for shipment of radioactive material shall be maintained for a period of 3 years after shipment.
17.21 Referenced Materials
17.21.1 This Part 17 of these regulations incorporates by reference material originally published elsewhere. Certified copies of the complete text of incorporated materials referenced are available for public inspection during regular business hours at the radiation control division. Copies of referenced material will be provided at cost upon request. Information regarding how the incorporated material may be obtained or examined is available from: Director, Radiation Control Division (RCD-DO-B1) Colorado Department of Public Health and Environment 4300 Cherry Creek Drive South Denver, Colorado 80222-1530 17.21.2 Any material that has been incorporated by reference may be examined in any state publications depository library. Copies of the incorporated materials have been sent to the state publications depository and distribution center, and are available for interlibrary loan.
17.21.3 Material referenced in this Part 17 of the regulations does not include amendments to or revised editions of the material published later than the effective date of the relevant section. Appendix A to Part 17 - Determination of A and A 1 2 I. Values of A and A for individual radionuclides, which are the bases for many activity limits 1 2 elsewhere in these regulations are given in Table A-1. The curie (Ci) values specified are obtained by converting from the Terabecquerel (TBq) figure. The curie values are expressed to three significant figures to assure that the difference in the TBq and Ci quantities is one tenth of one percent or less. Where values of A or A are unlimited, it is for radiation control purposes only. 1 2 For nuclear criticality safety, some materials are subject to controls placed on fissile material.
II. For individual radionuclides whose identities are known, but which are not listed in Table A-1, the determination of the values of A and A requires Department approval, except that the values 1 2 of A and A in Table A-2 may be used without obtaining Agency approval. 1 2 III. In the calculations of A and A for a radionuclide not in Table A-1, a single radioactive decay 1 2 chain, in which radionuclides are present in their naturally occurring proportions, and in which no daughter nuclide has a half-life either longer than 10 days, or longer than that of the parent nuclide, shall be considered as a single radionuclide, and the activity to be taken into account, and the A or A value to be applied shall be those corresponding to the parent nuclide of that 1 2 chain. In the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than 10 days, or greater than that of the parent nuclide, the parent and those daughter nuclides shall be considered as mixtures of different nuclides.
IV. For mixtures of radionuclides whose identities and respective activities are known, the following conditions apply:
(a) For special form radioactive material, the maximum quantity transported in a Type A package: 1007_1_Part17-Appendix-A_inline1.jpg (b) For normal form radioactive material, the maximum quantity transported in a Type A package: 1007_1_Part17-Appendix-A_inline2.jpg where B(i) is the activity of radionuclide I and A (i) and A (i) are the A and A values for 1 2 1 2 radionuclide respectively.
Alternatively, an A value for mixtures of special form material may be determined as follows: 1007_1_Part17-Appendix-A_inline3.jpg where f(i) is the fraction of activity of nuclide i in the mixture and A (i) is the appropriate A value 1 1 for nuclide i.
V. When the identity of each radionuclide is known, but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest A or A value, 1 2 as appropriate, for the radionuclides in each group may be used in applying the formulas in paragraph IV. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest A or A values for the alpha emitters and beta/gamma 1 2 emitters.
Table A-1: A 1 and A 2 Values for Radionuclides Big Table a International shipments of Einsteinium require multilateral approval of A1 and A2 values. Table A-2: General Values for A1 and A2 Contents A 1 (TBq) A 1 (Ci) A 2 (TBq)
Only beta- or gamma- 0.2 5 0.02 emitting nuclides are known to be present.
Alpha-emitting nuclides 0.10 2.70 -5 2 x 10 are known to be present, or no relevant data are available.
Table A-3: Activity-mass Relationships for Uranium Uranium Enrichment* Specific Activity Specific Activity wt % U-235 present . TBq/g Ci/g
0.45 -8 -7
0.72 -8 -7
1.0 -8 -7
1.5 -8 -6
5.0 -7 -6
10.0 -7 -6
20.0 -7 -5
35.0 -7 -5
50.0 -7 -5
90.0 -6 -5
93.0 -6 -5
95.0 -6 -5
* The figures for uranium include representative values for the activity of the uranium-235 which is concentrated during the enrichment process.