CHAPTER 45
RADIATION SAFETY REQUIREMENTS FOR INDUSTRIAL
RADIOGRAPHIC OPERATIONS
[Prior to 8/5/92, see 641—41.4(136C)]
641—45.1(136C) General requirements for industrial radiography operations.
	45.1(1) Purpose and scope.
	a. 	The rules in this chapter establish radiation safety requirements for using sources of radiation for industrial radiography. The requirements of this chapter are in addition to, and not in substitution for, other applicable requirements of 641—Chapters 38, 39, and 40. The rules in this chapter apply to all licensees or registrants who use sources of radiation for industrial radiography.
	b. 	All references to any Code of Federal Regulations (CFR) in this chapter are those in effect as of September 15, 2010.
The provisions of 641—Chapter 38 are in addition to, and not in substitution for, any other applicable portions of 641—Chapters 39 to 45.
	45.1(2) Definitions. For the purpose of this chapter, the definitions of 641—Chapter 38 may also apply. As used in this chapter, the following definitions apply:
“Annual refresher safety training” means a review conducted or provided by the licensee for its employees on radiation safety aspects of industrial radiography. The review may include, as appropriate, the results of internal inspections, new procedures or equipment, new or revised regulations, accidents or errors that have been observed, and should also provide opportunities for employees to ask safety questions.
“Associated equipment” means equipment that is used in conjunction with a radiographic exposure device to make radiographic exposures that drives, guides, or comes in contact with the source, e.g., guide tube, control tube, control (drive) cable, removable source stop, “J” tube and collimator when it is used as an exposure head.
“Cabinet X-ray system” means an X-ray system with the X-ray tube installed in an enclosure independent of existing architectural structures except the floor on which it may be placed. The cabinet X-ray system is intended to:
	1.	Contain at least that portion of a material being irradiated;
	2.	Provide radiation attenuation; and
	3.	Exclude personnel from its interior during generation of radiation. Included are all X-ray systems designed primarily for the inspection of carry-on baggage at airline, railroad, and bus terminals, and in similar facilities. An X-ray tube used within a shielded part of a building, or X-ray equipment which may temporarily or occasionally incorporate portable shielding, is not considered a cabinet X-ray system.
“Certifiable cabinet X-ray system” means an existing uncertified X-ray system that has been modified to meet certification requirements specified in 21 CFR 1020.40.
“Certified cabinet X-ray system” means an X-ray system which has been certified in accordance with 21 CFR 1010.2 as being manufactured and assembled pursuant to the provisions of 21 CFR 1020.40.
“Certifying entity” means an independent certifying organization meeting the requirements of Appendix A in 10 CFR Part 34 or an agreement state meeting the requirements in Appendix A, Parts II and III of 10 CFR Part 34.
“Collimator” means a small radiation shield of lead or other heavy metal that is placed on the end of a guide tube or directly onto a radiographic exposure device to restrict the size of the radiation beam when the sealed source is cranked into position to make a radiographic exposure.
“Control (drive) cable” means the cable that is connected to the source assembly and used to drive the source to and from the exposure location.
“Control drive mechanism” means a device that enables the source assembly to be moved to and from the exposure device.
“Control tube” means a protective sheath for guiding the control cable. The control tube connects the control drive mechanism to the radiographic exposure device.
“Crank-out device” means the cable, protective sheath, and handcrank used to move the sealed source from the shielded to the unshielded position to make an industrial radiographic exposure.
“Enclosed radiography” means industrial radiography conducted in an enclosed cabinet or room and includes cabinet radiography and shielded-room radiography.
“Exposure head” means a device that locates the gamma radiography sealed source in the selected working position. (An exposure head is also known as a source stop.)
“Field station” means a facility where licensed material may be stored or used and from which equipment is dispatched.
“Fluoroscopic imaging assembly” means a subsystem in which X-ray photons produce a fluoroscopic image. It includes the image receptors such as the image intensifier and spot-film device, electrical interlocks, if any, and structural material providing linkage between the image receptor and source assembly.
“GED” means general educational development.
“Guide tube (projection sheath)” means a flexible or rigid tube (i.e., “J” tube) for guiding the source assembly and the attached control cable from the exposure device to the exposure head. The guide tube may also include the connections necessary for attachment to the exposure device and to the exposure head.
“Hands-on experience” means experience in all of those areas considered to be directly involved in the radiography process.
“I.D. card” means the document issued by the agency, another Agreement State, a licensing state, or third-party certification to industrial radiographers following completion of requirements stated in 45.1(10)“b.”
“Independent certifying organization” means an independent organization that meets all of the criteria of Appendix A in 10 CFR Part 34.
“Lay-barge radiography” means industrial radiography performed on any water vessel used for laying pipe.
“Lixiscope” means a portable light-intensified imaging device using a sealed source.
“Lock-out survey” means a radiation survey performed to verify that a sealed source is in its shielded position. The lock-out survey is performed before moving the radiographic exposure device or source changer to a new location or when securing the radiographic exposure device or source changer.
“Minimal threat” means that during the operations of electronic devices capable of generating or emitting fields of radiation:
	1.	No deliberate exposure of an individual occurs;
	2.	The radiation is not emitted in an open beam configuration; and
	3.	No known physical injury to an individual has occurred.
“Offshore” means within the territorial waters of the United States.
“Offshore platform radiography” means industrial radiography conducted from an offshore platform over a body of water.
“Permanent radiographic installation” means an enclosed shielded room, cell, or vault, not located at a temporary job site, in which radiography is performed.
“Practical examination” means a demonstration through practical application of the safety rules and principles in industrial radiography including use of all appropriate equipment and procedures.
“Radiation safety officer” means an individual named by the licensee or registrant who has a knowledge of, responsibility for, and authority to enforce appropriate radiation protection rules, standards, and practices on behalf of the licensee or registrant and who meets the requirements of 45.1(10)“d.”
“Radiographer” means any individual who has successfully completed the training, testing, and documentation requirements of 45.1(10)“b,” who performs or personally supervises industrial radiographic operations, and is responsible to the licensee or registrant for ensuring compliance with the requirement of these rules and all license and certificate of registration conditions.
“Radiographer certification” means written approval received from a certifying entity stating that an individual has satisfactorily met certain established radiation safety, testing, and experience criteria.
“Radiographer’s assistant” means any individual who has successfully completed the training, testing, and documentation requirements of 45.1(10)“a” and who uses sources of radiation and related handling tools or radiation survey instruments under the direct supervision of a radiographer trainer.
“Radiographer trainer (instructor)” means any individual who instructs and supervises radiographer’s assistants during on-the-job training and who meets the requirements of 45.1(10)“c.”
“Radiographic exposure device” means any instrument containing a sealed source fastened or contained therein, in which the sealed source or shielding thereof may be moved or otherwise changed from a shielded to unshielded position for purposes of making a radiographic exposure (e.g., camera), or any other X-ray industrial system whereby a permanent or semipermanent image is recorded on an image receptor by action of ionizing radiation.
“Radiographic operations” means all activities associated with the presence of radioactive sources or radiation in a radiographic exposure device during use of the device or transport (except when being transported by a common or contract transport), to include surveys to confirm the adequacy of boundaries, setting up equipment and any activity inside restricted area boundaries.
“Radiographic personnel” means any radiographer or radiographer’s assistant.
“Residential location” means any area where structures in which people lodge or live are located, and the grounds on which such structures are located including, but not limited to, houses, apartments, condominiums, and garages.
“Shielded position” means the location within the radiographic exposure device or source changer where the sealed source is secured and restricted from movement.
“Shielded-room radiography” means industrial radiography conducted in a room shielded so that radiation levels at every location on the exterior meet the limitations specified in 641—40.26(136C).
“Source assembly” means an assembly that consists of the sealed source and a connector that attaches the source to the control cable. The source assembly may also include a stop ball used to secure the source in the shielded position.
“Source changer” means a device designed and used for replacement of sealed sources in radiographic exposure devices, including those source changers also used for transporting and storage of sealed sources.
“Source container” means a shielded device in which sealed sources are secured, transported, and stored.
“Storage area” means any location, facility, or vehicle which is used to store, to transport, or to secure a radiographic exposure device, a storage container, or a sealed source when it is not in use and which is locked or has a physical barrier to prevent accidental exposure, tampering with, or unauthorized removal of the device, container, or source.
“Storage container” means a shielded device in which sealed sources are secured, transported, and stored.
“S-tube” means a tube through which the radioactive source travels when inside a radiographic exposure device.
“Temporary job site” means any location where radiographic operations are conducted and where licensed material may be stored other than the location(s) listed in a specific license or certificate of registration.
“Trainee status card” means the document issued by the agency following completion of the requirements of 45.1(10)“a”(1) and (2).
“Transport container” means a package that is designed to provide radiation safety and security when sealed sources are transported and which meets all applicable requirements of the U.S. Department of Transportation.
“Underwater radiography” means industrial radiography performed when the radiographic exposure device and related equipment are beneath the surface of the water.
	45.1(3) Exemptions.
	a. 	Uses of certified and certifiable cabinet X-ray systems designed to exclude individuals are exempt from the requirements of this chapter, except for the requirements of 45.2(6)“b” and “c.”
	b. 	Industrial uses of lixiscopes are exempt from the requirements in this chapter.
	c. 	Radiation machines determined by the agency to constitute a minimal threat to human health and safety in accordance with 641—subrule 38.3(1) are exempt from the rules in this chapter, except for the requirements of this subrule.
	45.1(4) Receipt, transfer, and disposal of sources of radiation. Each licensee and registrant shall maintain records showing the receipt, transfer, and disposal of sources of radiation. These records shall include the date, the name of the individual making the record, the radionuclide, number of curies or mass (for DU), and the make, model, and serial number of each source of radiation and device, as appropriate. Records shall be maintained for three years after they are made.
	45.1(5) Radiation survey instruments.
	a. 	The licensee or registrant shall maintain sufficient calibrated and operable radiation survey instruments at each location where sources of radiation are present to make physical radiation surveys as required by this chapter and 641—subrule 40.36(1). Instrumentation required by this subrule shall have a range such that 2 millirems (0.02 millisievert) per hour through 1 rem (0.01 sievert) per hour can be measured.
	b. 	Notwithstanding the requirements of 641—subrule 40.36(2) each radiation survey instrument shall be calibrated:
	(1)	At energies appropriate for use and at intervals not to exceed six months and after each instrument servicing;
	(2)	Such that accuracy within plus or minus 20 percent of the calibration source can be demonstrated at each point checked;
	(3)	At 2 points located approximately 1/3 and 2/3 of full-scale on each scale for linear scale instruments; at midrange of each decade, and at 2 points of at least 1 decade for logarithmic scale instruments; and at 3 points between 2 and 1000 mrem per hour for digital instruments; and
	(4)	By a person licensed or registered by the agency, another agreement state, or the U.S. Nuclear Regulatory Commission to perform such service.
	c. 	Records of these calibrations shall be maintained for three years after the calibration date for inspection by the agency.
	d. 	Each radiation survey instrument shall be checked with a radiation source at the beginning of each day of use and at the beginning of each work shift to ensure it is operating properly.
	45.1(6) Quarterly inventory. Each licensee shall conduct a physical inventory at intervals not to exceed three months to account for all sealed sources and radiography exposure devices received and possessed. Sources of radiation include radiographic exposure devices containing depleted uranium. The records of the inventories shall be maintained for three years from the date of the inventory for inspection by the agency and shall include: the manufacturer, model number, serial number, radionuclide, number of curies, and location of each source of radiation; number of kilograms of depleted uranium shielding; date of the inventory; and name of the individual making the inventory.
	45.1(7) Utilization logs.
	a. 	Each licensee shall maintain utilization logs of the use of each sealed source. The logs shall include:
	(1)	A unique description, which includes the make, model, and serial number of each radiographic exposure device containing a sealed source or transport or storage container in which the sealed source is located;
	(2)	The identity and signature of the radiographer to whom the sealed source is assigned;
	(3)	The plant or site where each sealed source is used; and
	(4)	The date(s) each sealed source is removed from storage and returned to storage.
	b. 	Each registrant shall maintain current logs of the use of each source of radiation. The logs shall include:
	(1)	A unique identification, which includes the make, model and serial number of each source of radiation;
	(2)	The identity of the radiographer using the source of radiation;
	(3)	The date(s) each source of radiation is energized or used and the number of exposures made.
	c. 	Utilization logs may be kept on clear, legible records containing all the information required by 45.1(7)“a” or “b.” Copies of utilization logs shall be maintained for agency inspection for three years from the date of the recorded event. The records shall be kept at the location specified by the license or certificate of registration.
	45.1(8) Inspection and maintenance.
	a. 	Each licensee or registrant shall perform visual and operability checks on survey meters, radiographic exposure devices, transport and storage containers, associated equipment and source changers before use on each day the equipment is to be used to ensure that the equipment is in good working condition, that the sources are adequately shielded, and that required labeling is present. Survey instrument operability must be performed using check sources or other appropriate means.
	b. 	Each licensee or registrant shall have written procedures and conduct a program, at intervals not to exceed three months, or prior to the first use thereafter, of inspection and maintenance of radiation machines, radiographic exposure devices, transport and storage containers, source changers, survey instruments, and associated equipment to ensure proper functioning of components important to safety. All appropriate parts shall be maintained in accordance with manufacturer’s specifications. Replacement components shall meet design specifications. This program shall cover, as a minimum, the items in Appendix B of this chapter.
	c. 	Each licensee shall have a program and written procedures for the inspection and maintenance necessary to maintain the Type B packaging used to transport radioactive materials. The program must include procedures to ensure that Type B packages are shipped and maintained in accordance with the certificate of compliance or other approval.
	d. 	If equipment problems are found, the equipment must be removed from service until repaired.
	e. 	The record of equipment problems and of any maintenance performed under 45.1(8) must be retained for three years after the record is made. The record must include the date of check or inspection, name of inspector, equipment involved, any problems found, and what repair or maintenance, if any, was performed.
	45.1(9) Permanent radiographic installations. Permanent radiographic installations having high radiation area entrance controls of the type described in 641—paragraphs 40.42(1)“b” and “c” shall also meet the following requirements:
	a. 	Each entrance that is used for personnel access to the high radiation area shall have both visible and audible warning signals to warn of the presence of radiation. The visible signal shall be activated by radiation. The audible signal shall be activated when an attempt is made to enter the installation while the source is exposed.
	b. 	The control device or alarm system shall be tested for proper operation at the beginning of each day of equipment use. If a control device or alarm system is operating improperly, it shall be immediately labeled as defective and repaired before industrial radiographic operations are resumed. Records of these tests shall be maintained for inspection by the agency for three years from the date of the event.
