ML22223A178

VA Amended Regulations 12VAC5-481

ML22223A178
Person / Time
Issue date:	08/11/2022
From:	NRC/NMSS/DMSST/ASPB
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Project 7111 - Exempt Final Department of Health Amend RM Regulation 12VAC5-481 following Amendment of 10 CFR 12VAC5-481-451. Physical protection of Category 1 and Category 2 quantities of radioactive material.

A. Any licensee who possesses or uses an aggregated quantity of Category 1 or Category 2 radioactive material equal to or in excess of those in subdivision 1 of this subsection shall establish a physical protection program that meets all requirements detailed in this section.

1. Radionuclides of concern.

Radionuclide Category 1 Category 1 (Ci)1,2 Category 2 Category 2 (Ci)1,2 (TBq)1,2 (TBq)1,2 Am-241 60 1,620 0.6 16.2 Am-241/Be 60 1,620 0.6 16.2 Cf-252 20 540 0.2 5.4 Cm-244 50 1,350 0.5 13.5 Co-60 30 810 0.3 8.1 Cs-137 100 2,700 1 27 Gd-153 1,000 27,000 10 270 Ir-192 80 2,160 0.8 21.6 Pm-147 40,000 1,080,000 400 10,800 Pu-238 60 1,620 0.6 16.2 Pu-239/Be 60 1,620 0.6 16.2 Ra-226 40 1,080 0.4 10.8 Se-75 200 5,400 2 54 Sr-90 (Y-90) 1,000 27,000 10 270 Tm-170 20,000 540,000 200 5,400 Yb-169 300 8,100 3 81 Combinations of See footnote 4 radioactive below materials listed above3 1

The aggregate activity of multiple, collocated sources of the same radionuclides should be included when the total activity equals or exceeds the Category 1 or Category 2 threshold.

2 The primary values used for compliance are TBq. The curie (Ci) values are rounded to two significant figures for informational purposes only.

3 Radioactive materials are to be considered aggregated or collocated if breaching a common physical barrier (e.g., a locked door at the entrance to a storage room) would allow access to the radioactive material or devices containing the radioactive material.

4 If several radionuclides are aggregated, the sum of the ratios of the activity of each source, i of radionuclide, n, A (i,n), to the Category 1 or Category 2 threshold for radionuclide n, Qn, listed for that radionuclide equals or exceeds one. [(aggregated source activity for radionuclide A) /

(quantities of concern for radionuclide A)] + [(aggregated source activity for radionuclide B) /

(quantities of concern for radionuclide B)] + etc. 1.

2. A licensee that possesses radioactive waste that contains Category 1 or Category 2 quantities of radioactive material is exempt from the requirements of this section.

3. A licensee that possesses radioactive waste that contains discrete sources, ion-exchange resins, or activated material that weighs less than 2,000 kg (4,409 lbs) is not exempt from the requirements of this section. The licensee shall implement the following requirements to secure the radioactive waste:

a. Use continuous physical barriers that allow access to the radioactive waste only through established access control points;

b. Use a locked door or gate with monitored alarm at the access control point;

c. Assess and respond to each actual or attempted unauthorized access to determine whether an actual or attempted theft, sabotage, or diversion occurred; and

d. Immediately notify the local law-enforcement agency (LLEA) and request an armed response from the LLEA upon determination that there was an actual or attempted theft, sabotage, or diversion of the radioactive waste.

B. Background investigations and access authorization program.

1. Personnel access authorization requirements for Category 1 or Category 2 quantities of radioactive material.

a. Each licensee that possesses an aggregated quantity of radioactive material that equals or exceeds the Category 2 threshold shall establish, implement, and maintain its access authorization program in accordance with the requirements in this subsection. An applicant for a new license and each licensee that would become newly subject to the requirements in this subsection upon an amendment request of its license shall implement the requirements of this subsection, as appropriate, before taking possession of an aggregated quantity of radioactive material that equals or exceeds the Category 2 threshold. Any licensee that has not previously implemented the increased control requirements of this section shall implement the provisions of this subsection before aggregating radioactive material to a quantity that equals or exceeds the Category 2 threshold.

b. The licensee's access authorization program shall ensure that the individuals specified in subdivision 1 c of this subsection are trustworthy and reliable.

c. Licensees shall subject the following individuals to an access authorization program:

(1) Any individual whose assigned duties require unescorted access to Category 1 or Category 2 quantities of radioactive material; and (2) Reviewing officials.

d. Licensees shall approve for unescorted access to Category 1 or Category 2 quantities of radioactive material only those individuals whose assigned job duties require unescorted access to Category 1 or Category 2 quantities of radioactive material.

e. Licensees need not subject the categories of individuals listed in subdivision 5 a of this subsection to the investigation elements of the access authorization program.

2. Access authorization program requirements.

a. Granting unescorted access authorization.

(1) Licensees shall implement the requirements of this subsection for granting initial or reinstated unescorted access authorization.

(2) Individuals who have been determined to be trustworthy and reliable shall also complete the security training required by subdivision C 2 c of this section before being allowed unescorted access to Category 1 or Category 2 quantities of radioactive material.

b. Reviewing officials.

(1) Reviewing officials are the only individuals who may make trustworthiness and reliability determinations that allow individuals to have unescorted access to Category 1 or Category 2 quantities of radioactive materials possessed by the licensee.

(2) Each licensee shall name one or more individuals to be reviewing officials. After completing the background investigation on the reviewing official, the licensee shall provide under oath or affirmation a certification that the reviewing official is deemed trustworthy and reliable by the licensee. Provide oath or affirmation certifications to the agency via an appropriate means listed in 12VAC5-481-150. The fingerprints of the named reviewing official shall be taken by a law-enforcement agency, a federal or state agency that provides fingerprinting services to the public, or a commercial fingerprinting service authorized by a state to take fingerprints. The licensee shall recertify that the reviewing official is deemed trustworthy and reliable every 10 years in accordance with subdivision 3 c of this subsection.

(3) Reviewing officials shall be permitted to have unescorted access to Category 1 or Category 2 quantities of radioactive material.

(4) Reviewing officials cannot approve other individuals to act as reviewing officials.

(5) A reviewing official does not need to undergo a new background investigation before being named by the licensee as the reviewing official if:

(a) The individual has undergone a background investigation that included fingerprinting and an FBI criminal history records check and has been determined to be trustworthy and reliable by the licensee; or (b) The individual is subject to a category listed in subdivision 5 a of this subsection.

c. Informed consent.

(1) Licensees may not initiate a background investigation without the informed and signed consent of the subject individual. This consent shall include authorization to share personal information with other individuals or organizations as necessary to complete the background investigation. Before a final adverse determination, the licensee shall provide the individual with an opportunity to correct any inaccurate or incomplete information that is developed during the background investigation. Licensees do not need to obtain signed consent from those individuals who meet the requirements of subdivision 3 b of this subsection. A signed consent shall be obtained prior to any reinvestigation.

(2) The subject individual may withdraw his consent at any time. Licensees shall inform the individual that:

(a) If an individual withdraws his consent, the licensee may not initiate elements of the background investigation that were not in progress at the time the individual withdrew his consent; and (b) The withdrawal of consent for the background investigation is sufficient cause of denial or termination of unescorted access authorization.

d. Any individual who is applying for unescorted access authorization shall disclose the personal history information that is required by the licensee's access authorization program for the reviewing official to make a determination of the individual's trustworthiness and reliability. Refusal to provide, or the falsification of, any personal history information required by this subsection is sufficient cause for denial or termination of unescorted access.

e. Determination basis.

(1) The reviewing official shall determine whether to permit, deny, unfavorably terminate, maintain, or administratively withdraw an individual's unescorted access authorization based on an evaluation of all the information collected to meet the requirements of this subsection.

(2) The reviewing official may not permit any individual to have unescorted access until the reviewing official has evaluated all the information collected to meet the requirements of this subsection and determined that the individual is trustworthy and reliable. The reviewing official may deny unescorted access to any individual based on information obtained at any time during the background investigation.

(3) The licensee shall document the basis for concluding whether or not there is reasonable assurance that an individual is trustworthy and reliable.

(4) The reviewing official may terminate or administratively withdraw an individual's unescorted access authorization based on information obtained after the background investigation has been completed and the individual granted unescorted access information.

(5) Licensees shall maintain a list of persons currently approved for unescorted access authorization. When a licensee determines that a person no longer requires unescorted access or meets the access authorization requirement, the licensee shall remove the person from the approved list as soon as possible, but no later than seven working days, and take prompt measures to ensure that the individual is unable to have unescorted access to the material.

f. Licensees shall develop, implement, and maintain written procedures for implementing the access authorization program. The procedures shall include the provisions for the notification of individuals who are denied unescorted access. The procedures shall include provisions for the review, at the request of the affected individual, of a denial or termination of unescorted access authorization. The procedures shall contain a provision to ensure that the individual is informed of the grounds for the denial or termination of unescorted access authorization and allow the individual an opportunity to provide additional relevant information.

g. Right to correct and complete information.

(1) Prior to any final adverse determination, licensees shall provide each individual subject to this subsection with the right to complete, correct, and explain information obtained as a result of the licensee's background investigation. Confirmation of receipt by the individual of this notification shall be maintained by the licensee for a period of one year from the date of the notification.

(2) If, after reviewing his criminal history record, an individual believes that it is incorrect or incomplete in any respect and wishes to change, correct, update, or explain anything in the record, the individual may initiate challenge procedures. These procedures include direct application by the individual challenging the record to the law-enforcement agency that contributed the questioned information or a direct challenge as to the accuracy or completeness of any entry on the criminal history record to the Federal Bureau of

Investigation, Criminal Justice Information Services (CJIS) Division, ATTN: SCU, Mod. D-2, 1000 Custer Hollow Road, Clarksburg, WV 26306 as set forth in 28 CFR 16.30 through 28 CFR 16.34. In the latter case, the Federal Bureau of Investigation (FBI) will forward the challenge to the agency that submitted the data and will request that the agency verify or correct the challenged entry. Upon receipt of an official communication directly from the agency that contributed the original information, the FBI Identification Division will make any change necessary in accordance with the information supplied by that agency.

Licensees shall provide at least 10 days for an individual to initiate action to challenge the results of an FBI criminal history records check after the record being made available for his review. The licensee may make a final adverse determination based upon the criminal history records only after receipt of the FBI's confirmation or correction of the record.

h. Records.

(1) The licensee shall retain documentation regarding the trustworthiness and reliability of individual employees for three years from the date the individual no longer requires unescorted access to Category 1 or Category 2 quantities of radioactive material.

(2) The licensee shall retain a copy of the current access authorization program procedures as a record for three years after the procedure is no longer needed. If any portion of the procedure is superseded, the licensee shall retain the superseded material for three years after the record is superseded.

(3) The licensee shall retain the list of individuals approved for unescorted access authorization for three years after the list is superseded or replaced.

3. Background investigations.

a. Before allowing an individual unescorted access to Category 1 or Category 2 quantities of radioactive material or to the devices containing the material, licensees shall complete a background investigation of the individual seeking unescorted access authorization. The scope of the investigation shall encompass at least the seven years preceding the date of the background investigation or since the individual's 18th birthday, whichever is shorter.

The background investigation shall include at a minimum:

(1) Fingerprinting and an FBI identification and criminal history records check in accordance with subdivision 4 of this subsection; (2) Verification of true identity of the individual who is applying for unescorted access authorization. A licensee shall review official identification documents (e.g., driver's license; passport; government identification; certificate of birth issued by the state, province, or country of birth) and compare the documents to personal information data provided by the individual to identify any discrepancy in the information. Licensees shall document the type, expiration, and identification number of the identification document or maintain a photocopy of identifying documents on file in accordance with subdivision 6 of this subsection. Licensees shall certify in writing that the identification was properly reviewed and shall maintain the certification and all related documents for review upon inspection; (3) Verification of employment history, including military history. Licensees shall verify the individual's employment with each previous employer for the most recent seven years before the date of application; (4) Verification that the individual participated in the education process during the claimed period; (5) Completion of reference checks to determine the character and reputation of the individual who has applied for unescorted access authorization. Unless other references are not available, reference checks may not be conducted with any person who is known

to be a close member of the individual's family, including but not limited to, the individual's spouse, parents, siblings, or children, or any individual who resides in the individual's permanent household. Reference checks under this subsection shall be limited to whether the individual has been and continues to be trustworthy and reliable; (6) To the extent possible, obtain independent information to corroborate the information provided by the individual (e.g., seek references not supplied by the individual); and (7) If a previous employer, educational institution, or any other entity with which the individual claims to have been engaged fails to provide the information or indicates an inability or unwillingness to provide information within a timeframe deemed appropriate by the licensee but at least after 10 business days of the request or if the licensee is unable to reach the entity, the licensee shall document the refusal, unwillingness, or inability in the record of investigation and attempt to obtain the information from an alternate source.

b. Individuals who have been determined to be trustworthy and reliable for unescorted access to Category 1 or Category 2 quantities of radioactive material in accordance with fingerprint orders as effective on October 3, 2008, can continue to have unescorted access to Category 1 and Category 2 quantities of radioactive material without further investigation. These individuals shall be subject to the reinvestigation requirement of subdivision 3 c of this subsection.

c. Licensees shall conduct a reinvestigation every 10 years for any individual with unescorted access to Category 1 or Category 2 quantities of radioactive material. The reinvestigation shall consist of fingerprinting and an FBI identification and criminal history records check in accordance with subdivision 4 of this subsection. The reinvestigations shall be completed within 10 years of the date on which these elements were last completed.

4. Requirements for criminal history records checks of individuals granted unescorted access to Category 1 or Category 2 quantities of radioactive material.

a. General performance objective and requirements.

(1) Except for those individuals listed in subdivision 5 a of this subsection and those individuals grandfathered under subdivision 3 b of this subsection, each licensee subject to the provisions of this section shall fingerprint each individual who is to be permitted unescorted access to Category 1 or Category 2 quantities of radioactive material. The licensee shall submit all collected fingerprints to the NRC for transmission to the FBI. The licensee shall use the information received from the FBI as part of the required background investigation to determine whether to grant or deny further unescorted access to Category 1 or Category 2 quantities of radioactive materials for that individual.

(2) The licensee shall notify each affected individual that his fingerprints will be used to secure a review of his criminal history record and shall inform him of the procedures for revising the record or adding explanations to the record.

(3) Fingerprinting is not required if a licensee is reinstating an individual's unescorted access authorization to Category 1 or Category 2 quantities of radioactive material if:

(a) The individual returns to the same facility that granted unescorted access authorization within 365 days of the termination of his unescorted access authorization; and (b) The previous access was terminated under favorable conditions.

(4) Fingerprints do not need to be taken if an individual who is an employee of a licensee, contractor, manufacturer, or supplier has been granted unescorted access to Category 1 or Category 2 quantities of radioactive material, access to safeguards information, or safeguards information-modified handling by another licensee based upon a background investigation conducted under this subsection, regulations or Fingerprint Orders from

another Agreement state, or 10 CFR Part 73. An existing criminal history records check file may be transferred to the licensee asked to grant unescorted access in accordance with the provisions of subdivision 6 c of this subsection.

(5) Licensees shall use the information obtained as part of a criminal history records check solely for the purpose of determining an individual's suitability for unescorted access authorization to Category 1 or Category 2 quantities of radioactive materials, access to safeguards information, or safeguards information-modified handling.

b. Prohibitions.

(1) Licensees may not base a final determination to deny an individual unescorted access authorization to Category 1 or Category 2 quantities of radioactive material solely on the basis of information received from the FBI involving:

(a) An arrest more than one year old for which there is no information of the disposition of the case; or (b) An arrest that resulted in dismissal of the charge or an acquittal.

(2) Licensees may not use information received from a criminal history records check obtained under this subsection in a manner that would infringe upon the rights of any individual under the First Amendment to the Constitution of the United States, nor shall licensees use the information in any way that would discriminate among individuals on the basis of race, religion, national origin, gender, or age.

c. Procedures for processing of fingerprint checks.

(1) For the purpose of complying with this subsection, licensees shall use an appropriate method listed in 10 CFR 37.7 to submit to the U.S. Nuclear Regulatory Commission, Director, Division of Physical and Cyber Security Policy, 11545 Rockville Pike, ATTN:

Criminal History Program/Mail Stop T-8B20 T-07D04M, Rockville, MD, 20852, one completed, legible standard fingerprint card (form FD-258, ORIMDNRCOOOZ), electronic fingerprint scan, or, where practicable, other fingerprint record for each individual requiring unescorted access to Category 1 or Category 2 quantities of radioactive material. Copies of these forms may be obtained by emailing MAILSVS.Resource@nrc.gov. Guidance on submitting electronic fingerprints can be found at https://www.nrc.gov/security/chp.html.

(2) Fees for processing of fingerprint cards are due upon application. Licensees shall submit payment with the application for the processing of fingerprints through corporate check, certified check, cashier's check, money order, or electronic payment, made payable to the "U.S. NRC." (For guidance on making electronic payments, contact the Division of Physical and Cyber Security Policy by emailing crimhist.resource@nrc.gov.)

Combined payment for multiple applications is acceptable. The NRC publishes the amount of the fingerprint check application fee on the NRC public website. To find the current fee amount, go to the Licensee Criminal History Records Checks & Firearms Background Check information page at https://www.nrc.gov/security/chp.html and see the link for How do I determine how much to pay for the request?.

(3) The NRC will forward to the submitting licensee all data received from the FBI as a result of the licensee's application for a criminal history records check.

