Ames Procedural
Requirements

APR 1700.1

COMPLIANCE IS MANDATORY

Ames Health and Safety Procedural Requirements

Chapter 7 - Ames Radiation Safety Guide

7.14 Use of Offsite Contractor for Field Ratiation Testing
7.15 Personnel Under 18 Years of Age
7.16 Appendices

7.16.1 Appendix A: Notice to Employees (NRC Form 3)
7.16.2 Appendix B: Application for Radioisotope Procurement (ARC 343)
7.16.3 Appendix C: Record of Radioactive Material Transfer of Relocation
7.16.4 Appendix D: Receipt of Radiation Regulations
7.16.5 Appendix E: Radiation Project Approval Request
7.16.6 Appendix F: Radiation Experience Record
7.16.7 Appendix G: Radiation Project Authorization
7.16.8 Appendix H: Radiation Machine Operation Request
7.16.9 Appendix I: Radioisotope Inventory Record
7.16.10 Appendix J: Radiation Work Permit
7.16.11 Appendix K: Notification of Radiography
7.16.12 Appendix L: Notice of Radiation Testing
7.16.13 Appendix M: Daily Radiographic Check List
7.16.14 Appendix N: Caution Sign
7.16.15 Appendix O: Save for Future Use
7.16.16 Appendix P: Emergency Procedure
7.16.17 Appendix Q: Workplace for Radionuclides
7.16.18 Appendix R: Bioassay Program
7.16.19 Appendix S: Bioassay Action Levels

7.1 Policy

7.1.1 Overview

This chapter is a technical specification for the safe use of radioactive materials and ionizing radiation producing equipment. It describes the elements of the Ames Research Center Radiation Safety Program, including safety policies, organizations, procedures, and standards. Administrative procedures are outlined for regulating the purchase, use, disposal and transfer of radioisotopes. However, the responsibility for safety rests with the individual user of sources of radiation. No program can be effective without a conscious effort on the part of the user to assure the user's own safety and the safety of persons working nearby. For rules and regulations with regard to the use of non-ionizing radiation, such as laser and microwave radiation, please refer to Chapter 8 of this manual.

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7.1.2 Director's Policy

The basic safety policy of Ames Research Center is to conduct its operations in a manner that will minimize the risk of personal injury and facility damage from whatever source, consistent with the nature of the research and inquiry that the Center pursues. Accordingly, all sources of ionizing radiation shall be used in conformity with Federal Safety Regulations and the standards and procedures set out in this chapter.

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7.1.3 Federal Regulations

U.S. Nuclear Regulatory Commission (NRC) Rules and Regulations Title 10, Code of Federal Regulations, are expressly incorporated by reference in this chapter. A copy of these regulations is available through the Safety Division or on-line at the NRC web site http://www.nrc.gov.

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7.1.4 Distribution

The Radiation Safety Office shall ensure that this chapter is made available to each person designated as an Authorized User (AU). The AU should have a copy readily available on their laboratory computer for reference.

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7.2 Radiation Safety Organization

7.2.1 Center Director and the Executive Safety Committee

The Director is responsible for all Ames safety programs. Subject to the concurrence of the NRC, the Director is responsible for the enforcement of all safety programs that are implemented by the Ionizing Radiation Safety Committee. The Executive Safety Committee (ESC) provides leadership and guides the Center's Safety and Health Programs. In this capacity, the committee uses its authority to make unified policy decisions affecting Ames' injury prevention strategies and approves all major safety initiatives. The ESC charters Ames Safety Committees (Ionizing Radiation, Explosives, Traffic, Non-ionizing Radiation, etc.) and periodically requests information on key topics or report on accomplishments. Problems that cannot be resolved by Center Safety Committees are referred to the ESC.

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7.2.2 Ionizing Radiation Safety Committee

7.2.2.1 Purpose

The Ionizing Radiation Safety Committee was established in accordance with Title 10 Code of Federal Regulations, Part 33 (10 CFR 33) to supervise the purchase and use of radioactive materials under the license issued to the Center by the NRC and in accordance with agreements between the Center and the NRC.

The Committee also serves to review procedures for and to approve the use of ionizing radiation producing equipment at Ames Research Center.

Although the Committee has the responsibility for providing radiological advice to the Director and technical assistance to users upon request, the fundamental responsibility for seeking technical assistance and advice remains with the individual users under whose supervision radioactive byproduct materials are being used and ionizing radiation-producing equipment is being operated.

7.2.2.2 Membership

The Committee membership will be representative of all ionizing radiation use at Ames Research Center. It will be comprised of at least one member from the ionizing radiation research community, a NASA Ames representative capable of making decisions for Ames NASA Management, one member knowledgeable in the use of radiation producing equipment, and the Center's Radiation Safety Officer (RSO) and the Assistant RSO (if appointed). Professional experts from fields associated with the use of radioactive materials, such as hazardous materials experts or industrial operations experts, may also be asked to serve on the Committee to allow the Committee to benefit from their expertise. When membership of the Committee changes, the NRC shall be promptly notified by the Health, Safety and Medical Services Division.

7.2.2.3 Chairperson

The Center Director shall select and appoint the Chairperson for the Ionizing Radiation Safety Committee.

7.2.2.4 Functions

It is the responsibility of the Committee to assure by review, inspections, and audit the safe use of radioactive materials and ionizing radiation producing equipment.
The Committee is responsible for ensuring that the Center is in compliance with its NRC license.
The Committee must be familiar with all current Federal Regulations and ensure that they are enforced.
The Committee has the authority to determine the minimum acceptable qualifications for individuals using radioisotopes and other sources of ionizing radiation.
The Committee assures that new applications for the use of radioisotopes are approved before they are purchased. The RSO, Alternate RSO, or the Safety, Health and Medical Services Division will issue written approval.
The Committee reviews the provisions for the safe use of radiation-generating equipment before authorizing its use.
The Committee is responsible for ensuring that facilities and operations are surveyed at frequent intervals. If the survey records indicate the need, the Committee may require procedural changes.
The Committee oversees construction uses of radiation and demolition and construction of facilities containing radioactive material or radiation producing machines.
The Committee shall meet at least once per calendar quarter, to discuss overall radiation safety and radiation control policies, receive recommendations of the RSO or Alternate RSO, and take such action as those recommendations may warrant. The RSO, a NASA representative, and at least one member from the ionizing radiation research community must be present to establish a quorum for the meeting. Detailed minutes are to be kept of these meetings and placed on file for review.
Memorandums may handle business between meetings. If required, Committee business may also be conducted on the telephone or through electronic mail (e-mail), provided all conversations and actions are documented and reviewed at the next quarterly meeting.
All correspondence requiring Committee action will be placed on the meeting agenda by the RSO. Committee members may also add further agenda items.
The Committee reviews and investigates all serious radiation incidents. It then reports its findings to the Center Director.
The Committee reviews this chapter annually and makes any necessary revisions.

7.2.2.5 Human Research Approval

Human research or medical use of byproduct material is currently not approved by our NRC Byproduct Materials License. If human research or medical use of byproduct materials is deemed necessary in the future; the Radiation Safety Committee and the Human Research Institutional Review Board (HRIRB) will need to approve the research. The Center will need to apply for and receive a NRC license specifically allowing medical or research use of radioactive materials, and all researchers will need to be trained on the new requirements dictated by said license.

For human research or medical use of radiation producing machines or non-byproduct radioactive material not regulated by the NRC, approval will need to be obtained by both the Radiation Safety Committee and the HRIRB. This use of radiation will be in accordance with all Federal, State, and professional regulations and standards.

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7.2.3 Safety, Health and Medical Services Division

The Safety, Health and Medical Services Division has the responsibility, subject to review and approval of the Radiation Safety Committee, for surveillance of Center radiation activities and for providing services in radiation safety in conformity with policies and standards set out in this chapter.

The Chief, Safety, Health and Medical Services Division, is responsible for the review of performance with respect to the Center's policies on radiation and radiation safety and for informing the Center Director on matters relating to radiation and radiation safety.
Radiation Safety Officer (RSO)

The RSO is responsible for the day-to-day operation of the Radiation Safety Program. The ultimate responsibility for complying with NRC Regulations remains with the Center Director.
The RSO is responsible for ensuring that the use of radioactive material is in conformity with the NRC Materials License, applicable government regulations, and with the Center's policies.
The RSO shall analyze all radiological hazards associated with each new program.
The RSO shall maintain the Health Physics records of the Center and ensure that they are in compliance. (See Section 7.8, Record System)
The RSO is responsible for providing formal radiation safety training commensurate with the degree of hazard.
The RSO shall, to the extent practicable, use procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA) consistent with the purpose for which the licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvement in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and license materials in the public interest.

