10 C.F.R. Subpart D—Safety
Title 10 - Energy
Unless otherwise authorized by law, the Corporation shall confine its possession and use of radioactive material to the locations and purposes covered by the certificate and/or approved compliance plan. Except as otherwise provided, the certificate or approved compliance plan issued pursuant to the requirements in this part entitles the Corporation to receive title to, own, acquire, receive, possess, and use radioactive material in accordance with the certificate. (a) The Corporation may not transfer radioactive material except as authorized pursuant to this section. (b) Except as otherwise provided and subject to the provisions of paragraphs (c) and (d) of this section, the Corporation may transfer radioactive material: (1) From one component of the Corporation to another; (2) To the Department; (3) To the agency in any Agreement State which regulates radioactive materials pursuant to an agreement with the Commission under Section 274 of the Act, if the quantity transferred is not sufficient to form a critical mass; (4) To any person exempt from the licensing requirements of the Act and requirements in this part, to the extent permitted under the exemption; (5) To any person in an Agreement State, subject to the jurisdiction of that State, who has been exempted from the licensing requirements and regulations of that State, to the extent permitted under the exemption; (6) To any person authorized to receive the radioactive material under terms of a specific license or a general license or their equivalents issued by the Commission or an Agreement State; (7) To any person abroad pursuant to an export license issued under part 110 of this chapter; or (8) As otherwise authorized by the Commission in writing. (c) Before transferring radioactive material to any party specified in paragraph (b) of this section, the Corporation shall verify that the transferee is authorized to receive the type, form, and quantity of radioactive material to be transferred. (d) The following methods for the verification required by paragraph (c) of this section are acceptable: (1) The Corporation may have in its possession and read a current copy of the transferee's specific license or confirmation of registration. The Corporation shall retain a copy of each license or confirmation for 3 years from the date that it was obtained. (2) The Corporation may have in its possession a written confirmation by the transferee that the transferee is authorized by license or registration confirmation to receive the type, form, and quantity of special nuclear material to be transferred, specifying the license or registration confirmation number, issuing agency, and expiration date. The Corporation shall retain the written confirmation as a record for 3 years from the date of receipt of the confirmation; (3) For emergency shipments, the Corporation may accept a certification by the transferee that he or she is authorized by license or registration certification to receive the type, form, and quantity of special nuclear material to be transferred, specifying the license or registration number, issuing agency, and expiration date, provided that the oral confirmation is confirmed in writing within 10 days. The Corporation shall retain the written confirmation of the oral certification for 3 years from the date of receipt of the confirmation; (4) The Corporation may obtain other sources of information compiled by a reporting service from official records of the Commission or the licensing agency of an Agreement State as to the identity of licensees and the scope and expiration dates of licenses and registrations. The Corporation shall retain the compilation of information as a record for 3 years from the date that it was obtained; or (5) When none of the methods of verification described in paragraphs (d) (1) to (4) of this section are readily available or when the Corporation desires to verify that information received by one of these methods is correct or up to date, the Corporation may obtain and record confirmation from the Commission or the licensing agency of an Agreement State that the transferee is licensed to receive the special nuclear material. The Corporation shall retain the record of confirmation for 3 years from the date the record is made. The Corporation shall perform an analysis of potential accidents and consequences to establish the basis for limiting conditions for operation of the plant with respect to the potential for releases of radioactive material. Special attention must be directed to assurance that plant operation will be conducted in a manner to prevent or to mitigate the consequences from a reasonable spectrum of postulated accidents which include internal and external events and natural phenomena in order to ensure adequate protection of the public health and safety. Plant operating history relevant to the assessment should be included. In performing this assessment, the full range of operations should be considered including, but not necessarily limited to, operation at the maximum capacity contemplated. The assessment must be performed using an expected release rate resulting from anticipated operational occurrences and accidents with existing systems and procedures intended to mitigate the release consequences, along with site characteristics, including meteorology, to evaluate the offsite radiological consequences. (a) The Corporation shall establish technical safety requirements. In establishing the requirements, the