	45.1(10) Training and testing for radiographic personnel.
	a. 	Radiographer’s assistant requirements. No licensee or registrant shall permit any individual to act as a radiographer’s assistant, as defined in this chapter, until:
	(1)	It has been documented on the appropriate agency form or equivalent that such individual has received copies of and has demonstrated an understanding of:
	1.	The subjects outlined in Appendix A, presented in a 40-hour course approved by the agency, another agreement state, or the U.S. Nuclear Regulatory Commission;
	2.	The rules contained in this chapter and the applicable sections of 641—Chapters 38, 39, and 40;
	3.	The appropriate conditions of license(s) or certificate(s) of registration;
	4.	The licensee’s or registrant’s operating and emergency procedures;
	5.	And developed competence to use, under the personal supervision of the radiographer, the licensee’s or registrant’s radiographic exposure devices, sealed sources, associated equipment, and radiation survey instruments that the assistant will use;
	6.	And has demonstrated competence in the use of radiographic exposure devices, sources, survey instruments and associated equipment described in 45.1(10)“a”(1) by successful completion of a practical examination covering this material.
	(2)	The individual possesses a current agency-issued trainee status card issued after completion of 45.1(10)“a”(1). Trainee status will be granted only once for each individual and is valid for no longer than two years.
	b. 	Radiographer requirements. No licensee or registrant shall permit any individual to act as a radiographer:
	(1)	Until it has been documented to the agency that such individual:
	1.	Has completed the requirements of 45.1(10)“a”(1);
	2.	Has completed on-the-job training as a radiographic trainee supervised by one or more radiographic trainers. The on-the-job training shall be documented on the appropriate agency form or equivalent and shall include a minimum of two months (320 hours) of active participation in the performance of industrial radiography utilizing radioactive material or one month (160 hours) of active participation in the performance of industrial radiography utilizing radiation machines, or both. Individuals performing industrial radiography utilizing radioactive materials and radiation machines must complete both segments of the on-the-job training (three months or 480 hours). Active participation does not include safety meetings or classroom training;
	3.	Has demonstrated competence in the use of sources of radiation, radiographic exposure devices, related handling tools, and radiation survey instruments which may be employed in industrial radiographic assignments by successful completion of a practical examination covering this material;
	(2)	Unless the individual has successfully completed within the last five years the appropriate agency-administered examination prescribed in 45.1(10)“f”(2) or equivalent examination; and
	(3)	Unless the individual possesses a current I.D. card.
	c. 	Radiographer trainer. No individual shall act as a radiographer trainer unless such individual:
	(1)	Has met the requirements of 45.1(10)“a”(1) and “b”;
	(2)	Has one year of documented experience as an industrial radiographer and possesses a current ID card issued at least one year prior to the application for a trainer card; and
	(3)	Is named on the specific license or certificate of registration issued by the agency and under which an individual is acting as a radiographer trainer, or
	(4)	Possesses a valid radiographer trainer card issued by the agency.
	d. 	Radiation safety officer. The radiation safety officer shall ensure that radiation safety activities are being performed in accordance with approved procedures and regulatory requirements in the daily operation of the licensee’s program.
	(1)	A radiation safety officer (RSO) shall be designated for every industrial radiography license and certificate of registration issued by the agency.
	(2)	The RSO’s qualifications shall include:
	1.	Possession of a high school diploma or a certificate of high school equivalency based on the GED test;
	2.	Completion of the training and testing requirements of 45.1(10)“a”(1) and 45.1(10)“b”(1)“3,” (2), and (3);
	3.	2000 hours of hands-on experience as a qualified radiographer in industrial radiographic operations; and
	4.	Formal training in the establishment and maintenance of a radiation protection program.
The agency will consider alternatives when the RSO has either appropriate training or experience, or both, in the field of ionizing radiation and, in addition, has adequate formal training with respect to the establishment and maintenance of a radiation safety protection program.
	(3)	The specific duties of the RSO include, but are not limited to, the following:
	1.	To establish and oversee operating, emergency, and ALARA procedures and to review them regularly to ensure that the procedures are current and conform with these rules;
	2.	To oversee and approve all phases of the training program for radiographic personnel so that appropriate and effective radiation protection practices are taught;
	3.	To ensure that required radiation surveys and leak tests are performed and documented in accordance with these rules, including any corrective measures when levels of radiation exceed established limits;
	4.	To ensure that personnel monitoring devices are calibrated and used properly by occupationally exposed personnel, that records are kept of the monitoring results, and that timely notifications are made as required by 641—Chapter 40;
	5.	To ensure that any required interlock switches and warning signals are functioning and that radiation signs, ropes, and barriers are properly posted and positioned;
	6.	To investigate and report to the agency each known or suspected case of radiation exposure to an individual or radiation level detected in excess of limits established by these rules and each theft or loss of source(s) of radiation, to determine the cause, and to take steps to prevent its recurrence;
	7.	To have a thorough knowledge of management policies and administrative procedures of the licensee or registrant;
	8.	To assume control and have the authority to institute corrective actions including shutdown of operations when necessary in emergency situations or unsafe conditions;
	9.	To maintain records as required by these rules (see Appendix C);
	10.	To ensure the proper storing, labeling, transport, and use of exposure devices and sources of radiation;
	11.	To ensure that quarterly inventory and inspection and maintenance programs are performed in accordance with 45.1(6), 45.1(8), 45.2(3), and 45.3(6)“b”; and
	12.	To ensure that personnel are complying with these rules, the conditions of the license or the registration, and the operating and emergency procedures of the licensee or registrant.
	e. 	Training and testing records. Each licensee and registrant shall maintain, for agency inspection, training and testing records which demonstrate that the applicable requirements of 45.1(10)“a” and “b” are met for all industrial radiographic personnel. Records shall be maintained until disposal is authorized by the agency. The agency shall not release records for disposal unless the records have been maintained at least three years.
	f. 	Applications and examinations.
	(1)	Application.
	1.	An application for taking the examination shall be on forms prescribed and furnished by the agency along with the fee required in 641—subrule 38.8(3). The application shall be submitted only after the training requirements of 45.1(10)“a” and “b” have been completed.
	2.	An individual whose I.D. card has been suspended or revoked shall obtain prior approval from the agency to apply to take the examination.
	(2)	Examination. The examination shall be given for the purpose of determining the qualifications of applicants.
	1.	A written examination shall be held at such times and places as the agency shall determine. The scope of the examination and the methods of procedure, including determination of the passing score, shall be prescribed by the agency. The examination will emphasize the applicant’s ability to safely use sources of radiation and related equipment and the applicant’s knowledge of these rules.
	2.	A candidate failing an examination may apply for reexamination in accordance with 45.1(10)“f”(1) and will be reexamined. A candidate shall not retake the same version of the agency-administered examination.
	3.	The examination will be held at locations designated by the agency. The examination shall normally be offered quarterly. Dates, times, and locations of the examinations will be provided by the agency.
	4.	The examination will be in the English language.
	5.	To take the examination, an individual shall have a picture identification card (such as an Iowa driver’s license) at the time of the examination.
	6.	Calculators will be permitted during the examination; however, calculators or computers with preprogrammed data or formulas, including exposure calculations, will not be permitted.
	7.	The examination will be a “closed book” examination.
	8.	Examination material shall be returned to the agency at the end of the examination. No photographic or other copying of examination questions or materials shall be permitted. Disclosure by any individual of the contents of any examination prior to the administration is prohibited.
	9.	Any individual observed by an agency proctor to be compromising the integrity of the examination shall be required to surrender the examination, the answer sheet, and any work paper. Such individual will not be allowed to complete the examination, will forfeit the examination fee, and will leave the examination site to avoid disturbing other examinees. Such individual may resubmit an application and an additional examination fee to take the examination not earlier than three months later.
	10.	The names and scores of individuals taking the examination shall be a public record.
	g. 	Identification procedures.
	(1)	I.D. card.
	1.	An I.D. card shall be issued to each person who successfully completes the requirements of 45.1(10)“b” and the examination prescribed in 45.1(10)“f”(2) or an equivalent examination.
	2.	Each person’s I.D. card shall contain the person’s photograph.
	3.	The I.D. card remains the property of the state of Iowa and may be revoked or suspended under the provisions of 45.1(10)“h.”
	4.	Any individual who wishes to replace the I.D. card shall submit to the agency a written request for a replacement I.D. card, stating the reason a replacement I.D. card is needed and the fee required in 641—subrule 38.8(3). The individual shall maintain in possession a copy of the request while performing industrial radiographic operations until a replacement I.D. card is received from the agency.
	(2)	Expiration of I.D. card. Each I.D. card expires at the end of the day, in the month and year stated on the I.D. card.
	(3)	Renewal of I.D. card.
	1.	Applications for examination to renew an I.D. card shall be filed in accordance with 45.1(10)“f”(1).
	2.	The examination for renewal of an I.D. card shall be administered in accordance with 45.1(10)“f”(2).
	3.	A renewed I.D. card shall be issued in accordance with 45.1(10)“g”(1).
	h. 	Revocation or suspension of an I.D. card.
	(1)	Any radiographer who violates these rules may be required to show cause at a formal hearing why the I.D. card should not be revoked or suspended.
	(2)	When an agency order has been issued for an industrial radiographer to cease and desist from the use of radioactive material or revoking or suspending the I.D. card, the industrial radiographer shall surrender the I.D. card to the agency until such time as the order is changed or the suspension expires.
	(3)	An agency’s inspector may, in certain instances, confiscate any radiographer’s I.D. card on the spot while conducting an inspection or investigation. If the inspector determines that the activities being conducted by the radiographer are significant enough to be classified as severity I, II, or III, as specified in 641—38.5(136C), and after obtaining the approval of agency management, the inspector may take any radiographer’s I.D. card. The agency will then issue a cease and desist order to the radiographer’s employer, forward the I.D. card(s) to the issuing entity, and notify the U.S. Nuclear Regulatory Commission and other agreement states.
	i. 	Exemptions. Any person using a source of radiation to determine the presence of explosives in a package or the authenticity of a piece of art is exempt from the provisions of 45.1(10)“a” to “h.”
	j. 	Reciprocity.
	(1)	Reciprocal recognition by the agency of an individual radiographer certification will be granted provided that:
	1.	The individual holds a valid certification in the appropriate category and class issued by a certifying entity as defined in 45.1(2).
	2.	The requirements and procedures of the certifying entity issuing the certification require the same or comparable certification standards as those required by 45.1(10)“a” through “e”; and
	3.	The individual submits a legible copy of the certification to the agency prior to entry into Iowa.
	(2)	Enforcement actions with the agency, another agreement state, or the U.S. Nuclear Regulatory Commission or any sanctions by an independent certifying entity may be considered when reviewing a request for reciprocal recognition from a licensee, registrant, or certified radiographer.
	(3)	Certified radiographers who are granted reciprocity by the agency shall maintain the certification upon which the reciprocal recognition was granted, or prior to the expiration of such certification, shall meet the requirements of 45.1(10)“b.”
	45.1(11) Internal audits. Except as provided in 45.1(11)“c,” the RSO or designee shall conduct an inspection program of the job performance of each radiographer and radiographer’s assistant to ensure that these rules, license requirements, and the licensee’s or registrant’s operating and emergency procedures are followed. The inspection program must:
	a. 	Include observation of the performance of each radiographer and radiographer’s assistant during an actual industrial radiographic operation, at intervals not to exceed six months; and
	b. 	Provide that, if a radiographer or radiographer’s assistant has not participated in an industrial radiographic operation for more than six months since the last audit, the radiographer or radiographer’s assistant must demonstrate understanding of the subjects contained in Appendix A of this chapter by a practical examination before the individual can next participate in a radiographic operation.
	c. 	The agency may consider alternatives in those situations where the individual serves as both radiographer and RSO. In those operations where a single individual serves as both radiographer and RSO, and performs all radiography operations, an inspection program is not required.
	d. 	Records of audits shall be maintained by the licensee or registrant for agency inspection for three years from the date of the audit.
	45.1(12) Personnel monitoring control.
	a. 	The personnel monitoring program shall meet the applicable requirements of 641—Chapter 40.
	b. 	When performing industrial radiographic operations:
	(1)	No licensee or registrant shall permit an individual to act as a radiographer, radiographer’s assistant, or radiographer trainer unless at all times during radiographic operations each individual wears, on the trunk of the body, a combination of direct-reading pocket dosimeter, an operating alarm ratemeter, and a film badge, an optically stimulated luminescent device (OSL device) or a thermoluminescent dosimeter (TLD) that is processed and evaluated by an accredited National Voluntary Laboratory Accreditation Program (NVLAP). For permanent radiographic installations where other appropriate alarming or warning devices are in routine use, the wearing of an alarm ratemeter is not required.
	(2)	Pocket dosimeters or electronic personal dosimeters shall meet the criteria in ANSI N322-1977 and shall have a range of zero to at least 200 millirems. Electronic personal dosimeters may only be used in place of ion-chamber pocket dosimeters.
	(3)	Pocket dosimeters or electronic personal dosimeters shall be recharged at the start of each work shift.
	(4)	Pocket dosimeters or electronic personal dosimeters shall be read and exposures recorded at the beginning and at the end of each work shift, and before each recharging.
	(5)	If an individual’s pocket dosimeter is discharged beyond its range (i.e., goes “off scale”), or if the electronic personal dosimeter reads greater than 200 millirem (2 millisievert), and the possibility of radiation exposure cannot be ruled out as the cause, industrial radiographic operations by that individual shall cease and the individual’s film badge, OSL device, or TLD shall be within 24 hours sent for processing. The individual shall not return to work with sources of radiation until a determination of the radiation exposure has been made. This determination must be made by the RSO or the RSO’s designee. The results of this determination must be included in the exposure records maintained in accordance with 641—Chapter 40.
	(6)	Each individual monitoring device shall be assigned to and worn by only one individual.
	(7)	Film badges, OSL devices and TLDs must be replaced at least monthly.