5. Relief.

a. Fingerprinting, identification and criminal history records checks, and other elements of the background investigation required by this subsection are not required for the following individuals prior to granting unescorted access to Category 1 or Category 2 quantities of radioactive material:

(1) An employee of the NRC or of the executive branch of the U.S. government who has undergone fingerprinting for a prior U.S. government criminal history records check;

(2) A member of Congress; (3) An employee of a member of Congress or congressional committee who has undergone fingerprinting for a prior U.S. government criminal history records check; (4) The governor of a state or his designated state employee representative; (5) Federal, state, or local law-enforcement personnel; (6) State radiation control program directors and state homeland security advisors or their designated employee representatives; (7) State radiation program employees conducting security inspections on behalf of the NRC under an agreement executed under § 274i of the Atomic Energy Act (42 USC § 2021i);

(8) Representatives of the International Atomic Energy Agency (IAEA) engaged in activities associated with the U.S./IAEA Safeguards Agreement who have been certified by the NRC; (9) Emergency response personnel who are responding to an emergency; (10) Commercial vehicle drivers for road shipments of Category 1 and Category 2 quantities of radioactive material; (11) Package handlers at transportation facilities such as freight terminals and railroad yards; (12) Any individual who has an active federal security clearance and provides the appropriate documentation. Written confirmation from the agency or employer that granted the federal security clearance or reviewed the criminal history records check shall be provided to the licensee. The licensee shall retain this documentation for a period of three years from the date the individual no longer requires unescorted access to Category 1 or Category 2 quantities of radioactive material; and (13) Any individual employed by a service provider licensee for whom the service provider licensee has conducted the background investigation for the individual and approved the individual for unescorted access to Category 1 or Category 2 quantities of radioactive material. Written verification from the service provider shall be provided to the licensee.

The licensee shall retain the documentation for a period of three years from the date the individual no longer requires unescorted access to Category 1 or Category 2 quantities of radioactive material.

b. Fingerprinting and identification and criminal history records checks required by this subsection are not required for an individual who has had a favorably adjudicated U.S.

Government criminal history records check within the last five years, under a comparable U.S. Government program involving fingerprinting and an FBI identification and criminal history records check, and the individual provides the appropriate documentation. Written confirmation from the agency or employer that reviewed the criminal history records check shall be provided to the licensee. The licensee shall retain this documentation for a period of three years from the date the individual no longer requires unescorted access to Category 1 or Category 2 quantities of radioactive material. These programs include, but are not limited to:

(1) National Agency Check; (2) Transportation Worker Identification Credentials (TWIC) under 49 CFR Part 1572; (3) Bureau of Alcohol, Tobacco, Firearms, and Explosives background check and clearances under 27 CFR Part 555; (4) Health and Human Services security risk assessments for possession and use of select agents and toxins under 42 CFR Part 73;

(5) Hazardous material security threat assessment for hazardous material endorsement to commercial driver's license under 49 CFR Part 1572; and (6) Customs and Border Protection's Free and Secure Trade (FAST) Program.

6. Protection of information.

a. Each licensee that obtains background information on an individual under this subsection shall establish and maintain a system of files and written procedures for protection of the record and the personal information from unauthorized disclosure.

b. The licensee may not disclose the record or personal information collected and maintained to persons other than the subject individual, his representative, or to those who have a need to have access to the information in performing assigned duties in the process of granting or denying unescorted access to Category 1 or Category 2 quantities of radioactive material. No individual authorized to have access to the information may disseminate the information to any other individual who does not have a need to know.

c. The personal information obtained on an individual from a background investigation may be provided to another licensee:

(1) Upon the individual's written request to the licensee holding the data to disseminate the information contained in that individual's file; and (2) The recipient licensee verifies information such as name, date of birth, social security number, gender, and other applicable physical characteristics.

d. The licensee shall make background investigation records obtained under this subsection available for examination by an authorized representative of the agency to determine compliance with the regulations and laws.

e. The licensee shall retain all fingerprint and criminal history records (including data indicating no record) received from the FBI, or a copy of these records if the individual's file has been transferred, on an individual for three years from the date the individual no longer requires unescorted access to Category 1 or Category 2 quantities of radioactive material.

7. Access authorization program review.

a. Each licensee shall be responsible for the continuing effectiveness of the access authorization program. Each licensee shall ensure that access authorization programs are reviewed to confirm compliance with the requirements of this subsection and that comprehensive actions are taken to correct any noncompliance that is identified. The review program shall evaluate all program performance objectives and requirements. The review shall be performed at least annually.

b. The results of the reviews, along with all recommendations, shall be documented. Each review report shall identify conditions that are adverse to the proper performance of the access authorization program; the cause of the conditions and, when appropriate, recommend corrective actions; and corrective actions taken. The licensee shall review the findings and take additional corrective actions necessary to preclude repetition of the condition, including reassessment of the deficient areas where indicated.

c. Review records shall be maintained for three years.

C. Physical protection requirements during use.

1. Security program.

a. Each licensee that possesses an aggregated Category 1 or Category 2 quantity of radioactive material shall establish, implement, and maintain a security program in accordance with the requirements of this subsection. An applicant for a new license and each licensee that would become newly subject to the requirements of this subsection

upon an amendment request for modification of its license shall implement the requirements of this subsection, as appropriate, before taking possession of an aggregated Category 1 or Category 2 quantity of radioactive material. Any licensee that has not previously implemented the requirements of this subsection shall provide written notification to the agency at least 90 days before aggregating radioactive material to a quantity that equals or exceeds the Category 2 threshold.

b. Each licensee shall establish, implement, and maintain a security program that is designed to monitor and, without delay, detect, assess, and respond to an actual or attempted unauthorized access to Category 1 or Category 2 quantities of radioactive material.

c. Each licensee's security program shall include the program features, as appropriate, described in subdivisions 2 through 8 of this subsection.

2. General security program requirements.

a. Security plan.

(1) Each licensee identified in subdivision 1 a of this subsection shall develop a written security plan specific to its facilities and operations. The purpose of the security plan is to establish the licensee's overall security strategy to ensure the integrated and effective functioning of the security program required by this subsection. The security plan shall, at a minimum, (i) describe the measures and strategies used to implement the requirements of this subsection and (ii) identify the security resources, equipment, and technology used to satisfy the requirements of this subsection.

(2) The security plan shall be reviewed and approved by the individual with overall responsibility for the security program.

(3) A licensee shall revise its security plan as necessary to ensure the effective implementation of agency requirements. The licensee shall ensure that (i) the revision has been reviewed and approved by the individual with overall responsibility for the security program and (ii) the affected individuals are instructed on the revised plan before the changes are implemented.

(4) The licensee shall retain a copy of the current security plan as a record for three years after the security plan is no longer required. If any portion of the plan is superseded, the licensee shall retain the superseded material for three years after the record is superseded.

b. Implementing procedures.

(1) The licensee shall develop and maintain written procedures that document how the requirements of this subsection and the security plan will be met.

(2) The implementing procedures and revisions to these procedures shall be approved in writing by the individual with overall responsibility for the security program.

(3) The licensee shall retain a copy of the current procedure as a record for three years after the procedure is no longer needed. Superseded portions of the procedure shall be retained for three years after the record is superseded.

c. Training.

(1) Each licensee shall conduct training to ensure that those individuals implementing the security program possess and maintain the knowledge, skills, and abilities to carry out their assigned duties and responsibilities effectively. The training shall include at a minimum, instruction on:

(a) The licensee's security program and procedures to secure Category 1 or Category 2 quantities of radioactive material, and the purpose and function of the security measures employed; (b) The responsibility to report promptly to the licensee any condition that causes or may cause a violation of agency requirements; (c) The responsibility of the licensee to report promptly to the local law-enforcement agency and the agency any actual or attempted theft, sabotage, or diversion of Category 1 or Category 2 quantities of radioactive material; and (d) The appropriate response to security alarms.

(2) In determining those individuals who shall be trained on the security program, the licensee shall consider each individual's assigned activities during authorized use and response to potential situations involving actual or attempted theft, diversion, or sabotage of Category 1 or Category 2 quantities of radioactive material. The extent of the training shall be commensurate with the individual's potential involvement in the security of Category 1 or Category 2 quantities of radioactive material.

(3) Refresher training shall be provided at a frequency not to exceed 12 months and when significant changes have been made to the security program. This training shall include (i) review of the training requirements of this subsection and changes made to the security program since the last training; (ii) reports on all relevant security issues, problems, and lessons learned; (iii) relevant results of agency inspections; and (iv) relevant results of the licensee's program review and testing and maintenance.

(4) The licensee shall maintain records of the initial and refresher training for three years from the date of the training. The training records shall include dates of the training, topics covered, a list of licensee personnel in attendance, and related information.

d. Protection of information.

(1) Licensees authorized to possess Category 1 or Category 2 quantities of radioactive material shall limit access to and prevent the unauthorized disclosure of their security plan, implementing procedures, and the list of individuals who have been approved for unescorted access.

(2) Efforts to limit access shall include the development, implementation, and maintenance of written policies and procedures for controlling access to and for proper handling and protection against unauthorized disclosure of the security plan, implementing procedures, and the list of individuals who have been approved for unescorted access.

(3) Before granting an individual access to the security plan, implementing procedures, or the list of individuals who have been approved for unescorted access, licensees shall:

(a) Evaluate an individual's need to know the security plan, implementing procedures, or the list of individuals who have been approved for unescorted access; and (b) If the individual has not been authorized for unescorted access to Category 1 or Category 2 quantities of radioactive material, the licensee shall complete a background investigation to determine the individual's trustworthiness and reliability. A trustworthiness and reliability determination shall be conducted by the reviewing official and shall include the background investigation elements contained in subdivisions B 3 a (2) through (7) of this section.

(4) Licensees need not subject any individual to background investigation elements for protection of information if that individual is included in the categories of individuals listed in subdivisions B 5 a (1) through (12) of this section or is a security service provider employee, provided written verification that the employee has been determined to be

trustworthy and reliable, by the required background investigation in subdivisions B 3 a (2) though (7) of this subsection, has been provided by the security service provider.

(5) The licensee shall document the basis for concluding that an individual is trustworthy and reliable and should be granted access to the security plan, implementing procedures, or the list of individuals who have been approved for unescorted access.

(6) Licensees shall maintain a list of persons currently approved for access to the security plan implementing procedures, or the list of individuals who have been approved for unescorted access. When a licensee determines that a person no longer needs access to the security plan, implementing procedures, or the list of individuals who have been approved for unescorted access or no longer meets the access authorization requirements for access to the information, the licensee shall remove the person from the approved list as soon as possible, but no later than seven working days after the determination, and take prompt measures to ensure that the individual is unable to obtain the security plan, implementing procedures, or the list of individuals who have been approved for unescorted access.

(7) When not in use, the licensee shall store its security plan, implementing procedures, and the list of individuals who have been approved for unescorted access in a manner to prevent unauthorized access. Information stored in nonremovable electronic form shall be password protected.

(8) The licensee shall retain as a record a copy of the information protection procedures and the list of individuals approved for access to the security plan, implementing procedures, or the list of individuals who have been approved for unescorted access for three years after the document has been superseded.

3. Local law-enforcement agency (LLEA) coordination.

a. A licensee subject to this subsection shall coordinate, to the extent practicable, with an LLEA for responding to threats to the licensee's facility, including any necessary armed response. The information provided to the LLEA shall include:

(1) A description of the facilities and the Category 1 and Category 2 quantities of radioactive materials along with a description of the licensee's security measures that have been implemented to comply with this subsection; and (2) A notification that the licensee will request a timely armed response by the LLEA to any actual or attempted theft, sabotage, or diversion of Category 1 or Category 2 quantities of material.

b. The licensee shall notify the agency within three business days if:

(1) The LLEA has not responded to the request for coordination within 60 days of the coordination request; or (2) The LLEA notifies the licensee that the LLEA does not plan to participate in coordination activities.

c. The license shall document its efforts to coordinate with the LLEA. The documentation shall be kept for three years.

d. The licensee shall coordinate with the LLEA at least every 12 months, or when changes to the facility design or operation adversely affect the potential vulnerability of the licensee's material to theft, sabotage, or diversion.

4. Security zones.

a. Licensees shall ensure that all aggregated Category 1 or Category 2 quantities of radioactive material are used or stored within licensee-established security zones.

Security zones may be permanent or temporary.

b. Temporary security zones shall be established as necessary to meet the licensee's transitory or intermittent business activities, such as periods of maintenance, source delivery, and source replacement.

c. Security zones shall, at a minimum, allow unescorted access only to approved individuals by:

(1) Isolation of Category 1 and Category 2 quantities of radioactive materials by the use of continuous physical barriers that allow access to the security zone only through established access control points. A physical barrier is a natural or man-made structure or formation sufficient for the isolation of the Category 1 or Category 2 quantities of radioactive material within a security zone; (2) Direct control of the security zone by approved individuals at all times; or (3) A combination of continuous physical barriers and direct control.

d. For Category 1 quantities of radioactive material during periods of maintenance, source receipt, preparation for shipment, installation, or source removal or exchange, the licensee shall, at a minimum, provide sufficient individuals approved for unescorted access to maintain continuous surveillance of sources in temporary security zones and in any security zone in which physical barriers or intrusion detection systems have been disabled to allow such activities.

e. Individuals not approved for unescorted access to Category 1 or Category 2 quantities of radioactive material shall be escorted by an approved individual when in a security zone.

5. Monitoring, detection, and assessment.

a. Monitoring and detection.

(1) Licensees shall establish and maintain the capability to continuously monitor and detect without delay all unauthorized entries into its security zones. Licensees shall provide the means to maintain continuous monitoring and detection capability in the event of a loss of the primary power source, or provide for an alarm and response in the event of a loss of this capability to continuously monitor and detect unauthorized entries.

(2) Monitoring and detection shall be performed by:

(a) A monitored intrusion detection system that is linked to an onsite or offsite central monitoring facility; (b) Electronic devices for intrusion detection alarms that will alert nearby facility personnel; (c) A monitored video surveillance system; (d) Direct visual surveillance by approved individuals located within the security zone; or (e) Direct visual surveillance by a licensee designed individual located outside the security zone.

(3) A licensee subject to this subsection shall also have a means to detect unauthorized removal of the radioactive material from the security zone. This detection capability shall provide:

(a) For Category 1 quantities of radioactive material, immediate detection of any attempted unauthorized removal of the radioactive material from the security zone. Such immediate detection capability shall be provided by electronic sensors linked to an alarm, continuous monitored video surveillance, or direct visual surveillance; and (b) For Category 2 quantities of radioactive material, weekly verification through physical checks, tamper indicating devices, use, or other means to ensure that the radioactive material is present.

b. Licensees shall immediately assess each actual or attempted unauthorized entry into the security zone to determine whether the unauthorized access was an actual or attempted theft, sabotage, or diversion.

c. For personnel and automated or electronic systems supporting the licensee's monitoring, detection, and assessments system, licensees shall:

(1) Maintain continuous capability for personnel communication and electronic data transmission and processing among site security systems; and (2) Provide an alternate communication capability for personnel, and an alternative data transmission and processing capability, in the event of a loss of the primary means of communication or data transmission and processing. Alternative communications and data transmissions systems may not be subject to the same failure modes as the primary systems.

d. Licensees shall immediately respond to any actual or attempted unauthorized access to the security zones, or actual or attempted theft, sabotage, or diversion of Category 1 or Category 2 quantities of radioactive material at licensee facilities or temporary job sites.

For any unauthorized access involving an actual or attempted theft, sabotage, or diversion of Category 1 or Category 2 quantities of radioactive material, the licensee's response shall include requesting, without delay, an armed response from the LLEA.

6. Maintenance and testing.

a. Each licensee subject to this subsection shall implement a maintenance and testing program to ensure that intrusion alarms, associated communication systems, and other physical components of the systems used to secure or detect unauthorized access to radioactive material are maintained in operable condition and are capable of performing their intended function when needed. The equipment relied on to meet the security requirements of this subsection shall be inspected and tested for operability and performance at the manufacturer's suggested frequency. If there is no frequency suggested by the manufacturer or the frequency specified is greater than three months, the testing shall be performed at least quarterly, not to exceed three months.

b. The licensee shall maintain records on the maintenance and testing activities for three years.

7. Requirements for mobile devices. Each licensee that possesses mobile devices containing Category 1 or Category 2 quantities of radioactive material shall:

a. Have two independent physical controls that form tangible barriers to secure the material from unauthorized removal when the device is not under direct control and constant surveillance by the licensee; and

b. For devices in or on a vehicle or trailer, unless the health and safety requirements for a site prohibit the disabling of the vehicle, the licensee shall utilize a method to disable the vehicle or trailer when not under direct control and constant surveillance by the licensee.

Licensees shall not rely on the removal of an ignition key to meet this requirement.

8. Security program review.

a. Each licensee shall be responsible for the continuing effectiveness of the security program. Each licensee shall ensure that the security program is reviewed to confirm compliance with the requirements of this subsection and that comprehensive actions are taken to correct any noncompliance that is identified. The review shall include the radioactive material security program content and implementation. The review shall be conducted at least annually, not to exceed 12 months.

b. The results of the review, along with all recommendations, shall be documented. Each review report shall identify conditions that are adverse to the proper performance of the

security program, the cause of the condition, corrective actions taken, and, when appropriate, recommend corrective actions. The licensee shall review the findings and take any additional corrective actions necessary to preclude repetition of the condition, including reassessment of the deficient areas where indicated.

c. The licensee shall maintain the review documentation for three years.

9. Reporting of events.

a. The licensee shall immediately notify the LLEA after determining that an unauthorized entry resulted in an actual or attempted theft, sabotage, or diversion of Category 1 or Category 2 quantity of radioactive material. As soon as possible after initiating a response, but not at the expense of causing delay or interfering with the LLEA response to the event, the licensee shall notify the agency by telephone at 804-864-8150 during normal business hours and 804-674-2400 after hours. In no case shall the notification to the agency be later than four hours after the discovery of any attempted or actual theft, sabotage, or diversion.

b. The licensee shall assess any suspicious activity related to possible theft, sabotage, or diversion of Category 1 or Category 2 quantities of radioactive material and notify the LLEA as appropriate. As soon as possible but not later than four hours after notifying the LLEA, the licensee shall notify the agency by telephone 804-864-8150 during normal business hours and 804-674-2400 after hours.

c. The initial telephonic notification shall be followed within a period of 30 days by a written report submitted to the agency. The report shall include sufficient information for agency analysis and evaluation, including identification of any necessary corrective actions to prevent future instances.