Corporation shall consider the analyses and results of the safety analysis report submitted pursuant to §76.35. (b) The format for the technical safety requirements must be appropriate for each individual requirement. (c) Appropriate references to established procedures and/or equipment to address each of the following safety topics must be included in technical safety requirements: (1) Effects of natural phenomena; (2) Building and process ventilation and offgas; (3) Criticality prevention; (4) Fire prevention; (5) Radiation protection; (6) Radioactive waste management; (7) Maintenance; (8) Environmental protection; (9) Packaging and transporting nuclear materials; (10) Accident analysis; (11) Chemical safety; (12) Sharing of facilities, structures, systems and components; (13) Utilities essential to radiological safety; and (14) Operations. (d) Technical safety requirements must include items in the following categories: (1) Safety limits. (i) If any safety limit is exceeded, corrective action must be taken as stated in the response procedures associated with the technical safety requirements or the affected part of the process must be shut down unless this action would increase the risk to the health and safety of the public or plant personnel. (ii) If any safety limit is exceeded, the Corporation shall notify the Commission if required by §76.120, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. (iii) The Corporation shall retain the record of the results of each review until the Commission no longer has certification authority. (2) Limiting control settings. (i) Where a limiting control setting is specified for a variable on which a safety limit has been placed, the setting must be so chosen that protective action, either automatic or manual, will correct the abnormal situation before a safety limit is exceeded. If, during operation, the automatic alarm or protective devices do not function as required, appropriate action must be taken to maintain the variables within the limiting control-setting values and to repair promptly the automatic devices or to shut down the affected part of the process. (ii) If, during operation, an automatic alarm or protective device does not function as required, the Corporation shall notify the Commission if required by 76.120, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. (iii) The Corporation shall retain the record of the results of each review until the Commission no longer has certification authority. (3) Limiting conditions for operation. When a limiting condition for operation of any process step in the system is not met, the Corporation shall shut down that part of the operation or follow any remedial action permitted by the technical safety requirements until the condition can be met. (i) If a limiting condition for operation of any process step in the system is not met, the Corporation shall notify the Commission if required by §76.120, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. (ii) The Corporation shall retain the record of the results of each review until the Commission no longer has certification authority. (4) Design features. Design features to be included are those systems, components, or structures of the plant which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (d) (1), (2), and (3) of this section. (5) Surveillance requirement. (6) Administrative controls. (a) The Corporation must maintain and operate a criticality monitoring and audible alarm system meeting the requirements of paragraph (b) of this section in all areas of the facility. The Corporation may describe for the approval of the Commission defined areas to be excluded from the monitoring requirement. This submittal must describe the measures that will be used to ensure against criticality, including kinds and quantities of material that will be permitted and measures that will be used to control those kinds and quantities of material. (b) The system must detect and annunciate a criticality that produces an absorbed dose in soft tissue of 20 rads of combined neutron and gamma radiation at an unshielded distance of 2 meters from the reacting material within 1 minute. Coverage of all monitored areas must be provided by two detectors. The Corporation shall establish, maintain, and be prepared to follow a written emergency plan. The emergency plan submitted under §76.35(f) must include the following information: (a) Plant description. A brief description of the plant and area near the plant site. (b) Types of accidents. An identification of each type of radioactive materials accident for which protective actions may be needed. (c) Classification of accidents. A system for classifying accidents as alerts or site area emergencies. (d) Detection of accidents. Identification of the means of detecting each type of accident in a timely manner. (e) Mitigation of consequences. A brief description of the means and equipment for mitigating the consequences of each type of accident, including those provided to protect workers onsite, and a description of the program for maintaining the equipment. (f) Assessment of releases. A brief description of the methods and equipment to assess releases of radioactive materials. (g) Responsibilities. A brief description of the responsibilities of all individuals supporting emergency response should an accident occur, including identification of personnel responsible for promptly notifying offsite response organizations and the NRC, as well as a brief description of responsibilities