	(8)	If an individual monitoring device is lost or damaged, the worker shall cease work immediately until a replacement individual monitoring device is provided and the exposure is calculated for the time period from issuance to loss or damage of the individual monitoring device. The results of the calculated exposure and the time period for which the individual monitoring device was lost or damaged must be included in the records maintained in 45.1(12)“c.”
	c. 	Records of pocket dosimeter readings of personnel exposures and yearly operability checks required in 45.1(12)“d” shall be maintained for three years by the licensee or registrant for agency inspection. If the dosimeter readings were used to determine external radiation dose (i.e., no TLD or film badge exposure records exist), the records shall be maintained for three years after they are recorded. Records of estimates of exposures as a result of off-scale personal direct reading dosimeters, or lost or damaged film badges, OSLs, or TLDs, shall be maintained until the agency terminates the license.
	d. 	Pocket dosimeters shall be checked for correct response to radiation at periods not to exceed one year. Acceptable dosimeters shall read within plus or minus 20 percent of the true radiation exposure. Records of this check shall be maintained for inspection by the agency for three years from the date of the event.
	e. 	Reports received from the film badge, OSL device or TLD processor shall be kept for inspection by the agency until the agency terminates the license.
	f. 	Each alarm ratemeter must:
	(1)	Be checked to ensure that the alarm functions properly (sounds) prior to use at the start of each shift. Records of alarm function checks shall be maintained for two years by the licensee or registrant for agency inspection;
	(2)	Be set to give an alarm signal at a preset dose rate of 500 mR/hr;
	(3)	Require special means to change the preset alarm function; and
	(4)	Be calibrated at periods not to exceed one year for correct response to radiation: Acceptable ratemeters must alarm within plus or minus 20 percent of the true radiation dose rate. Records of the alarming ratemeter calibrations shall be maintained for three years by the licensee or registrant for agency inspection.
	45.1(13) Supervision of radiographer’s assistant. Whenever a radiographer’s assistant uses radiographic exposure devices, sealed sources or associated equipment or conducts radiation surveys required by 45.2(5) or 45.3(7) to determine that the sealed source has returned to the shielded position after an exposure, the radiographer’s assistant shall be under the direct supervision of a radiographer instructor. The direct supervision must include:
	a. 	The radiographer’s physical presence at the site where the source(s) of radiation is being used;
	b. 	The availability of the radiographer to give immediate assistance if required; and
	c. 	The radiographer’s direct observation of the radiographer’s assistant’s performance of the operations referred to in this subrule.
	45.1(14) Access control.
	a. 	During each industrial radiographic operation, a radiographer or radiographer’s assistant shall maintain continuous, direct visual surveillance of the operation to protect against unauthorized entry into a restricted area, radiation area or high radiation area, except at permanent radiographic installations where all entryways are locked to protect against unauthorized or accidental entry and the requirements of 45.1(9) are met.
	b. 	Radiographic exposure devices shall not be left unattended except when in storage or physically secured against unauthorized removal.
	45.1(15) Posting.
	a. 	Notwithstanding any provisions in 641—subrule 40.62(1) areas in which radiography is being performed shall be conspicuously posted as required by 641—subrules 40.61(1) and 40.61(2).
	b. 	Whenever practicable, ropes or barriers shall be used in addition to appropriate signs to designate areas in accordance with 641—subrule 40.26(1) and to help prevent unauthorized entry.
	c. 	During pipeline industrial radiography operations, sufficient radiation signs and other barriers shall be posted to prevent unmonitored individuals from entering the radiation area.
	d. 	Notwithstanding the requirements of 45.1(15)“a,” a restricted area may be established in accordance with 641—subrule 40.26(1) and may be posted in accordance with 40.61(1) and 40.61(2), i.e., both signs may be posted at the same location at the boundary of the restricted area.
	45.1(16) Temporary job site requirements.
	a. 	Documents and records. Each licensee or registrant conducting industrial radiography at a temporary job site shall have the following records available at that site for inspection by the agency:
	(1)	Appropriate license or certificate of registration or equivalent document;
	(2)	The appropriate operating and emergency procedures;
	(3)	The applicable agency rules;
	(4)	Survey records required pursuant to 45.2(5)“d” and 45.3(7)“j” for the period of operation at the site;
	(5)	Daily pocket dosimeter records for the period of operation at the site;
	(6)	The daily alarming ratemeter records for the period of operation at the site; and
	(7)	The latest radiation survey instrument calibration and leak test records for specific devices and sealed sources in use at the site. Acceptable records include tags or labels which are affixed to the device or survey meter and decay charts for sources which have been manufactured within the last six months.
	b. 	Reserved.
	45.1(17) Specific requirements for radiographic personnel performing industrial radiography.
	a. 	At a job site, the following shall be supplied by the licensee or registrant:
	(1)	At least one operable, calibrated radiation survey instrument;
	(2)	A current whole body personnel monitor (TLD, OSL device or film badge) for each individual;
	(3)	An operable, calibrated pocket dosimeter with a range of 0 to 200 milliroentgens (5.16 × 10-5 C/kg) for each worker; and
	(4)	An operable, calibrated alarm ratemeter for each worker; and
	(5)	The appropriate barrier ropes and signs.
	b. 	Each radiographer at a job site shall possess a valid I.D. card.
	c. 	Each radiographer’s assistant at a job site shall possess a valid trainee status card issued by the agency.
	d. 	Industrial radiographic operations shall not be performed if any of the items in 45.1(17)“a,” “b,” and “c” are not available at the job site or are inoperable.
	e. 	No individual other than a radiographer or a radiographer’s assistant who is under the direct supervision of a radiographer trainer shall manipulate controls or operate equipment used in industrial radiographic operations.
	f. 	During an inspection by the agency, the agency inspector may terminate an operation if any of the items in 45.1(17)“a” are not available and operable or if the required number of radiographic personnel are not present. Operations shall not be resumed until such conditions are met.
	45.1(18) Notification of incidents.
	a. 	The agency shall be notified of thefts or losses of sources of radiation, overexposures, and excessive levels in accordance with 641—40.95(136C) and 40.97(136C).
	b. 	Each licensee or registrant shall submit a written report within 30 days to the agency whenever one of the following events occurs:
	(1)	The source assembly cannot be returned to the fully shielded position and properly secured;
	(2)	The source assembly becomes disconnected from the drive cable;
	(3)	The failure of any component (critical to safe operation of the radiographic exposure device) to properly perform its intended function; or
	(4)	An indicator on a radiation-producing machine fails to show that radiation is being produced or an exposure switch fails to terminate production of radiation when turned to the off position.
	c. 	The licensee or registrant shall include the following information in each report submitted in accordance with 45.1(18)“b”:
	(1)	A description of the equipment problem;
	(2)	Cause of each incident, if known;
	(3)	Manufacturer and model number of equipment involved in the incident;
	(4)	Location, time, and date of the incident;
	(5)	Actions taken to establish normal operations;
	(6)	Corrective actions taken or planned to prevent recurrence; and
	(7)	Names of personnel involved in the incident.
	45.1(19) Copies of operating and emergency procedures. Each licensee or registrant shall maintain a copy of current operating and emergency procedures until the agency terminates the license. Superseded material must be retained for three years after the change is made.
[ARC 8982B, IAB 8/11/10, effective 9/15/10]
641—45.2(136C) Radiation safety requirements for the use of radiation machines in industrial radiography.
	45.2(1) Locking of sources of radiation. The control panel of each radiation machine shall be equipped with a locking device that will prevent the unauthorized use of an X-ray system or the accidental production of radiation. The radiation machine shall be kept locked and the key removed at all times except when under the direct visual surveillance of a radiographer.
	45.2(2) Permanent storage precautions. Radiation machines shall be secured while in storage to prevent tampering or removal by unauthorized individuals.
	45.2(3) Requirements for radiation machines used in industrial radiographic operations.
	a. 	Equipment used in industrial radiographic operations involving radiation machines manufactured after January 1, 1992, shall be certified at the time of manufacture to meet the criteria set forth by ANSI N537-1976.
	b. 	The registrant’s name and city or town where the main business office is located shall be prominently displayed with a durable, clearly visible label(s) on all vehicles used to transport radiation machines for temporary job site use.
	45.2(4) Operating and emergency procedures.
	a. 	The registrant’s operating and emergency procedures shall include instructions in at least the following:
	(1)	Operation and safety instruction on the radiation machine(s) to be used;
	(2)	Methods and occasions for conducting radiation surveys;
	(3)	Methods for controlling access to radiographic areas;
	(4)	Methods and occasions for locking and securing sources of radiation;
	(5)	Personnel monitoring and the use of personnel monitoring equipment, including steps that must be taken immediately by radiography personnel in the event a pocket dosimeter is found to be off-scale;
	(6)	Minimizing exposure of individuals in the event of an accident;
	(7)	The procedure for notifying proper personnel in the event of an accident;
	(8)	Maintenance of records; and
	(9)	Inspection and maintenance of radiation machines.
	b. 	Each registrant shall provide, as a minimum, two radiographic personnel when radiation machines are used for any industrial radiography conducted other than at a permanent radiographic installation (shielded room, bay, or bunker). If one of the personnel is a radiographer’s assistant, the other shall be a radiographer trainer authorized by the certificate of registration.
	c. 	No individual other than a radiographer or a radiographer’s assistant who is under the direct supervision of a radiographer trainer shall manipulate controls or operate equipment used in industrial radiographic operations.
	d. 	Rescinded IAB 4/8/98, effective 7/1/98.
	45.2(5) Radiation surveys and survey records.
	a. 	No radiographic operation shall be conducted unless calibrated and operable radiation survey instrumentation, as described in 45.1(5), is available and used at each site where radiographic exposures are made.
	b. 	A physical radiation survey shall be made after each radiographic exposure using radiation machines to determine that the machine is “off.”
	c. 	All potential radiation areas where industrial radiographic operations are to be performed shall be posted in accordance with 45.1(15), based on calculated dose rates, before industrial radiographic operations begin. An area survey shall be performed during the first radiographic exposure to confirm that 45.1(15) requirements have been met and that unrestricted areas do not have radiation levels in excess of the limits specified in 641—subrule 40.26(1).
	d. 	Records shall be kept of the surveys required by 45.2(5)“b” and “c.” Such records shall be maintained for inspection by the agency for two years after completion of the survey. If the survey was used to determine an individual’s exposure, however, the records of the survey shall be maintained until the agency authorizes their disposition.
	45.2(6) Special requirements and exemptions for enclosed radiography.
	a. 	Systems for enclosed radiography, including shielded-room radiography and cabinet radiography, designed to allow admittance of individuals shall:
	(1)	Comply with all applicable requirements of this chapter and 641—subrule 40.26(1). If such a system is a certified cabinet X-ray system, it shall comply with all applicable requirements of this chapter and 21 CFR 1020.40.
	(2)	Be evaluated at intervals not to exceed one year to ensure compliance with the applicable requirements as specified in 641—subrule 40.26(1). Records of these evaluations shall be maintained for inspection by the agency for a period of three years after the evaluation.
	b. 	Certified and certifiable cabinet X-ray systems are exempt from the requirements of this chapter except that:
	(1)	Operating personnel must be provided with individual monitoring devices in accordance with the appropriate provisions of 641—40.37(136C).
	(2)	No registrant shall permit any individual to operate a cabinet X-ray system until such individual has received a copy of and instruction in the operating procedures for the unit and has demonstrated competence in its use. Records which demonstrate compliance with this subparagraph shall be maintained for inspection by the agency until disposition is authorized by the agency.
	(3)	Tests for proper operation of interlocks used to control entry to the high radiation area or alarm systems, where applicable, shall be conducted and recorded every three months. Records of these tests shall be maintained for agency inspection until disposal is authorized by the agency.
	(4)	The registrant shall perform an evaluation, at intervals not to exceed one year, to determine conformance with 641—subrule 40.26(1). If such a system is a certified cabinet X-ray system, it shall be evaluated at intervals not to exceed one year to determine conformance with 21 CFR 1020.40. Records of these evaluations shall be maintained for inspection by the agency for a period of two years after the evaluation.
	c. 	Certified cabinet X-ray systems shall be maintained in compliance with 21 CFR 1020.40 unless prior approval has been granted by the agency pursuant to 641—38.3(136C).
	45.2(7) Registration for industrial radiographic operations.
	a. 	Radiation machines used in industrial radiographic operations shall be registered in accordance with 641—Chapter 39.
	b. 	In addition to the registration requirements in 641—Chapter 39, an application for a certificate of registration shall include the following information:
	(1)	A schedule or description of the program for training radiographic personnel which specifies:
	1.	Initial training,
	2.	Periodic training,
	3.	On-the-job training, and
	4.	Methods to be used by the registrant to determine the knowledge, understanding, and ability of radiographic personnel to comply with agency rules, registration requirements, and the operating and emergency procedures of the applicant.
	(2)	Written operating and emergency procedures, including all items listed in Appendix D.
	(3)	A description of the internal inspection system or other management control to ensure that radiographic personnel follow registration provisions, rules of the agency, and the applicant’s operating and emergency procedures.
	(4)	A list of permanent radiographic installations and descriptions of permanent storage and use locations.
	(5)	A description of the organization of the industrial radiographic program, including delegations of authority and responsibility for operation of the radiation safety program.
	c. 	A certificate of registration will be issued if the requirements of 641—Chapter 39 and this subrule are met.
641—45.3(136C) Radiation safety requirements for use of sealed sources of radiation in industrial radiography.
	45.3(1) Limits on external radiation levels from storage containers and source changers. The maximum exposure rate limits for storage containers and source changers are 200 millirem (2 millisieverts) per hour at any exterior surface, and 10 millirem (0.1 millisievert) per hour at 1 meter from any exterior surface with the sealed source in the shielded position.
	45.3(2) Locking of sources of radiation.
	a. 	Each source of radiation shall be provided with a lock or lockable outer container designed to prevent unauthorized or accidental removal of the sealed source. Either the exposure device or its container must be kept locked and, if applicable, the key removed, at all times when not under the direct surveillance of a radiographer or a radiographer’s assistant except at permanent radiographic installations as stated in 45.1(14). Each sealed source storage container and source changer must have a lock or outer locked container designed to prevent unauthorized or accidental removal of the sealed source from its shielded position. Storage containers and source changers must be kept locked (and if the lock is a keyed lock, with the key removed at all times) when containing sealed sources except when the container is under the direct surveillance of a radiographer or radiographer’s assistant.
	b. 	Radiographic exposure devices, source changers, and storage containers, prior to being moved from one location to another and also prior to being secured at a given location, shall be locked and surveyed to ensure that the sealed source is in the shielded position.
	c. 	The sealed source shall be secured in its shielded position by locking the exposure device or securing the remote control each time the sealed source is returned to its shielded position. Then a survey shall be performed to determine that the sealed source is in the shielded position pursuant to 45.3(7)“b.”
