The American National Standards Institute Subcommittee on Transportation of Radioactive Waste, with NRC participation, is preparing a standard for the packaging for transportation of liquid aqueous radioactive wastes from nuclear power plants. It will require that liquid wastes be solidified prior to shipment and that a high-integrity container be used.

In March 1979, the NRC published a draft report, NUREG-0535, "Review and Assessment of Package Requirements (Yellowcake) and Emergency Response to Transportation Accidents." The report was prepared by an NRC/DOT task force following a truck accident in September 1977 in which a shipment of uranium concentrate (yellowcake) was spilled onto a highway near Springfield, Colo. The draft report has been issued for public comment, which will be considered in preparing the final report. (See 1978 NRC Annual Report, p. 81.)

Irradiated Fuel Packaging

Spent (irradiated) nuclear fuel is transported off-site in specially designed shipping casks that are capable of containing the radioactive fuel assembly materials during normal and postulated design accident transportation conditions.

On April 6, 1979, NRC issued an Order to Show Cause (immediately effective) prohibiting the use of the Model No. NFS-4 packaging until a determination is made that it meets specified requirements. During a meeting on March 29, 1979, and later by letter dated April 2, 1979, Nuclear Assurance Corporation informed the NRC staff that a cask had not been fabricated in accordance with its certificate of compliance. In view of the unknown safety implications for this and other packages fabricated to the same design, and in the interest of public health and safety, all seven packages

were removed from use until an assessment could be made of their safety as fabricated. On Dec. 12, NRC permitted three casks to be returned to service. Eighteen owner/users were affected by the orders.

The staff is reviewing two applications for spent fuel casks designed for shipment by rail that are significantly different from design concepts presently used. Each of these designs uses a thick, solid, cylindrical carbon steel containment vessel wall as a gamma shield. Existing designs use lead or uranium in the gamma shield. One factor being considered in the review is fracture toughness of thick steel forgings. The two spent fuel casts are the Transnuclear Inc. Model No. TN-12 and the Nuclear Assurance Corporation Model No. NAC-3K.

Safety of Transportation Workers

In June 1979, the NRC initiated a study entitled "Radiation Exposure of Transportation Workers Handling Large Numbers of Radioactive Material Packages." The objectives of the study are to:

(1) Identify carriers where employees may receive exposures exceeding regulatory limits.

(2) Determine actual exposures received either by direct measurement or by studying the carrier's records.

(3) Observe procedures in use at carrier's facilities and prepare suggestions for techniques to reduce exposure.

(4) Identify relationship between quantity of radioactive material handled and exposure.

The study began in July 1979 and should be completed by October 1980. The information will be used to prepare a recommendation to DOT on what further measures may be necessary to control radiation exposures in selected portions of the transportation industry.

During fiscal year 1979, the NRC-sponsored State Surveillance Program on Transportation of Radioactive Materials was continued. (See Chapter 8, "State Programs," for details of the program's activities during 1979.)

Transportation in Urban Areas

During 1979, Sandia Laboratories, under contract to the NRC, continued its work to assess the environmental impacts resulting from the transportation of radioactive materials through urban areas. The study has been examining the impacts resulting from incident-free transport, vehicular accidents during transport, and from other abnormal situations. In performing this study, Sandia has developed computer

models to account for the special features of the urban environment. The study will form the basis for a generic environmental impact statement, to be published by the NRC, on the transportation of radioactive material in urban areas.

Information resulting from the study suggests that the sabotage of spent fuel shipments has the potential for producing serious radiological consequences in areas of high population density. This information, in part, led the NRC in June 1979 to establish interim requirements for the protection of spent fuel in transit. (See Chapter 5, "Domestic Safeguards.")

Emergency Response Planning

In October 1978, Indiana University, under contract to the NRC, began work on a study entitled "Survey of Current State Radiological Emergency Response Capabilities for Transportation Related Incidents." The objective is to assemble and condense available information on current state emergency response capabilities for transportation-related radiological incidents in order to assist NRC in its role regarding radiological incident planning, emergency response training, and other assistance activities within State and local governments.

The NRC will use the information obtained from this study to (1) identify response requirements for protection of the health and safety of the public with regard to transportation-related radiological incidents, (2) develop and promulgate guidance to State and local governments in coordination with other Federal agencies for the preparation of emergency response plans, and (3) determine whether additional Federal participation is required to ensure adequate protection of the health and safety of the public with regard to transportation-related radiological incidents. The study will be completed in fiscal year 1980.