Alternate Radiation Safety Officer (ARSO)

The ARSO is empowered to act in the RSO's absence with the full authority of the RSO's position.
An ARSO must be designated whenever the RSO is away from the Center for extended periods on travel or leave.
The ARSO is a member of the Radiation Safety Committee whenever an ARSO is designated. While this position is only required whenever the RSO is away from the Center for extended periods on travel or leave, the Center may appoint a safety professional to this position on a permanent basis to ensure the ARSO is current on all aspects of the program when assigned.

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7.2.4 Division & Branch Chiefs

Division and Branch Chiefs are responsible for the review and approval of proposed uses of radioisotopes and radiation producing-machines within their jurisdiction. Such approval of line management officials signifies that they will provide the resources necessary to control hazards and will establish, as organization policy, the procedures necessary to comply with pertinent Center and government standards and regulations.

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7.2.5 Authorized Users

The Authorized User (AU) is personally responsible for compliance with Center and government regulations as they pertain to authorized use of radioisotopes or radiation. Specific responsibilities include:

Maintaining current records with respect to the receipt, use, disposal, and inventory of radioisotopes.
Conducting self-monitoring surveys, including wipe tests, of the user's laboratory on a periodic basis as agreed upon by the Radiation Safety Committee and AU. Frequency of surveys will be determined based on the level of hazard for each project. A copy of these survey records will be made available for review during RSO audits. The surveys performed by the safety division will not serve as a substitute for the surveys required of the authorized user.
Making the records available for inspection at reasonable times by the RSO or the NRC.
Instructing personnel under the AU's supervision in the proper procedures for controlling radiation hazards and for limiting their own exposures to radiation. Ensuring supervised personnel maintain proficiency in radiation safety techniques and principals. Ensuring that supervised personnel complete and understand radiation safety refresher training given by the Radiation Safety Officer and staff. If deemed appropriate by the RSO, the AU may give the practical portion of the "Introduction to Radiation Safety" training to supervised personnel.
Posting of hazard warning signs and properly posting, labeling, storing, and securing radioisotope containers. (10 CFR 20.1901-1905 Appendix 7.16.14).
The AU shall post each area or room in which there is used or stored an amount of licensed material exceeding 10 times the quantity of such material specified in Appendix C to 10 CFR 20.1001-20.2401 with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, RADIOACTIVE MATERIAL(S)" or "DANGER, RADIOACTIVE MATERIAL(S)." Additional or more restrictive posting requirements may be mandated as deemed necessary or prudent by the Radiation Safety Officer.
Enforcing the use of required dosimeters and survey meters by personnel under the AU's supervision, as applicable.

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7.2.6 Radiation Safety Contractor

Purpose: The Center Director may approve a Radiation Safety Contractor to provide advice, assistance, support, and consultation in the safe handling and use of byproduct material and ionizing radiation-producing equipment. The Radiological Safety Contractor shall obtain authority from the Center Director and shall submit all recommendations to the Committee in writing.
The Radiation Safety Contractor shall be available to attend committee meetings and conduct investigations as requested by the Committee and/or the RSO.
The Radiation Safety Contractor, while during normal support services, shall possess the authority of the RSO and the Committee to take appropriate action to prevent any unsafe handling of radioactive material.
Prior to the issuance of a User Permit, the Radiation Safety Contractor may be asked to investigate and report to the Committee on the following:
Safety aspects of the proposed activity;

Adequacy of training of the individuals concerned;
Suitability of available equipment; and,
Space and facilities for the safe conduct of the specific use of ionizing radiation.

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7.3 The NRC Licenses

7.3.1 Specific Licenses

The following NRC license is currently held by Ames Research Center: A Materials License authorizing the use of specific byproduct, source, and/or special nuclear materials of specific chemical and/or physical form with a maximum amount that may be possessed at any one time. The Materials License does not authorize human use studies.

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7.3.2 Limits & Conditions

The NRC licenses stipulate specific limits and conditions as follows:

The provisions and regulations with which the licensee must comply, including the provisions of the Title 10, Part 20 Code of Federal Regulations (10 CFR 20) "Standards for Protection Against Radiation" and the provisions of this chapter.
The maximum amount of radioactivity acquired under the license that may be possessed at any one time.
The locations where licensed materials may be used.
Purpose and conditions of use.

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7.3.3 Instruction to Workers (Notice to Employees)

10 CFR 19.12 requires that all individuals working in or frequenting any portion of a restricted area shall post Form NRC-3 (See 7.16.1) and be:

Kept informed of the storage, transfer, or use of radioactive materials or of radiation in such portions of the restricted area.
Instructed in the health protection problems associated with exposure to such radioactive materials or radiation, in precautions or procedures to minimize exposure, and in the purposes and functions of protective devices employed.
Instructed in, and instructed to observe, to the extent within the worker's control, the applicable provisions of Commission regulations and licenses for the protection of personnel from exposures to radiation or radioactive materials occurring in such areas.
Instructed of their responsibility to report promptly to the licensee any condition that may lead to or cause a violation of Commission regulations and licenses or unnecessary exposure to radiation or to radioactive material.
Instructed in the appropriate response to warnings made in the event of any unusual occurrence or malfunction that may involve exposure to radiation or radioactive material.
Advised of radiation exposure reports that workers may request.
The extent of these instructions shall be commensurate with potential radiological health protection problems in the restricted area.

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7.3.4 NASA Ames Training

Training provided at NASA Ames includes the following:

Introductory (Authorized Users and Laboratory Technicians)--6 to 7 hours web based or classroom with a 1 hour practical.
Introductory (Personnel from other institutions)--Personnel coming to the Center from other licensed facilities to work under the NASA Ames NRC Byproduct Materials License whose Radiation Safety Training is current within the last year from another institution will not be required to take the full 6 hour course and one hour practical. The RSO will review each individual's qualifications and make a determination as to what additional training will be needed prior to work at Ames. As a minimum, personnel will be required to read and understand the Center's Policies and Procedures (this chapter of the Ames Safety and Health Procedural Requirements) and the NRC's requirements (10 CFR 20). Individuals who have not received training for over 1 year will be required to take the full introductory class. The practical portion may be waived at the discretion of the RSO.
Refresher (Authorized Users and Laboratory Technicians)--4 hours annually given in 20 minute monthly training assignments or a 4 hour annual classroom session at the discretion of the RSO.
Ancillary--1-hour training commensurate with their duties.
X-ray (equipment dependent)--2 hours annual web based or classroom.
Users of the Center's Troxler, Series 3400, Moisture Density Gauge must be trained by Troxler Electronic Laboratories, Campbell Pacific Nuclear, or equivalent prior to handling the unit. Certificates of training must be kept on file. Training records must be maintained at least three years with at least the most current training records available during any period that the Troxler is being operated.
Sealed Source - Annual training commensurate with the type and strength (i.e., hazard) of the sealed source. Hands-on practical training and additional security requirements may be required if large quantity sources are used.

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7.3.5 Compliance Inspections

Licensees are subject to unannounced inspections by the NRC Compliance Office. Violations of the conditions under which a license is issued may result in penalties, including revocation of the license. License revocations could impact research center-wide, not solely in the specific area of violation.

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7.4 ALARA Policy

7.4.1 Management Statement

The management of this research institution is committed to maintaining exposures As Low As Reasonably Achievable (ALARA). The NASA Ames Research Center Radiation Safety Guide has been developed to provide instruction on keeping exposures to radiation ALARA.

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7.4.2 Contamination Limits

Action levels for removable surface contamination shall be those found in Table 2, NRC Regulatory Guide 8.23.

ALARA limits for area surface contamination will be one-fourth the NRC limits specified in section 7.4.2 above..
Acceptable surface contamination levels for uncontrolled release of equipment shall not exceed 80% of those found in Table 3, NRC Regulatory Guide 8.23. These limits may be set lower by the RSO.