	45.3(3) Storage precautions.
	a. 	Labeling, storage, and transportation.
	(1)	The licensee may not use a source changer or a container to store licensed material unless the source changer or the storage container has securely attached to it a durable, legible, and clearly visible label bearing the standard trefoil radiation caution symbol in conventional colors, i.e., magenta, purple or block on a yellow background, having a minimum diameter of 25 mm, and the wording: “CAUTION RADIOACTIVE MATERIAL, NOTIFY CIVIL AUTHORITIES (or name of company),” or “DANGER.”
	(2)	The licensee may not transport licensed material unless the material is packaged, and the package is labeled, marked, and accompanied with appropriate shipping papers in accordance with 641—39.5(136C).
	(3)	Locked radiographic exposure devices and storage containers must be physically secured to prevent tampering or removal by unauthorized personnel. The licensee shall store licensed material in a manner which will minimize danger from explosion or fire.
	(4)	The licensee shall lock and physically secure the transport package containing licensed material in the transporting vehicle to prevent accidental loss, tampering, or unauthorized removal of the licensed material from the vehicle.
	b. 	Radiographic exposure devices, source changers, or storage containers that contain radioactive material shall not be stored in residential locations. This requirement does not apply to storage of radioactive material in a vehicle in transit for use at temporary job sites, if the licensee complies with 45.3(3)“c,” and if the vehicle does not constitute a permanent storage location as described in 45.1(9).
	c. 	If a vehicle is to be used for storage of radioactive material, a vehicle survey shall be performed after securing radioactive material in the vehicle and before transport to ensure that radiation levels do not exceed the limits specified in 641—subrule 40.26(1) at the exterior surface of the vehicle.
	d. 	A storage or use location is permanent if radioactive material is stored at the location for more than 90 days and any one or more of the following applies to the location:
	(1)	Telephone service is established by the licensee;
	(2)	Industrial radiographic services are advertised for or from the location;
	(3)	Industrial radiographic operations are conducted at other sites due to arrangements made from the location.
	45.3(4) Performance requirements for radiography equipment. Equipment used in industrial radiographic operations must meet the following minimum criteria:
	a. 	Each radiographic exposure device, source assembly or sealed source, and all associated equipment must meet the requirements specified in American National Standard N432-1980 “Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography” (published as NBS Handbook 136, issued January 1981). This publication has been approved for incorporation by reference by the Director of the Federal Register in accordance with 5 U.S.C. 552(a) and 1 CFR Part 51. This publication may be purchased from the American National Standards Institute, Inc., 1430 Broadway, New York, New York 10018, telephone (212)642-4900. Copies of the document are available for inspection at the Iowa Department of Public Health, Bureau of Radiological Health, Lucas State Office Building, Des Moines, Iowa 50319.
	b. 	In addition to the requirements specified in paragraph “a” of this subrule, the following requirements apply to radiographic exposure devices, source changers, source assemblies, sealed sources, and associated equipment.
	(1)	Each radiographic exposure device must have attached to it by the user a durable, legible, clearly visible label bearing the:
	1.	Chemical symbol and mass number of the radionuclide in the device;
	2.	Activity and the date on which this activity was last measured;
	3.	Model number (or product code) and serial number of the sealed source;
	4.	Manufacturer’s identity of the sealed source; and
	5.	Licensee’s name, address, and telephone number.
	(2)	Radiographic exposure devices intended for use as Type B transport containers must meet the applicable requirements of 641—39.5(136C).
	(3)	Modification of any radiographic exposure devices, source changers, and source assemblies and associated equipment is prohibited, unless the design of any replacement component, including source holder, source assembly, controls or guide tubes would not compromise the design safety features of the system.
	c. 	In addition to the requirements specified in paragraphs “a” and “b” of this subrule, the following requirements apply to radiographic exposure devices, source assemblies, and associated equipment that allow the source to be moved out of the device for radiographic operation or source changing:
	(1)	The coupling between the source assembly and the control cable must be designed in such a manner that the source assembly will not become disconnected if cranked outside the guide tube. The coupling must be such that it cannot be unintentionally disconnected under normal and reasonably foreseeable abnormal conditions;
	(2)	The device must automatically secure the source assembly when it is cranked back into the fully shielded position within the device. This securing system may only be released by means of a deliberate operation on the exposure device;
	(3)	The outlet fittings, lock box, and drive cable fittings on each radiographic exposure device must be equipped with safety plugs or covers which must be installed during storage and transportation to protect the source assembly from water, mud, sand, or other foreign matter;
	(4)	Each sealed source or source assembly must have attached to it or engraved in it, a durable, legible, visible label with the words: “DANGER—RADIOACTIVE.” The label must not interfere with safe operation of the exposure device or associated equipment;
	(5)	The guide tube must be able to withstand a crushing test that closely approximates the crushing forces that are likely to be encountered during use, and be able to withstand a kinking resistance test that closely approximates the kinking forces that are likely to be encountered during use;
	(6)	Guide tubes must be used when moving the source out of the device;
	(7)	An exposure head or similar device designed to prevent the source assembly from passing out of the end of the guide tube must be attached to the outermost end of the guide tube during radiographic operations;
	(8)	The guide tube exposure head connection must be able to withstand the tensile test for control units specified in ANSI N432-1980;
	(9)	Source changers must provide a system for ensuring that the source will not be accidentally withdrawn from the changer when connecting or disconnecting the drive cable to or from a source assembly.
	d. 	All newly manufactured radiographic exposure devices and associated equipment acquired by licensees after January 10, 1992, must comply with the requirements of this subrule.
	e. 	All radiographic exposure devices and associated equipment in use after January 10, 1996, must comply with the requirements of this subrule.
	f. 	Notwithstanding the requirements of 45.3(4)“a,” equipment used in industrial radiographic operations need not comply with § 8.9.2(c) of the Endurance Test in American National Standards Institute N432-1980, if the prototype equipment has been tested using a torque value representative of the torque that an individual using the radiography equipment can realistically exert on the lever or crankshaft of the drive mechanism.
	g. 	Engineering analysis may be submitted by an applicant or licensee to demonstrate the applicability of previously performed testing on similar individual radiography equipment components. Upon review, the agency may find this an acceptable alternative to actual testing of the component pursuant to the above-referenced standard.
	45.3(5) Leak testing, repair, tagging, opening, modification, and replacement of sealed sources.
	a. 	The replacement of any sealed source fastened to or contained in a radiographic exposure device and leak testing, repair, tagging, opening, or any other modification of any sealed source shall be performed only by persons specifically authorized to do so by the agency, the U.S. Nuclear Regulatory Commission, or an agreement state.
	b. 	Leak testing requirements.
	(1)	Each licensee that uses a sealed source shall have the source tested for leakage at intervals not to exceed 6 months. The leak testing of the source must be performed using a method approved by this agency. The wipe sample should be taken from the nearest accessible point to the sealed source where contamination might accumulate. The wipe sample must be analyzed for radioactive contamination. The analysis must be capable of detecting the presence of 0.005 microcuries (185 Bq) of radioactive material on the test sample and must be performed by a person specifically authorized by this agency to perform the analysis.
	(2)	The licensee shall maintain records of the leak tests results for sealed sources and devices containing depleted uranium (DU). The results must be stated in units of microcuries (becquerels). The licensee shall retain each record for three years after it is made or until the source in storage is removed.
	(3)	Unless a sealed source is accompanied by a certificate from the transferor that shows that it has been leak tested within 6 months before the transfer, it may not be used by the licensee until tested for leakage. Sealed sources that are in storage and not in use do not require leak testing, but must be tested before use or transfer to another person if the interval of storage exceeds 6 months.
	c. 	Any test conducted under this subrule which reveals the presence of 0.005 microcuries (185 Bq) or more of removable radioactive material must be considered evidence that the sealed source is leaking. The licensee shall immediately withdraw from use the equipment involved and shall have it decontaminated and repaired or disposed of in accordance with agency rules. Within five days after obtaining the results of the test, the licensee shall file a report with the agency describing the equipment involved, the test results, and the corrective action taken.
	d. 	Each exposure device using DU shielding and an “S” tube configuration must be tested for DU contamination at intervals not to exceed 12 months. The analysis must be capable of detecting the presence of 0.005 microcuries (185 Bq) of radioactive material on the test sample and must be performed by a person specifically authorized by the agency to perform the analysis. Should such testing reveal the presence of 0.005 microcuries (185 Bq) or more of removable DU contamination, the exposure device must be removed from use until an evaluation of the wear on the S-tube has been made. Should the evaluation reveal that the S-tube is worn through, the device may not be used again. DU-shielded devices do not have to be tested for DU contamination while in storage and not in use. Before using or transferring such a device, however, the device must be tested for DU contamination if the interval of storage exceeds 12 months.
	e. 	Each radiographic exposure device shall have permanently attached to it a durable label which has, as a minimum, the instruction: “Danger—Radioactive Material—Do Not Handle—Notify Civil Authorities if Found.”
	45.3(6) Operating and emergency procedures.
	a. 	The licensee’s operating and emergency procedures shall include instructions in at least the following:
	(1)	Handling and use of sources of radiation to be employed such that no individual is likely to be exposed to radiation doses in excess of the limits established in 641—Chapter 40;
	(2)	Methods and occasions for conducting radiation surveys;
	(3)	Methods for controlling access to radiographic areas;
	(4)	Methods and occasions for locking and securing sources of radiation;
	(5)	Personnel monitoring and the use of personnel monitoring equipment, including steps that must be taken immediately by radiography personnel in the event a pocket dosimeter is found to be off-scale;
	(6)	Transportation to field locations, including packing of sources of radiation in the vehicles, posting of vehicles, and control of sources of radiation during transportation;
	(7)	Minimizing exposure of individuals in the event of an accident;
	(8)	The procedure for notifying proper personnel in the event of an accident;
	(9)	Maintenance of records;
	(10)	The inspection and maintenance of radiographic exposure devices, source changers, storage containers, and radiation machines;
	(11)	The procedure(s) for identifying and reporting defects and noncompliance in 10 CFR Part 21; and
	(12)	Source recovery procedure if the licensee will perform source recovery.
	b. 	Rescinded IAB 4/8/98, effective 7/1/98.
	c. 	Whenever radiography is performed at a location other than a permanent radiographic installation, the radiographer must be accompanied by at least one other qualified radiographer or a radiographer’s assistant. If one of the personnel is a radiographer’s assistant, the other shall be a radiographer trainer authorized by the license. The additional qualified individual shall observe the operations and be capable of providing immediate assistance to prevent unauthorized entry. Radiography shall not be performed if only one qualified individual is present.
	d. 	Collimators shall be used in industrial radiographic operations which use crank-out devices except when physically impossible.
	e. 	All radiographic operations conducted at locations of use authorized on the license must be conducted in a permanent radiographic installation, unless specifically authorized by the agency.
	45.3(7) Radiation surveys and survey records.
	a. 	No radiographic operation shall be conducted unless calibrated and operable radiation survey instrumentation, as described in 45.1(5), is available and for each exposure device used at each site where radiographic exposures are made.
	b. 	A survey with a calibrated and operable radiation survey instrument shall be made after each radiographic exposure to determine that the sealed source has been returned to its shielded position. The entire circumference of the radiographic exposure device shall be surveyed. If the radiographic exposure device has a source guide tube, the survey shall also include the entire length of the guide tube and collimator. The survey required by this subrule must be done before exchanging films, repositioning the exposure head or dismantling the equipment.
	c. 	(1)	All potential radiation areas where industrial radiographic operations are to be performed shall be posted in accordance with 641—40.61(136C), based on calculated dose rates, before industrial radiographic operations begin. An area survey shall be performed during the first radiographic exposure (i.e., with the sealed source in the exposed position) to confirm that 641—40.61(136C) requirements have been met and that unrestricted areas do not have radiation levels in excess of the limits specified in 641—subrule 40.26(1).
	(2)	Each time the exposure device is relocated or the exposed position of the sealed source is changed, the requirements of 45.3(7)“c”(1) shall be met.
	(3)	The requirements of 45.3(7)“c”(2) do not apply to pipeline industrial radiographic operations when the conditions of exposure include, but are not limited to, the radiographic exposure device, duration of exposure, source strength, pipe size, and pipe thickness remain constant.
	d. 	A lock-out survey, in which all accessible surfaces of the radiographic exposure device or source changer are surveyed, shall be made to determine that each sealed source is in its shielded position before securing the radiographic exposure device or source changer.
	e. 	The sealed source shall be secured in its shielded position by locking the radiographic exposure device or source changer each time the sealed source is returned to its shielded position.
	f. 	Each radiographic exposure device and source changer shall be locked and the key removed from any keyed lock prior to being moved or transported from one location to another and also prior to being stored at a given location.
	g. 	If a vehicle is to be used for storage of radioactive material, a vehicle survey shall be performed after securing radioactive material in the vehicle and before transport to ensure that radiation levels do not exceed the limits specified in 641—subrule 40.26(1) at the exterior surface of the vehicle.
	h. 	Surveys shall be performed on storage containers to ensure that radiation levels do not exceed the limits specified in 641—40.15(136C). These surveys shall be performed initially with the maximum amount of radioactive material present in the storage location and thereafter at the time of the quarterly inventory and whenever storage conditions change.
	i. 	A survey meeting the requirements of 45.3(7)“b” shall be performed on the radiographic exposure device and the source changer after every sealed source exchange. A survey shall be made of the storage area as defined in 641—45.2(136C) whenever a radiographic exposure device is being placed in storage.
	j. 	Records shall be kept of the surveys required by 45.3(7)“c,” “d,” “g,” “h,” and “i.” Such records shall be maintained for inspection by the agency for two years after completion of the survey. If the survey was used to determine an individual’s exposure, however, the records of the survey shall be maintained until the agency authorizes their disposition.