D. Physical protection in transit.

1. Additional requirements for transfer of Category 1 and Category 2 quantities of radioactive material. A licensee transferring a Category 1 or Category 2 quantity of radioactive material to a licensee of the agency, the NRC, or another Agreement state shall meet the license verification provisions listed in this subdivision instead of those listed in 12VAC5-481-570.

a. Any licensee transferring Category 1 quantities of radioactive material to a licensee of the agency, the NRC, or another Agreement state, prior to conducting such transfer, shall verify with the NRC's license verification system or the license issuing authority that the transferee's license authorizes the receipt of the type, form, and quantity of radioactive material to be transferred and that the licensee is authorized to receive radioactive material at the location requested for delivery. If the verification is conducted by contacting the license-issuing authority, the transferor shall document the verification. For transfers within the same organization, the licensee does not need to verify the transfer.

b. Any licensee transferring Category 2 quantities of radioactive material to a licensee of the agency, the NRC, or another Agreement state, prior to conducting such transfer, shall verify with the NRC's license verification system or the license-issuing authority that the transferee's license authorizes the receipt of the type, form, and quantity of radioactive material to be transferred. If the verification is conducted by contacting the license-issuing authority, the transferor shall document the verification. For transfers within the same organization, the licensee does not need to verify the transfer.

c. In an emergency where the licensee cannot reach the license-issuing authority and the license verification system is nonfunctional, the licensee may accept a written certification by the transferee that it is authorized by license to receive the type, form, and quantity of radioactive material to be transferred. The certification shall include the license number, current revision number, issuing agency, expiration date, and for a Category 1 shipment,

the authorized address. The licensee shall keep a copy of the certification. The certification shall be confirmed by use of the NRC's license verification system or by contacting the license-issuing authority by the end of the next business day.

d. The transferor shall keep a copy of the verification documentation as a record for three years.

2. Applicability of physical protection of Category 1 and Category 2 quantities of radioactive material during transit.

a. For shipments of category 1 quantities of radioactive material, each shipping licensee shall comply with the requirements for physical protection contained in subdivisions 3 a, 3 e, 4, 5 a (1), 5 b (1), 5 c, 6 a, 6 c, 6 e, 6 g, and 6 h of this subsection.

b. For shipments of Category 2 quantities of radioactive material, each shipping licensee shall comply with the requirements for physical protection contained in subdivisions 3 b through 3 e, 5 a (2), 5 a (3), 5 b (2), 5 c, 6 b, 6 d, 6 f, 6 g, and 6 h of this subsection.

c. The shipping licensee shall be responsible for meeting the requirements of this subsection unless the receiving licensee has agreed in writing to arrange for the in-transit physical protection required under this subsection.

3. Preplanning and coordination of shipment of Category 1 or Category 2 quantities of radioactive material.

a. Each licensee that plans to transport, or deliver to a carrier for transport, licensed material that is a Category 1 quantity of radioactive material outside the confines of the licensee's facility or other place of use or storage shall:

(1) Preplan and coordinate shipment arrival and departure times with the receiving licensee; (2) Preplan and coordinate shipment information with the governor or the governor's designee of any state through which the shipment will pass to discuss the state's intention to provide law-enforcement escorts and identify safe havens; and (3) Document the preplanning and coordination activities.

b. Each licensee that plans to transport, or deliver to a carrier for transport, licensed material that is a Category 2 quantity of radioactive material outside the confines of the licensee's facility or other place of use or storage shall coordinate the shipment no-later-than arrival time and the expected shipment arrival with the receiving licensee. The licensee shall document the coordination activities.

c. Each licensee that receives a shipment of a Category 2 quantity of radioactive material shall confirm receipt of the shipment with the originator. If the shipment has not arrived by the no-later-than arrival time, the receiving licensee shall notify the originator.

d. Each licensee that transports or plans to transport a shipment of a Category 2 quantity of radioactive material and determines that the shipment will arrive after the no-later-than arrival time provided pursuant to subdivision 3 b of this subsection, shall promptly notify the receiving licensee of the new no-later-than arrival time.

e. The licensee shall retain a copy of the documentation for preplanning and coordination and any revision thereof as a record for three years.

4. As specified in subdivision 3 of this subsection, each licensee shall provide advance notification to the agency and the governor of a state, or the governor's designee, of the shipment of licensed material in a Category 1 quantity, through or across the boundary of the state, before the transport or delivery to a carrier for transport of the licensed material outside the confines of the licensee's facility or other place of use or storage.

a. Procedures for submitting advance notification:

(1) The notification shall be made to the agency and to the office of each appropriate governor or governor's designee. The contact information, including telephone and mailing addresses, of governors and governor's designees is available on the NRC website at https://scp.nrc.gov/special/designee.pdf. The notification to the agency shall be in accordance with 12VAC5-481-150.

(2) A notification delivered by mail shall be postmarked at least seven days before transport of the shipment commences at the shipping facility.

(3) A notification delivered by any means other than mail shall reach the agency at least four days before the transport of the shipment commences and shall reach the office of the governor or the governor's designee at least four days before transport of a shipment within or through the state.

b. Each advance notification of shipment of Category 1 quantities of radioactive material shall contain the following information, if available at the time of the notification:

(1) The name, address, and telephone number of the shipper, carrier, and receiver of the Category 1 radioactive material; (2) The license numbers of the shipper and receiver; (3) A description of the radioactive material contained in the shipment, including the radionuclides and quantity; (4) The point of origin of the shipment and the estimated time and date that shipment will commence; (5) The estimated time and date that the shipment is expected to enter each state along the route; (6) The estimated time and date of arrival for the shipment at the destination; and (7) A point of contact, with a telephone number, for current shipment information.

c. Revision notice.

(1) The licensee shall provide any information not previously available at the time of the initial notification, as soon as the information becomes available but not later than commencement of the shipment, to the agency and the governor of the state or the governor's designee.

(2) A licensee shall promptly notify the agency and governor of the state or the governor's designee of any changes to the information provided in accordance with this subdivision.

d. Each licensee who cancels a shipment for which advance notification has been sent shall send a cancellation notice to the agency and the governor of each state or to the governor's designee previously notified. The licensee shall send the cancellation notice before the shipment would have commenced or as soon thereafter as possible. The licensee shall state in the notice that it is a cancellation and identify the advance notification that is being canceled.

e. The licensee shall retain a copy of the advance notification and any revision and cancellation notices as a record for three years.

f. State officials, state employees, and other individuals, whether or not licensees of the agency, NRC, or another Agreement state, who receive schedule information of the kind specified in subdivision 4 b of this subsection shall protect that information against unauthorized disclosure as specified in subdivision C 2 d of this section.

5. Requirements for physical protection of Category 1 and Category 2 quantities of radioactive material during shipment.

a. Shipments by road.

(1) Each licensee who transports or delivers to a carrier for transport in a single shipment a Category 1 quantity of radioactive material shall:

(a) Ensure that movement control centers are established that maintain position information from a remote location. These control centers shall monitor shipments 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, seven days a week and have the ability to communicate immediately, in an emergency, with the appropriate law-enforcement agencies; (b) Ensure that redundant communications are established that allow the transport to contact the escort vehicle, when an escort vehicle is used, and movement control center at all times. Redundant communications may not be subject to the same interference factors as the primary communication; (c) Ensure that shipments are continuously and actively monitored by a telemetric position monitoring system or an alternative tracking system reporting to a movement control center. A movement control center shall provide positive confirmation of the location, status, and control over the shipment. The movement control center shall be prepared to promptly implement preplanned procedures in response to deviations from the authorized route or a notification of actual, attempted, or suspicious activities related to the theft, loss, or diversion of a shipment. These procedures will include, but not be limited to, the identification of and contact information for the appropriate LLEA along the shipment route; (d) Provide an individual to accompany the driver for those highway shipments with a driving time period greater than the maximum number of allowable hours of service in a 24-hour duty day as established by the U.S. Department of Transportation Federal Motor Carrier Safety Administration. The accompanying individual may be another driver; and (e) Develop written normal and contingency procedures to address (i) notifications to the communication center and law-enforcement agencies; (ii) communication protocols that shall include a strategy for the use of authentication codes and duress codes and provisions for refueling and other stops, detours, and locations where communication is expected to be temporarily lost; (iii) loss of communication; and (iv) responses to an actual or attempted theft or diversion of a shipment.

(f) Each licensee who makes arrangements for the shipment of Category 1 quantities of radioactive material shall ensure that drivers, accompanying personnel, and movement control center personnel have access to the normal and contingency procedures.

(2) Each licensee that transports Category 2 quantities of radioactive material shall maintain constant control and surveillance during transit and have the capability for immediate communication to summon appropriate response or assistance.

(3) Each licensee who delivers to a carrier for transport in a single shipment a Category 2 quantity of radioactive material shall:

(a) Use carriers that have established package tracking systems. An established package tracking system is a documented, proven, and reliable system routinely used to transport objects of value. In order for a package tracking system to maintain constant control and surveillance, the package tracking system shall allow the shipper or transporter to identify when and where the package was last and when it should arrive at the next point of control; (b) Use carriers that maintain constant control and surveillance during transit and have the capability for immediate communication to summon appropriate response or assistance; and (c) Use carriers that have established tracking systems that require an authorized signature prior to releasing the package for delivery or return.

b. Shipments by rail.

(1) Each licensee who transports, or delivers to a carrier for transport, in a single shipment a Category 1 quantity of radioactive material shall:

(a) Ensure that rail shipments are monitored by a telemetric position monitoring system or an alternative tracking system reporting to the licensee, third-party, or railroad communications center. The communications center shall provide positive confirmation of the location of the shipment and its status. The communications center shall implement preplanned procedures in response to deviations from the authorized route or to a notification of actual, attempted, or suspicious activities related to the theft or diversion of a shipment. These procedures will include, but not be limited to, the identification of and contact information for the appropriate LLEA along the shipment route; and (b) Ensure that periodic reports to the communications center are made at preset intervals.

(2) Each licensee who transports, or delivers to a carrier for transport, in a single shipment a Category 2 quantity of radioactive material shall:

(a) Use carriers that have established package tracking systems. An established package tracking system is a documented, proven, and reliable system routinely used to transport objects of value. In order for a package tracking system to maintain constant control and surveillance, the package tracking system shall allow the shipper or transporter to identify when and where the package was last and when it should arrive at the next point of control; (b) Use carriers that maintain constant control and surveillance during transit and have the capability for immediate communication to summon appropriate response or assistance; and (c) Use carriers that have established tracking systems that require an authorized signature prior to releasing the package for delivery or return.

c. Each licensee who makes arrangements for the shipment of Category 1 quantities of radioactive material shall immediately conduct an investigation upon discovery that a Category 1 shipment is lost or missing. Each licensee who makes arrangements for the shipment of Category 2 quantities of radioactive material shall immediately conduct an investigation, in coordination with the receiving licensee, of any shipment that has not arrived by the designated no-later-than arrival time.

6. Reporting of events.

a. The shipping licensee shall notify the appropriate LLEA and the agency within one hour of its determination that a shipment of Category 1 quantities of radioactive material is lost or missing. The appropriate LLEA would be the law-enforcement agency in the area of the shipment's last confirmed location. During the investigation required by this subsection, the shipping licensee will provide agreed upon updates to the agency on the status of the investigation.

b. The shipping licensee shall notify the agency within four hours of its determination that a shipment of Category 2 quantities of radioactive material is lost or missing. If, after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of its determination that the shipment is lost or missing, the radioactive material has not been located and secure, the licensee shall immediately notify the agency.

c. The shipping licensee shall notify the designated LLEA along the shipment route as soon as possible upon discovery of any actual or attempted theft of diversion of a shipment or suspicious activities related to the theft or diversion of a shipment of a Category 1 quantity of radioactive material. As soon as possible after notifying the LLEA, the licensee shall notify the agency upon discovery of any actual or attempted theft or diversion of a shipment, or any suspicious activity related to the shipment, of Category 1 radioactive material.

d. The shipping licensee shall notify the agency as soon as possible upon discovery of any actual or attempted theft or diversion of a shipment, or any suspicious activity related to the shipment, of a Category 2 quantity of radioactive material.

e. The shipping licensee shall notify the agency and the LLEA as soon as possible upon recovery of any lost or missing Category 1 quantities of radioactive material.

f. The shipping licensee shall notify the agency as soon as possible upon recovery of any lost or missing Category 2 quantities of radioactive material.

g. The initial telephonic notification required by subdivisions 6 a through 6 d of this subsection shall be followed within a period of 30 days by a written report submitted to the agency. A written report is not required for notifications on suspicious activities required by subdivisions 6 c and 6 d of this subsection. The report shall include the following information:

(1) A description of the licensed material involved, including kind, quantity, and chemical and physical form; (2) A description of the circumstances under which the loss or theft occurred; (3) A statement of disposition, or probable disposition, of the licensed material involved; (4) Actions that have been taken, or will be taken, to recover the material; and (5) Procedures or measures that have been, or will be, adopted to ensure against a recurrence of the loss or theft of licensed material.

h. Subsequent to filing the written report, the licensee shall also report any additional substantive information on the loss or theft within 30 days after the licensee learns of such information.

E. Records.

1. Each record required by this section shall be legible throughout the retention period specified. The record may be the original or a reproduced copy or a microform, provided that the copy or microform is authenticated by authorized personnel and that the microform is capable of producing a clear copy throughout the required retention period. The record may also be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period. Records such as letters, drawings, and specifications shall include all pertinent information such as stamps, initials, and signatures.

The licensee shall maintain adequate safeguards against tampering with and loss of records.

2. Licensees shall maintain the records that are required by this section for the period specified. If a retention period is not otherwise specified, these records shall be retained until the agency terminates the facility's license. All records related to this section may be destroyed upon agency termination of the facility license.

12VAC5-481-1700. Authority and responsibilities for the radiation protection programs and changes.

A. In addition to the radiation protection program requirements of 12VAC5-481-630, the a licensee's management or designee shall approve, in writing:

1. Requests for a license application, renewal, or amendment before submittal to the agency;

2. Any individual before allowing that individual to work as an authorized user, authorized nuclear pharmacist, or an authorized medical physicist; and

3. Radiation protection program changes that do not require a license amendment and are permitted under subsection F I of this section.

B. The licensee's management shall appoint a radiation safety officer (RSO) who agrees, in writing, to be responsible for implementing the radiation protection program.

The licensee, through the RSO, shall ensure that radiation safety activities are being performed in accordance with licensee-approved procedures and regulatory requirements. A licensee's management may appoint, in writing, one or more associate radiation safety officers to support the RSO. The RSO, with written agreement of the licensee's management, must assign the specific duties and tasks to each associate RSO. These duties and tasks are restricted to the types of use for which the associate radiation safety officer is listed on a license. The RSO may delegate duties and tasks to the associate radiation safety officer but shall not delegate the authority or responsibilities for implementing the radiation protection program.

C. For up to 60 days each year, licensees may permit an authorized user or an individual qualified to be a RSO, under 12VAC5-481-1750 and 12VAC5-481-1790, to function as a temporary radiation safety officer and to perform the functions of a Radiation Safety Officer, as provided in subsection G if the licensee takes the actions required in subsections B, E, G, and H of this section and notifies the agency in accordance with 12VAC5-481-1690 B.

D. Licensees may simultaneously appoint more than one temporary RSO in accordance with subsection C of this section, if needed to ensure that the temporary RSO licensee has a temporary Radiation Safety Officer that satisfies the requirements to be a RSO for each of the different types of uses of radioactive material permitted by the licensee license.

E. A licensee shall establish the authority, duties, and responsibilities of the Radiation Safety Officer in writing.

E. F. Licensees that are authorized for two or more different types of uses of radioactive material under Articles 6, 7, and 9 of this part, or two or more types of units under 12VAC5-481-2040 B, shall establish a Radiation Safety Committee (RSC) to oversee all uses of radioactive material permitted by the license. The RSC shall must include an authorized user for of each type of use permitted by the license, the RSO, a representative of the nursing service, and a representative of management who is neither an authorized user nor a RSO. The RSC may include other members the licensee considers appropriate.

F. G. A licensee shall provide the Radiation Safety Officer sufficient authority, organizational freedom, time, resources, and management prerogative, to-

1. Identify radiation safety problems;

2. Initiate, recommend, or provide corrective actions;

3. Stop unsafe operations; and,

4. Verify implementation of corrective actions.

H. A licensee shall retain a record of actions taken under paragraphs A, B and E of this section in accordance with 12VAC5-481-2070.

I. A licensee may revise its radiation protection program without agency approval if:

1. The revision does not require a license amendment under 12VAC5-481-450 or 12VAC5-481-1680;

2. The revision is in compliance with this chapter and the license;

3. The revision has been reviewed and approved by the RSO and licensee management; and

4. The affected individuals are instructed on the revised program before the changes are implemented.

12VAC5-481-1750. Training for radiation safety officer and associate radiation safety officer.