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7.4.3 Dose Guidelines

The ALARA recommendations are 10% of the limits as set forth in 10 Code of Federal Regulation 20.1201 Occupational Dose Limits for adults.
The dose to an embryo/fetus during the entire pregnancy, from occupational exposure of a declared pregnant woman, shall not exceed 500 mRem (5mSv). Effort shall be initiated to preclude substantial variation above a uniform monthly exposure rate to a declared pregnant woman that would satisfy the 500 mRem (5mSv) limit. These limits may be found in the NRC Regulatory Guide 8.36.
Any unexpected exposure will require an informal inquiry . Any unexpected exposure greater than 50 mrem will require a formal, written investigation. By "unexpected exposure" it is meant exposure that would not be expected if the person followed the Radiation Safety Committee approved procedures for the given project.

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7.5 Project Authorization

7.5.1 Application Procedure

The prospective AU submits a request to the Radiation Safety Committee for approval to use radioisotopes in a specific project. The AU attaches the following forms (see Appendix) to the application: All forms are available from RSO.

A QH-20, Radiation Project Approval Request, including a discussion of proposed operational steps, goals of the experiment, and safety procedures.
The AU will also include specific steps to keep personal radiation exposures as low as reasonably achievable (ALARA).
Emergency Procedures, including call list.
A QH-21, Radiation Experience Record, (see 7.16.6), for the AU and each worker.
Calculations of Hazard Guide Values for all procedures using radioactive material (see 7.16.17).
A QH-3, (see 7.16.4), Receipt of Radiation Regulations, indicating that the AU has read and understood this chapter and the Code of Federal Regulations, Title 10, Part 20.
An Application for Radioisotope Procurement ARC Form 343 (see 7.16.2)-- to be completed after project approved prior to first shipment of radioactive material.

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7.5.2 Radiation Safety Officer's Review

The RSO reviews the application and evaluates the following factors:

The qualifications of the AU and all persons who will be working with isotopes under the AU's supervision.
Personal exposure history of individual(s) (internal and external).
Chemical forms and amounts of the specific radionuclides to be used.
Adequacy of facilities for working with the proposed quantities of isotopes.
Adequacy of written operating procedures. If necessary, the RSO will provide appropriate modifications to the AU.
Provisions for ensuring the safety of personnel, including the use of hoods and special equipment, methods of monitoring the environment, appropriate dosimetry, and the AU's written ALARA program.
Radioisotope control records, including inventory, use, storage, and disposal.
Possibility of low-level contamination.
Emergency Response Procedures for uncontained spills.

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7.5.3 Radiation Safety Committee's Review

The Radiation Safety Committee reviews the application and the analysis of the project submitted by the RSO and approves, disapproves or suggests changes to the project.

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7.5.4 Project Authorization Form

The Committee completes a QH-22 form, Radiation Project Authorization (see 7.16.7), setting out, among other things, any extraordinary conditions that need to be addressed, as well as the date the project expires. Copies of the form are to be sent to the AU and the AU's Branch Chief. This form needs to be signed by both the Branch Chief and the AU and sent back to the Radiation Safety Office including responses to any issue raised before the project is authorized.

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7.5.5 Authorized User

QH-22, Radiation Project Authorization, specifies the Authorized User. The responsibilities of the AU are detailed in Paragraph (7.2.5) of this chapter.

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7.5.6 Project Changes and Renewals

The AU may request project changes and renewals. To do this, the AU must submit:

A project Amendment or Renewal form,
A memo describing change request with justification and operating procedure changes or operating procedures for renewal,
An updated radioisotope inventory,
An updated "Radiation Experience Record" (QH-21) for all personnel on the project for renewals, all new personnel for amendments.

The Committee amends the QH-22, Radiation Project Authorization, to reflect approved changes or renewal.
The AU will turn over to the RSO copies of personnel training records, radiological surveys, and any other radiological information pertaining to the project at the completion of the project for archiving and use in future decommissioning activities.

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7.6 Radiation & Radioactive Materials Area

7.6.1 Radiation Safety Officer's Review

The RSO reviews all areas proposed for the use of radiation and radioactive sources. Specific precautions may be required, depending on the degree of radiological hazard (e.g., negative pressure area, fume hood use, adequate shielding, etc.). (See Appendix 7.16.17)

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7.6.2 Warning Signs

Warning signs must be conspicuously posted by the RSO or delegate at entrances to approved radiation areas and radioactive materials use areas. Radioisotope projects may only be conducted in posted radioactive areas. The proper posting for radioactive material use areas is the universal three bladed radioactive symbol with the words "Caution-Radioactive Materials" (see 7.16.14). Other signs may also be posted in addition to this posting if required (e.g.: Caution Radiation Area).

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7.6.3 Fume Hoods

Locations approved for radioisotope use, where airborne radioactivity may be a possibility, must be equipped with standard radio-chemical fume hoods and laboratory apparatus as specified below:

Fume hoods must have an exhaust system separate from the rest of the building at each location and have an approved radioisotope filter. The exhaust must exit seven (7) feet above any occupied surface. These hoods shall be reviewed and approved by the Radiation Safety Officer or designee.
Each fume hood used for radioactive material containment will be evaluated to ensure it will contain radioactive material fumes or vapors and that it will exhaust the material properly through the designated exhaust ducting. This evaluation will consist at a minimum of face velocity measurements and smoke tests. Whenever possible the industry standards for face velocities will be used, but the final evaluation of the fume hood's ability to contain the material will be determined by the Radiation Safety professional or Industrial Hygienist conducting the test. These professionals will use a standard operating procedure approved by Code QH to perform this evaluation. Whenever maintenance is performed on radioactive material fume hoods, the maintenance personnel are required to contact the Radiation Safety Officer or the Safety Division Health Physics Manager prior to such work. The Radiation Safety Officer will ensure there are no hazards to maintenance personnel from radioactive materials prior to the performance of maintenance. At the completion of maintenance, the Radiation Safety Office personnel will re-test the fume hood for proper containment.
Whenever maintenance is performed on or near radioactive material fume hood exhausts, the maintenance personnel are required to contact the Radiation Safety Officer or the Safety Division Health Physics Manager prior to such work. The Radiation Safety Officer will ensure there are no hazards to maintenance personnel from radioactive materials prior to the performance of maintenance.

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7.6.4 Maintenance Personnel Access

Maintenance personnel must not work in areas where radioisotopes or radiation-generating equipment are used without the notification and approval of the AU. The AU or technician must accompany maintenance personnel. Approval of the RSO is also required prior to working on drain lines, sink traps that may contain radioisotopes, or on ventilation ducting from radioisotope fume hoods. Annual radiation safety training is provided to Ancillary Supervisory staff and ancillary staff that may be required to access areas where radioisotopes or ionizing radiation is in use. Outside contractor personnel will be apprised of all risks and be accompanied by radiation safety staff when working in an area in which radiation exposure may occur.

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7.6.5 Declassification

Any room or area approved for radioisotope work must not be reclaimed as a nonradioisotope area until it has been thoroughly surveyed by a Health Physicist and evaluated as safely suitable for release as an unrestricted area by the Radiation Safety Officer. Requests for closeout must be submitted to the Radiation Safety Officer. No equipment/ furniture shall be moved from an active radioisotope lab without contacting the RSO.

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7.7 Radioisotopes Acquisition, Use, & Disposal

7.7.1 Acquisition

7.7.1.1 Purchase Requests

All purchase requests for licensable and nonlicensable radioisotopes must be originated by a AU and must be accompanied by an ARC 343, Application for Radioisotope Procurement (See 7.16.2). The Radiation Safety Officer or QH approves the request after confirming that:

The isotopes are to be used on an authorized project.
The quantity of isotopes does not exceed that approved for the project. A significant increase requires action by the Radiation Safety Committee.

If the AU possess a Blanket Purchase Order (BPO) he/she still must submit a copy of the ARC 343 to the RSO to be placed in the project file.
All radioactive material to be received at Ames Research Center will be addressed to:

Radiation Safety Officer
NASA Ames Research Center
Shipping and Receiving, Building N255
Moffett Field, CA 94035
Attn.: "Insert Authorized User Name Here"

7.7.1.2 Receiving

Incoming radioactive materials shipments will be processed in accordance with 10 CFR 20, 1906 "Procedures for receiving and opening packages" Personnel who have responsibility for receiving incoming radioactive material shipments are required to be familiar with this section of the regulations.
Upon arrival at Ames, receiving personnel will inspect packages for damage, monitor for radiation levels, and place packages in the designated radioactive material refrigerator, freezer, or other secured location in Building N255 depending on the contents of the shipped item.
Notification will be made to the Radiation Safety Officer or designee within 30 minutes of receipt of a radioactive material shipment or immediately if the package is damaged or is reading greater that 1 mrem per hour at three feet from the package. If the package is received after normal working hours, the package will be locked in the designated radioactive material refrigerator, freezer or other secured location, and the Radiation Safety Officer or designee will be notified within 30 minutes of the beginning of the next working day.