	45.3(8) Requirements for enclosed radiography.
	a. 	Systems for enclosed radiography, including shielded-room radiography designed to allow admittance of individuals shall comply with all applicable requirements of this chapter.
	b. 	Procedures shall be evaluated at intervals not to exceed one year to ensure compliance with the applicable requirements as specified in 641—subrule 40.26(1). Records of these evaluations shall be maintained for inspection by the agency for a period of two years after the evaluation.
	c. 	Tests for proper operation of high radiation area control devices or alarm systems, where applicable, shall be conducted, recorded, and maintained in accordance with 45.1(9)“b.”
	45.3(9) Underwater, offshore platform, and lay-barge radiography.
	a. 	Underwater, offshore platform, or lay-barge radiography shall not be performed unless specifically authorized in a license issued by the agency in accordance with 641—paragraph 39.4(27)“e.”
	b. 	In addition to the other rules of this chapter, the following rules apply to the performance of lay-barge or offshore platform radiography:
	(1)	Cobalt-60 sources with activities in excess of 20 curies (nominal) and iridium-192 sources with activities in excess of 100 curies (nominal) shall not be used in the performance of lay-barge or offshore platform industrial radiography.
	(2)	Collimators shall be used for all industrial radiographic operations performed on lay-barge or offshore platforms.
	45.3(10) Prohibitions. Industrial radiography performed with a sealed source which is not fastened to or contained in a radiographic exposure device (fishpole technique) is prohibited unless specifically authorized in a license issued by the agency.
	45.3(11) Licensing for industrial radiographic operations. Rescinded IAB 4/5/00, effective 5/10/00.
641—45.4(136C) Radiation safety requirements for the use of particle accelerators for nonhuman use.
	45.4(1) Purpose and scope.
	a. 	This rule establishes procedures for the registration or licensing and the use of particle accelerators.
	b. 	Unless specifically required otherwise by this rule, all registrants or licensees performing operations with a particle accelerator are subject to the requirements of 641—Chapters 38 to 40 and 641—45.1(136C).
	c. 	The requirements of 45.1(10)“b”(2) and (3) and 45.1(10)“d”(1)“2” do not apply to nonradiographic uses.
	45.4(2) Definitions. For purposes of this subrule, definitions in 641—Chapters 38 and 40 and subrule 45.1(2) may also apply. As used in this rule, the following definitions apply:
“Cold pasteurization” means the process of using radiation for destroying disease-causing microorganisms in commercial products.
“Self-shielded particle accelerator” means a particle accelerator with the accelerator installed in an enclosure independent of the existing architectural structures except the floor on which it may be placed. The enclosure must have been evaluated by a qualified expert and that evaluation approved by an appropriate regulatory authority through a device evaluation. The self-shielded accelerator is intended to contain at least that portion of material being irradiated, provide radiation attenuation, and exclude personnel from its interior during generation of radiation. A particle accelerator used within a shielded part of a building, or which may temporarily or occasionally incorporate portable shielding, is not a self-shielded particle accelerator.
“Shielded facility” means an accelerator facility where shielding is required to be constructed on site in order to assure compliance with the requirements of 641—Chapter 40, or where shielding supplied with the accelerator has been evaluated by qualified experts and that evaluation approved by an appropriate regulatory authority through a device evaluation.
	45.4(3) Registration or license requirements. No person shall receive, possess, use, transfer, own, or acquire a particle accelerator except as authorized in a registration or license issued pursuant to 641—39.1(136C) to 39.4(136C) and the following requirements:
	a. 	Accelerator facilities whose operations result in nuclear transformations that produce or are likely to produce radioactive material more than the exempt quantities and concentrations listed in Appendices A and B of 641—Chapter 39 shall be authorized by the issuance of a radioactive material license in accordance with 641—Chapter 39. Accelerator facilities that produce or are likely to produce radioactive material less than the exempt quantities and concentrations shall be authorized by registration.
	b. 	For accelerator facilities required to be licensed in accordance with 45.4(3), those operations that would require personnel monitoring, pursuant to 641—40.37(136C), due to the presence of radioactive material, shall be performed only by a specific licensee. Such operations would normally include installation, testing and maintenance as well as routine operations.
	45.4(4) General requirements for the issuance of a registration or license for particle accelerators. Along with the requirements of 641—39.1(136C) to 39.4(136C), an application for use of a particle accelerator will be approved only if the agency determines that:
	a. 	The applicant is qualified by reason of training and experience to use the accelerator in question for the purpose requested in accordance with this rule and 641—Chapter 40 in such a manner as to minimize danger to public health and safety or property;
	b. 	The applicant’s proposed or existing equipment, facilities, and operating and emergency procedures are adequate to protect health and minimize danger to public health and safety or property;
	c. 	The issuance of the registration or license will not be inimical to the health and safety of the public, and the applicant satisfies any applicable special requirement in 45.4(4);
	d. 	The applicant has appointed a radiation safety officer responsible for the day-to-day operation of the radiation safety program;
	e. 	The applicant and the applicant’s staff have experience in the use of particle accelerators and training sufficient for application to its intended uses;
	f. 	The applicant has an adequate training program for operators of particle accelerators.
	45.4(5) Personnel monitoring. In addition to the requirements of 641—Chapter 40, personnel monitoring shall be provided to and used by all individuals entering any area for which interlocks are required unless a survey of the area has determined that radiation levels are below that of a high radiation area; and
	a. 	Power to an accelerator cannot be activated; or
	b. 	An accelerated beam cannot be directed to the area.
	45.4(6) Operations.
	a. 	No registrant shall permit any individual to act as an operator of a particle accelerator until such individual:
	(1)	Has been instructed in radiation safety and shall have demonstrated an understanding thereof;
	(2)	Has received copies of and instruction in this rule and the applicable requirements of 641—Chapter 40, pertinent registration and the registrant’s operating and emergency procedures, and shall have demonstrated understanding thereof; and
	(3)	Has demonstrated competence to use the particle accelerator, related equipment, and survey instruments which will be employed.
	b. 	The radiation safety officer or radiation safety committee, if applicable, shall have the authority to terminate the operations at a particle accelerator facility if such action is deemed necessary to minimize danger to public health and safety or property.
	c. 	Along with the audit required in 641—subrule 40.10(3), each operator’s performance during an actual accelerator operation shall be audited by the radiation safety officer or designee at intervals not to exceed six months. If an operator has not participated in an accelerator operation for more than six months since the last audit, the individual’s performance shall be observed and recorded at the first opportunity the individual participates in an accelerator operation. Records of the audits shall be maintained by the registrant for the agency inspection for three years from the date of the audit.
	d. 	Operators of particle accelerators used for industrial radiography shall meet the requirements of 45.1(10).
	45.4(7) Shielding and safety design requirements.
	a. 	A qualified expert acceptable to the agency shall be consulted in the design of a particle accelerator installation and called upon to perform a radiation survey when the accelerator is first capable of producing radiation.
	b. 	Each particle accelerator installation shall be provided with such primary and secondary barriers as are necessary to ensure compliance with 641—40.15(136C) and 641—40.26(136C).
	c. 	In addition to the requirements of 45.4(8)“a” and “b,” shielded facilities or self-shielded particle accelerators shall meet the following requirements:
	(1)	Authorization, by issuance of a construction permit, shall be granted upon a determination of adequacy being made pursuant to the review of an initial application of the shielding design, physical plant, and site specifications, and of the applicant’s proposed equipment, uses and workloads. For a shielded facility, the applicant shall submit an evaluation of the shielding design by a qualified expert. For a self-shielded particle accelerator, the applicant need not submit an evaluation of a shielding design if an evaluation by an appropriate regulatory authority has been performed. The applicant may instead reference this evaluation. The applicant shall maintain a copy of the evaluation of shielding design for agency review.
	(2)	Authorization for installation and testing of an accelerator shall be given only after a determination of adequacy of testing protocols, testing safety procedures, staff training, and radiation detection instrumentation has been made; and
	(3)	Operational use of an accelerator shall be authorized only after determination of adequacy of the items listed in 45.4(4) has been made by the agency.
	45.4(8) Particle accelerator controls and interlock systems.
	a. 	Instrumentation, readouts, and controls on the particle accelerator control console shall be clearly identified, easily discernible and located outside the high radiation area.
	b. 	Each entrance into a target area or other high radiation area shall be provided with two safety interlocks that shut down the machine when the barrier is breached.
	c. 	Each safety interlock shall be on a circuit that allows it to operate independently of all other safety interlocks.
	d. 	All safety interlocks shall be designed so that any defect or component failure in the safety interlock system prevents operation of the accelerator.
	e. 	When a safety interlock system has been tripped, it shall only be possible to resume operation of the accelerator by manually resetting controls at the position where the safety interlock has been tripped and, lastly, at the main control console.
	f. 	A scram button or other emergency power cutoff switch shall be located and easily identifiable in all high radiation areas. Such a cutoff switch shall include a manual reset so that the accelerator cannot be restarted from the accelerator control console without resetting the cutoff switch.
	45.4(9) Warning devices.
	a. 	Each location designated as a high radiation area, and each entrance to such location, shall be equipped with easily observable warning lights that operate when, and only when, radiation is being produced.
	b. 	Each high radiation area shall have an audible warning device that shall be activated for 15 seconds prior to the possible creation of such high radiation area. Such warning device shall be clearly discernible in all high radiation areas.
	c. 	Barriers, temporary or otherwise, and pathways leading to high radiation areas shall be posted in accordance with 641—40.61(136C).
	45.4(10) Operating and emergency procedures.
	a. 	Particle accelerators, when not in operation, shall be secured to prevent unauthorized use.
	b. 	The safety interlock system shall not be used to turn off the accelerator beam except in an emergency.
	c. 	All safety and warning devices, including interlocks, shall be checked for proper operation intervals not to exceed three months. Results of such tests shall be maintained at the accelerator facility for inspection by the agency for three years.
	d. 	All incidents in which the interlock system fails to operate properly or where the operation is terminated by the interlock system shall be investigated and reported to the radiation safety officer or, if applicable, the radiation safety committee. Documentation shall be maintained for inspection by the agency for three years.
	e. 	If, for any reason, it is necessary to intentionally bypass a safety interlock or interlocks, such action shall be:
	(1)	Authorized by the radiation safety officer and, if applicable, the radiation safety committee;
	(2)	Recorded in a permanent log and a notice posted at the accelerator control console; and
	(3)	Terminated as soon as possible.
	f. 	The registrant’s operating and emergency procedures shall include the following:
	(1)	Operation and safety instructions on the accelerator(s) to be used;
	(2)	Methods for controlling access to restricted areas;
	(3)	Methods and occasions for locking and securing sources of radiation;
	(4)	Use of personnel monitoring equipment;
	(5)	The procedure for notifying proper personnel in the event of an accident;
	(6)	Maintenance of records;
	(7)	Inspections and maintenance of the accelerator; and
	(8)	Steps to be taken in the case of an emergency.
	g. 	A copy of the current operating and emergency procedures shall be maintained at the accelerator control panel.
	45.4(11) Radiation monitoring requirements.
	a. 	A radiation protection survey shall be performed and documented by a qualified expert, acceptable to the agency, when changes have been made in shielding, operation, equipment, or occupancy of adjacent areas.
	b. 	Accelerator facilities shall survey with a radiation detection instrument at intervals not to exceed 12 months. Records of this survey shall be maintained for agency review for three years.
	c. 	Accelerator facilities registered or licensed pursuant to 45.4(3)“a” shall survey for removable contamination at intervals not to exceed six months to determine the degree of contamination.
	d. 	Each time removable shields on self-shielded particle accelerators are opened, a visual survey of the shielding must be performed to observe physical damage. In addition, when these shields are returned to the closed position, a physical radiation survey shall be conducted upon initial reactivating of the accelerator. Records of this survey shall be maintained for agency review for three years.
	e. 	Accelerator facilities registered or licensed pursuant to 45.4(3)“a” shall perform a survey with a radiation detection instrument and surveys for removable contamination before maintenance or servicing of its particle accelerator(s) or associated equipment located in the high radiation area.
	f. 	Radiation levels in all high radiation areas shall be continuously monitored. The monitoring devices shall be electrically independent of the accelerator control and safety interlock systems and capable of providing a readout at the control panel.
	g. 	Upon installation, all area monitoring equipment shall be tested to assure proper operation under operating conditions of the particle accelerator. All area monitors shall be calibrated at intervals not to exceed one year and after each servicing and repair.
	h. 	Whenever applicable, accelerator facilities registered or licensed pursuant to 45.4(3)“a” shall perform surveys at intervals not to exceed six months to determine the amount of airborne particulate radioactivity present.
	i. 	All surveys shall be made in accordance with the written procedures established by the radiation safety officer or a qualified expert who is acceptable to the agency.
	j. 	Records of all radiation protection surveys, calibrations, and instrumentation tests shall be maintained at the accelerator facility for inspection by the agency.
	45.4(12) Radiation safety officer.
	a. 	Each registrant shall appoint a radiation safety officer that meets the following requirements:
	(1)	Possesses a high school diploma or a certificate of high school equivalency based on the GED test;
	(2)	Documents two years of radiation protection experience.
	b. 	The specific duties of the RSO include, but are not limited to, the following:
	(1)	To establish and oversee operating, emergency, and ALARA procedures and to review them regularly to ensure that the procedures are current and conform with these rules;
	(2)	To oversee and approve all phases of the training program for accelerator operators so that appropriate and effective radiation protection practices are taught;
	(3)	To ensure that required radiation surveys are performed and documented in accordance with these rules, including any corrective measures when levels of radiation exceed established limits;
	(4)	To ensure that personnel monitoring devices are calibrated and used properly by occupationally exposed personnel, that records are kept of the monitoring results, and that timely notifications are made as required by 641—Chapter 40;
	(5)	To ensure that any required interlock switches and warning signals are functioning and that radiation signs, ropes, and barriers are properly posted and positioned;
	(6)	To investigate and report to the agency each known or suspected case of radiation exposure to an individual or radiation level detected in excess of limits established by these rules and each theft or loss of source(s) of radiation, to determine the cause, and to take steps to prevent its recurrence;
	(7)	To have a thorough knowledge of management policies and administrative procedures of the licensee or registrant;
	(8)	To assume control and have the authority to institute corrective actions including shutdown of operations when necessary in emergency situations or unsafe conditions;
	(9)	To maintain records as required by these rules;
	(10)	To ensure the proper storing, labeling, and use of the accelerator;
	(11)	To ensure that inspection and maintenance programs are performed in accordance with 45.1(6), 45.1(8), 45.4(10)“c”; and
	(12)	To ensure that personnel are complying with these rules and the operating and emergency procedures of the registrant.