Packaging Standards

In March 1979, the NRC issued for comment Regulatory Guide 7.9, which identifies the information to be provided in an application for the approval of packaging for shipping Type B, large quantity, and fissile radioactive material and presents a uniform format for presenting the information. The guide assists the applicant in preparing an application and ensures the completeness of the information provided. Use of a uniform format assists the NRC staff and others in locating the information and aids in shortening the time needed for the review process.

In August 1979, the NRC issued for public comment a revision to 10 CFR Part 71, “Packaging of Radioactive Material for Transportation and Transportation of Radioactive Material Under Certain Conditions." The NRC is considering revising its regulations for the transportation of radioactive material to make them

compatible with those of the International Atomic Energy Agency (IAEA) and thus with those of most major nuclear nations of the world. Although several substantive changes are proposed in order to provide a more uniform degree of safety for various types of shipments, the Commission's basic standards for radioactive material packaging would remain unchanged. The DOT is also proposing a corresponding rule change to its hazardous materials transport regulations.

The major changes to NRC's regulations that are being proposed are:

(1) Elimination of the system currently used to specify the quantities of radioactive materials permitted to be shipped in certain types of packages. Under the present system, all radioactive materials are divided into seven transport groups that are used as the basis for determining the amount of those materials that can be shipped in Type A packages and the amounts that must be shipped in the more stringently designed, accident-resistant Type B packages. This system has proved to be unduly restrictive because less hazardous radioactive materials included in one transport group are required to be packed in the same manner as other, more hazardous radioactive materials belonging to the same transport group. Under the proposed rules, the use of a Type A or Type B package would depend on the degree of radioactivity for each material being shipped.

(2) Establishment of two classifications of Type B packages. This change would facilitate foreign acceptance of U.S. export shipments by conforming package types to international standards. International Standards

In 1983, the IAEA will issue a revision to its Safety Series No. 6, "Regulations for the Safe Transport of Radioactive Materials." In preparation for this revision, the IAEA has asked member countries to submit proposed changes to the regulations and to identify areas where revision should be considered. The NRC prepared recommended changes to the regulations which were submitted to the IAEA by the DOT, which serves as the U.S. competent authority on matters involving international shipments of radioactive material. In addition, the NRC assisted the DOT in its review of comments submitted by various private organizations and other government agencies.

The NRC also participated as an observer in a meeting of the IAEA Advisory Group on Radiation Protection and Safety Principles for Safe Transport of Radioactive Materials. The meeting was held in July 1979 at the IAEA Headquarters in Vienna, Austria. The purpose of the meeting was to review the principles upon which the IAEA's transport regulations are

This radiograph of the Liberty Bell is reduced from its original size of seven feet by 12% feet, reportedly the largest single sheet of X-ray film ever exposed. The exposure to a 670-curie cobalt-60 source lasted 71⁄2 hours. The famous crack in the bell is the dark irregular line at left center.

based and to provide recommendations to a revision panel that will meet in 1980 to begin the comprehensive review of the transport regulations.

Radioactive Material
Licensing

Radioactive materials have wide use in industrial applications, medical diagnosis and treatment, applied research and development, in the academic fields, and in products distributed to the public. Some 8,500 materials licenses are administered by the NRC which require the annual processing of 5,000 to 6,000 applications for new licenses, license amendments and license renewals. An additional 12,000 licenses are administered by 26 states which have assumed authority over certain materials under regulatory agreements with the NRC, as part of the Agreement States program, (see Chapter 8). The NRC licensing program is designed to provide reasonable assurance that the

public health and safety is adequately protected and that applications for licenses are processed in an efficient and timely manner.

In 1979, the materials licensing function was reorganized. The former Radioisotopes Licensing Branch was dissolved and two new branches were created: the Material Licensing Branch and the Material Certification and Procedures Branch. The purpose of the reorganization was twofold. It permits the Material Licensing Branch to focus its efforts on the review of license applications and the Material Certification and Procedures Branch to devote its efforts to functions related to materials licensing, such as sealed source and device evaluations, preparation of guides for licensees and applicants, the review of regulatory practices, and other non-casework needs.