7.7.1.3 Radioisotope Inventory Record

Each vial or other container of radioisotopes delivered to an Authorized User must be accompanied by a DQH-24, Radioisotope Inventory Record (See 7.16.9), or equivalent, completed by the Radiation Safety Officer, or designee, listing the contents of the vial and the delivery date. The AU must maintain a record of the radioisotope use and disposal until such information is transferred to the Radiation Safety Office. Any transfer of radioisotopes from the original receiving and approved AU requires Radiation Safety Office approval.

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7.7.2 Custody

The Authorized User is responsible for the custody of any radioactive material acquired and for the proper accountability, storage, labeling, use, and disposal of the material. Radioactive material must always be in the direct control of an authorized user or be under lock and key control. Radioactive material laboratories containing radioactive material or surfaces or equipment contaminated with radioactive material must always be locked or occupied by trained and approved personnel. If the laboratory is unlocked, it is the responsibility of all personnel in the laboratory to ensure only trained and approved personnel are allowed access to the laboratory. The AU must maintain proper records of the status and location of all radioactive material in the AU's possession.

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7.7.3 Storage

All radioisotopes must be stored in appropriately shielded and labeled containers such that the surface dose rate at the outside of the container is less than 25 mrem/hr.

Hydrogen-3 (tritium), Carbon-14, Sulfur-35 in less than 100-mCi quantities may be stored in properly posted storage cabinets or refrigerators in radioisotope approved areas.
Properly labeled residues, intermediates and biological specimens containing Hydrogen-3 (tritium), Carbon-14, Sulfur-35 may be temporarily stored on bench tops pending further processing or disposal.
Any quantity of tritium in excess of 50 mCi or tritiated materials that are volatile or that could conceivably exchange with moisture in the atmosphere must be stored in sealed ampules. The ampules must be properly labeled and stored.
The Radiation Safety Officer has custody of stored materials not otherwise assigned. When a radioisotope project expires, all radioactive materials must be returned to the Radiation Safety Officer for safe storage.
The AU must maintain a sealed source inventory and transfer to the Radiation Safety Office any sources no longer needed. Property records for equipment bearing a NASA decal that may contain sealed sources shall include a statement requiring RSO authorization prior to any surplus or disposal activity. Additional requirements for sealed source use are specified in the radiation safety training for sealed source users.
The Radiation Safety Officer performs periodic reviews of radioactive material in storage and evaluates if disposal is appropriate.

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7.7.4 Waste Disposal

Solid and liquid waste must be placed in appropriate containers provided for each project by the Radiation Safety Officer. A QH-395 Radioactive Waste Checklist form, or equivalent, must be attached to each container to indicate the quantity of radioisotopes in the container.
Upon request, the RSO will have the container removed to the central storage area where it will be held until transferred to the custody of an authorized waste disposal agency.
Radioactive liquid, including washout of contaminated glassware, shall not be transferred to the sanitary sewerage unless the Radiation Safety Officer has given prior approval.
Incineration of radioactive waste is PROHIBITED.
Hazardous non-radioactive wastes are not to be placed in radioactive waste containers. The generation of mixed regulated hazardous and radioactive waste is strongly discouraged. All such generation will be evaluated by the Radiation Safety Committee and Code QE representatives to determine that it is absolutely necessary and that no alternative to the generation exists. Acceptable methods of disposal and recycling will also be evaluated. If a mixed waste is generated as a normal product of the experiment and its generation is approved by the Radiation Safety Committee, special waste containers will be provided. Generators of mixed waste must assume responsibility for the proper disposal of the waste. Unauthorized generation of mixed waste may result of revocation of the AU's approval to use radioactive materials at Ames Research Center, as well as civil actions and penalties to the Center and the AU by regulatory agencies.
Radioactive waste, even normally occurring materials, i.e., uranium as found in the compound uranyl acetate, must be disposed of as radioactive waste. It is not to be discarded in the nonradioactive waste stream.
Waste shall be segregated with respect to form (e.g.; dry, aqueous liquid, scintillation liquid, sharps, or biological) and half-life (e.g., greater than 88 days, less than 88 days). Waste will be packaged as appropriate for its form to prevent spills or hazard to the waste packager or handler
Empty packages that have formally contained radioactive material will be surveyed with an appropriate radioactive material contamination detector to ensure they are free of radioactive material. All radioactive material markings will be removed from the package or defaced completely.
Lead pigs, or shields, that previously contained radioactive materials should be surveyed with an appropriate radioactive material contamination detector to ensure they are free of radioactive material contamination. Attach a copy of the survey to the lead pigs and contact the Radiation Safety Office for pick-up and disposal. Lead is a hazardous material and cannot be disposed of in the normal trash.

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7.7.5 Transfer & Shipment

7.7.5.1 Transfer to the Center

Prior to arranging for radioactive material transfer to Ames, the AU must contact the RSO to assure all requirements have been completed.

7.7.5.2 Transfer within the Center

A "Record of Radioactive Material Transfer or Relocation" Form (See 7.16.3) must be completed and receive Radiation Safety Officer approval prior to transfer or relocation of radioactive material.

7.7.5.3 Shipment from the Center

The Radiation Safety Officer must approve all shipments of radioactive materials from the Center. This requirement applies to all methods of removal, including mailing or hand carrying. Packaging, monitoring, and labeling of radioactive materials must be performed under the direct supervision of the RSO or designee and must comply with State and Federal Regulations. Shipments must be made through NASA Ames' Shipping unless otherwise coordinated with the RSO.

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7.7.6 Animal Use

7.7.6.1 Responsibility

The Authorized User is responsible for the safe use of isotopes in animal experiments, and must instruct the caretakers in correct radiation safety procedures. All information listed in Section 7.5.1, Application Procedure, must also be submitted for animal use radioisotope projects.

7.7.6.2 Caging

The cages for animals containing radioactive materials must be labeled with signs or tape stating "Caution Radioactive Material" and these cages must be kept segregated from other cages. Only personnel properly trained in the procedures for cleaning and release of radioactive material cages may handle these cages. As with all radioactive material, or items contaminated with radioactive material, the cages must be kept in a properly posted and locked room or under the direct control of personnel trained and approved by the Radiation Safety Office.

7.7.6.3 Waste Disposal

The Radiation Safety Officer must approve the method of disposing of radioactive wastes and carcasses before the experiments begin.

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7.8 Record System

7.8.1 Requirements for Records

Under 10 CFR 20 and 30, detailed records of the use and disposition of all radioactive materials must be maintained. These records are subject to NRC inspection at any time.

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7.8.2 Types of Records

The records listed below are maintained in the Radiation Safety Office, kept current, and completely reviewed at least annually, including records of order, receipt, inventory, transfer and disposal of radioactive material. All radioactive materials under Ames control must be included even if the activity represents a nonlicensable quantity. These records are in addition to those kept by each AU. Sample forms are shown in Appendix 7.16.

A separate file for each authorized project containing the application form, work experience form, and project authorization.
An inventory of all licensed radioactive material at Ames Research Center.
Records of leak tests of all sealed sources as required by Federal Regulations.
Reports of quarterly inspections of projects and radiation and contamination surveys of laboratories. These inspections will include a review of the projects survey records which will comply with the following requirements:

Weekly monitoring is required when experiments require using greater than 100 uCi of radioisotope(s) at a time.
Monthly monitoring is satisfactory if experiments require less than 100 uCi of radioisotope(s) to be in use.
Monthly monitoring is required for radioisotopes in storage, i.e. freezers, etc.
Monitoring must be conducted in such a manner that radioisotopes in use can be detected by the monitoring methodology.

Reports of the results of the dosimetry evaluations.
Reports of bioassay results (Appendix 7.16.18).
Results of investigations of those dosimetry results that indicate significant exposure.
Calibration records of all instruments used to monitor radiation levels.
Records of all radioactive material waste shipments.