Except as provided in 12VAC5-481-1780, licensees shall require an individual fulfilling the responsibilities of the radiation safety officer (RSO) or an individual assigned duties and tasks as an associate radiation safety officer as provided in 12VAC5-481-1700 to be an individual who:

1. Is certified by a specialty board who has been recognized by the agency, the NRC, or an agreement state and who meets the requirements of subdivision 5 of this section. The names of board certifications that have been recognized by the NRC or an agreement state are posted on the NRC's Medical Uses Licensee Toolkit Web page. To have its certification process recognized, a specialty board shall require all candidates for certification to (i) hold a bachelor's or graduate degree from an accredited college or university in physical science or engineering or biological science with a minimum of 20 college credits in physical science; (ii) have five or more years of professional experience in health physics (graduate training may be substituted for no more than two years of the required experience) including at least three years in applied health physics; and (iii) pass an examination administered by diplomates of the specialty board that evaluates knowledge and competence in radiation physics and instrumentation, radiation protection, mathematics pertaining to the use and measurement of radioactivity, radiation biology, and radiation dosimetry; or

2. Holds a master's or doctor's degree in physics, medical physics, other physical science, engineering, or applied mathematics from an accredited college or university; has two years of full-time practical training or supervised experience in medical physics (i) under the supervision of a medical physicist who is certified in medical physics by a specialty board recognized by the agency, NRC, or an agreement state or (ii) in clinical nuclear medicine facilities providing diagnostic or therapeutic services under the direction of physicians who meet the requirements for authorized users in 12VAC5-481-1780, 12VAC5-481-1940, or 12VAC5-481-1980; and has passed an examination administered by diplomates of the specialty board that assesses knowledge and competence in clinical diagnostic radiological or nuclear medicine physics and in radiation safety; or

3. Has completed a structured educational program consisting of provisions, as follows:

a. 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of classroom and laboratory training in the following areas:

(1) Radiation physics and instrumentation; (2) Radiation protection; (3) Mathematics pertaining to the use and measurement of radioactivity; (4) Radiation biology; and (5) Radiation dosimetry; and

b. One year of full-time radiation safety experience under the supervision of the individual identified as the RSO on an agency, NRC, or another agreement state license or permit issued by an NRC master material licensee that authorizes similar types of uses of radioactive material. An associate radiation safety officer may provide supervision for those areas for which the associate radiation safety officer is authorized on an agency, NRC, or another agreement state license or permit issued by an NRC master material licensee. The full-time radiation safety experience must involve the following:

(1) Shipping, receiving, and performing related radiation surveys; (2) Using and performing checks for proper operation of instruments used to determine the activity of dosages, survey meters, and instruments used to measure radionuclides; (3) Securing and controlling radioactive material; (4) Using administrative controls to avoid mistakes in the administration of radioactive material; (5) Using procedures to prevent or minimize radioactive contamination and using proper decontamination procedures; (6) Using emergency procedures to control radioactive material; and (7) Disposing of radioactive material; and

c. This individual must obtain a written attestation signed by a preceptor radiation safety officer or associate radiation safety officer who has experience with the radiation safety aspects of similar types of use of radioactive material for which the individual is seeking approval as a radiation safety officer or an associate radiation safety officer. The written attestation must state that the individual has satisfactorily completed the requirements in subdivisions 3 a, 3 b, and 5 of this section and is able to independently fulfill the radiation safety-related duties as a radiation safety officer or has an associate radiation safety officer for a medical use licensee; or

4. Meets the following qualifications:

a. Is a medical physicist who has been certified by a specialty board whose certification process has been recognized by the agency, NRC, or an agreement state under subdivision 1 of 12VAC5-481-1760 and has experience in radiation safety for similar types of use of radioactive material for which the licensee is seeking the approval of the individual as RSO or an associate radiation safety officer and who meets the requirements in subdivision 5 of this section; or

b. Is an authorized user, authorized medical physicist, or authorized nuclear pharmacist (i) identified on an agency, NRC, or another agreement state license; a permit issued by a NRC master material licensee; a permit issued by an agency, NRC, or another agreement state board scope licensee; or a permit issued by a NRC master material license board scope permittee; (ii) has experience with the radiation safety aspects of similar types of use of radioactive material for which the individual has RSO or associate radiation safety officer responsibilities; and (iii) meets subdivision 5 of this section; or

c. Has experience with the radiation safety aspects of the types of use of radioactive material for which the individual is seeking simultaneous approval both as a radiation safety officer and the authorized user on the same new medical use license or new medical use permit issued by a NRC master material license licensee. The individual must also meet the requirements in subdivision 5 of this section.

5. Has training in the radiation safety, regulatory issues, and emergency procedures for the types of use for which a licensee seeks approval. This training requirement may be satisfied by completing training that is supervised by a RSO, an associate radiation safety officer, authorized medical physicist, authorized nuclear pharmacist, or authorized user, as appropriate, who is authorized for the types of use for which the licensee is seeking approval.

12VAC5-481-1770. Training for an authorized nuclear pharmacist.

Except as provided in 12VAC5-481-1780, licensees shall require the authorized nuclear pharmacist (ANP) to be a pharmacist who:

1. Is certified by a specialty board whose certification process has been recognized by the NRC, the agency, or an agreement state. The names of board certifications that have been recognized by the NRC or an agreement state are posted on the NRC's Medical Uses Licensee Toolkit web page. To have its certification process recognized, a specialty board shall require all candidates for certification to:

a. Have graduated from a pharmacy program accredited by the American Council on Pharmaceutical Education Accreditation Council for Pharmacy Education (ACPE)

(previously named the American Council on Pharmaceutical Education) or have passed the Foreign Pharmacy Graduate Examination Committee (FPGEC) examination;

b. Hold a current, active license to practice pharmacy;

c. Provide evidence of having acquired at least 4000 hours0.0463 days <br />1.111 hours <br />0.00661 weeks <br />0.00152 months <br /> of training or experience in nuclear pharmacy practice. Academic training may be substituted for no more than 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of the required training and experience; and

d. Pass an examination in nuclear pharmacy administered by diplomates of the specialty board that assesses knowledge and competency in procurement, compounding, quality assurance, dispensing, distribution, health and safety, radiation safety, provision of information and consultation, monitoring patient outcomes, research, and development; or

2. Meets the following requirements:

a. Has completed 700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> in a structured educational program consisting:

(1) 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of classroom and laboratory training in the following areas:

(a) Radiation physics and instrumentation; (b) Radiation protection; (c) Mathematics pertaining to the use and measurement of radioactivity; (d) Chemistry of byproduct material for medical use; and (e) Radiation biology; and (2) Supervised practical experience in a nuclear pharmacy involving:

(a) Shipping, receiving, and performing related radiation surveys; (b) Using and performing checks for proper operation of instruments used to determine the activity of dosages, survey meters, and, if appropriate, instruments used to measure alpha-emitting or beta-emitting radionuclides; (c) Calculating, assaying, and safely preparing dosages for patients or human research subjects; (d) Using administrative controls to avoid medical events in the administration of radioactive material; and (e) Using procedures to prevent or minimize radioactive contamination and using proper decontamination procedures; and

3. Has obtained written attestation, signed by a preceptor ANP, that the individual has satisfactorily completed the requirements in subdivision 2 of this section and is able to independently fulfill the radiation safety-related duties as an authorized nuclear pharmacist.

12VAC5-481-1780. Training for experienced radiation safety officer, teletherapy or medical physicist, authorized medical physicist, nuclear pharmacist, authorized nuclear pharmacist, and authorized user.

A. The following applies to individuals with experience as a radiation safety officer (RSO),

teletherapy or medical physicist, authorized medical physicist (AMP), nuclear pharmacist, or authorized nuclear pharmacist (ANP):

1. An individual identified on an agency, NRC, or agreement state license or a permit issued by the agency, the NRC, or another agreement state broad scope licensee or master material license permit or by a master material license permittee of broad scope as a RSO, a teletherapy or medical physicist, AMP, a nuclear pharmacist, or an ANP on or before January 14, 2019, need not comply with the training requirements of 12VAC5-481-1750, 12VAC5-481-1760, or 12VAC5-481-1770, respectively, except the RSO and AMP identified in this subdivision must meet the training requirements in subdivision 5 of 12VAC5-481-1750 or subdivision 3 of 12VAC5-481-1760, as appropriate, for any material or uses for which they were not authorized prior to this date.

2. An individual certified by the American Board of Health Physics in Comprehensive Health Physics, American Board of Radiology, American Board of Nuclear Medicine, American Board of Science in Nuclear Medicine, Board of Pharmaceutical Specialties in Nuclear Pharmacy, American Board of Medical Physics in Radiation Oncology Physics, Royal College of

Physicians and Surgeons of Canada in Nuclear Medicine, American Osteopathic Board of Radiology, or American Osteopathic Board of Nuclear Medicine on or before October 24, 2005, need not comply with the training requirements of 12VAC5-481-1750 to be identified as an RSO or as an associate RSO on an agency, NRC, or another agreement state license or NRC master material permit for those materials and uses that these individuals performed on or before October 24, 2005. Any individual certified by the American Board of Radiology in therapeutic radiological physics, Roentgen ray and gamma ray physics, x-ray and radium physics, or radiological physics, or certified by the American Board of Medical Physics in radiation oncology physics, on or before October 24, 2005, need not comply with the training requirements for an authorized medical physicist described in 12VAC5-481-1760 for those materials and uses that these individuals performed on or before October 24, 2005.

3. An RSO, AMP, or ANP, who used only accelerator-produced radioactive materials or discrete sources of radium-226, or both, for medical uses or in the practice of nuclear pharmacy at a government agency or federally recognized Indian Tribe before November 30, 2007, or at all other locations of use before August 8, 2009, or an earlier date as noticed by the NRC, need not comply with the training requirements of 12VAC5-481-1750, 12VAC5-481-1760, or 12VAC5-481-1770, respectively, when performing the same uses. A nuclear pharmacist, who prepared only radioactive drugs containing accelerator-produced radioactive materials, or a medical physicist, who used only accelerator-produced radioactive materials, at the locations and time period identified in this subdivision, qualifies as an authorized nuclear pharmacist or an authorized medical physicist, respectively, for those materials and uses performed before these dates, for purposes of this part.

B. The following applies to experienced authorized users (AU):

1. Physicians, dentists, or podiatrists identified as AUs for the medical use of radioactive material on a license issued by the agency, the NRC, or another Agreement state; a permit issued by an NRC master material licensee; a permit issued by an agency, NRC, or other Agreement state broad scope licensee; or a permit issued by an NRC master material license broad scope permittee on or before January 14, 2019, who perform only those medical uses for which they were authorized on or before that date need not comply with the training requirements of Articles 5 (12VAC5-481-1900 et seq.) through 9 (12VAC5-481-2040 et seq.)

of this part.

2. Physicians, dentists, or podiatrists identified as AUs for the medical use of radioactive material on a license issued by the agency, the NRC, or another Agreement state; a permit issued by an NRC master material licensee; a permit issued by an agency, NRC, or other Agreement state broad scope licensee; or a permit issued by an NRC master material license broad scope permittee on or before October 24, 2005 or a permit issued in accordance with an NRC master material broad scope license on or before October 24, 2005 need not comply with the training requirements of Articles 5 (12VAC5-481-1900 et seq.) through 9 (12VAC5-481-2040 et seq.) of this part for those materials and uses that these individuals performed on or before October 24, 2005, as follows:

a. For uses authorized under 12VAC5-481-1900 or 12VAC5-481-1920, or oral administration of sodium iodide I-131 requiring a written directive for imaging and localization purposes, a physician who was certified on or before October 24, 2005, in nuclear medicine by the American Board of Nuclear Medicine; diagnostic radiology by the American Board of Radiology; diagnostic radiology or radiology by the American Osteopathic Board of Radiology; nuclear medicine by the Royal College of Physicians and Surgeons of Canada; or American Osteopathic Board of Nuclear Medicine in nuclear medicine;

b. For uses authorized under 12VAC5-481-1950, a physician who was certified on or before October 24, 2005, by the American Board of Nuclear Medicine; the American Board of Radiology in radiology, therapeutic radiology, or radiation oncology; nuclear medicine by the Royal College of Physicians and Surgeons of Canada; or the American Osteopathic Board of Radiology after 1984;

c. For uses authorized under 12VAC5-481-2010 or 12VAC5-481-2040, a physician who was certified on or before October 24, 2005, in radiology, therapeutic radiology or radiation oncology by the American Board of Radiology; radiation oncology by the American Osteopathic Board of Radiology; radiology, with specialization in radiotherapy, as a British "Fellow of the Faculty of Radiology" or "Fellow of the Royal College of Radiology"; or therapeutic radiology by the Canadian Royal College of Physicians and Surgeons; and

d. For uses authorized under 12VAC5-481-2020, a physician who was certified on or before October 24, 2005, in radiology, diagnostic radiology, therapeutic radiology, or radiation oncology by the American Board of Radiology; nuclear medicine by the American Board of Nuclear Medicine; diagnostic radiology or radiology by the American Osteopathic Board of Radiology; or nuclear medicine by the Royal College of Physicians and Surgeons of Canada.

3. Physicians, dentists, or podiatrists who used only accelerator-produced radioactive materials or discrete sources of radium-226, or both, for medical uses performed at a government agency or federally recognized Indian Tribe before November 30, 2007, or at all other locations of use before August 8, 2009, or an earlier date as noticed by the NRC, need not comply with the training requirements of Articles 5 (12VAC5-481-1900 et seq.) through 9 (12VAC5-481-2040 et seq.) of this part when performing the same medical uses. A physician, dentist, or podiatrist, who used only accelerator-produced radioactive materials, discrete sources of radium-226, or both for medical uses at the locations and time period identified in this subdivision, qualifies as an AU for those materials and uses performed before these dates for purposes of this chapter.

C. Individuals who need not comply with training requirements as described in this section may serve as preceptors for, and supervisors of, applicants seeking authorization on NRC licenses for the same uses for which these individuals are authorized.

12VAC5-481-2018. Training for use of manual brachytherapy sources.

Except as provided in 12VAC5-481-1780, licensees shall require an authorized user of a manual brachytherapy source for uses authorized under 12VAC5-481-2010 to be a physician:

1. Who is certified by a medical specialty board whose certification process has been recognized by the NRC, the agency, or an agreement state. The names of board certifications that have been recognized by the NRC or an agreement state are posted on the NRC's Medical Uses Licensee Toolkit Web page. To have its certification process recognized, a specialty board shall require all candidates for certification to:

a. Successfully complete a minimum of three years of residency training in a radiation oncology program approved by the Residency Review Committee of the Accreditation Council for Graduate Medical Education or the Royal College of Physicians and Surgeons of Canada or the Committee on Post-Graduate Training Council on Postdoctoral Training of the American Osteopathic Association; and

b. Pass an examination administered by diplomates of the specialty board that tests knowledge and competence in radiation safety, radionuclide handling, treatment planning, quality assurance, and clinical use of manual brachytherapy; or

2. Who has:

a. Completed a structured educational program in basic radionuclide handling techniques applicable to the use of manual brachytherapy sources that includes:

(1) 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of classroom and laboratory training in the following areas:

(a) Radiation physics and instrumentation; (b) Radiation protection; (c) Mathematics pertaining to the use and measurement of radioactivity; and (d) Radiation biology; and (2) 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of work experience, under the supervision of an authorized user who meets the requirements in this subsection, 12VAC5-481-1780, or equivalent NRC or another agreement state requirements at a medical facility authorized to use radioactive material under 12VAC5-481-2010, involving:

(a) Ordering, receiving, and unpacking radioactive materials safely and performing the related radiation surveys; (b) Checking survey meters for proper operation; (c) Preparing, implanting, and removing brachytherapy sources; (d) Maintaining running inventories of material on hand; (e) Using administrative controls to prevent a medical event involving the use of radioactive material; (f) Using emergency procedures to control radioactive material; and

b. Completed three years of supervised clinical experience in radiation oncology, under an AU who meets the requirements in this section, 12VAC5-481-1780, or equivalent NRC or another Agreement state requirements, as part of a formal training program approved by the Residency Review Committee for Radiation Oncology of the Accreditation Council for Graduate Medical Education or the Royal College of Physicians and Surgeons of Canada or the Committee Council on Postdoctoral Training of the American Osteopathic Association. This experience may be obtained concurrently with the supervised work experience required by subdivision 2 a (2) of this section.

3. Who has obtained written attestation that the individual has satisfactorily completed the requirements in subdivision 2 of this section and has achieved a level of competency sufficient to function independently as an AU of manual brachytherapy sources for the medical uses authorized in 12VAC5-481-2010. This attestation must be obtained from either:

a. A preceptor authorized user who meets the requirements in this section, 12VAC5-481-1780, or equivalent NRC or other agreement state requirements; or

b. A residency program director who affirms in writing that the attestation represents the residency program faculty where at least one faculty member is an authorized user who meets the requirement in this section, 12VAC5-481-1780, or equivalent NRC or other agreement state requirements and concurs with the attestation provided by the residency program director. The residency training program must be approved by the Residency Review Committee of the Accreditation Council for Graduate Medical Education or the Royal College of Physicians and Surgeons of Canada or the Council on Postdoctoral Training of the American Osteopathic Association and must include training and experience specific in subsection 2 of this section.

12VAC5-481-2040. Training requirements and use of a sealed source in a remote afterloader unit, teletherapy unit, or gamma stereotactic radiosurgery unit.

A. Except as provided in 12VAC5-481-1780, licensees shall require an authorized user (AU) of a sealed source in remote afterloader units, teletherapy units, and gamma stereotactic radiosurgery units to be a physician:

1. Who is certified by a medical specialty board whose certification process has been recognized by the NRC, the agency, or an agreement state and who meets the requirements in subdivision 4 of this section. The names of board certifications that have been recognized by the agency, NRC, or an agreement state are posted on the NRC's Medical Uses Licensee Toolkit Web page. To have its certification process recognized, a specialty board shall require all candidates for certification to:

a. Successfully complete a minimum of three years of residency training in a radiation therapy program approved by the Residency Review Committee of the Accreditation Council for Graduate Medical Education or the Royal College of Physicians and Surgeons of Canada or the Committee on Post-Graduate Training Council on Postdoctoral Training of the American Osteopathic Association; and

b. Pass an examination administered by diplomates of the specialty board that tests knowledge and competence radiation safety, radionuclide handling, treatment planning, quality assurance, and clinical use of stereotactic radiosurgery, remote afterloaders and external beam therapy; or

2. Who has:

a. Completed a structured educational program in basic radionuclide techniques applicable to the use of a sealed source in a therapeutic medical unit that includes:

(1) 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of classroom and laboratory training in the following areas: radiation physics and instrumentation; radiation protection; mathematics pertaining to the use and measurement of radioactivity; and radiation biology; and (2) 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of work experience, under the supervision of an AU who meets the requirements in this section, 12VAC5-481-1780, or equivalent NRC or another agreement state requirements at a medical institution that is authorized for subsections B and C of this section, involving: reviewing full calibration measurements and periodic spot-checks; preparing treatment plans and calculating treatment doses and times; using administrative controls to prevent a medical event involving the use of radioactive material; implementing emergency procedures to be followed in the event of the abnormal operation of the medical unit or console; checking and using survey meters; and selecting the proper dose and knowing how it is to be administered; and

b. Completed three years of supervised clinical experience in radiation therapy under an AU who meets the requirements in this section, 12VAC5-481-1780, or equivalent NRC or another Agreement state requirements as part of a formal training program approved by the Residency Review Committee for Radiation Oncology of the Accreditation Council for Graduate Medical Education or the Royal College of Physicians and Surgeons of Canada or the Committee Council on Postdoctoral Training of the American Osteopathic Association. This experience may be obtained concurrently with the supervised work experience required by this subdivision.