In March 1978, the NRC initiated a pilot regionalization licensing program to determine the feasibility of conducting licensing activities from NRC regional offices. The initial effort involved six of the eight States in NRC's Region III and reviews were conducted for medical institutions and industrial firms using gauging devices. As the program progressed, all eight of the States were included in the program, and academic institutions and industrial research and development licensees were included in those involved in the regional licensing program. The program is scheduled for completion in early 1980 and the feasibility of continuing or expanding the regional licensing program will be determined.

Consumer Products. Numerous products containing small amounts of radioactive materials are in daily use. These products are authorized for distribution only after careful evaluation by the NRC indicates that there is minimal risk to the general public. Among these products are smoke detector devices containing americium-241 and liquid crystal display timepieces containing tritium. A two-year study to determine the environmental impact of the use of radioactive materials in consumer products is expected to be completed in October 1980.

Gauging Devices. These devices have wide use for controlling density, levels, thickness, and weight of materials. NRC approves their use only after evaluation of the sealed sources and the devices to determine that the gauging devices may be used safely by individuals who have minimal training and experience in radiation safety. Due to the relatively low radiation levels, normal use of these devices presents minimal hazard to workers and the general public.

Gas Chromatographs. These devices typically contain radioactive materials in the form of foil or plated sources containing nickel-63 or tritium. Due to increased concern for the environment and the usefulness in measuring small amounts of materials, gas chromatograph usage has increased dramatically

This well-logging tool uses a radioactive source in taking measurements in boreholes. The neutron source, shown in the upper part of the logging tool, activates the different earth strata as it passes down the hole permitting identification of the composition of the strata.

for analyses of substances which could contain environmentally undesirable constituents.

Well Logging. The use of radioactive materials in well logging-in search of new energy sources and or utilization of gas and oil fields formerly thought underproductive-has increased markedly. Most of these activities are being performed by large service companies, although many small companies are also active in the use of well logging techniques.

Nuclear Medicine

The NRC issues licenses to hospitals and physicians for the use of radioactive materials in the diagnosis and treatment of patients. These diagnostic procedures include both in vitro tests involving the addition of radioactive materials to laboratory samples taken from patients and in vivo tests, the direct administration of radioactive drugs to patients. In vivo tests are for the purpose of:

• Measuring the uptake, dilution or excretion of a radioactive drug within an organ system (blood

volume determinations and kidney function studies are examples of these).

• Visualizing the distribution of a radioactive drug within an organ in order to locate tumors, blood clots, etc.

Therapeutic radiation treatment continues to be an important element licensed by the NRC. These procedures include the use of liquid radioactive drugs to treat certain medical conditions such as the use of iodine-131 for treatment of hyperthyroidism. In the radiation therapy mode called brachytherapy, encapsulated or sealed radiation sources are placed directly on or in the patient's body to treat cancer. Naturally occurring radium sources with their many problems are rapidly being replaced by NRC-licensed materials such as cesium-137 and iridium-192. Teletherapy is another area of radiation therapy licensed by NRC. In this method the patient is treated at a distance with radiation from a sealed radioactive source, usually cobalt-60.

Currently, the most rapidly growing area in nuclear medicine is nuclear cardiology. Using radioactive materials, physicians are able to identify specific areas in the heart that are not receiving an adequate blood supply, thus predicting potential heart attack victims. Nuclear cardiology studies also enable the physicians to locate infarcted areas and monitor healing and recovery processes after a heart attack occurs.

Advisory Committee on Medical Uses of Isotopes. NRC's Advisory Committee on Medical Uses of Isotopes (ACMUI) consists of physicians and medical physics specialists from the public sector and it provides NRC with advice on many medical questions. During a December 1978 meeting, the NRC staff recommended minimum criteria for training and experience of physicians to be licensed to perform nuclear cardiology studies. The committee also discussed NRC's cooperative efforts with the Society of Nuclear Medicine to develop a medical licensee model program designed to minimize radiation exposure to personnel and minimize releases of radioactive material to the environment. During the year, in accordance with NRC's policy of rotating membership on the ACMUI, NRC formally requested nominations from the public to replace several members. Four well-qualified physicians were selected from 47 persons nominated by professional societies and members of the public.

Order on Use of Technetium-99m. Many hospitals obtain technetium-99 (Tc-99m), a radioactive isotope widely used in nuclear medicine, from a molybdenum-99 (Mo-99) generator. The generator is a shielded device that contains Mo-99 absorbed onto an alumina column. When a sterile saline solution is fed through the column, Tc-99m, a daughter product, is removed and Mo-99 remains on the column. Very little, if any of the Mo-99 is normally removed with the