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7.9 Operational Safety

7.9.1 General Radiation Safety

Only authorized and trained personnel may be permitted to use radioisotopes or radiation generating equipment. Such persons must have read APR 1700-1, Health and Safety Procedural Requirements, and be familiar with Federal Regulations bearing on radiation. They must be familiar with monitoring procedures. They are expected to ask their supervisors or the RSO to explain anything not understood.
The Radiation Safety Officer will determine the requirements for personnel dosimetry monitoring based on the quantity and type radioactive material or radiation being used.
All personnel working with quantities of gamma emitters in excess of 100 mCi or working in areas designated as high radiation areas must wear self-reading pocket dosimeters. Permanent daily records of exposures must be kept in a log in the area and initialed by the wearer.
Operations involving byproduct material shall be conducted in workplaces that shall be designed and equipped to provide maximum practicable protection of the personnel against the hazards of ionizing radiation. Appendix 7.16.17 is used as a guideline in assessing the relative hazards of each workplace.
The Radiation Safety Officer must be notified immediately if an over-exposure to radiation is suspected. The dosimetry of the individual concerned will be processed to assess the dose. The affected individual will be assigned work outside of radioactive material use and radiation areas until the dosimetry results are received and analyzed.

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7.9.2 Laboratory Radiation Safety

Radiation laboratories must be posted with appropriate radiation warning signs.
Each AU of radioactive materials must have on hand, or have ready access to, a calibrated and operable radiation survey instrument appropriate for monitoring the radioisotope in use. Liquid Scintillation Counters may serve in this capacity. Instrument operability must be checked with an appropriate radioactive source prior to each use to ensure proper instrument response. If the survey being performed is for official documentation (i.e., accident investigation, release of equipment), this source must be a NIST traceable source.
All persons must wear laboratory coats and closed-toe shoes or special-issue clothing while working with radioisotopes. Shoe covers or other clothing must be used when required by the RSO. Short pants or dresses with bare legs are only allowable if the laboratory coat protects the bare skin of the leg.
Laboratory coats and other protective clothing worn in radioisotope areas must not be worn outside these areas, e.g., in the cafeteria.
Rubber gloves, respiratory protection, or other protective equipment must be worn when considered necessary by the Radiation Safety Officer.
Eating, drinking, smoking, chewing tobacco, or applying cosmetics is not allowed in radioisotope laboratories. Food for human consumption or drink containers are not allowed in radioisotope laboratories and must never be stored with radioisotopes (i.e., in radioisotope refrigerators).
Pipettes, suction tubes, or other equipment may not be placed in the mouth while in a radioisotope area.
Hands must be washed after handling radioisotopes, prior to leaving radioisotope areas.
The RSO, after consultation with the AU, may require additional monitoring of personnel exiting radioisotope areas.
Locations approved for radioisotope use, where airborne radioactivity may be a possibility, must be equipped with standard radio-chemical fume hoods and laboratory apparatus as specified in section 7.6.3 of this Chapter.
Operations with radioactive solutions must be conducted in a tray or basin of sufficient capacity to hold all solutions if spilled or over absorbent paper that is backed by nonabsorbent material. Heating of a container that holds radioactive material must be done above a pan or tray to catch the material if spilled and must be done in a radio-chemical fume hood, even if the material is considered nonvolatile. If a radioactive solution is to be heated during an experiment, it must be specifically called out in the submitted project procedures and the temperature the solution will be heated to stated.
All personnel using radioisotopes are responsible for the frequent monitoring of their areas and for maintaining them free from radioactive contamination.
Whenever a radioactive spill is suspected, the Radiation Safety Officer or a member of the radiation safety staff must be notified immediately. The Radiation Safety Officer will notify members of the Radiation Safety Committee of significant contamination accidents or loss of control of radioactive material.
Decontamination of any area must be carried out by the AU for the area under the direction of the Radiation Safety Officer or designee.
Equipment, tools, furniture, or instruments employed in a radioisotope laboratory area may not be removed from the area until monitored and, if necessary, decontaminated. The RSO will make the final decision to release items from radiological controls.
Vials or other containers that have been in contact with radioisotopes must not be handled with bare hands whenever contamination of the user's hands or body is possible. Gloves and lab coats must be worn when handling such containers.
Open containers may not be used for transporting radioactive materials outside approved areas (e.g., hallway).
Radiation warning signs must not be removed from a controlled access area or room without the approval of the RSO. Prior to the RSO's approval, the area must be thoroughly surveyed to ensure that no residual radioactive contamination remains.
Additional periodic surveys, supervised by the RSO, must be made in accordance with Section 7.11, Surveillance and Review.

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7.10 Emergency Procedures

7.10.1 Accidents inside Buildings

In emergencies involving radioactive materials of the kind that might be caused by plant operations (fire, explosives, accidental release of materials, etc.) or by external forces (earthquake, storm, etc.), the following general procedures apply:

All personnel must be evacuated immediately from the affected area.
The evaluation and care of the injured personnel must take precedence over assistance to other personnel.
All personnel involved must be confined to one appropriate safe area.
The Radiation Safety Officer or other members of the Radiation Safety Committee and the Director of Safety, Environmental, and Mission Assurance must be notified of the emergency.
A qualified Health Physicist or emergency responder trained by the Radiation Safety Officer must survey the affected area as soon as possible to assess any radiological hazard.
All personnel dosimeters must be removed from exposed personnel immediately after they are removed from the radiation area. Self-reading dosimeters must be read and the readings recorded.
Dosimeters must be sent immediately to the service company for emergency evaluation.
Specific emergency procedures will be developed by the AU and will be included in the project file and posted in the appropriate work area.

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7.10.2 Transportation Accidents

In the event of an accident or emergency that results in the escape of radioactive materials while such materials are being transported outside of a building, personnel authorized to use or transport radionuclides must:

Survey the situation and assess the radiological hazard or otherwise assist the RSO.
Erect barriers as indicated.
Remain at the scene in a safe area as the responsible person(s) until relieved.
Notify a member of the Radiation Safety Committee and the Director of Safety, Environmental, and Mission Assurance as soon as possible.

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7.10.3 Specific Laboratory Radiation Safety Emergency Procedures

7.10.3.1 Spill of radioactive material

Perform "SWIM" actions as trained.

Stop the Spill--Stopping the spill means putting the spill in a safe condition where no additional radioactive material is being spilled. This may mean up-righting a tipped vial, wiping up a spilled drop from a pipette, or covering a large puddle of radioactive liquid from an overflowed experiment or defrosted radioactive refrigerator. If the spill is too much for you to control or would be hazardous to attempt immediate cleanup, back out of the area and secure access. Spills greater that 1uCi of volatile radioisotopes, such as radioiodine in the form of liquid Nal, should be considered very hazardous. Unless these spills are in fume hoods, cover the spill with absorbent material and exit the area.
Warn Others--Alert people immediately when you have a spill. It doesn't have to be dramatic. "I have a spill!" stated in a loud clear voice is fine.
Isolate the Area--Isolate the spill to prevent personnel from spreading contamination and making your spill larger. The spill boundries should be as large as necessary to encompass the radioactive material, but not so large that it impedes cleanup. Sometimes you can simply put a sign on the lab door and close and lock it, other times you may simply isolate a fume hood. It all depends on the size and extent of the spill. Remember to check your boundry with meter surveys and/or wipes for adequacy- especially if you are going to leave the area.
Minimize Exposure to Radiation and Contamination--When cleaning-up a spill, it is important to be aware of your exposure to both the radiation being emitted from the spill and the contamination associated with the spill. Care should be taken to keep it off of you, out of you, and away from you! Wear gloves and lab coats, change gloves frequently, keep your breathing zone away from the spill, and perform the spill actions quickly and efficiently. Be aware of bagged spill materials as well, they become the source of radiation after you clean up the spill.
Notify the Radiation Safety Officer at 4-3979 a) immediately for spills >1 uCi inside posted areas or any spill outside posted areas. b) During normal working hours for small spills that have been decontaminated.

7.10.3.2 Contaminated Personnel Procedures

Perform the following actions in the most appropriate order that does not spread the contamination.

Carefully remove contaminated clothing (this is why it is good to have a clean lab coat or Tyvec suit available in your spill supplies).
If there is radioactive material on the skin, gently wash the area with warm water and soap. Control the water if possible by plugging the drain or by washing over a plastic tub.
Continue gentle washing until no material can be detected with a contamination survey or you can no longer reduce the amount of material by at least one-half. The Radiation Safety Officer or staff member responding will supervise or direct further decontamination methods if necessary upon arrival or consultation.
If there is radioactive material in your eyes, flush eyes for 15 minutes with water as you would with any chemical in your eyes.
Call the Radiation Safety Officer at 4-3979 as soon as it is possible to do so without spreading contamination.
Perform "SWIM" action as appropriate.