3. Who has obtained written attestation that the individual has satisfactorily completed the requirements in subdivisions 2 a, 2 b, and 4 of this subsection and has achieved a level of competency sufficient to function independently as an AU of each type of therapeutic medical unit for which the individual is requesting AU status. The written attestation shall be signed by either:

a. A preceptor AU who meets the requirements in this subsection, 12VAC5-481-1780, or equivalent NRC or another agreement state requirements for an AU for each type of therapeutic medical unit for which the individual is requesting AU status; or

b. A residency program director who affirms in writing that the attestation of the residency program faculty where at least one faculty member is an authorized user who meets the requirements in this subsection, 12VAC5-481-1780, or equivalent NRC or other agreement state requirements for the type of therapeutic medical unit for which the individual is requesting authorized user status and concurs with the attestation provided by the residency program director. The residency training program must be approved by the Residency Committee of the Accreditation Council for Graduate Medical Education or the Royal College of Physicians and Surgeons of Canada or the Council on Postdoctoral Training of the American Osteopathic Association and must include training and experience specified in subdivisions 2 a and 2 b of this subsection.

4. Who has received training in device operation, safety procedures, and clinical use for the types of use for which authorization is sought. This training requirement may be satisfied by satisfactory completion of a training program provided by the vendor for new users or by receiving training supervised by an AU or authorized medical physicist, as appropriate, who is authorized for the types of use for which the individual is seeking authorization.

B. Licensees shall use sealed sources in photon-emitting remote afterloader units, teletherapy units, or gamma stereotactic radiosurgery units for therapeutic medical uses:

1. As approved in the Sealed Source and Device Registry; or

2. In research in accordance with an active Investigational Device Exemption application accepted by the U.S. Food and Drug Administration provided the requirements of 12VAC5-481-1740 are met.

C. Licensees shall use photon-emitting remote afterloader units, teletherapy units, or gamma stereotactic radiosurgery units:

1. As approved in the Sealed Source and Device Registry to deliver a therapeutic dose for medical use. These devices may be used for therapeutic medical treatments that are not explicitly provided for in the Sealed Source and Device Registry but must be used in accordance with radiation safety conditions and limitations described in the Sealed Source and Device Registry; or

2. In research in accordance with an active Investigational Device Exemption application accepted by the U.S. Food and Drug Administration provided the requirements of 12VAC5-481-1740 are met.

12VAC5-481-3120. Advance notification of transport of nuclear waste.

A. Prior to the transport of any nuclear waste outside of the confines of the licensee's facility or other place of use or storage, or prior to the delivery of any nuclear waste to a carrier for transport, each licensee shall provide advance notification of such transport.

B. Advance notification for transport of licensed material is required when:

1. The licensed material is required to be in Type B packaging for transportation;

2. The licensed material is being transported to or across state boundary en route to a disposal facility or to a collection point for transport to a disposal facility; and

3. The quantity of licensed material in a single package exceeds:

a. 3000 times the A1 value of the radionuclides as specified in 12VAC5-481-3770;

b. 3000 times the A2 value of the radionuclides as specified in 12VAC5-481-3770; or

c. 1000 terabecquerel (27,000 curies).

C. Each advance notification required by subsections A and B of this section shall contain the following information:

1. The name, address, and telephone number of the shipper, carrier, and receiver of the shipment;

2. A description of the nuclear waste contained in the shipment as required by 49 CFR 172.202 and 172.203(d);

3. The point of origin of the shipment and the seven-day period during which departure of the shipment is estimated to occur;

4. The seven-day period during which arrival of the shipment at state boundaries or tribal reservation boundaries is estimated to occur;

5. The destination of the shipment, and the seven-day period during which arrival of the shipment is estimated to occur; and

6. A point of contact with a telephone number for current shipment information.

D. The notification required by subsections A and B of this section shall be made in writing to each office of the governor or governor's designee, the office of each appropriate tribal official or tribal official's designee, and to the agency. A notification delivered by mail shall be postmarked at least seven days before the beginning of the seven-day period during which departure of the shipment is estimated to occur. A notification delivered by any other means than mail shall reach each office of the governor or governor's designee, the office of each appropriate tribal official or tribal official's designee, and the agency, at least four days before the beginning of the seven-day period during which departure of the shipment is estimated to occur. A copy of the notification shall be retained by the licensee for three years.

1. A list of names and mailing addresses of the governors' designees receiving advance notification of transportation of nuclear waste was published in the Federal Register on June 30, 1995 (60 FR 34306). Reserved.

2. Contact information for each state, including telephone and mailing addresses of governors and governors' designees, and participating tribes, including telephone and mailing addresses of tribal officials and tribal officials' designees, is available on the NRC website at:

https://scp.nrc.gov/special/designee.pdf.

3. A list of the names and mailing addresses of the governors' designees and tribal officials' designees of participating tribes is available on request from the Director, Division of Materials Safety, Security, State, and Tribal Programs, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

E. The licensee shall notify the governor or governor's designee, the office of each appropriate tribal official or tribal official's designee, and the agency of any changes to schedule information provided pursuant to subsections A and B of this section. Such notification shall be by telephone to a responsible individual in the office of the governor or governor's designee, the office of each appropriate tribal official or tribal official's designee, and the agency. The licensee shall maintain for three years a record of the name of the individual contacted.

F. Each licensee who cancels a nuclear waste shipment, for which advance notification has been sent, shall send a cancellation notice, identifying the advance notification that is being canceled, to the governor or governor's designee, the office of each appropriate tribal official or tribal official's designee, and to the agency. A copy of the notice shall be retained by the licensee for three years.

12VAC5-481-3770. Determination of A1 and A2.

A. Values of A1 and A2 for individual radionuclides, which are the bases for many activity limits elsewhere in these regulations, are given in Table 1 of this section. The curie (Ci) values specified are obtained by converting from the Terabecquerel (TBq) value. The terabecquerel values are the

regulatory standard. The curie values are for information only and are not intended to be the regulatory standard. Where values of A1 and A2 are unlimited, it is for radiation control purposes only.

For nuclear criticality safety, some materials are subject to controls placed on fissile material.

B. For individual radionuclides whose identities are known, but that are not listed in Table 1 or Table 2 of this section, the A1 and A2 values or exempt material activity concentration and exempt consignment activity values contained in Table 3 of this section may be used. Otherwise, the licensee shall obtain prior agency approval for radionuclides not listed in Table 1 or Table 2 of this section, before shipping the material. The licensee shall submit requests for prior approval to the agency.

C. In the calculations of A1 and A2 for a radionuclide not in Table 1 of this section, a single radioactive decay chain, in which radionuclides are present in their naturally occurring proportions, and in which no daughter radionuclide has a half-life either longer than 10 days, or longer than that of the parent radionuclide, shall be considered as a single radionuclide, and the activity to be taken into account, and the A1 or A2 value to be applied, shall be those corresponding to the parent radionuclide of that chain. In the case of radioactive decay chains in which any daughter radionuclide has a half-life either longer than 10 days or greater than that of the parent radionuclide, the parent and those daughter radionuclides shall be considered as mixtures of different radionuclides.

D. For mixtures of radionuclides whose identities and respective activities are known, the following conditions apply:

1. For special form radioactive material, the maximum quantity transported in a Type A package is as follows:

where B(i) is the activity of radionuclide (i) in special form, and A1(i) is the A1 value for radionuclide (i).

2. For normal form radioactive material, the maximum quantity transported in a Type A package is as follows:

B(i)/A2(i)1 where B(i) is the activity of radionuclide (i) in normal form, and A2(i) is the A2 value for radionuclide (i).

3. If the package contains both special and normal form radioactive material, the activity that may be transported in the Type A package is as follows:

B(i)\A1(i)+C(j)\A2(j)1 Where B(i) is the activity of radionuclide i (i) as special form radioactive material, A1(i) is the A1 value for the radionuclide (i), C(j) is the activity of radionuclide (j) as normal form radioactive material, and A2(j) is the A2 value for radionuclide (j).

4. Alternatively, the A1 value for mixtures of special form material may be determined as follows:

where f(i) is the fraction of activity for radionuclide (i) in the mixture, and A1(i) is the appropriate A1 value for radionuclide (i).

5. Alternatively, the A2 value for mixtures of normal form material may be determined as follows:

where f(i) is the fraction of activity for radionuclide (i) in the mixture, and A2(i) is the appropriate A2 value for radionuclide (i).

6. The exempt activity concentration for mixtures of nuclides may be determined as follows:

where f(i) is the fraction of activity concentration of radionuclide (i) in the mixture, and [A](i) is the activity concentration for exempt material containing radionuclide (i).

7. The activity limit for an exempt consignment for mixtures of radionuclides may be determined as follows:

where f(i) is the fraction of activity of radionuclide (i) in the mixture, and [A](i) is the activity limit for exempt consignments for radionuclide (i).

E. When the identity of each radionuclide is known, but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped, and the lowest A1 or A2 value or lowest [A] (activity concentration for exempt material or A (activity limit for exempt consignment) value, as appropriate, for the radionuclides in each group may be used in applying the formulas in subsection D of this section. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest A1 or A2 values or the lowest [A] or A value, as appropriate, for the alpha emitters and beta/gamma emitters.

F. Table 1. A1 and A2 Values for Radionuclides.

Symbol of Element and Specific activity A1 (TBq) A1(Ci)b A2 (TBq) A2(Ci)b radionuclide atomic number (TBq/g) (Ci/g)

Ac-225 (a) Actinium (89) 8.0X10-1 2.2X10-1 6.0X10-3 1.6X10-1 2.1X103 5.8X104 Ac-227 (a) 9.0X10-1 2.4X101 9.0X10-5 2.4X10-3 2.7 7.2X101 Ac-228 6.0X10-1 1.6X101 5.0X10-1 1.4X101 8.4X104 2.2X106 Ag-105 Silver (47) 2.0 5.4X101 2.0 5.4X101 1.1X103 3.0X104 Ag-108m 7.0X10-1 1.9X101 7.0X10-1 1.9X101 9.7X10-1 2.6X101 (a)

Ag-110m 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.8X102 4.7X103 (a)

Ag-111 2.0 5.4X101 6.0X10-1 1.6X101 5.8X103 1.6X105 Al-26 Aluminum (13) 1.0X10-1 2.7 1.0X10-1 2.7 7.0X10-4 1.9X10-2 Americium Am-241 1.0X101 2.7X102 1.0X10-3 2.7X10-2 1.3X10-1 3.4 (95)

Am-242m 1.0X101 2.7X102 1.0X10-3 2.7X10-2 3.6X10-1 1.0X101 (a)

Am-243 (a) 5.0 1.4X102 1.0X10-3 2.7X10-2 7.4X10-3 2.0X10-1 Ar-37 Argon (18) 4.0X101 1.1X103 4.0X101 1.1X103 3.7X103 9.9X104 Ar-39 4.0X101 1.1X103 2.0X101 5.4X102 1.3 3.4X101 Ar-41 3.0X10-1 8.1 3.0X10-1 8.1 1.5X106 4.2X107 As-72 Arsenic (33) 3.0X10-1 8.1 3.0X10-1 8.1 6.2X104 1.7X106 As-73 4.0X101 1.1X103 4.0X101 1.1X103 8.2X102 2.2X104 As-74 1.0 2.7X101 9.0X10-1 2.4X101 3.7X103 9.9X104 As-76 3.0X10-1 8.1 3.0X10-1 8.1 5.8X104 1.6X106 As-77 2.0X101 5.4X102 7.0X10-1 1.9X101 3.9X104 1.0X106 At-211 (a) Astatine (85) 2.0X101 5.4X102 5.0X10-1 1.4X101 7.6X104 2.1X106 Au-193 Gold (79) 7.0 1.9X102 2.0 5.4X101 3.4X104 9.2X105 Au-194 1.0 2.7X101 1.0 2.7X101 1.5X104 4.1X105 Au-195 1.0X101 2.7X102 6.0 1.6X102 1.4X102 3.7X103 Au-198 1.0 2.7X101 6.0X10-1 1.6X101 9.0X103 2.4X105 Au-199 1.0X101 2.7X102 6.0X10-1 1.6X101 7.7X103 2.1X105 Ba-131 (a) Barium (56) 2.0 5.4X101 2.0 5.4X101 3.1X103 8.4X104 Ba-133 3.0 8.1X101 3.0 8.1X101 9.4 2.6X102 Ba-133m 2.0X101 5.4X102 6.0X10-1 1.6X101 2.2X104 6.1X105 Ba-140 (a) 5.0X10-1 1.4X101 3.0X10-1 8.1 2.7X103 7.3X104 Be-7 Beryllium (4) 2.0X101 5.4X102 2.0X101 5.4X102 1.3X104 3.5X105 Be-10 4.0X101 1.1X103 6.0X10-1 1.6X101 8.3X10-4 2.2X10-2 Bi-205 Bismuth (83) 7.0X10-1 1.9X101 7.0X10-1 1.9X101 1.5X103 4.2X104 Bi-206 3.0X10-1 8.1 3.0X10-1 8.1 3.8X103 1.0X105 Bi-207 7.0X10-1 1.9X101 7.0X10-1 1.9X101 1.9 5.2X101 Bi-210 1.0 2.7X101 6.0X10-1 1.6X101 4.6X103 1.2X105 Bi-210m (a) 6.0X10-1 1.6X101 2.0X10-2 5.4X10-1 2.1X10-5 5.7X10-4 Bi-212 (a) 7.0X10-1 1.9X101 6.0X10-1 1.6X101 5.4X105 1.5X107 Bk-247 Berkelium (97) 8.0 2.2X102 8.0X10-4 2.2X10-2 3.8X10-2 1.0 Bk-249 (a) 4.0X101 1.1X103 3.0X10-1 8.1 6.1X101 1.6X103

Br-76 Bromine (35) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 9.4X104 2.5X106 Br-77 3.0 8.1X101 3.0 8.1X101 2.6X104 7.1X105 Br-82 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.0X104 1.1X106 C-11 Carbon (6) 1.0 2.7X101 6.0X10-1 1.6X101 3.1X107 8.4X108 C-14 4.0X101 1.1X103 3.0 8.1X101 1.6X10-1 4.5 Ca-41 Calcium (20) Unlimited Unlimited Unlimited Unlimited 3.1X10-3 8.5X10-2 Ca-45 4.0X101 1.1X103 1.0 2.7X101 6.6X102 1.8X104 Ca-47 (a) 3.0 8.1X101 3.0X10-1 8.1 2.3X104 6.1X105 Cd-109 Cadmium (48) 3.0X101 8.1X102 2.0 5.4X101 9.6X101 2.6X103 Cd-113m 4.0X101 1.1X103 5.0X10-1 1.4X101 8.3 2.2X102 Cd-115 (a) 3.0 8.1X101 4.0X10-1 1.1X101 1.9X104 5.1X105 Cd-115m 5.0X10-1 1.4X101 5.0X10-1 1.4X101 9.4X102 2.5X104 Ce-139 Cerium (58) 7.0 1.9X102 2.0 5.4X101 2.5X102 6.8X103 Ce-141 2.0X101 5.4X102 6.0X10-1 1.6X101 1.1X103 2.8X104 Ce-143 9.0X10-1 2.4X101 6.0X10-1 1.6X101 2.5X104 6.6X105 Ce-144 (a) 2.0X10-1 5.4 2.0X10-1 5.4 1.2X102 3.2X103 Californium Cf-248 4.0X101 1.1X103 6.0X10-3 1.6X10-1 5.8X101 1.6X103 (98)

Cf-249 3.0 8.1X101 8.0X10-4 2.2X10-2 1.5X10-1 4.1 Cf-250 2.0X101 5.4X102 2.0X10-3 5.4X10-2 4.0 1.1X102 Cf-251 7.0 1.9X102 7.0X10-4 1.9X10-2 5.9X10-2 1.6 Cf-252 1.0X10-1 2.7 3.0X10-3 8.1X10-2 2.0X101 5.4X102 Cf-253 (a) 4.0X101 1.1X103 4.0X10-2 1.1 1.1X103 2.9X104 Cf-254 1.0X10-3 2.7X10-2 1.0X10-3 2.7X10-2 3.1X102 8.5X103 Cl-36 Chlorine (17) 1.0X101 2.7X102 6.0X10-1 1.6X101 1.2X10-3 3.3X10-2 Cl-38 2.0X10-1 5.4 2.0X10-1 5.4 4.9X106 1.3X108 Cm-240 Curium (96) 4.0X101 1.1X103 2.0X10-2 5.4X10-1 7.5X102 2.0X104 Cm-241 2.0 5.4X101 1.0 2.7X101 6.1X102 1.7X104 Cm-242 4.0X101 1.1X103 1.0X10-2 2.7X10-1 1.2X102 3.3X103 Cm-243 9.0 2.4X102 1.0X10-3 2.7X10-2 1.9X10-3 5.2X104 Cm-244 2.0X101 5.4X102 2.0X10-3 5.4X10-2 3.0 8.1X101

Cm-245 9.0 2.4X102 9.0X10-4 2.4X10-2 6.4X10-3 1.7X10-1 Cm-246 9.0 2.4X102 9.0X10-4 2.4X10-2 1.1X10-2 3.1X10-1 Cm-247 (a) 3.0 8.1X101 1.0X10-3 2.7X10-2 3.4X10-6 9.3X10-5 Cm-248 2.0X10-2 5.4X10-1 3.0X10-4 8.1X10-3 1.6X10-4 4.2X10-3 Co-55 Cobalt (27) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.1X105 3.1X106 Co-56 3.0X10-1 8.1 3.0X10-1 8.1 1.1X103 3.0X104 Co-57 1.0X101 2.7X102 1.0X101 2.7X102 3.1X102 8.4X103 Co-58 1.0 2.7X101 1.0 2.7X101 1.2X103 3.2X104 Co-58m 4.0X101 1.1X103 4.0X101 1.1X103 2.2X105 5.9X106 Co-60 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.2X101 1.1X103 Cr-51 Chromium (24) 3.0X101 8.1X102 3.0X101 8.1X102 3.4X103 9.2X104 Cs-129 Cesium (55) 4.0 1.1X102 4.0 1.1X102 2.8X104 7.6X105 Cs-131 3.0X101 8.1X102 3.0X101 8.1X102 3.8X103 1.0X105 Cs-132 1.0 2.7X101 1.0 2.7X101 5.7X103 1.5X105 Cs-134 7.0X10-1 1.9X101 7.0X10-1 1.9X101 4.8X101 1.3X103 Cs-134m 4.0X101 1.1X103 6.0X10-1 1.6X101 3.0X105 8.0X106 Cs-135 4.0X101 1.1X103 1.0 2.7X101 4.3X10-5 1.2X10-3 Cs-136 5.0X10-1 1.4X101 5.0X10-1 1.4X101 2.7X103 7.3X104 Cs-137 (a) 2.0 5.4X101 6.0X10-1 1.6X101 3.2 8.7X101 Cu-64 Copper (29) 6.0 1.6X102 1.0 2.7X101 1.4X105 3.9X106 Cu-67 1.0X101 2.7X102 7.0X10-1 1.9X101 2.8X104 7.6X105 Dysprosium Dy-159 2.0X101 5.4X102 2.0X101 5.4X102 2.1X102 5.7X103 (66)