641—45.5(136C) Radiation safety requirements for analytical X-ray equipment.
	45.5(1) Purpose and scope. This rule provides special requirements for analytical X-ray equipment. The requirements of this rule are in addition to, and not in substitution for, 641—Chapters 38, 39, and 40. The requirements of rules 641—45.1(136C) to 641—45.4(136C) do not apply.
	45.5(2) Definitions. For the purpose of this subrule, definitions in 641—Chapter 38 may also apply. As used in this rule, the following definitions apply:
“Analytical X-ray equipment” means equipment used for X-ray diffraction or fluorescence analysis.
“Analytical X-ray system” means a group of components utilizing X-rays or gamma rays to determine the elemental composition or to examine the microstructure of materials.
“Fail-safe characteristics” means a design feature which causes beam port shutters to close, or otherwise prevents emergence of the primary beam, upon the failure of a safety or warning device.
“Local components” means part of an analytical X-ray system and includes X-ray areas that are struck by X-rays such as radiation source housings, port and shutter assemblies, collimators, sample holders, cameras, goniometers, detectors, and shielding, but does not include power supplies, transformers, amplifiers, readout devices, and control panels.
“Normal operating procedures” means step-by-step instructions necessary to accomplish the analysis. These procedures shall include sample insertion and manipulation, equipment alignment, routine maintenance by the registrant or licensee, and data recording procedures, which are related to radiation safety.
“Open-beam configuration” means an analytical X-ray system in which an individual could accidentally place some part of his body in the primary beam path during normal operation.
“Primary beam” means radiation which passes through an aperture of the source housing by a direct path from the X-ray tube or a radioactive source located in the radiation source housing.
	45.5(3) Equipment requirements.
	a. 	Safety device. A device which prevents the entry of any portion of an individual’s body into the primary X-ray beam path or which causes the beam to be shut off upon entry into its path shall be provided on all open-beam configurations. A registrant or licensee may apply to the agency for an exemption from the requirement of a safety device. Such application shall include:
	(1)	A description of the various safety devices that have been evaluated;
	(2)	The reason each of these devices cannot be used; and
	(3)	A description of the alternative methods that will be employed to minimize the possibility of an accidental exposure, including procedures to ensure that operators and others in the area will be informed of the absence of safety devices.
	b. 	Warning devices.
	(1)	Open-beam configurations shall be provided with a readily discernible indication of:
	1.	X-ray tube “on-off” status located near the radiation source housing, if the primary beam is controlled in this manner; or
	2.	Shutter “open-closed” status located near each port on the radiation source housing, if the primary beam is controlled in this manner.
	(2)	An easily visible warning light labeled with the words “X-RAY ON,” or words having a similar intent, shall be located:
	1.	Near any switch that energizes an X-ray tube and shall be illuminated only when the tube is energized; or
	2.	In the case of a radioactive source, near any switch that opens a housing shutter and shall be illuminated only when the shutter is open.
	(3)	Warning devices shall be labeled so that their purpose is easily identified. On equipment installed after the effective date of these rules, warning devices shall have fail-safe characteristics.
	c. 	Ports. Unused ports on radiation source housings shall be secured in the closed position in a manner which will prevent casual opening.
	d. 	Labeling. All analytical X-ray equipment shall be labeled with a readily discernible sign or signs bearing the radiation symbol and the words:
	(1)	“CAUTION—HIGH INTENSITY X-RAY BEAM,” or words having a similar intent, on the X-ray source housing; and
	(2)	“CAUTION—RADIATION—THIS EQUIPMENT PRODUCES RADIATION WHEN ENERGIZED,” or words having a similar intent, near any switch that energizes an X-ray tube if the radiation source is an X-ray tube; or
	(3)	“CAUTION—RADIOACTIVE MATERIAL,” or words having a similar intent, on the source housing in accordance with 641—40.63(136C) if the radiation source is a radionuclide.
	e. 	Shutters. On open-beam configurations, each port on the radiation source housing shall be equipped with a shutter that cannot be opened unless a collimator or a coupling has been connected to the port.
	f. 	Radiation source housing. Each radiation source housing shall be subject to the following requirements:
	(1)	Each X-ray tube housing shall be equipped with an interlock that shuts off the tube if it is removed from the radiation source housing or if the housing is disassembled.
	(2)	Each radioactive source housing or port cover or each X-ray tube housing shall be so constructed that, with all shutters closed, the radiation measured at a distance of 5 centimeters from its surface is not capable of producing a dose in excess of 2.5 millirems (0.025 mSv) in one hour. For systems utilizing X-ray tubes, this limit shall be met at any specified tube rating.
	g. 	Generator cabinet. Each X-ray generator shall be supplied with a protective cabinet which limits leakage radiation measured at a distance of 5 centimeters from its surface such that it is not capable of producing a dose in excess of 0.25 millirem (2.5 mSv) in one hour.
	45.5(4) Area requirements.
	a. 	Radiation levels. The local components of an analytical X-ray system shall be located and arranged and shall include sufficient shielding or access control such that no radiation levels exist in any area surrounding the local component group which could result in a dose to an individual present therein in excess of the dose limits given in 641—40.26(136C). For systems utilizing X-ray tubes, these levels shall be met at any specified tube rating.
	b. 	Surveys.
	(1)	Radiation surveys, as required by 641—40.36(136C), of all analytical X-ray systems sufficient to show compliance with 45.5(4)“a” shall be performed:
	1.	Upon installation of the equipment, and at least once every 12 months thereafter;
	2.	Following any change in the initial arrangement, number, or type of local components in the system;
	3.	Following any maintenance requiring the disassembly or removal of a local component in the system;
	4.	During the performance of maintenance and alignment procedures if the procedures require the presence of a primary X-ray beam when any local component in the system is disassembled or removed;
	5.	Anytime a visual inspection of the local components in the system reveals an abnormal condition; and
	6.	Whenever personnel monitoring devices show a significant increase over the previous monitoring period or the readings are approaching the limits specified in 641—40.15(136C).
	(2)	Radiation survey measurements shall not be required if a registrant or licensee can demonstrate compliance with 45.5(4)“a” to the satisfaction of the agency.
	c. 	Posting. Each area or room containing analytical X-ray equipment shall be conspicuously posted with a sign or signs bearing the radiation symbol and the words “CAUTION—X-RAY EQUIPMENT” or words having a similar intent in accordance with 641—subrule 40.61(1).
	45.5(5) Operating requirements.
	a. 	Procedures. Normal operating procedures shall be written and available to all analytical X-ray equipment workers. No individual shall be permitted to operate analytical X-ray equipment in any manner other than that specified in the procedures unless such individual has obtained written approval of the radiation safety officer.
	b. 	Bypassing. No individual shall bypass a safety device or interlock unless such individual has obtained the approval of the radiation safety officer. Such approval shall be for a specified period of time. When a safety device or interlock has been bypassed, a readily discernible sign bearing the words “SAFETY DEVICE NOT WORKING,” or words having a similar intent, shall be placed on the radiation source housing.
	c. 	Repair or modification of X-ray tube systems. Except as specified in 45.5(5)“b,” no operation involving removal of covers, shielding materials or tube housings or modifications to shutters, collimators, or beam stops shall be performed without ascertaining that the tube is off and will remain off until safe conditions have been restored. The main switch, rather than interlocks, shall be used for routine shutdown in preparation for repairs.
	d. 	Radioactive source replacement, testing, or repair. Radioactive source housings shall be opened for source replacement, leak testing, or other maintenance or repair procedures only by individuals authorized to specifically conduct such procedures under a license issued by the U.S. Nuclear Regulatory Commission, an agreement state, or a licensing state.
	45.5(6) Personnel requirements.
	a. 	Instruction. No individual shall be permitted to operate or maintain analytical X-ray equipment unless such individual has received instruction in and demonstrated competence as to:
	(1)	Identification of radiation hazards associated with the use of the equipment;
	(2)	Significance of the various radiation warnings, safety devices, and interlocks incorporated into the equipment, or the reasons they have not been installed on certain pieces of equipment and the extra precautions required in such cases;
	(3)	Proper operating procedures for the equipment;
	(4)	Recognition of symptoms of an acute localized exposure; and
	(5)	Proper procedures for reporting an actual or suspected exposure.
	b. 	Personnel monitoring.
	(1)	Finger or wrist dosimetry devices shall be provided to and shall be used by:
	1.	Analytical X-ray equipment workers using systems having an open-beam configuration and not equipped with a safety device; and
	2.	Personnel maintaining analytical X-ray equipment if the maintenance procedures require the presence of a primary X-ray beam when any local component in the analytical X-ray system is disassembled or removed.
	(2)	Reported dose values shall not be used for the purpose of determining compliance with 641—subrule 40.2(1) unless evaluated by a qualified expert.
641—45.6(136C) Radiation safety requirements for well-logging, wireline service operations and subsurface tracer studies.
	45.6(1) Purpose. This rule establishes radiation safety requirements for using sources of radiation for wireline service operations including mineral-logging, radioactive markers, and subsurface tracer studies. The requirements of this rule are in addition to, and not in substitution for, the requirements of 641—Chapters 38, 39, and 40. The requirements of 641—45.1(136C) to 641—45.5(136C) do not apply.
	45.6(2) Scope. This rule applies to all licensees or registrants who use sources of radiation for wireline service operations including mineral-logging, radioactive markers, or subsurface tracer studies.
	45.6(3) Definitions. For the purpose of this subrule, the definitions of 641—Chapter 38 may also apply. As used in this rule, the following definitions apply:
“Energy compensation source (ECS)” means a small sealed source, with an activity not exceeding 3.7 MBq (100 microcuries), used within a logging tool, or other tool components, to provide a reference standard to maintain the tool’s calibration when in use.
“Fresh water aquifer” means a geologic formation that is capable of yielding fresh water to a well or spring.
“Injection tool” means a device used for controlled subsurface injection of radioactive tracer material.
“Logging assistant” means any individual who, under the direct 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 45.6(22).
“Logging supervisor” means the individual who uses licensed material or provides direct supervision in the use of licensed material at a temporary job site and who is responsible to the licensee for ensuring compliance with the requirements of these rules and the conditions of the license.
“Logging tool” means a device used subsurface to perform well-logging.
“Personal supervision” means guidance and instruction by the logging supervisor who is physically present at the temporary job site, who is in personal contact with logging assistants, and who can give immediate assistance.
“Radioactive marker” means licensed material used for depth determination or direction orientation. For purposes of this rule, this term includes radioactive collar markers and radioactive iron nails.
“Safety review” means a periodic review on radiation safety aspects of well-logging provided by the licensee for its employees. The review may include, as appropriate, the results of internal inspections, new procedures or equipment, accidents or errors that have been observed, and opportunities for employees to ask safety questions.
“Source holder” means a housing or assembly into which a sealed source is placed to facilitate the handling and use of the source in well-logging operations.
“Subsurface tracer study” means the release of unsealed licensed material or a substance labeled with licensed material in a single well for the purpose of tracing the movement or position of the material or substance in the well or adjacent formation.
“Surface casing” for protecting fresh water aquifers means a pipe or tube used as a lining in a well to isolate fresh water aquifers from the well.
“Temporary job site” means a place where licensed materials are present for the purpose of performing well-logging or subsurface tracer studies.
“Tritium neutron generator target source” means a tritium source used within a neutron generator tube to produce neutrons for use in well-logging applications.
“Uranium sinker bar” means a weight containing depleted uranium used to pull a logging tool down toward the bottom of a well.
“Well” means a drilled hole in which well-logging may be performed. As used in this rule, “well” includes drilled holes for the purpose of oil, gas, mineral, groundwater, or geological exploration.
“Well-logging” means all operations involving the lowering and raising of measuring devices or tools which may contain licensed material or are used to detect licensed materials in wells for the purpose of obtaining information about the well or adjacent formations and which may be used in oil, gas, mineral, groundwater, or geological exploration.
“Wireline” means a cable containing one or more electrical conductors which is used to lower and raise logging tools in the well-bore.
“Wireline service operation” means any evaluation or mechanical service which is performed in the well-bore using devices on a wireline.
	45.6(4) Agreement with well owner or operator.
	a. 	A licensee may perform well-logging with a sealed source only after the licensee has a written agreement with the employing well owner or operator. This written agreement must identify who will meet the following requirements:
	(1)	If a sealed source becomes lodged in the well, a reasonable effort will be made to recover it;
	(2)	A person may not attempt to recover a sealed source in a manner which, in the licensee’s opinion, could result in its rupture;
	(3)	The radiation monitoring required in 45.6(8) and 45.6(17) will be performed;
	(4)	If the environment, any equipment, or personnel are contaminated with licensed material, they must be decontaminated before release from the site or release for unrestricted use; and
	(5)	If the sealed source is classified as irretrievable after reasonable efforts at recovery have been expended, the following requirements must be implemented within 30 days:
	1.	Each irretrievable well-logging source must be immobilized and sealed in place with a cement plug;
	2.	There must be a means to prevent inadvertent intrusion on the source, unless the source is not accessible to any subsequent drilling operations; and
	3.	A permanent identification plaque, constructed of long-lasting material, such as stainless steel, brass, bronze, or Monel, must be mounted at the surface of the well, unless the mounting of the plaque is not practical. The size of the plaque must be at least 17 cm (7 inches) square and 3 mm (1/8-inch) thick. The plaque must contain:
	●	The word “Caution”;
	●	The radiation symbol (the color requirement in 641— 40.60(136C) need not be met);
	●	The date the source was abandoned;
	●	The name of the well owner or well operator, as appropriate;
	●	The well name and well identification number(s) or other designation;
	●	An identification of the sealed source(s) by radionuclide and quantity;
	●	The depth of the source and depth to the top of the plug; and
	●	An appropriate warning such as, “Do not reenter this well.”
	b. 	The licensee shall retain a copy of the written agreement for three years after the completion of the well-logging operation.
	c. 	A licensee may apply, pursuant to 641—38.3(136C), for agency approval, on a case-by-case basis, of proposed procedures to abandon an irretrievable well-logging source in a manner not otherwise authorized in 45.6(26)“a”(5).
	d. 	A written agreement between the licensee and the well owner or operator is not required if the licensee and the well owner or operator are part of the same corporate structure or otherwise similarly affiliated. However, the licensee shall still otherwise meet the requirements in 45.6(26)“a”(1) through (5).