7.10.3.3 Injured and Contaminated Personnel Procedures

The actions you take will be based on the degree and severity of your injury. For a small cut, the actions above for contaminated skin may be appropriate with special attention given to cleansing the cut before bandaging. If the injury is serious or life threatening, first aid and medical attention will be the first priority, with contamination control being second. The following actions should be used as a guide:

Get medical treatment for serious and life threatening injuries immediately without regard for radiological considerations. Call 911.
If the injured person is to be taken to the Ames Health Unit, have someone call ahead (4-5827 or 911) and inform them that they will be receiving a "radioactive material contaminated and injured patient" if it is possible to do so. This will allow them to prep a treatment room.
At the scene, remove any contaminated clothing and flush contaminated areas on the injured person if possible.
Call the Radiation Safety Officer at 4-3979.

7.10.3.4 Fire Alarm While Working with Radioactive Material

Remove anti-contamination clothing (gloves, lab coats) and leave at your work area. Calmly evacuate the area per the building emergency action plan (BEAP). This is one reason we post radioactive material use areas, workbenches, and fume hoods. These areas will always be treated as contaminated. You should not hesitate to leave them in an emergency.

7.10.3.5 Earthquake While Working with Radioactive Material

Protect yourself from falling debris. Once the area is safe, follow the appropriate procedures listed above.

7.10.4 Notification Procedures

The Radiation Safety Officer or a member of the Radiation Safety Committee must notify the nearest NRC Operations Office [(301) 816-5100] of any incident as required by 10 CFR 20.2201-20.2203.

The Radiation Safety Officer must notify local civil authorities if a hazard exists for the general public.

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7.11 Surveillance & Review

7.11.1 Radioactive Laboratory Surveys

The Radiation Safety Division staff will perform surveys of all radioactive laboratory areas quarterly. Authorized Users of radioactive material are required to conduct monthly surveys if unsealed radioisotope use is less than 100 uCi per month or if radioisotopes are in storage. Authorized Users of radioactive material are required to conduct weekly surveys if unsealed radioisotope use exceeds 100 uCi per month during the period of radionuclide use. Authorized Users must maintain records of all survey results. Measurements or observations for surveys and audits include:

Radiation exposure levels in and around the work areas. The Radiation Safety staff will normally perform these on the quarterly survey. The AU will not normally be required to take these surveys unless specified by the RSO. The AU should be aware of higher that normal areas of radiation in their laboratories and should shield these areas as appropriate.
Wipe tests for removable contamination on working surfaces, sinks, floors, and storage containers.
Face velocity airflow in all radioisotope hoods.
Availability and functionality of radiation monitoring instruments.
Any violations of posting requirements, access control, or safe laboratory procedures.
Areas found to have removable contamination greater than the limit specified in section 7.4.2 of this Chapter will be classified as a radiation safety hazard requiring decontamination. These areas will be barricaded until thoroughly decontaminated.
Radioisotopes secured from unauthorized removal.

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7.11.2 Sealed Sources

Sealed sources must be inspected and tested for leakage or external contamination under the supervision of the Radiation Safety Officer at six-month intervals or as specified in the NRC license under which they were acquired. If any leak test reveals the presence of 0.005 uCi of contamination or greater, the sources must be removed from use, decontaminated and repaired or disposed. Any leak test results greater then 0.005 uCi must be reported to the nearest NRC Operations Office as per NRC license conditions.

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7.11.3 Annual Program Review

The Radiation Safety Officer will review the radiation safety program at least annually. This review will include:

Records required by the NRC license
Incidents and violations
Dose to the public
ALARA program
Radiation Safety Office controlled areas

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7.12 Medical Control Program

7.12.1 Surveillance

When required, precautionary medical programs for employees working with radioactive materials or equipment will be established under the direction of a competent Medical Consultant and the Radiation Safety Committee. These programs may include such things as blood analyses, bioassay programs, and physical examinations as determined necessary by the Medical Consultant.

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7.12.2 Overexposures

All cases of known or suspected exposures to radiation levels that exceed permissible values must be reviewed immediately by the Medical Consultant. The review may include a medical examination and treatment, if indicated.

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7.13 X-Ray Generating Equipment & Other Radiation Machines

7.13.1 Approval Requirements

The ionizing radiation produced in this equipment is a hazard to Ames personnel and therefore the Center Director has an obligation to ensure the safe use of this equipment. The Executive Safety Committee has chartered the Radiation Safety Committee to approve and oversee all uses of ionizing radiation on the Center. Each prospective operator must submit a QH-23, Radiation Machine Operation Request (See 7.16.8), to the Committee for approval and must successfully complete the radiation safety training for x-ray machine use as described in section 7.3.4 NASA Ames Training in this Chapter.

7.13.1.1 Human Use

Diagnostic and therapeutic human radiation exposure must be approved by the Radiation Safety Committee and the Human Research Institutional Review Board

7.13.1.2 Nonhuman Use

Any person using X-ray machines for animal work or physical experiments must demonstrate to the Radiation Safety Committee a working knowledge of the unit intended to be used and cognizance of the hazards associated with it. The user must have approved written operating procedures.

7.13.1.3 Records

A file must be maintained in the Radiation Safety Office for each Approved X-Ray Operator. It must indicate whether the user is authorized to expose humans to radiation and which machines the user is qualified to use. Before an X-ray unit can be operated it must be surveyed by the Radiation Safety Officer or delegate. If any concerns are noted they must be addressed and approved by the Committee before operation can be initiated.

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7.13.2 Veterinary Medicine Radiographic Installations

7.13.2.1 Equipment

The tube housing shall be of diagnostic type.
Diaphragms or cones shall be provided for collimating the useful beam to the area of clinical interest and shall provide the same degree of protection as is required of the housing.
The total filtration permanently in the useful beam shall not be less than 1.5 mm aluminum-equivalent for equipment operating up to 70 kVp and 2.0 mm aluminum-equivalent for machines operated in excess of 70 kVp.
A device shall be provided to terminate the exposure after a preset time or exposure.
A dead-man type of exposure switch shall be provided, together with an electrical cord of sufficient length so that the operator can stand out of the useful beam and at least six feet from the animal during all X-ray exposures.

7.13.2.2 Structural Shielding

All wall, ceiling, and floor areas shall be equivalent to or provided with applicable protective barriers as required in NCRP Report No. 147 "Structural Shielding Design for Medical X-ray Imaging Facilities" (2004).

7.13.2.3 Operating Procedures

The operator shall stand well away from the tube housing and the animal during radiographic exposures. The operator shall not stand in the useful beam. If film must be held, it shall be held by individuals not normally occupationally exposed to radiation. Hand-held fluoroscopic screens shall not be used. The tube housing shall not be held by the operator. No individuals other than the operator shall be in the X-ray room while exposures are being made unless such person's assistance is required. No personnel will be allowed to be exposed to radiation in this capacity unless trained in the risks of radiation exposure and are made knowledgeable on the radiation they are likely to receive. The use of assistants not normally exposed occupationally to radiation will be only allowed with the approval of the Radiation Safety Committee.
In any application in which the operator is not located behind a protective barrier, clothing consisting of a protective apron having a lead-equivalent of not less than 0.25 mm shall be worn by the operator and any other individuals in the room during exposures.
No individual shall be regularly employed to hold or support animals during radiation exposures. Operating personnel shall not perform this service except very infrequently and then only in cases in which no other method is available (see above). Any individual holding or supporting an animal during radiation exposure shall wear protective gloves and an apron having a lead equivalent of not less than 0.25 mm.

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7.13.3 Radiation Machines Capable of Producing High Radiation Area

7.13.3.1 Special Requirements

The following special requirements are applicable for high radiation areas:

Each entrance or access point to a high radiation area shall be:

Equipped with a control device that shall cause the level of radiation to be reduced below that at which an individual might receive a dose of 100 mrem/hr upon entry into the area; or
Equipped with a control device that shall energize a conspicuous visible or audible alarm signal in such manner that the individual entering the high radiation area and the licensee or a supervisor of the activity are made aware of the entry; or
Kept locked, except during periods when access to the area is required with positive control over each individual entry.

The controls required of this subsection shall be established in such a way that no individual will be prevented from leaving a high radiation area.
In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted for the controls required by 7.13.3.1.1.
Any AU may apply to the Radiation Safety Committee for approval of methods not included in the above subsection for controlling access to high radiation areas. The Radiation Safety Committee will approve the proposed alternatives if the AU demonstrates that the alternative methods of control will prevent unauthorized entry into a high radiation area, and that the requirement 7.13.3.1.2 is met.