Dy-165 9.0X10-1 2.4X101 6.0X10-1 1.6X101 3.0X105 8.2X106 Dy-166 (a) 9.0X10-1 2.4X101 3.0X10-1 8.1 8.6X103 2.3X105 Er-169 Erbium (68) 4.0X101 1.1X103 1.0 2.7X101 3.1X103 8.3X104 Er-171 8.0X10-1 2.2X101 5.0X10-1 1.4X101 9.0X104 2.4X106 Eu-147 Europium (63) 2.0 5.4X101 2.0 5.4X101 1.4X103 3.7X104 Eu-148 5.0X10-1 1.4X101 5.0X10-1 1.4X101 6.0X102 1.6X104 Eu-149 2.0X101 5.4X102 2.0X101 5.4X102 3.5X102 9.4X103 Eu-150 2.0 5.4X101 7.0X10-1 1.9X101 6.1X104 1.6X106 (short lived)

Eu-150 7.0X10-1 1.9X101 7.0X10-1 1.9X101 6.1X104 1.6X106 (long lived)

Eu-152 1.0 2.7X101 1.0 2.7X101 6.5 1.8X102 Eu-152m 8.0X10-1 2.2X101 8.0X10-1 2.2X101 8.2X104 2.2X106 Eu-154 9.0X10-1 2.4X101 6.0X10-1 1.6X101 9.8 2.6X102 Eu-155 2.0X101 5.4X102 3.0 8.1X101 1.8X101 4.9X102 Eu-156 7.0X10-1 1.9X101 7.0X10-1 1.9X101 2.0X103 5.5X104 F-18 Fluorine (9) 1.0 2.7X101 6.0X10-1 1.6X101 3.5X106 9.5X107 Fe-52 (a) Iron (26) 3.0X10-1 8.1 3.0X10-1 8.1 2.7X105 7.3X106 Fe-55 4.0X101 1.1X103 4.0X101 1.1X103 8.8X101 2.4X103 Fe-59 9.0X10-1 2.4X101 9.0X10-1 2.4X101 1.8X103 5.0X104 Fe-60 (a) 4.0X101 1.1X103 2.0X10-1 5.4 7.4X10-4 2.0X10-2 Ga-67 Gallium (31) 7.0 1.9X102 3.0 8.1X101 2.2X104 6.0X105 Ga-68 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.5X106 4.1X107 Ga-72 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.1X105 3.1X106 Gadolinium Gd-146 (a) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 6.9X102 1.9X104 (64)

Gd-148 2.0X101 5.4X102 2.0X10-3 5.4X10-2 1.2 3.2X101 Gd-153 1.0X101 2.7X102 9.0 2.4X102 1.3X102 3.5X103 Gd-159 3.0 8.1X101 6.0X10-1 1.6X101 3.9X104 1.1X106 Germanium Ge-68 (a) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 2.6X102 7.1X103 (32)

Ge-71 4.0X101 1.1X103 4.0X101 1.1X103 5.8X103 1.6X105 Ge-77 3.0X10-1 8.1 3.0X10-1 8.1 1.3X105 3.6X106 Hf-172 (a) Hafnium (72) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 4.1X101 1.1X103 Hf-175 3.0 8.1X101 3.0 8.1X101 3.9X102 1.1X104 Hf-181 2.0 5.4X101 5.0X10-1 1.4X101 6.3X102 1.7X104 Hf-182 Unlimited Unlimited Unlimited Unlimited 8.1X10-6 2.2X10-4 Hg-194 (a) Mercury (80) 1.0 2.7X101 1.0 2.7X101 1.3X10-1 3.5 Hg-195m 3.0 8.1X101 7.0X10-1 1.9X101 1.5X104 4.0X105 (a)

Hg-197 2.0X101 5.4X102 1.0X101 2.7X102 9.2X103 2.5X105

Hg-197m 1.0X101 2.7X102 4.0X10-1 1.1X101 2.5X104 6.7X105 Hg-203 5.0 1.4X102 1.0 2.7X101 5.1X102 1.4X104 Ho-166 Holmium (67) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 2.6X104 7.0X105 Ho-166m 6.0X10-1 1.6X101 5.0X10-1 1.4X101 6.6X10-2 1.8 I-123 Iodine (53) 6.0 1.6X102 3.0 8.1X101 7.1X104 1.9X106 I-124 1.0 2.7X101 1.0 2.7X101 9.3X103 2.5X105 I-125 2.0X101 5.4X102 3.0 8.1X101 6.4X102 1.7X104 I-126 2.0 5.4X101 1.0 2.7X101 2.9X103 8.0X104 I-129 Unlimited Unlimited Unlimited Unlimited 6.5X10-6 1.8X10-4 I-131 3.0 8.1X101 7.0X10-1 1.9X101 4.6X103 1.2X105 I-132 4.0X10-1 1.1X101 4.0X10-1 1.1X101 3.8X105 1.0X107 I-133 7.0X10-1 1.9X101 6.0X10-1 1.6X101 4.2X104 1.1X106 I-134 3.0X10-1 8.1 3.0X10-1 8.1 9.9X105 2.7X107 I-135 (a) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 1.3X105 3.5X106 In-111 Indium (49) 3.0 8.1X101 3.0 8.1X101 1.5X104 4.2X105 In-113m 4.0 1.1X102 2.0 5.4X101 6.2X105 1.7X107 In-114m (a) 1.0X101 2.7X102 5.0X10-1 1.4X101 8.6X102 2.3X104 In-115m 7.0 1.9X102 1.0 2.7X101 2.2X105 6.1X106 Ir-189 (a) Iridium (77) 1.0X101 2.7X102 1.0X101 2.7X102 1.9X103 5.2X104 Ir-190 7.0X10-1 1.9X101 7.0X10-1 1.9X101 2.3X103 6.2X104 2.7X101 Ir-192 1.0 (c) 6.0X10-1 1.6X101 3.4X102 9.2X103 (c)

Ir-194 3.0X10-1 8.1 3.0X10-1 8.1 3.1X104 8.4X105 Potassium K-40 9.0X10-1 2.4X101 9.0X10-1 2.4X101 2.4X10-7 6.4X10-6 (19)

K-42 2.0X10-1 5.4 2.0X10-1 5.4 2.2X105 6.0X106 K-43 7.0X10-1 1.9X101 6.0X10-1 1.6X101 1.2X105 3.3X106 Kr-79 Krypton (36) 4.0 1.1X102 2.0 5.4X101 4.2X104 1.1X106 Kr-81 4.0X101 1.1X103 4.0X101 1.1X103 7.8X10-4 2.1X10-2 Kr-85 1.0X101 2.7X102 1.0X101 2.7X102 1.5X101 3.9X102 Kr-85m 8.0 2.2X102 3.0 8.1X101 3.0X105 8.2X106 Kr-87 2.0X10-1 5.4 2.0X10-1 5.4 1.0X106 2.8X107

Lanthanum La-137 3.0X101 8.1X102 6.0 1.6X102 1.6X10-3 4.4X10-2 (57)

La-140 4.0X10-1 1.1X101 4.0X10-1 1.1X101 2.1X104 5.6X105 Lu-172 Lutetium (71) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 4.2X103 1.1X105 Lu-173 8.0 2.2X102 8.0 2.2X102 5.6X101 1.5X103 Lu-174 9.0 2.4X102 9.0 2.4X102 2.3X101 6.2X102 Lu-174m 2.0X101 5.4X102 1.0X101 2.7X102 2.0X102 5.3X103 Lu-177 3.0X101 8.1X102 7.0X10-1 1.9X101 4.1X103 1.1X105 Magnesium Mg-28 (a) 3.0X10-1 8.1 3.0X10-1 8.1 2.0X105 5.4X106 (12)

Manganese Mn-52 3.0X10-1 8.1 3.0X10-1 8.1 1.6X104 4.4X105 (25)

Mn-53 Unlimited Unlimited Unlimited Unlimited 6.8X10-5 1.8X10-3 Mn-54 1.0 2.7X101 1.0 2.7X101 2.9X102 7.7X103 Mn-56 3.0X10-1 8.1 3.0X10-1 8.1 8.0X105 2.2X107 Molybdenum Mo-93 4.0X101 1.1X103 2.0X101 5.4X102 4.1X10-2 1.1 (42)

Mo-99 (a) 1.0 2.7X101 6.0X10-1 1.6X101 1.8X104 4.8X105 (h)

N-13 Nitrogen (7) 9.0X10-1 2.4X101 6.0X10-1 1.6X101 5.4X107 1.5X109 Na-22 Sodium (11) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 2.3X102 6.3X103 Na-24 2.0X10-1 5.4 2.0X10-1 5.4 3.2X105 8.7X106 Nb-93m Niobium (41) 4.0X101 1.1X103 3.0X101 8.1X102 8.8 2.4X102 Nb-94 7.0X10-1 1.9X101 7.0X10-1 1.9X101 6.9X10-3 1.9X10-1 Nb-95 1.0 2.7X101 1.0 2.7X101 1.5X103 3.9X104 Nb-97 9.0X10-1 2.4X101 6.0X10-1 1.6X101 9.9X105 2.7X107 Neodymium Nd-147 6.0 1.6X102 6.0X10-1 1.6X101 3.0X103 8.1X104 (60)

Nd-149 6.0X10-1 1.6X101 5.0X10-1 1.4X101 4.5X105 1.2X107 Ni-59 Nickel (28) Unlimited Unlimited Unlimited Unlimited 3.0X10-3 8.0X10-2 Ni-63 4.0X101 1.1X103 3.0X101 8.1X102 2.1 5.7X101 Ni-65 4.0X10-1 1.1X101 4.0X10-1 1.1X101 7.1X105 1.9X107 Neptunium Np-235 4.0X101 1.1X103 4.0X101 1.1X103 5.2X101 1.4X103 (93)

Np-236 2.0X101 5.4X102 2.0 5.4X101 4.7X10-4 1.3X10-2 (short-lived)

Np-236 9.0X100 2.4X102 2.0X10-2 5.4X10-1 4.7X10-4 1.3X10-2 (long-lived)

Np-237 2.0X101 5.4X102 2.0X10-3 5.4X10-2 2.6X10-5 7.1X10-4 Np-239 7.0 1.9X102 4.0X10-1 1.1X101 8.6X103 2.3X105 Os-185 Osmium (76) 1.0 2.7X101 1.0 2.7X101 2.8X102 7.5X103 Os-191 1.0X101 2.7X102 2.0 5.4X101 1.6X103 4.4X104 Os-191m 4.0X101 1.1X103 3.0X101 8.1X102 4.6X104 1.3X106 Os-193 2.0 5.4X101 6.0X10-1 1.6X101 2.0X104 5.3X105 Os-194 (a) 3.0X10-1 8.1 3.0X10-1 8.1 1.1X101 3.1X102 Phosphorus P-32 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.1X104 2.9X105 (15)

P-33 4.0X101 1.1X103 1.0 2.7X101 5.8X103 1.6X105 Protactinium Pa-230 (a) 2.0 5.4X101 7.0X10-2 1.9 1.2X103 3.3X104 (91)

Pa-231 4.0 1.1X102 4.0X10-4 1.1X10-2 1.7X10-3 4.7X10-2 Pa-233 5.0 1.4X102 7.0X10-1 1.9X101 7.7X102 2.1X104 Pb-201 Lead (82) 1.0 2.7X101 1.0 2.7X101 6.2X104 1.7X106 Pb-202 4.0X101 1.1X103 2.0X101 5.4X102 1.2X10-4 3.4X10-3 Pb-203 4.0 1.1X102 3.0 8.1X101 1.1X104 3.0X105 Pb-205 Unlimited Unlimited Unlimited Unlimited 4.5X10-6 1.2X10-4 Pb-210 (a) 1.0 2.7X101 5.0X10-2 1.4 2.8 7.6X101 Pb-212 (a) 7.0X10-1 1.9X101 2.0X10-1 5.4 5.1X104 1.4X106 Pd-103 (a) Palladium (46) 4.0X101 1.1X103 4.0X101 1.1X103 2.8X103 7.5X104 Pd-107 Unlimited Unlimited Unlimited Unlimited 1.9X10-5 5.1X10-4 Pd-109 2.0 5.4X101 5.0X10-1 1.4X101 7.9X104 2.1X106 Promethium Pm-143 3.0 8.1X101 3.0 8.1X101 1.3X102 3.4X103 (61)

Pm-144 7.0X10-1 1.9X101 7.0X10-1 1.9X101 9.2X101 2.5X103 Pm-145 3.0X101 8.1X102 1.0X101 2.7X102 5.2 1.4X102 Pm-147 4.0X101 1.1X103 2.0 5.4X101 3.4X101 9.3X102

Pm-148m 8.0X10-1 2.2X101 7.0X10-1 1.9X101 7.9X102 2.1X104 (a)

Pm-149 2.0 5.4X101 6.0X10-1 1.6X101 1.5X104 4.0X105 Pm-151 2.0 5.4X101 6.0X10-1 1.6X101 2.7X104 7.3X105 Po-210 Polonium (84) 4.0X101 1.1X103 2.0X10-2 5.4X10-1 1.7X102 4.5X103 Praseodymium Pr-142 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.3X104 1.2X106 (59)

Pr-143 3.0 8.1X101 6.0X10-1 1.6X101 2.5X103 6.7X104 Pt-188 (a) Platinum (78) 1.0 2.7X101 8.0X10-1 2.2X101 2.5X103 6.8X104 Pt-191 4.0 1.1X102 3.0 8.1X101 8.7X103 2.4X105 Pt-193 4.0X101 1.1X103 4.0X101 1.1X103 1.4 3.7X101 Pt-193m 4.0X101 1.1X103 5.0X10-1 1.4X101 5.8X103 1.6X105 Pt-195m 1.0X101 2.7X102 5.0X10-1 1.4X101 6.2X103 1.7X105 Pt-197 2.0X101 5.4X102 6.0X10-1 1.6X101 3.2X104 8.7X105 Pt-197m 1.0X101 2.7X102 6.0X10-1 1.6X101 3.7X105 1.0X107 Pu-236 Plutonium (94) 3.0X101 8.1X102 3.0X10-3 8.1X10-2 2.0X101 5.3X102 Pu-237 2.0X101 5.4X102 2.0X101 5.4X102 4.5X102 1.2X104 Pu-238 1.0X101 2.7X102 1.0X10-3 2.7X10-2 6.3X10-1 1.7X101 Pu-239 1.0X101 2.7X102 1.0X10-3 2.7X10-2 2.3X10-3 6.2X10-2 Pu-240 1.0X101 2.7X102 1.0X10-3 2.7X10-2 8.4X10-3 2.3X10-1 Pu-241 (a) 4.0X101 1.1X103 6.0X10-2 1.6 3.8 1.0X102 Pu-242 1.0X101 2.7X102 1.0X10-3 2.7X10-2 1.5X10-4 3.9X10-3 Pu-244 (a) 4.0X10-1 1.1X101 1.0X10-3 2.7X10-2 6.7X10-7 1.8X10-5 Ra-223 (a) Radium (88) 4.0X10-1 1.1X101 7.0X10-3 1.9X10-1 1.9X103 5.1X104 Ra-224 (a) 4.0X10-1 1.1X101 2.0X10-2 5.4X10-1 5.9X103 1.6X105 Ra-225 (a) 2.0X10-1 5.4 4.0X10-3 1.1X10-1 1.5X103 3.9X104 Ra-226 (a) 2.0X10-1 5.4 3.0X10-3 8.1X10-2 3.7X10-2 1.0 Ra-228 (a) 6.0X10-1 1.6X101 2.0X10-2 5.4X10-1 1.0X101 2.7X102 Rb-81 Rubidium (37) 2.0 5.4X101 8.0X10-1 2.2X101 3.1X105 8.4X106 Rb-83 (a) 2.0 5.4X101 2.0 5.4X101 6.8X102 1.8X104 Rb-84 1.0 2.7X101 1.0 2.7X101 1.8X103 4.7X104 Rb-86 5.0X10-1 1.4X101 5.0X10-1 1.4X101 3.0X103 8.1X104

Rb-87 Unlimited Unlimited Unlimited Unlimited 3.2X10-9 8.6X10-8 Rb(nat) Unlimited Unlimited Unlimited Unlimited 6.7X106 1.8X108 Re-184 Rhenium (75) 1.0 2.7X101 1.0 2.7X101 6.9X102 1.9X104 Re-184m 3.0 8.1X101 1.0 2.7X101 1.6X102 4.3X103 Re-186 2.0 5.4X101 6.0X10-1 1.6X101 6.9X103 1.9X105 Re-187 Unlimited Unlimited Unlimited Unlimited 1.4X10-9 3.8X10-8 Re-188 4.0X10-1 1.1X101 4.0X10-1 1.1X101 3.6X104 9.8X105 Re-189 (a) 3.0 8.1X101 6.0X10-1 1.6X101 2.5X104 6.8X105 Re(nat) Unlimited Unlimited Unlimited Unlimited 0.0 2.4X10-8 Rh-99 Rhodium (45) 2.0 5.4X101 2.0 5.4X101 3.0X103 8.2X104 Rh-101 4.0 1.1X102 3.0 8.1X101 4.1X101 1.1X103 Rh-102 5.0X10-1 1.4X101 5.0X10-1 1.4X101 4.5X101 1.2X103 Rh-102m 2.0 5.4X101 2.0 5.4X101 2.3X102 6.2X103 Rh-103m 4.0X101 1.1X103 4.0X101 1.1X103 1.2X106 3.3X107 Rh-105 1.0X101 2.7X102 8.0X10-1 2.2X101 3.1X104 8.4X105 Rn-222 (a) Radon (86) 3.0X10-1 8.1 4.0X10-3 1.1X10-1 5.7X103 1.5X105 Ruthenium Ru-97 5.0 1.4X102 5.0 1.4X102 1.7X104 4.6X105 (44)