for developing, maintaining, and updating the plan. (h) Notification and coordination. A commitment to and a brief description of the means to promptly notify offsite response organizations, including the request for offsite assistance and medical assistance for the treatment of contaminated injured onsite workers when appropriate. A control point must be established. The notification and coordination must be planned so that unavailability of some personnel, parts of the plant, and some equipment does not prevent the notification and coordination. The Corporation shall also commit to notify the NRC Operations Center immediately after notification of the appropriate offsite response organizations and not later than 1 hour after the Corporation declares an emergency. These reporting requirements do not supersede or release the Corporation from complying with the requirements under the Emergency Planning and Community Right-to-Know Act of 1986, Title III, Public Law 99–499, or other State or Federal reporting requirements. (i) Information to be communicated. A brief description of the plant status, radioactive releases, and recommended protective actions, if necessary, to be provided to offsite response organizations and to the NRC. (j) Training. A brief description of the frequency, performance objectives, and plans for the training that the Corporation will provide workers on how to respond to an emergency including any special instructions, briefings, and orientation tours the Corporation would offer to fire, police, medical, and other emergency personnel. The training must familiarize personnel with site-specific emergency procedures. The training must also prepare site personnel for their responsibilities for the accident scenarios postulated as most probable for the specific site, including the use of team training for these accident scenarios. (k) Safe shutdown. A brief description of the means of restoring the plant to a safe condition after an accident. (l) Exercises. Provisions for conducting quarterly communications checks with offsite response organizations and biennial onsite exercises to test response to simulated emergencies. Quarterly communications checks with offsite response organizations must include the check and update of all necessary telephone numbers. The Corporation shall invite offsite response organizations to participate in the biennial exercises. Participation of offsite response organizations in biennial exercises, although recommended, is not required. Exercises must use accident scenarios postulated as most probable for the specific site and the accident scenarios must not be made known to most exercise participants. The Corporation shall critique each exercise using individuals that do not have direct implementation responsibility for the plan. Critiques of exercises must evaluate the appropriateness of the plan, emergency procedures, facilities, equipment, training of personnel, and overall effectiveness of the response. Deficiencies found by the critiques must be corrected. (m) Hazardous chemicals. Confirmation that the Corporation has met its responsibilities under the Emergency Planning and Community Right-to-Know Act of 1986, Title III, Public Law 99–499, if applicable to the Corporation's activities at the proposed place of use of the special nuclear material. (n) Comment from offsite response organizations. The Corporation shall allow the offsite response organizations that are expected to respond in case of an accident 60 days to comment on the emergency plan before submitting it to NRC. The Corporation shall provide any comments received within the 60 days to the NRC with the emergency plan. (o) Changes to emergency plan. The Corporation may make changes to the emergency plan without prior Commission approval if the changes do not decrease the effectiveness of the plan. The Corporation shall furnish these changes to the NRC in accordance with §76.5 and to affected offsite response organizations within 6 months after the change is made. [59 FR 48960, Sept. 23, 1994, as amended at 64 FR 44650, Aug. 17, 1999] The Corporation shall establish, maintain, and execute a quality assurance program satisfying each of the applicable requirements of ASME NQA–1–1989, “Quality Assurance Program Requirements for Nuclear Facilities,” or satisfying acceptable alternatives to the applicable requirements. The Corporation shall execute the criteria in a graded approach to an extent that is commensurate with the importance to safety. A training program must be established, implemented, and maintained for individuals relied upon to operate, maintain, or modify the GDPs in a safe manner. The training program shall be based on a systems approach to training that includes the following: (a) Systematic analysis of the jobs to be performed. (b) Learning objectives derived from the analysis which describe desired performance after training. (c) Training design and implementation based on the learning objectives. (d) Evaluation of trainee mastery of the objectives during training. (e) Evaluation and revision of the training based on the performance of trained personnel in the job setting.
Title 10: Energy
PART 76—CERTIFICATION OF GASEOUS DIFFUSION PLANTS
Subpart D—Safety
§ 76.81 Authorized use of radioactive material.
§ 76.83 Transfer of radioactive material.
§ 76.85 Assessment of accidents.
§ 76.87 Technical safety requirements.
§ 76.89 Criticality accident requirements.
§ 76.91 Emergency planning.
§ 76.93 Quality assurance.
§ 76.95 Training.