7.13.3.2 Dose Rates in Excess of 100 mRem/hr

Each radiation machine that is capable of producing, in any area accessible to individuals, a dose rate in excess of 100 mrem/hr shall be provided with a conspicuous visible or audible alarm signal such that any individual at or approaching the tube head or radiation port is made aware that the machine is producing radiation. The alarm signal shall be activated automatically only when radiation is being produced.

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7.14 Use of Offsite Contractor for Field Radiography Testing

7.14.1 Applicability

This applies to any use of an outside contractor that performs work using X-ray or radioactive materials at NASA Ames including but not limited to:

Industrial Radiography
Portable Nuclear Gauges (i.e. Troxlers)
X-ray fluorescence guns (both x-ray and gamma-ray types)
Nuclear well logging devices
Any device other than those specifically called out above that contains radioactive materials.

7.14.2 Requirements

Prior to permitting the contactor access to NASA Ames, the NASA Ames Project Manager shall ensure that the following documentation is submitted to the radiation safety office for approval.

Copy of the companies' agreement state and/or federal radioactive materials license
If above license is a license issued by the state of California or any other agreement state, the company MUST submit a copy of an NRC reciprocity agreement (NRC Form 241). The company needs to have applied for reciprocity with the NRC in order to legally perform work on federal property.
Copy of company radiation safety manual
Copies of any NRC required certifications to perform work with radioactive material

If approved, the NASA Ames Project manager shall ensure that all radiation testing is carried out in compliance with NRC and NASA Ames regulations

7.14.3 Additional Requirements for Industrial Radiography

The Radiation Safety Office shall be notified in writing, using a Notification of Radiography (see 7.16.11) or equivalent of the field radiography operation two workdays in advance for a one-day job.
For any operation requiring more than one day of work, a three-workday written notification (Notification of Radiography or equivalent) is required.

(Exceptions to the notification requirements described in 1 and 2 may be waived by the RSO if all other conditions have been met.)
Radiographers shall have a current safety manual and radioactive material license on file with the Ames Radiation Safety Officer along with a NRC reciprocity agreement to work on a Federal site if they do not possess a NRC license. Radiographers must maintain a copy of such documentation at the job site pursuant to 10 CFR 30.52(b).
Division Managers, Branch Chiefs, COTRs, contractors, and other managers of any affected facility must be notified to assure that any disruptions to their operations are understood. Coordination by the NASA Ames Project Manager shall also include notification of the Security and Fire personnel as well as any other contractor operations if impacted.
The NASA Ames Project Manager must ensure that entrances to affected facilities are posted at each entry/exit in advance of the radiography with a "Notice of Radiation Testing" (See 7.16.12) providing dates, times, and description of the areas that will be affected.
Upon fulfillment of the above requirement, the radiographer will be granted approval to perform services at Ames under the following conditions:

The radiographer and an assistant must be present at all times during
the operation.
All work will be performed under the conditions set forth in the Notification of Radiography, or equivalent.
For each day of radiography a Daily Radiographic Checklist (see Appendix 7.16.13) or equivalent must be completed. The checklist shall be returned to the Safety Division.

A Safety Division representative shall conduct safety audits of the radiography installation and monitoring procedures prior to the start of work. The radiographer(s) assume full responsibility in controlling personnel access to and from radiation exposures in restricted radiographic areas.
At any time during the operation, a representative of the Safety, Health and Medical Services Division shall have the authority to stop any operation if it is felt that the safety of the radiographer(s) or any ancillary people is in jeopardy.

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7.15 Personnel Under 18 Years of Age

No personnel under the age of 18 shall be authorized to handle radioactive material or equipment. Should an AU decide to allow access to the laboratory to such individuals, the following written assurance must be provided the RSO.

Statement testifying that the individual will not directly handle radioactive materials.
Statement that the individual has received a detailed safety briefing on specific areas of radiological concern within the laboratory.
Statement that the AU acknowledges the individual will be under direct supervision while in areas of radioisotope usage.
Statement of parental/guardian consent must be obtained for individuals under 18 years of age.

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7.16 Appendices

Note: The forms in the following appendices are for information purposes only. Please contact the Radiation Safety Officer for the official QH forms by calling Ames-Moffett Extension 4-3573, Safety, Health, and Medical Services, Radiation Safety Division. by calling Ames-Moffett Extension 4-3573, Safety, Health, and Medical Services, Radiation Safety Division.

Appendix A: Notice to Employees (NRC Form 3)

Obtain blanks of ARC forms from http://server-mpo.arc.nasa.gov/Services/AEFS/AEFSHome.tml.

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7.16.1 Appendix A: Notice to Employees

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7.16.2 Appendix B: Application for Radioisotope Procurement (ARC 343)

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7.16.3 Appendix C: Record of Radioactive Material Transfer or Relocation

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7.16.4 Appendix D: Receipt Of Radiation Regulations

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7.16.5 Appendix E: Radiation Project Approval Request

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7.16.6 Appendix F: Radiation Experience Record

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7.16.7 Appendix G: Radiation Project Authorization

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7.16.8 Appendix H: Radiation Machine Operation Request

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7.16.9 Appendix I: Radioisotope Inventory Record

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7.16.10 Appendix J: Radiation Work Permit

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7.16.11 Appendix K: Notification of Radiography

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7.16.12 Appendix L: Notice of Radiation Testing

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7.16.13 Appendix M: Daily Radiographic Check List

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7.16.14 Appendix N: Caution Sign

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7.16.15 Appendix O: Save for Future Use

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7.16.16 Appendix P: Emergency Procedure

In the event of an uncontained spill of radioactive material greater than 1.0 uCi:

All persons will leave the room immediately and wait in a restricted area until they can be surveyed for release from the area.
Prior to cleaning a spill, notify the Radiation Safety Officer (RSO) or Radiation Safety Staff (RSS), day or night, at the following numbers:

If the room is to be left unattended, make certain that the door is locked and the room is posted "NO ENTRY."
No personnel will be allowed into the spill area without proper personal protective equipment (PPE).
PPE will consist of a lab coat, double gloves, disposable shoe covers, and a respirator (unless deemed unnecessary by the RSO.
Unless otherwise directed by the Radiation Safety Office, the spill will be cleaned up using paper towels or other absorbent materials. Lab coat, gloves, shoe covers, respirator and absorbent materials will be surveyed prior to disposal and if contaminated, disposed of as radioactive waste.
RSO and/or RSS will survey spill area and involved personnel to verify decontamination progress.
Personnel involved in the spill may be required to submit a urine specimen, if there is any concern of internal contamination (the specimen is for radiological testing and not for drug screening).

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7.16.17 Appendix Q: Workplace For Radionuclides

Operations involving radioactive material shall be designated, equipped and conducted to provide the maximum practicable protection of personnel against the hazards of ionizing radiation.

1. Requirements and Classification

The requirements and classification of workplaces is based on the relative hazard of the manipulations and on the quantity and relative radiotoxicity of the radionuclides involved. The relative hazard of an operation is determined by an evaluation of the following facts:

The method by which the material may enter the body.
The solubility of the materials.
The portion of the body that may be affected because of the chemical properties of the material.
The nature of the operation to be performed.
The quantity of the material that will be used.

2. Guide for Classifying Workplaces

3. Relative Toxicity Factor

4. Use Factor

5. Examples

It is desired to store 14 uCi of 90Sr,

From the factor tables:
T = 100
U = 0.01
Then H = QTU
= (14)(100)(0.01)
= 14

This value indicates the need for a Type I workplace.

1.4 grams of natural uranium will be dry mixed into pigment,

1.4 gm NatU = 0.95 uCi
T = 10
U = 100
Then H = QTU
= (0.95)(10)(100)
= 950

This value indicates the need for a Type II workplace.

A solution containing 1 mCi of 239U will be filtered,

T = 100
U = 1
Then H = QTU
= (1000)(100)(1)
= 100,000

This value indicates the need for a Type III workplace.

6. Classification of Workplaces

The classification of workplaces below serves to select areas and equipment suitable for safe operations with the radioactive material to be used. TYPE I WORKPLACES - Used only for low-hazard operations. The minimum requirements for such workplaces are:

The atmosphere in the workplace shall be maintained at negative pressure with respect to other parts of the building.
Work surfaces shall be smooth and impermeable.
Personnel shall wear aprons or laboratory coats.
Sources of radiation shall be stored in metal cabinets.
A monitoring program shall be maintained to detect any contaminated surfaces. The minimum monitoring frequency shall be once per month when isotopes are in use.
Personnel shall be surveyed for contamination in the event of an accident.