Ru-103 (a) 2.0 5.4X101 2.0 5.4X101 1.2X103 3.2X104 Ru-105 1.0 2.7X101 6.0X10-1 1.6X101 2.5X105 6.7X106 Ru-106 (a) 2.0X10-1 5.4 2.0X10-1 5.4 1.2X102 3.3X103 S-35 Sulphur (16) 4.0X101 1.1X103 3.0 8.1X101 1.6X103 4.3X104 Sb-122 Antimony (51) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.5X104 4.0X105 Sb-124 6.0X10-1 1.6X101 6.0X10-1 1.6X101 6.5X102 1.7X104 Sb-125 2.0 5.4X101 1.0 2.7X101 3.9X101 1.0X103 Sb-126 4.0X10-1 1.1X101 4.0X10-1 1.1X101 3.1X103 8.4X104 Sc-44 Scandium (21) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 6.7X105 1.8X107 Sc-46 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.3X103 3.4X104 Sc-47 1.0X101 2.7X102 7.0X10-1 1.9X101 3.1X104 8.3X105 Sc-48 3.0X10-1 8.1 3.0X10-1 8.1 5.5X104 1.5X106 Se-75 Selenium (34) 3.0 8.1X101 3.0 8.1X101 5.4X102 1.5X104

Se-79 4.0X101 1.1X103 2.0 5.4X101 2.6X10-3 7.0X10-2 Si-31 Silicon (14) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 1.4X106 3.9X107 Si-32 4.0X101 1.1X103 5.0X10-1 1.4X101 3.9 1.1X102 Sm-145 Samarium (62) 1.0X101 2.7X102 1.0X101 2.7X102 9.8X101 2.6X103 8.5X10-1 Sm-147 Unlimited Unlimited Unlimited Unlimited 2.3X10-8 8.5X10-10 Sm-151 4.0X101 1.1X103 1.0X101 2.7X102 9.7X10-1 2.6X101 Sm-153 9.0 2.4X102 6.0X10-1 1.6X101 1.6X104 4.4X105 Sn-113 (a) Tin (50) 4.0 1.1X102 2.0 5.4X101 3.7X102 1.0X104 Sn-117m 7.0 1.9X102 4.0X10-1 1.1X101 3.0X103 8.2X104 Sn-119m 4.0X101 1.1X103 3.0X101 8.1X102 1.4X102 3.7X103 Sn-121m 4.0X101 1.1X103 9.0X10-1 2.4X101 2.0 5.4X101 (a)

Sn-123 8.0X10-1 2.2X101 6.0X10-1 1.6X101 3.0X102 8.2X103 Sn-125 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.0X103 1.1X105 Sn-126 (a) 6.0X10-1 1.6X101 4.0X10-1 1.1X101 1.0X10-3 2.8X10-2 Sr-82 (a) Strontium (38) 2.0X10-1 5.4 2.0X10-1 5.4 2.3X103 6.2X104 Sr-85 2.0 5.4X101 2.0 5.4X101 8.8X102 2.4X104 Sr-85m 5.0 1.4X102 5.0 1.4X102 1.2X106 3.3X107 Sr-87m 3.0 8.1X101 3.0 8.1X101 4.8X105 1.3X107 Sr-89 6.0X10-1 1.6X101 6.0X10-1 1.6X101 1.1X103 2.9X104 Sr-90 (a) 3.0X10-1 8.1 3.0X10-1 8.1 5.1 1.4X102 Sr-91 (a) 3.0X10-1 8.1 3.0X10-1 8.1 1.3X105 3.6X106 Sr-92 (a) 1.0 2.7X101 3.0X10-1 8.1 4.7X105 1.3X107 T(H-3) Tritium (1) 4.0X101 1.1X103 4.0X101 1.1X103 3.6X102 9.7X103 Ta-178 Tantalum (73) 1.0 2.7X101 8.0X10-1 2.2X101 4.2X106 1.1X108 (long-lived)

Ta-179 3.0X101 8.1X102 3.0X101 8.1X102 4.1X101 1.1X103 Ta-182 9.0X10-1 2.4X101 5.0X10-1 1.4X101 2.3X102 6.2X103 Tb-157 Terbium (65) 4.0X101 1.1X103 4.0X101 1.1X103 5.6X10-1 1.5X101 Tb-158 1.0 2.7X101 1.0 2.7X101 5.6X10-1 1.5X101 Tb-160 1.0 2.7X101 6.0X10-1 1.6X101 4.2X102 1.1X104

Technetium Tc-95m (a) 2.0 5.4X101 2.0 5.4X101 8.3X102 2.2X104 (43)

Tc-96 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.2X104 3.2X105 Tc-96m (a) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.4X106 3.8X107 Tc-97 Unlimited Unlimited Unlimited Unlimited 5.2X10-5 1.4X10-3 Tc-97m 4.0X101 1.1X103 1.0 2.7X101 5.6X102 1.5X104 Tc-98 8.0X10-1 2.2X101 7.0X10-1 1.9X101 3.2X10-5 8.7X10-4 Tc-99 4.0X101 1.1X103 9.0X10-1 2.4X101 6.3X10-4 1.7X10-2 Tc-99m 1.0X101 2.7X102 4.0 1.1X102 1.9X105 5.3X106 Te-121 Tellurium (52) 2.0 5.4X101 2.0 5.4X101 2.4X103 6.4X104 Te-121m 5.0 1.4X102 3.0 8.1X101 2.6X102 7.0X103 Te-123m 8.0 2.2X102 1.0 2.7X101 3.3X102 8.9X103 Te-125m 2.0X101 5.4X102 9.0X10-1 2.4X101 6.7X102 1.8X104 Te-127 2.0X101 5.4X102 7.0X10-1 1.9X101 9.8X104 2.6X106 Te-127m 2.0X101 5.4X102 5.0X10-1 1.4X101 3.5X102 9.4X103 (a)

Te-129 7.0X10-1 1.9X101 6.0X10-1 1.6X101 7.7X105 2.1X107 Te-129m 8.0X10-1 2.2X101 4.0X10-1 1.1X101 1.1X103 3.0X104 (a)

Te-131m 7.0X10-1 1.9X101 5.0X10-1 1.4X101 3.0X104 8.0X105 (a)

Te-132 (a) 5.0X10-1 1.4X101 4.0X10-1 1.1X101 1.1X104 3.0X105 Th-227 Thorium (90) 1.0X101 2.7X102 5.0X10-3 1.4X10-1 1.1X103 3.1X104 Th-228 (a) 5.0X10-1 1.4X101 1.0X10-3 2.7X10-2 3.0X101 8.2X102 Th-229 5.0 1.4X102 5.0X10-4 1.4X10-2 7.9X10-3 2.1X10-1 Th-230 1.0X101 2.7X102 1.0X10-3 2.7X10-2 7.6X10-4 2.1X10-2 Th-231 4.0X101 1.1X103 2.0X10-2 5.4X10-1 2.0X104 5.3X105 Th-232 Unlimited Unlimited Unlimited Unlimited 4.0X10-9 1.1X10-7 Th-234 (a) 3.0X10-1 8.1 3.0X10-1 8.1 8.6X102 2.3X104 Th(nat) Unlimited Unlimited Unlimited Unlimited 8.1X10-9 2.2X10-7 Ti-44 (a) Titanium (22) 5.0X10-1 1.4X101 4.0X10-1 1.1X101 6.4 1.7X102 Tl-200 Thallium (81) 9.0X10-1 2.4X101 9.0X10-1 2.4X101 2.2X104 6.0X105

Tl-201 1.0X101 2.7X102 4.0 1.1X102 7.9X103 2.1X105 Tl-202 2.0 5.4X101 2.0 5.4X101 2.0X103 5.3X104 Tl-204 1.0X101 2.7X102 7.0X10-1 1.9X101 1.7X101 4.6X102 Tm-167 Thulium (69) 7.0 1.9X102 8.0X10-1 2.2X101 3.1X103 8.5X104 Tm-170 3.0 8.1X101 6.0X10-1 1.6X101 2.2X102 6.0X103 Tm-171 4.0X101 1.1X103 4.0X101 1.1X103 4.0X101 1.1X103 U-230 (fast Uranium (92) 4.0X101 1.1X103 1.0X10-1 2.7 1.0X103 2.7X104 lung absorption)

(a)(d)

U-230 4.0X101 1.1X103 4.0X10-3 1.1X10-1 1.0X103 2.7X104 (medium lung absorption)

(a)(e)

U-230 (slow 3.0X101 8.1X102 3.0X10-3 8.1X10-2 1.0X103 2.7X104 lung absorption)

(a)(f)

U-232 (fast 4.0X101 1.1X103 1.0X10-2 2.7X10-1 8.3X10-1 2.2X101 lung absorption)

(d)

U-232 4.0X101 1.1X103 7.0X10-3 1.9X10-1 8.3X10-1 2.2X101 (medium lung absorption)

(e)

U-232 (slow 1.0X101 2.7X102 1.0X10-3 2.7X10-2 8.3X10-1 2.2X101 lung absorption)

(f)

U-233 (fast 4.0X101 1.1X103 9.0X10-2 2.4 3.6X10-4 9.7X10-3 lung absorption)

(d)

U-233 4.0X101 1.1X103 2.0X10-2 5.4X10-1 3.6X10-4 9.7X10-3 (medium lung absorption)

(e)

U-233 (slow 4.0X101 1.1X103 6.0X10-3 1.6X10-1 3.6X10-4 9.7X10-3 lung absorption)

(f)

U-234 (fast 4.0X101 1.1X103 9.0X10-2 2.4 2.3X10-4 6.2X10-3 lung absorption)

(d)

U-234 4.0X101 1.1X103 2.0X10-2 5.4X10-1 2.3X10-4 6.2X10-3 (medium lung absorption)

(e)

U-234 (slow 4.0X101 1.1X103 6.0X10-3 1.6X10-1 2.3X10-4 6.2X10-3 lung absorption)

(f)

U-235 (all Unlimited Unlimited Unlimited Unlimited 8.0X10-8 2.2X10-6 lung absorption types)

(a),(d),(e),(f)

U-236 (fast Unlimited Unlimited Unlimited Unlimited 2.4X10-6 6.5X10-5 lung absorption)

(d)

U-236 4.0X101 1.1X103 2.0X10-2 5.4X10-1 2.4X10-6 6.5X10-5 (medium lung absorption)

(e)

U-236 (slow lung 4.0X101 1.1X103 6.0X10-3 1.6X10-1 2.4X10-6 6.5X10-5 absorption)

(f)

U-238 (all Unlimited Unlimited Unlimited Unlimited 1.2X10-8 3.4X10-7 lung absorption types)

(d),(e),(f)

U (nat) Unlimited Unlimited Unlimited Unlimited 2.6X10-8 7.1X10-7 U (enriched Unlimited Unlimited Unlimited Unlimited See See to 20% or Table Table less) (g) A-4 A-4

See See U (dep) Unlimited Unlimited Unlimited Unlimited Table Table A-4 A-3 V-48 Vanadium (23) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 6.3X103 1.7X105 V-49 4.0X101 1.1X103 4.0X101 1.1X103 3.0X102 8.1X103 W-178 (a) Tungsten (74) 9.0 2.4X102 5.0 1.4X102 1.3X103 3.4X104 W-181 3.0X101 8.1X102 3.0X101 8.1X102 2.2X102 6.0X103 W-185 4.0X101 1.1X103 8.0X10-1 2.2X101 3.5X102 9.4X103 W-187 2.0 5.4X101 6.0X10-1 1.6X101 2.6X104 7.0X105 W-188 (a) 4.0X10-1 1.1X101 3.0X10-1 8.1 3.7X102 1.0X104 Xe-122 (a) Xenon (54) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.8X104 1.3X106 Xe-123 2.0 5.4X101 7.0X10-1 1.9X101 4.4X105 1.2X10 Xe-127 4.0 1.1X102 2.0 5.4X101 1.0X103 2.8X104 Xe-131m 4.0X101 1.1X103 4.0X101 1.1X103 3.1X103 8.4X104 Xe-133 2.0X101 5.4X102 1.0X101 2.7X102 6.9X103 1.9X105 Xe-135 3.0 8.1X101 2.0 5.4X101 9.5X104 2.6X106 Y-87 (a) Yttrium (39) 1.0 2.7X101 1.0 2.7X101 1.7X104 4.5X105 Y-88 4.0X10-1 1.1X101 4.0X10-1 1.1X101 5.2X102 1.4X104 Y-90 3.0X10-1 8.1 3.0X10-1 8.1 2.0X104 5.4X105 Y-91 6.0X10-1 1.6X101 6.0X10-1 1.6X101 9.1X102 2.5X104 Y-91m 2.0 5.4X101 2.0 5.4X101 1.5X106 4.2X10 Y-92 2.0X10-1 5.4 2.0X10-1 5.4 3.6X105 9.6X106 Y-93 3.0X10-1 8.1 3.0X10-1 8.1 1.2X105 3.3X106 Yb-169 Ytterbium (70) 4.0 1.1X102 1.0 2.7X101 8.9X102 2.4X104 Yb-175 3.0X101 8.1X102 9.0X10-1 2.4X101 6.6X103 1.8X105 Zn-65 Zinc (30) 2.0 5.4X101 2.0 5.4X101 3.0X102 8.2X103 Zn-69 3.0 8.1X101 6.0X10-1 1.6X101 1.8X106 4.9X10 Zn-69m (a) 3.0 8.1X101 6.0X10-1 1.6X101 1.2X105 3.3X106 Zr-88 Zirconium (40) 3.0 8.1X101 3.0 8.1X101 6.6X102 1.8X104 Zr-93 Unlimited Unlimited Unlimited Unlimited 9.3X10 2.5X10 Zr-95 (a) 2.0 5.4X101 8.0X10-1 2.2X101 7.9X102 2.1X104 Zr-97 (a) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 7.1X104 1.9X106

a A1 and/or A2 values include contributions from daughter nuclides with half-lives less than 10 days, as listed in the following:

Mg-28 Al-28 Ca-47 Sc-47 Ti-44 Sc-44 Fe-52 Mn-52m Fe-60 Co-60m Zn-69m Zn-69 Ge-68 Ga-68 Rb-83 Kr-83m Sr-82 Rb-82 Sr-90 Y-90 Sr-91 Y-91m Sr-92 Y-92 Y-87 Sr-87m Zr-95 Nb-95m Zr-97 Nb-97m, Nb-97 Mo-99 Tc-99m Tc-95m Tc-95 Tc-96m Tc-96 Ru-103 Rh-103m Ru-106 Rh-106 Pd-103 Rh-103m Ag-108m Ag-108 Ag-110m Ag-110 Cd-115 In-115m In-114m In-114 Sn-113 In-113m Sn-121m Sn-121 Sn-126 Sb-126m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-132 I-135 Xe-135m Xe-122 I-122 Cs-137 Ba-137m Ba-131 Cs-131 Ba-140 La-140 Ce-144 Pr-144m, Pr-144 Pm-148m Pm-148 Gd-146 Eu-146 Dy-166 Ho-166 Hf-172 Lu-172 W-178 Ta-178 W-188 Re-188 Re-189 Os-189m Os-194 Ir-194 Ir-189 Os-189m Pt-188 Ir-188

Hg-194 Au-194 Hg-195m Hg-195 Pb-210 Bi-210 Pb-212 Bi-212, Po-212, TI-208 Bi-210m Tl-206 Bi-212 Tl-208, Po-212 At-211 Po-211 Rn-222 Po-218, Pb-214, At-218, Bi-214, Po-214 Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207 Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 Ra-225 Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209 Ra-228 Ac-228 Ac-225 Fr-221, At-217, Bi-213, Po-213, Pb-209, TI-209 Ac-227 Fr-223 Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 Th-234 Pa-234m, Pa-234 Pa-230 Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214 U-230 Th-226, Ra-222, Rn-218, Po-214 U-235 Th-231 Pu-241 U-237 Pu-244 U-240, Np-240m Am-242m Am-242, Np-238 Am-243 Np-239 Cm-247 Pu-243 Bk-249 Am-245 Cf-253 Cm-249 b

The values of A1 and A2 in Curies (Ci) are approximate and for information only; the regulatory standard units are terabecquerels (TBq).

c The activity of Ir-192 in special form may be determined from a measurement of the rate of decay or a measurement of the radiation level at a prescribed distance from the source.

d These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident conditions of transport.

e These values apply only to compounds of uranium that take the chemical form of UO3, UF4, UCl4 and hexavalent compounds in both normal and accident conditions of transport.

f These values apply to all compounds of uranium other than those specified in notes d and e of this table.

g These values apply to unirradiated uranium only.

h A2 = 0.74 TBq (20 Ci) for Mo-99 for domestic use.