	45.6(5) Limits on levels of radiation. Sources of radiation shall be used, stored, and transported in such a manner that the transportation requirements of 641—39.5(136C) and the dose limitation requirements of 641—Chapter 40 are met.
	45.6(6) Storage precautions.
	a. 	Each source of radiation 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.
	b. 	Sources of radiation shall be stored in a manner which will minimize danger from explosion or fire.
	45.6(7) Transport precautions. Transport containers shall be physically secured to the transporting vehicle to prevent accidental loss, tampering, or unauthorized removal.
	45.6(8) Radiation survey instruments.
	a. 	The licensee or registrant shall maintain sufficient calibrated and operable radiation survey instruments at each field station to make physical radiation surveys as required by this subrule and by 641—40.36(136C). Instrumentation shall be capable of measuring 0.1 milliroentgen (25.8 nanocoulombs/kg) per hour through at least 50 milliroentgens (12.9 microcoulombs/kg) per hour.
	b. 	Each radiation survey instrument shall be calibrated:
	(1)	At intervals not to exceed six months and after each instrument servicing;
	(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
	(3)	So that accuracy within 20 percent of the true radiation level can be demonstrated on each scale.
	c. 	Calibration records shall be maintained for a period of two years for inspection by the agency.
	45.6(9) Leak testing of sealed sources.
	a. 	Testing and record-keeping requirements. Each licensee using sealed sources of radioactive material shall have the sources tested for leakage periodically. Records of leak test results shall be kept in units of microcuries (Bq) and maintained for three years after the leak test is performed.
	b. 	Method of testing. Tests for leakage shall be performed only by persons specifically authorized to perform such tests by the NRC, an agreement state, or a licensing state. The wipe of a sealed source must be performed using a leak test kit or method approved by the NRC, an agreement state, or a licensing state. The wipe sample must be taken from the nearest assessable point to the sealed source where contamination might accumulate. The test sample shall be analyzed for radioactive contamination, and the analysis shall be capable of detecting the presence of 0.005 microcurie (185 Bq) of radioactive material on the test sample.
	c. 	Interval of testing.
	(1)	Each sealed source of radioactive material (except an energy compensation source (ECS)) shall be tested at intervals not to exceed six months. In the absence of a certificate from a transferor indicating that a test has been made six months prior to the transfer, the sealed source shall not be put into use until tested. 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.
	(2)	Each ECS that is not exempt from testing in accordance with 45.6(9)“c”(1) must be tested at intervals not to exceed three years. In the absence of a certificate from a transferor that a test has been made within the three years before the transfer, the ECS may not be used until tested.
	d. 	Leaking or contaminated sources.
	(1)	If the test in 45.6(9)“c” reveals the presence of 0.005 microcurie (185 Bq) or more of removable radioactive material, the licensee shall immediately withdraw the source from use and shall cause it to be decontaminated, repaired, or disposed of by an NRC, agreement state, or licensing state licensee that is authorized to perform these functions. The licensee shall check the equipment associated with the leaking source for radioactive contamination and, if contaminated, have it decontaminated or disposed of by an NRC, agreement state, or licensing state licensee that is authorized to perform these functions.
	(2)	A report describing the equipment involved, the test results, any contamination which resulted from the leaking source, and the corrective action taken up to the time of the report shall be filed with the agency within five days of receiving the test results.
	e. 	Exemptions. The following sources are exempted from the periodic leak test requirements of 45.6(9)“a” to “d”:
	(1)	Hydrogen-3 (tritium) sources;
	(2)	Sources of radioactive material with a half-life of 30 days or less;
	(3)	Sealed sources of radioactive material in gaseous form;
	(4)	Sources of beta- or gamma-emitting radioactive material with an activity of 100 microcuries (3.7 MBq) or less; and
	(5)	Sources of alpha- or neutron-emitting radioactive material with an activity of 10 microcuries (0.370 MBq) or less.
	45.6(10) Quarterly inventory. Each licensee or registrant shall conduct a quarterly physical inventory to account for all sources of radiation. Records of inventories shall be maintained for two years from the date of the inventory for inspection by the agency 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.
	45.6(11) Utilization records. Each licensee or registrant shall maintain current records, which shall be kept available for inspection by the agency for two years from the date of the recorded event, showing the following information for each source of radiation:
	a. 	Make, model number, and a serial number or a description of each source of radiation used;
	b. 	The identity of the well-logging supervisor or field unit to whom assigned;
	c. 	Locations where used and dates of use; and
	d. 	In the case of tracer materials and radioactive markers, the utilization record shall indicate the radionuclide and activity used in a particular well.
	45.6(12) Design, performance, and certification criteria for sealed sources used in well-logging operations.
	a. 	A licensee may use a sealed source for use in well-logging applications if:
	(1)	The sealed source is doubly encapsulated construction;
	(2)	The sealed source contains chemical and physical forms that are as insoluble and nondispersible as practical; and
	(3)	The sealed source meets the requirements of 45.6(12)“b,” “c,” and “d.”
	b. 	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 USASI N5.10-1968, “Classification of Sealed Radioactive Sources,” or the requirements in 45.6(12)“c” or “d.”
	c. 	For a sealed source manufactured after July 14, 1989, a licensee may use the sealed source for well-logging applications if it meets the oil-well-logging requirements of ANSI/HPS N43.6-1997, “Sealed Radioactive Sources—Classification.”
	d. 	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.
	(1)	Temperature. The test source must be held at -40 degrees C for 20 minutes, 600 degrees C for one hour, and then be subject to a thermal shock test with a temperature drop from 600 degrees C within 15 seconds.
	(2)	Impact test. A 5 kg steel hammer, 2.5 cm in diameter, must be dropped from a height of 1 m onto the test source.
	(3)	Vibration test. The test source must be subject to a vibration from 25 Hz to 500 Hz at 5 g amplitude for 30 minutes.
	(4)	Puncture test. A one gram hammer and pin, 0.3 cm pin diameter, must be dropped from a height of 1 m onto the test source.
	(5)	Pressure test. The test source must be subject to an external pressure of 1.695 × 107 pascals (24,600 pounds per square inch absolute).
	e. 	The requirements in 45.6(12)“a,” “b,” “c,” and “d” do not apply to sealed sources that contain licensed material in gaseous form.
	f. 	The requirements of 45.6(12)“a,” “b,” “c,” and “d” do not apply to energy compensation sources (ECS). ECSs must be registered with the NRC, licensing state, or agreement state.
	45.6(13) Labeling.
	a. 	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:
DANGER1
RADIOACTIVE
This labeling shall be on the smallest component transported as a separate piece of equipment.
	b. 	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:
DANGER1
RADIOACTIVE
NOTIFY CIVIL AUTHORITIES
[OR NAME OF COMPANY]
	45.6(14) Inspection and maintenance.
	a. 	Each licensee or registrant shall conduct, at intervals not to exceed six months, a program of inspection and maintenance of source holders, logging tools, source handling tools, storage containers, transport containers, and injection tools to ensure proper labeling and physical condition. Records of inspection and maintenance shall be maintained for a period of two years for inspection by the agency.
	b. 	If any inspection conducted pursuant to 45.6(14)“a” reveals damage to labeling or components critical to radiation safety, the device shall be removed from service until repairs have been made.
	c. 	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.
	d. 	The repair, opening, or modification of any sealed source shall be performed only by persons specifically authorized to do so by the agency, the U.S. Nuclear Regulatory Commission, an agreement state, or a licensing state.
	45.6(15) Training requirements.
	a. 	No licensee or registrant shall permit any individual to act as a logging supervisor as defined in this rule until such individual has:
	(1)	Received, in a course recognized by the agency, the U.S. Nuclear Regulatory Commission, an agreement state, or a licensing state, instruction in the subjects outlined in Appendix E of this chapter and demonstrated an understanding thereof;
	(2)	Read and received instruction in the rules contained in this chapter and the applicable sections of 641—Chapters 38, 39, and 40 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
	(3)	Demonstrated competence to use sources of radiation, related handling tools, and radiation survey instruments which will be used on the job.
	b. 	No licensee or registrant shall permit any individual to assist in the handling of sources of radiation until such individual has:
	(1)	Read or received instruction in the licensee’s or registrant’s operating and emergency procedures and demonstrated an understanding thereof; and
	(2)	Demonstrated competence to use, under the direct supervision of the logging supervisor, the sources of radiation, related handling tools, and radiation survey instruments which will be used on the job.
	c. 	The licensee or registrant shall maintain employee training records for inspection by the agency for two years following termination of the individual’s employment.
	45.6(16) Operating and emergency procedures. Each licensee or registrant shall develop and follow written operating and emergency procedures that cover:
	a. 	The handling and use of sources of radiation, including the use of sealed sources in wells without surface casing for protecting fresh water aquifers, if appropriate;
1or CAUTION
	b. 	The use of remote handling tools for handling sealed sources and radioactive tracer material except low-activity calibration sources;
	c. 	Methods and occasions for conducting radiation surveys, including surveys for detecting contamination, as required by 45.6(22);
	d. 	Minimizing personnel exposure, including exposures from inhalation and ingestion of licensed tracer materials;
	e. 	Methods and occasions for locking and securing stored licensed or registered materials;
	f. 	Personnel monitoring and the use of personnel monitoring equipment;
	g. 	Transportation of licensed or registered materials to field stations or temporary job sites, packaging of licensed or registered materials for transport in vehicles, placarding of vehicles when needed, and physically securing licensed materials in transport vehicles during transportation to prevent accidental loss, tampering, or unauthorized removal;
	h. 	Picking up, receiving, and opening packages containing licensed or registered materials, in accordance with 641—40.65(136C);
	i. 	For the use of tracers, decontamination of the environment, equipment, and personnel;
	j. 	Maintenance of records generated by well logging personnel at temporary job sites;
	k. 	The inspection and maintenance of sealed sources, source holders, logging tools, injection tools, source handling tools, storage containers, transport containers, and uranium sinker bars as required by 45.6(14);
	l. 	Identifying and reporting defects and noncompliance;
	m. 	Actions to be taken if a sealed source is lodged in a well;
	n. 	Notifying proper persons in the event of an accident; and
	o. 	Actions to be taken if a sealed source is ruptured that include actions to prevent the spread of contamination and minimize inhalation and ingestion of licensed materials and actions to obtain suitable radiation survey instruments as required in 45.6(8).
	45.6(17) Personnel monitoring.
	a. 	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 licensed radioactive materials, a film badge, OSL device or thermoluminescent dosimeter (TLD) that is processed and evaluated by an accredited National Voluntary Laboratory Accreditation Program (NVLAP). Each film badge, OSL device or TLD shall be assigned to and worn by only one individual. Film badges must be replaced at least monthly and OSL devices and TLDs replaced at least quarterly. After replacement, each film badge, OSL device or TLD must be promptly processed.
	b. 	The licensee shall provide bioassay services to individuals using licensed materials in subsurface tracer studies if required by the license.
	c. 	Personnel monitoring records and bioassay results shall be maintained for inspection until the agency authorizes disposition.
	45.6(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 641—Chapter 38.
	45.6(19) Handling tools. The licensee shall provide and require the use of tools that will ensure remote handling of sealed sources other than low activity calibration sources.
	45.6(20) Subsurface tracer studies.
	a. 	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.
	b. 	No licensee shall cause the injection of radioactive material into potable aquifers without prior written authorization from the agency and any other appropriate state agency.
	45.6(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 so controlled or shielded that the requirements of 641—40.15(136C) and 641—40.26(136C), as applicable, are met.
	45.6(22) Radiation surveys.
	a. 	Radiation surveys or calculations shall be made and recorded for each area where radioactive materials are used and stored.
	b. 	Radiation surveys 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 shall include each source of radiation or combination of sources to be transported in the vehicle.
	c. 	If the sealed source assembly is removed from the logging tool before departing the job site, the logging tool detector shall be energized, or a survey meter used, to ensure that the logging tool is free of contamination.
	d. 	Radiation surveys shall be made and recorded at the job site 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.
	e. 	Records required pursuant to 45.6(22)“a” to “d” 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 agency for two years after completion of the survey.
	45.6(23) Documents and records required at field stations. Each licensee or registrant shall maintain, for inspection by the agency, the following documents and records for the specific devices and sources used at the field station:
	a. 	Appropriate license, certificate of registration, or equivalent document(s);
	b. 	Operating and emergency procedures;
	c. 	Applicable regulations;
	d. 	Records of the latest survey instrument calibrations pursuant to 45.6(8);
	e. 	Records of the latest leak test results pursuant to 45.6(9);
	f. 	Records of quarterly inventories required pursuant to 45.6(10);
	g. 	Utilization records required pursuant to 45.6(11);
	h. 	Records of inspection and maintenance required pursuant to 45.6(14);
	i. 	Survey records required pursuant to 45.6(22); and
	j. 	Training records required pursuant to 45.6(15).
	45.6(24) Documents and records required at temporary job sites. Each licensee or registrant conducting operations at a temporary job site shall have the following documents and records available at that site for inspection by the agency:
	a. 	Operating and emergency procedures;
	b. 	Survey records required pursuant to 45.6(22) for the period of operation at the site;
	c. 	Evidence of current calibration for the radiation survey instruments in use at the site;
	d. 	When operating in the state under reciprocity, a copy of the appropriate license, certificate of registration, or equivalent document(s); and
	e. 	Shipping papers for the transportation of radioactive material.
	45.6(25) Notification of incidents, abandonment, and lost sources.
	a. 	Notification of incidents and sources lost in other than downhole logging operations shall be made in accordance with appropriate provisions of 641—Chapter 40.
	b. 	Whenever a sealed source or device containing radioactive material is lodged downhole, the licensee shall:
	(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
	(2)	Notify the agency 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 planned or being taken to mitigate these consequences.
	c. 	When it becomes apparent that efforts to recover the radioactive source will not be successful, the licensee shall:
	(1)	Advise the well operator of the regulations of the appropriate state agency regarding abandonment and an appropriate method of abandonment, which shall include:
	1.	The immobilization and sealing in place of the radioactive source with a cement plug;
	2.	The setting of a whipstock or other deflection device; and
	3.	The mounting of a permanent identification plaque at the surface of the well, containing the appropriate information required by 45.6(25)“d.”