TYPE II WORKPLACES - Used for operations of moderate or low hazards. The minimum requirements for such workplaces are:

Operations shall be carried out in hoods with a minimum face velocity of 100 linear feet per minute and an approximate average velocity of 125 linear feet per minute. At any point in the plane of the opening, the face should not vary more than 20 percent.
The walls shall be smooth and the floors shall be protected with impermeable coverings.
The coverings of work surfaces shall be smooth, impermeable, and adapted to the type of operation.
Personnel shall wear laboratory coats and waterproof gloves.
Sources of radiation shall be stored in a hood or in a glove box.
A monitoring program shall be maintained to detect external radiation and surface contamination. Measurements shall be taken at least weekly while isotopes are being used.
A monitoring program shall be maintained to detect atmospheric contamination. Measurements shall be taken at least weekly while isotopes are being used.
Contamination of hands shall be checked at appropriate times during operations.
Contamination of clothing shall be checked after accidents and at any other frequency set by the Radiation Safety Officer.
Special receptacles shall be provided for separate collection of solid and liquid residues generated in the workplace.

TYPE III WORKPLACES - Used for operations classed as high hazard. These workplaces must be isolated from other working areas. The minimum requirements for such workplaces are:

Operations shall be carried out in glove boxes equipped with negative pressure ventilation and high efficiency filters. Other protective devices shall be included commensurate with the degree of hazard associated with the operations; namely, shielding, remote handling devices, air locks, bag-out ports, etc.
The walls, ceilings, and floor shall be provided with impermeable coverings.
The coverings of work surfaces shall be smooth, impermeable and adapted to the type of operation.
The atmosphere in workrooms shall be maintained at negative pressure with respect to other parts of the building.
Room exhaust shall be filtered through high-efficiency filters.
Access to the workplace shall be limited to those persons actually needed to perform the operations.
Personnel shall wear waterproof gloves when working in a glove box.
Sources of radiation shall be stored in glove boxes, source pits, water pools, or other devices commensurate with the degree of hazard and the nature of the material.
Atmospheric contamination measurements, external radiation surveys, and surface contamination measurements shall be taken daily while the isotopes are being used.
Hands and clothing shall be checked for contamination at appropriate stages during operations.
Special receptacles shall be provided for separate collection of solid and liquid residues generated during operations.
Respiratory protection equipment and head coverings shall be immediately available to personnel in case of emergency, but shall not be relied upon for ordinary operations.

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7.16.18 Appendix R: Bioassay Program

The following procedures are required by the NRC and are referenced in 10 CFR 20.1204, Determination of Internal Exposure. All annual limits of intake (ALI) are calculated from the Appendix B to 20.1001-20.2401 of 10 CFR 20.

The ALARA principle requires that individual's handling radionuclides be monitored in order to determine the effective dose equivalent from internal radiation exposures. ALIs are the annual intakes of a given radionuclide that would result in either (1) a committed effective dose of 5 Rem (stochastic ALI) or (2) a committed dose equivalent of 50 Rem to an organ or tissue (non-stochastic ALI).

All radionuclides are of concern, but certain action levels must be reached before mandatory bioassay monitoring is initiated. The applicable levels of monitoring are dependent upon the possibility of oral ingestion or inhalation of radionuclides during the occupationally work situation. The program is not applicable to those situations where an individual has received diagnostic or therapeutic radionuclides.

The following are the ALIs for some of the radionuclides used at this facility. These are the maximum allowable uptakes. Bioassays will be required when an individual is suspected of having ingested or inhaled quantities or radionuclides that may exceed specific action levels.

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7.16.19 Appendix S: Bioassay Action Levels

Bioassays shall be performed within 24 hours (of primary use) for persons handling tritium in an unsealed form if the quantity handled any one time or cumulatively over a month's period is 100 mCi or more as a precursor of deoxyribose nucleic acid, HTO, or in other forms of tritiated compounds. (U.S. Nuclear Regulatory Commission, Regulatory Guide 8.32, Criteria for Establishing a Tritium Bioassay Program, July, 1988.)
Hydrogen-3 shall not be used in such a manner that the whole body uptake exceeds 6.3 mCi in any calendar quarter.
Bioassays shall be performed within one week (of primary use) for persons handling at any one time or cumulatively over a month's period quantities of 100 mCi or more of Carbon-14, Phosphorous-32, Phosphorous-33, or Sulfur-35 in unsealed form.
Phosphorous-32 shall not be used in such a manner that the bone uptake exceeds 1.5 uCi in a calendar quarter.
Bioassays shall be performed within 72 hours (of primary use) for persons handling radioiodine if at any one time or cumulatively over a month's period quantities of:

10 mCi or more in a volatile form, or
100 mCi or more in a form that is chemically bound and processed in such a manner that the radioiodine remains in a nonvolatile form is used.

Iodine-125 and/or 131 shall not be used in such a manner that the thyroid uptake exceeds 1.0 uCi in a calendar quarter. (Nuclear Regulatory Commission, Regulatory Guide 8.20, Applications of Bioassay for I-125 and I-131, Revision 1, September 1979.)

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Chapter 7 - Ames Radiation Safety Guide

Table of Contents

7.1 Policy

7.2 Radiation Safety Organization

7.3 The NRC Licenses

7.4 ALARA Policy

7.5 Project Authorization

7.6 Radiation & Radioactive Materials Area

7.7 Radioisotopes Acquisition, Use, & Disposal

7.8 Record System

7.9 Operational Safety

7.10 Emergency Procedures

7.11 Surveillance & Review

7.12 Medical Control Program

7.13 X-Ray Generating Equipment & Other Radiation Machines

7.14 Use of Offsite Contractor for Field Ratiation Testing 7.15 Personnel Under 18 Years of Age 7.16 Appendices

7.1 Policy

7.1.1 Overview

7.1.2 Director's Policy

7.1.3 Federal Regulations

7.1.4 Distribution

7.2 Radiation Safety Organization

7.2.1 Center Director and the Executive Safety Committee

7.2.2 Ionizing Radiation Safety Committee

7.2.3 Safety, Health and Medical Services Division

7.2.4 Division & Branch Chiefs

7.2.5 Authorized Users

7.2.6 Radiation Safety Contractor

7.3 The NRC Licenses

7.3.1 Specific Licenses

7.3.2 Limits & Conditions

7.3.3 Instruction to Workers (Notice to Employees)

7.3.4 NASA Ames Training

7.3.5 Compliance Inspections

7.4 ALARA Policy

7.4.1 Management Statement

7.4.2 Contamination Limits

7.4.3 Dose Guidelines

7.5 Project Authorization

7.5.1 Application Procedure

7.5.2 Radiation Safety Officer's Review

7.5.3 Radiation Safety Committee's Review

7.5.4 Project Authorization Form

7.5.5 Authorized User

7.5.6 Project Changes and Renewals

7.6 Radiation & Radioactive Materials Area

7.6.1 Radiation Safety Officer's Review

7.6.2 Warning Signs

7.6.3 Fume Hoods

7.6.4 Maintenance Personnel Access

7.6.5 Declassification

7.7 Radioisotopes Acquisition, Use, & Disposal

7.7.1 Acquisition

7.7.2 Custody

7.7.3 Storage

7.7.4 Waste Disposal

7.7.5 Transfer & Shipment

7.7.6 Animal Use

7.8 Record System

7.8.1 Requirements for Records

7.8.2 Types of Records

7.9 Operational Safety

7.9.1 General Radiation Safety

7.9.2 Laboratory Radiation Safety

7.10 Emergency Procedures

7.10.1 Accidents inside Buildings

7.10.2 Transportation Accidents

7.10.3 Specific Laboratory Radiation Safety Emergency Procedures

7.10.4 Notification Procedures

7.11 Surveillance & Review

7.11.1 Radioactive Laboratory Surveys

7.11.2 Sealed Sources

7.11.3 Annual Program Review

7.12 Medical Control Program

7.12.1 Surveillance

7.12.2 Overexposures

7.13 X-Ray Generating Equipment & Other Radiation Machines

7.13.1 Approval Requirements

7.13.2 Veterinary Medicine Radiographic Installations

7.13.3 Radiation Machines Capable of Producing High Radiation Area

7.14 Use of Offsite Contractor for Field Ratiation Testing
7.15 Personnel Under 18 Years of Age
7.16 Appendices