G. Table 2. Exempt Material Activity Concentrations and Exempt Consignment Activity Limits for Radionuclides.

Activity Activity Activity limit Activity limit concentration Symbol of Element and concentration for exempt for exempt for exempt radionuclide atomic number for exempt consignment consignment material material (Ci/g) (Bq) (Ci)

(Bq/g)

Ac-225 Actinium (89) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Ac-227 1.0X10-1 2.7X10-12 1.0X103 2.7X10-8

Ac-228 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ag-105 Silver (47) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ag-108m (b) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ag-110m 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ag-111 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Al-26 Aluminum (13) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Americium Am-241 1.0 2.7X10-11 1.0X104 2.7X10-7 (95)

Am-242m (b) 1.0 2.7X10-11 1.0X104 2.7X10-7 Am-243 (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Ar-37 Argon (18) 1.0X106 2.7X10-5 1.0X108 2.7X10-3 Ar-39 1.0X107 2.7X10-4 1.0X104 2.7X10-7 Ar-41 1.0X102 2.7X10-9 1.0X109 2.7X10-2 As-72 Arsenic (33) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 As-73 1.0X103 2.7X10-8 1.0X107 2.7X10-4 As-74 1.0X101 2.7X10-10 1.0X106 2.7X10-5 As-76 1.0X102 2.7X10-9 1.0X105 2.7X10-6 As-77 1.0X103 2.7X10-8 1.0X106 2.7X10-5 At-211 Astatine (85) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Au-193 Gold (79) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Au-194 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Au-195 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Au-198 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Au-199 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-131 Barium (56) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-133 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-133m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-140 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Be-7 Beryllium (4) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Be-10 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Bi-205 Bismuth (83) 1.0X101 2.7X10-10 1.0X106 2.7X10-5

Bi-206 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Bi-207 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Bi-210 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Bi-210m 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Bi-212 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Bk-247 Berkelium (97) 1.0 2.7X10-11 1.0X104 2.7X10-7 Bk-249 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Br-76 Bromine (35) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Br-77 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Br-82 1.0X101 2.7X10-10 1.0X106 2.7X10-5 C-11 Carbon (6) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 C-14 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Ca-41 Calcium (20) 1.0X105 2.7X10-6 1.0X107 2.7X10-4 Ca-45 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Ca-47 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Cd-109 Cadmium (48) 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Cd-113m 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Cd-115 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Cd-115m 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Ce-139 Cerium (58) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ce-141 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Ce-143 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ce-144 (b) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Californium Cf-248 1.0X101 2.7X10-10 1.0X104 2.7X10-7 (98)

Cf-249 1.0 2.7X10-11 1.0X103 2.7X10-8 Cf-250 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cf-251 1.0 2.7X10-11 1.0X103 2.7X10-8 Cf-252 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cf-253 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cf-254 1.0 2.7X10-11 1.0X103 2.7X10-8

Cl-36 Chlorine (17) 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Cl-38 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cm-240 Curium (96) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cm-241 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Cm-242 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cm-243 1.0 2.7X10-11 1.0X104 2.7X10-7 Cm-244 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cm-245 1.0 2.7X10-11 1.0X103 2.7X10-8 Cm-246 1.0 2.7X10-11 1.0X103 2.7X10-8 Cm-247 1.0 2.7X10-11 1.0X104 2.7X10-7 Cm-248 1.0 2.7X10-11 1.0X103 2.7X10-8 Co-55 Cobalt (27) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Co-56 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Co-57 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Co-58 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Co-58m 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Co-60 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cr-51 Chromium (24) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Cs-129 Cesium (55) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cs-131 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Cs-132 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cs-134 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cs-134m 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Cs-135 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Cs-136 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cs-137 (b) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cu-64 Copper (29) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Cu-67 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Dysprosium Dy-159 1.0X103 2.7X10-8 1.0X107 2.7X10-4 (66)

Dy-165 1.0X103 2.7X10-8 1.0X106 2.7X10-5

Dy-166 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Er-169 Erbium (68) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Er-171 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Eu-147 Europium (63) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Eu-148 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Eu-149 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Eu-150 (short 1.0X103 2.7X10-8 1.0X106 2.7X10-5 lived)

Eu-150 (long 1.0X101 2.7X10-10 1.0X106 2.7X10-5 lived)

Eu-152 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Eu-152m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Eu-154 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Eu-155 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Eu-156 1.0X101 2.7X10-10 1.0X106 2.7X10-5 F-18 Fluorine (9) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Fe-52 Iron (26) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Fe-55 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Fe-59 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Fe-60 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Ga-67 Gallium (31) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ga-68 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Ga-72 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Gadolinium Gd-146 1.0X101 2.7X10-10 1.0X106 2.7X10-5 (64)

Gd-148 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Gd-153 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Gd-159 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Germanium Ge-68 1.0X101 2.7X10-10 1.0X105 2.7X10-6 (32)

Ge-71 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Ge-77 1.0X101 2.7X10-10 1.0X105 2.7X10-6

Hf-172 Hafnium (72) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Hf-175 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hf-181 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Hf-182 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hg-194 Mercury (80) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Hg-195m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hg-197 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Hg-197m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hg-203 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Ho-166 Holmium (67) 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Ho-166m 1.0X101 2.7X10-10 1.0X106 2.7X10-5 I-123 Iodine (53) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 I-124 1.0X101 2.7X10-10 1.0X106 2.7X10-5 I-125 1.0X103 2.7X10-8 1.0X106 2.7X10-5 I-126 1.0X102 2.7X10-9 1.0X106 2.7X10-5 I-129 1.0X102 2.7X10-9 1.0X105 2.7X10-6 I-131 1.0X102 2.7X10-9 1.0X106 2.7X10-5 I-132 1.0X101 2.7X10-10 1.0X105 2.7X10-6 I-133 1.0X101 2.7X10-10 1.0X106 2.7X10-5 I-134 1.0X101 2.7X10-10 1.0X105 2.7X10-6 I-135 1.0X101 2.7X10-10 1.0X106 2.7X10-5 In-111 Indium (49) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 In-113m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 In-114m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 In-115m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ir-189 Iridium (77) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Ir-190 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ir-192 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Ir-194 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Potassium K-40 1.0X102 2.7X10-9 1.0X106 2.7X10-5 (19)

K-42 1.0X102 2.7X10-9 1.0X106 2.7X10-5 K-43 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Kr-79 Krypton (36) 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Kr-81 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Kr-85 1.0X105 2.7X10-6 1.0X104 2.7X10-7 Kr-85m 1.0X103 2.7X10-8 1.0X1010 2.7X10-1 Kr-87 1.0X102 2.7X10-9 1.0X109 2.7X10-2 Lanthanum La-137 1.0X103 2.7X10-8 1.0X107 2.7X10-4 (57)

La-140 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Lu-172 Lutetium (71) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Lu-173 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Lu-174 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Lu-174m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Lu-177 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Magnesium Mg-28 1.0X101 2.7X10-10 1.0X105 2.7X10-6 (12)

Manganese Mn-52 1.0X101 2.7X10-10 1.0X105 2.7X10-6 (25)

Mn-53 1.0X104 2.7X10-7 1.0X109 2.7X10-2 Mn-54 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Mn-56 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Molybdenum Mo-93 1.0X103 2.7X10-8 1.0X108 2.7X10-3 (42)

Mo-99 1.0X102 2.7X10-9 1.0X106 2.7X10-5 N-13 Nitrogen (7) 1.0X102 2.7X10-9 1.0X109 2.7X10-2 Na-22 Sodium (11) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Na-24 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Nb-93m Niobium (41) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Nb-94 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Nb-95 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Nb-97 1.0X101 2.7X10-10 1.0X106 2.7X10-5

Neodymium Nd-147 1.0X102 2.7X10-9 1.0X106 2.7X10-5 (60)

Nd-149 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ni-59 Nickel (28) 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Ni-63 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Ni-65 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Neptunium Np-235 1.0X103 2.7X10-8 1.0X107 2.7X10-4 (93)

Np-236 (short-1.0X103 2.7X10-8 1.0X107 2.7X10-4 lived)

Np-236 (long-1.0X102 2.7X10-9 1.0X105 2.7X10-6 lived)

Np-237 (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Np-239 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Os-185 Osmium (76) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Os-191 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Os-191m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Os-193 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Os-194 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Phosphorus P-32 1.0X103 2.7X10-8 1.0X105 2.7X10-6 (15)

P-33 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Protactinium Pa-230 1.0X101 2.7X10-10 1.0X106 2.7X10-5 (91)

Pa-231 1.0 2.7X10-11 1.0X103 2.7X10-8 Pa-233 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Pb-201 Lead (82) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pb-202 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Pb-203 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pb-205 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Pb-210 (b) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Pb-212 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Pd-103 Palladium (46) 1.0X103 2.7X10-8 1.0X108 2.7X10-3

Pd-107 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Pd-109 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Promethium Pm-143 1.0X102 2.7X10-9 1.0X106 2.7X10-5 (61)

Pm-144 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pm-145 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Pm-147 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Pm-148m 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pm-149 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Pm-151 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Po-210 Polonium (84) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Praseodymium Pr-142 1.0X102 2.7X10-9 1.0X105 2.7X10-6 (59)

Pr-143 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Pt-188 Platinum (78) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pt-191 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pt-193 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Pt-193m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Pt-195m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pt-197 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Pt-197m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pu-236 Plutonium (94) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Pu-237 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Pu-238 1.0 2.7X10-11 1.0X104 2.7X10-7 Pu-239 1.0 2.7X10-11 1.0X104 2.7X10-7 Pu-240 1.0 2.7X10-11 1.0X103 2.7X10-8 Pu-241 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Pu-242 1.0 2.7X10-11 1.0X104 2.7X10-7 Pu-244 1.0 2.7X10-11 1.0X104 2.7X10-7 Ra-223 (b) Radium (88) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Ra-224 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Ra-225 1.0X102 2.7X10-9 1.0X105 2.7X10-6

Ra-226 (b) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Ra-228 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Rb-81 Rubidium (37) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rb-83 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Rb-84 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rb-86 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Rb-87 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Rb(nat) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Re-184 Rhenium (75) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Re-184m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Re-186 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Re-187 1.0X106 2.7X10-5 1.0X109 2.7X10-2 Re-188 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Re-189 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Re(nat) 1.0X106 2.7X10-5 1.0X109 2.7X10-2 Rh-99 Rhodium (45) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rh-101 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Rh-102 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rh-102m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Rh-103m 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Rh-105 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Rn-222 (b) Radon (86) 1.0X101 2.7X10-10 1.0X108 2.7X10-3 Ruthenium Ru-97 1.0X102 2.7X10-9 1.0X107 2.7X10-4 (44)

Ru-103 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ru-105 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ru-106 (b) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 S-35 Sulphur (16) 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Sb-122 Antimony (51) 1.0X102 2.7X10-9 1.0X104 2.7X10-7 Sb-124 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Sb-125 1.0X102 2.7X10-9 1.0X106 2.7X10-5

Sb-126 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sc-44 Scandium (21) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sc-46 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Sc-47 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sc-48 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Se-75 Selenium (34) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Se-79 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Si-31 Silicon (14) 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Si-32 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Sm-145 Samarium (62) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Sm-147 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Sm-151 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Sm-153 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sn-113 Tin (50) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Sn-117m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sn-119m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Sn-121m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Sn-123 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Sn-125 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Sn-126 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sr-82 Strontium (38) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sr-85 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sr-85m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Sr-87m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sr-89 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Sr-90 (b) 1.0X102 2.7X10-9 1.0X104 2.7X10-7 Sr-91 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sr-92 1.0X101 2.7X10-10 1.0X106 2.7X10-5 T(H-3) Tritium (1) 1.0X106 2.7X10-5 1.0X109 2.7X10-2 Ta-178 (long-Tantalum (73) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 lived)

Ta-179 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Ta-182 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Tb-157 Terbium (65) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Tb-158 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tb-160 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Technetium Tc-95m 1.0X101 2.7X10-10 1.0X106 2.7X10-5 (43)

Tc-96 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tc-96m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Tc-97 1.0X103 2.7X10-8 1.0X108 2.7X10-3 Tc-97m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Tc-98 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tc-99 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Tc-99m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Te-121 Tellurium (52) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Te-121m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Te-123m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Te-125m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Te-127 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Te-127m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Te-129 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Te-129m 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Te-131m 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Te-132 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Th-227 Thorium (90) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Th-228 (b) 1.0 2.7X10-11 1.0X104 2.7X10-7 Th-229 (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Th-230 1.0 2.7X10-11 1.0X104 2.7X10-7 Th-231 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Th-232 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Th-234 (b) 1.0X103 2.7X10-8 1.0X105 2.7X10-6

Th (nat) (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Ti-44 Titanium (22) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Tl-200 Thallium (81) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tl-201 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Tl-202 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Tl-204 1.0X104 2.7X10-7 1.0X104 2.7X10-7 Tm-167 Thulium (69) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Tm-170 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Tm-171 1.0X104 2.7X10-7 1.0X108 2.7X10-3 U-230 (fast lung Uranium (92) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 absorption)

(b),(d)

U-230 (medium 1.0X101 2.7X10-10 1.0X104 2.7X10-7 lung absorption)

(e)

U-230 (slow 1.0X101 2.7X10-10 1.0X104 2.7X10-7 lung absorption)

(f)

U-232 (fast lung 1.0 2.7X10-11 1.0X103 2.7X10-8 absorption)

(b),(d)

U-232 (medium 1.0X101 2.7X10-10 1.0X104 2.7X10-7 lung absorption)

(e)

U-232 (slow 1.0X101 2.7X10-10 1.0X104 2.7X10-7 lung absorption)

(f)

U-233 (fast lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (d)

U-233 (medium 1.0X102 2.7X10-9 1.0X105 2.7X10-6 lung absorption)

(e)

U-233 (slow 1.0X101 2.7X10-10 1.0X105 2.7X10-6 lung absorption)

(f)

U-234 (fast lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (d)

U-234 (medium 1.0X102 2.7X10-9 1.0X105 2.7X10-6 lung absorption)

(e)

U-234 (slow 1.0X101 2.7X10-10 1.0X105 2.7X10-6 lung absorption)

(f)

U-235 (all lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption types)

(b),(d),(e),(f)

U-236 (fast lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (d)

U-236 (medium 1.0X102 2.7X10-9 1.0X105 2.7X10-6 lung absorption)

(e)

U-236 (slow 1.0X101 2.7X10-10 1.0X104 2.7X10-7 lung absorption)

(f)

U-238 (all lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption types)

(b),(d),(e),(f)

U (nat) (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 U (enriched to 1.0 2.7X10-11 1.0X103 2.7X10-8 20% or less) (g)

U (dep) 1.0 2.7X10-11 1.0X103 2.7X10-8 V-48 Vanadium (23) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 V-49 1.0X104 2.7X10-7 1.0X107 2.7X10-4 W-178 Tungsten (74) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 W-181 1.0X103 2.7X10-8 1.0X107 2.7X10-4 W-185 1.0X104 2.7X10-7 1.0X107 2.7X10-4 W-187 1.0X102 2.7X10-9 1.0X106 2.7X10-5 W-188 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Xe-122 Xenon (54) 1.0X102 2.7X10-9 1.0X109 2.7X10-2 Xe-123 1.0X102 2.7X10-9 1.0X109 2.7X10-2 Xe-127 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Xe-131m 1.0X104 2.7X10-7 1.0X104 2.7X10-7

Xe-133 1.0X103 2.7X10-8 1.0X104 2.7X10-7 Xe-135 1.0X103 2.7X10-8 1.0X1010 2.7X10-1 Y-87 Yttrium (39) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Y-88 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Y-90 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Y-91 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Y-91m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Y-92 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Y-93 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Yb-169 Ytterbium (70) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Yb-175 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Zn-65 Zinc (30) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Zn-69 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Zn-69m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Zr-88 Zirconium (40) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Zr-93 (b) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Zr-95 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Zr-97 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 a

(Reserved) b Parent nuclides and their progeny included in secular equilibrium are listed in the following:

Sr-90 Y-90 Zr-93 Nb-93m Zr-97 Nb-97 Ru-106 Rh-106 Cs-137 Ba-137m Ce-144 Pr-144 Ba-140 La-140 Bi-212 Tl-208 (0.36), Po-212 (0.64)

Pb-210 Bi-210, Po-210 Pb-212 Bi-212, Tl-208 (0.36), Po-212 (0.64)

Rn-222 Po-218, Pb-214, Bi-214, Po-214 Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Tl-207

Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208(0.36), Po-212 (0.64)

Ra-226 Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 Ra-228 Ac-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 Th-228 (0.64)

Th-229 Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209 Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Th-nat Tl-208 (0.36), Po-212 (0.64)

Th-234 Pa-234m U-230 Th-226, Ra-222, Rn-218, Po-214 Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-U-232 212 (0.64)

U-235 Th-231 U-238 Th-234, Pa-234m Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, U-nat Bi-214, Po-214, Pb-210, Bi-210, Po-210 Np-237 Pa-233 Am-242m Am-242 Am-243 Np-239 c

(Reserved) d These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident conditions of transport.

e These values apply only to compounds of uranium that take the chemical form of UO3, UF4, UCl4 and hexavalent compounds in both normal and accident conditions of transport.

f These values apply to all compounds of uranium other than those specified in notes (d) and (e) of this table.

g These values apply to unirradiated uranium only.

H. Table 3. General Values for A1 and A2.

A1 A2 Activity Activity Activity limits Activity limits concentratio concentratio for exempt for exempt Contents (TBq (Ci (TBq (Ci n for exempt n for exempt consignment consignment

) ) ) ) material material s (Bq) s (Ci)

(Bq/g) (Ci/g)

Only beta or 1 x 2.7 2 x 5.4 1 x 101 2.7 x10-10 1 x 104 2.7 x10-7 gamma 10-1 x 10-2 x emitting 10 0 10-radionuclide 1 s are known to be present

Alpha 2x 5.4 9 x 2.4 1 x 10-1 2.7 x10-12 1 x 103 2.7 x10-8 emitting 10-1 x 10-5 x radionuclide 100 10-s, but no 3 neutron emitters, are known to be present (a)

Neutron 1x 2.7 9 x 2.4 1 x 10-1 2.7 x 10-12 1 x 103 2.7 x 10-8 emitting 10-3 x 10-5 x nuclides are 10-10-known to be 2 3 present or no relevant data are available a

If beta or gamma emitting nuclides are known to be present, the A1 value of 0.1 TBq (2.7 Ci) should be used.

I. Table 4. Activity-Mass Relationships for Uranium.

Uranium Enrichment1 Specific Activity wt % U-235 present TBq/g Ci/g 0.45 1.8 x 10-8 5.0 x 10-7 0.72 2.6 x 10-8 7.1 x 10-7 1 2.8 x 10-8 7.6 x 10-7 1.5 3.7 x 10-8 1.0 x 10-6 5 1.0 x 10-7 2.7 x 10-6 10 1.8 x 10-7 4.8 x 10-6 20 3.7 x 10-7 1.0 x 10-5 35 7.4 x 10-7 2.0 x 10-5 50 9.3 x 10-7 2.5 x 10-5 90 2.2 x 10-6 5.8 x 10-5 93 2.6 x 10-6 7.0 x 10-5 95 3.4 x 10-6 9.1 x 10-5 1

The figures for uranium include representative values for the activity of the uranium-234 that is concentrated during the enrichment process.