	(2)	Notify the agency by telephone, giving the circumstances of the loss, and request approval of the proposed abandonment procedures, or specify the implemented abandonment before receiving approval because the licensee believed there was an immediate threat to public health and safety; and
	(3)	File a written report with the agency 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:
	1.	Date of occurrence;
	2.	A description of the well-logging source involved, including the radionuclide and its quantity, chemical, and physical form;
	3.	Surface location and identification of the well;
	4.	Results of efforts to immobilize and seal the source in place;
	5.	A brief description of the attempted recovery effort;
	6.	Depth of the source;
	7.	Depth of the top of the cement plug;
	8.	Depth of the well;
	9.	The immediate threat to public health and safety justification for implementing abandonment if prior approval was not obtained in accordance with 45.6(25)“c”(2);
	10.	Any other information, such as a warning statement, contained on the permanent identification plaque; and
	11.	The names of state agencies receiving a copy of this report.
	d. 	Whenever a sealed source containing radioactive material is abandoned downhole, the licensee shall provide a permanent plaque2 for posting the well or well-bore. This plaque shall:
	(1)	Be constructed of long-lasting material, such as stainless steel or Monel; and
	(2)	Contain the following information engraved on its face:
	1.	The word “CAUTION”;
	2.	The radiation symbol without the conventional color requirement;
	3.	The date of abandonment;
	4.	The name of the well operator or well owner;
	5.	The well name and well identification number(s) or other designation;
	6.	The sealed source(s) by radionuclide and activity;
	7.	The source depth and the depth to the top of the plug; and
	8.	An appropriate warning, depending on the specific circumstances of each abandonment.3
	e. 	The licensee shall immediately notify the agency 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.
	45.6(26) Reserved.
	45.6(27) Radioactive markers. The licensee may use radioactive markers in wells only if the individual markers contain quantities of licensed material not exceeding the quantities specified in 641—Chapter 39, Appendix B, Exempt Quantities. The use of markers is subject only to the requirements of 45.6(10).
	45.6(28) Uranium sinker bars. The licensee may use uranium sinker bars in well-logging applications only if they are legibly impressed with the words “CAUTION—RADIOACTIVE-DEPLETED URANIUM” and “NOTIFY CIVIL AUTHORITIES [or Company name] IF FOUND.”
	45.6(29) Use of a sealed source in a well without a surface casing. The licensee may use a sealed source in a well without a surface casing for protecting fresh water aquifers only if the licensee follows a procedure for reducing the probability of the source’s becoming lodged in the well. The procedure must be approved by the NRC or licensing or agreement state.
	45.6(30) Energy compensation source. The licensee may use an energy compensation source (ECS) which is contained within a logging tool, or other tool components, only if the ECS contains quantities of licensed material not exceeding 100 microcuries (3.7 MBq).
	a. 	For well-logging applications with a surface casing for protecting fresh water aquifers, use of the ECS is only subject to the requirements of 45.6(9) to 45.6(11).
	b. 	For well-logging applications without a surface casing for protecting fresh water aquifers, use of the ECS is only subject to the requirements of 45.6(4), 45.6(9) to 45.6(11), 45.6(25), and 45.6(29).
	45.6(31) Tritium neutron generator target source.
	a. 	Use of a tritium neutron generator target source that contains quantities not exceeding 30 curies (1110 MBq) and that is in a well with a surface casing to protect fresh water aquifers is subject to the requirements of this rule except subrules 45.6(4), 45.6(12), and 45.6(25).
	b. 	Use of a tritium neutron generator target source that contains quantities exceeding 30 curies (1110 MBq) or that is in a well without a surface casing to protect fresh water aquifers is subject to the requirements of this rule except subrule 45.6(12).
2An example of a suggested plaque is shown in Appendix F of this chapter.
3Appropriate warnings may include: (a) “Do not drill below plug-back depth”; (b) “Do not enlarge casing”; or (c) “Do not re-enter the hole”, followed by the words, “before contacting the Iowa Department of Public Health.”
CHAPTER 45—APPENDIX A
SUBJECTS FOR INSTRUCTION OF
RADIOGRAPHER’S ASSISTANTS
Training provided to qualify individuals as radiographer’s assistants in compliance with 45.1(10) shall be presented on a formal basis. The training shall include the following subjects:
I. Fundamentals of radiation safety
A. Characteristics of radiation
B. Units of radiation dose and quantity of radioactivity
C. Significance of radiation dose
1. Radiation protection standards
2. Biological effects of radiation
3. Case histories of radiography accidents
D. Levels of radiation from sources of radiation
E. Methods of controlling radiation dose
1. Working time
2. Working distances
3. Shielding
II. Radiation detection instrumentation to be used
A. Use of radiation survey instruments
1. Operation
2. Calibration
3. Limitations
B. Survey techniques
C. Use of personnel monitoring equipment
1. Film badges
2. Thermoluminescent dosimeters (TLDs)
3. Pocket dosimeters
4. OSL devices
III. The requirements of pertinent federal and state regulations
IV. The licensee’s or registrant’s written operating and emergency procedures
V. Radiographic equipment to be used
A. Remote handling equipment
B. Operation and control of radiographic exposure devices and sealed
sources, including pictures or models of source assemblies (pigtails)
C. Storage and transport containers, source changers
D. Operation and control of X-ray equipment
E. Collimators
CHAPTER 45—APPENDIX B
GENERAL REQUIREMENTS FOR INSPECTION OF
INDUSTRIAL RADIOGRAPHIC EQUIPMENT
I. Panoramic devices (devices in which the sealed source is physically removed from the
shielded container during exposure) shall be inspected for:
A. Radiographic exposure unit
1. Abnormal surface radiation levels anywhere on camera, collimator, or guide tube;
2. Condition of safety plugs;
3. Proper operation of locking mechanism;
4. Condition of pigtail connector;
5. Condition of carrying device (straps, handle, etc.);
6. Proper labeling.
B. Source tube
1. Rust, dirt, or sludge buildup inside the source tube;
2. Condition of source tube connector;
3. Condition of source stop;
4. Kinks or damage that could prevent proper operation;
5. Presence of radioactive contamination.
C. Control cables and drive mechanism
1. Proper drive mechanism with camera, as appropriate;
2. Changes in general operating characteristics;
3. Condition of connector on drive cable;
4. Drive cable flexibility, wear, and rust;
5. Excessive wear or damage to crank assembly parts;
6. Damage to drive cable conduit that could prevent the cable from moving easily;
7. Connection of the control cable connector with the pigtail connector for proper mating;
8. Proper operation of source position indicator, if applicable;
9. Presence of radioactive contamination.
II. Directional beam devices shall be inspected for:
A. Abnormal surface radiation;
B. Changes in the general operating characteristics of the unit;
C. Proper operation of shutter mechanism;
D. Chafing or binding of shutter mechanism;
E. Damage to the device that might impair its operation;
F. Proper operation of locking mechanism;
G. Proper drive mechanism with camera, as appropriate;
H. Condition of carrying device (strap, handle, etc.);
I. Proper labeling.
III. X-ray equipment shall be inspected for:
A. Change in the general operating characteristics of the unit;
B. Wear of electrical cables and connectors;
C. Proper labeling of console;
D. Proper console with machine, as appropriate;
E. Proper operation of locking mechanism;
F. Timer run-down cutoff;
G. Damage to tube head housing that might result in excessive radiation levels.
CHAPTER 45—APPENDIX C
TIME REQUIREMENTS FOR RECORD KEEPING

Specific
Section	Name of Record	 	Time Interval Required for
Record Keeping	
		
45.1(4)	Receipt, transfer and disposal.	 	3 years.	
45.1(5)	Survey instrument calibrations.	 	3 years.	
45.1(6)	Quarterly inventory.	 	3 years.	
45.1(7)	Utilization logs.	 	3 years.	
45.1(8)	Quarterly inspection and
maintenance.	 	3 years.	
45.1(9)	High radiation area control
devices or alarm systems.	 	Until disposal is authorized
by the agency.	
45.1(10)	Training and testing records.	 	3 years.	
45.1(12)	Pocket dosimeter readings.	 	3 years.	
 	Pocket dosimeter calibrations.	 	3 years.	
 	Film badge, OSL device,
or TLD reports.	 	Until the agency terminates the license.	
 	Alarming ratemeter calibrations.	 	3 years.	
 	Alarming ratemeter functions.	 	3 years.	
 	Estimates of overexposures.	 	Until the agency terminates the license.	
45.1(19)	Current operating and emergency procedures.	 	Until the license is terminated.	
 	Superseded material.	 	3 years after change.	
40.81(1)	Internal audit program.	 	3 years.	
45.1(11)	Radiographer audits.	 	3 years.	
45.2(5)
and
45.3(7)	Radiation surveys.	 	2 years or until disposal is
authorized by the agency if a
survey was used to determine
an individual’s exposure.	
45.1(16)	Records at temporary job sites.	 	During temporary job site
operations.	
45.2(6)
and
45.3(8)	Annual evaluation of enclosed
X-ray systems.	 	2 years.	
45.3(5)	Leak tests.	 	3 years.	
45.2(6)	Evaluation of certified cabinet
X-ray systems.	 	2 years.	
CHAPTER 45—APPENDIX D
OPERATING AND EMERGENCY PROCEDURES
The licensee’s or registrant’s operating and emergency procedures shall include instructions in at least the following:
A. Handling and use of sources of radiation for industrial radiography such that no individual is likely to be exposed to radiation doses that exceed the limits established in 641—Chapter 40;
B. Methods and occasions for conducting radiation surveys, including lock-out survey requirements;
C. Methods for controlling access to industrial radiography areas;
D. Methods and occasions for locking and securing sources or radiation;
E. Personnel monitoring and the use of personnel monitoring equipment, including steps to be taken immediately by industrial radiographic personnel in the event a pocket dosimeter is found to be off-scale;
F. Methods of transporting equipment to field locations, including packing of sources of radiation in the vehicles, placarding of vehicles, and controlling of sources of radiation during transportation (including applicable U.S. Department of Transportation requirements);
G. Methods or procedures for minimizing exposure of individuals in the event of an accident, including procedures for a disconnect accident, a transportation accident, and loss of a sealed source;
H. Procedures for notifying proper personnel in the event of an accident;
I. Specific posting requirements;
J. Maintenance of records (Appendix C); and
K. Inspection and maintenance of radiographic exposure devices, source changers, storage containers, transport containers, source guide tubes, crank-out devices, and radiation machines.
CHAPTER 45—APPENDIX E
SUBJECTS TO BE INCLUDED IN TRAINING COURSES FOR LOGGING SUPERVISORS
I. Fundamentals of radiation safety.
A. Characteristics of radiation.
B. Units of radiation dose and quantity of radioactivity.
C. Significance of radiation dose.
1. Radiation protection standards.
2. Biological effects of radiation dose.
D. Levels of radiation from sources of radiation.
E. Methods of minimizing radiation dose.
1. Working time.
2. Working distances.
3. Shielding.
F. Radiation safety practices including prevention of contamination and methods of decontamination.
II. Radiation detection instrumentation to be used.
A. Use of radiation survey instruments.
1. Operation.
2. Calibration.
3. Limitations.
B. Survey techniques.
C. Use of personnel monitoring equipment.
III. Equipment to be used.
A. Handling equipment.
B. Sources of radiation.
C. Storage and control of equipment.
D. Operation and control of equipment.
IV. The requirements of pertinent federal and state regulations.
V. The licensee’s or registrant’s written operating and emergency procedures.
VI. The licensee’s or registrant’s record-keeping procedures.
CHAPTER 45—APPENDIX F
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, e.g., a 7-inch square. Letter size of the word “CAUTION” should be approximately twice the letter size of the rest of the information, e.g., ½-inch and ¼-inch letter size, respectively.
These rules are intended to implement Iowa Code chapters 136B and 136C.
[Filed 4/7/80, Notice 2/6/80—published 4/30/80, effective 7/1/80]
[Filed 5/17/85, Notice 2/27/85—published 6/5/85, effective, see rule 41.7]
[Filed 11/6/87, Notice 9/23/87—published 12/2/87, effective 1/6/88]
[Filed 7/17/92, Notice 5/27/92—published 8/5/92, effective 9/9/92]
[Filed 9/17/93, Notice 8/4/93—published 10/13/93, effective 1/1/94]
[Filed 7/14/94, Notice 6/8/94—published 8/3/94, effective 9/7/94]
[Filed 5/15/95, Notice 3/29/95—published 6/7/95, effective 7/12/95]
[Filed 1/11/96, Notice 10/11/95—published 1/31/96, effective 3/6/96]
[Filed 9/16/96, Notice 7/17/96—published 10/9/96, effective 11/16/96]
[Filed 5/16/97, Notice 4/9/97—published 6/4/97, effective 7/9/97]
[Filed 3/18/98, Notice 1/14/98—published 4/8/98, effective 7/1/98]
[Filed 4/2/99, Notice 1/13/99—published 4/21/99, effective 7/1/99]
[Filed 6/25/99, Notice 5/5/99—published 7/14/99, effective 9/15/99]
[Filed 3/15/00, Notice 1/26/00—published 4/5/00, effective 5/10/00]
[Filed 3/16/01, Notice 2/7/01—published 4/4/01, effective 5/9/01]
[Filed 5/10/01, Notice 4/4/01—published 5/30/01, effective 7/4/01]
[Filed 3/14/02, Notice 2/6/02—published 4/3/02, effective 5/8/02]
[Filed 11/15/02, Notice 10/2/02—published 12/11/02, effective 1/15/03]
[Filed 3/14/03, Notice 2/5/03—published 4/2/03, effective 5/7/03]
[Filed 3/12/04, Notice 2/4/04—published 3/31/04, effective 5/5/04]
[Filed 3/11/05, Notice 2/2/05—published 3/30/05, effective 5/4/05]
[Filed 3/9/06, Notice 2/1/06—published 3/29/06, effective 5/3/06]
[Filed 7/13/07, Notice 6/6/07—published 8/1/07, effective 9/5/07]
[Filed ARC 8982B (Notice ARC 8762B, IAB 5/19/10), IAB 8/11/10, effective 9/15/10]