regulation of radioisotopes module 1

Room postings provide specific information to the individual entering the area. What is the possible range of exposure potential for an individual working in a room posted as "Caution Radiation Area"?

mR/hr5 mR/hr to 100 at 30 cm

An agreement state is a state which:

asserts its willingness to regulate the use of radiation and radioactive material within its boundaries.

Can radioactive material be used in a room without the room being posted with a "Caution Radioactive Material" sign on the door?

yes

The rules and regulations established within an agreement state an be less restrictive than the regulations found in the Code of Federal Regulations.

false

patient room

for pts receiving a therapeutic dose, they must be quarantined in a private room with private restroom, room posted with dose info, material, and emergency contact info, visitors limited, room surveyed with removable contamination < 200 dpm/ 100 cm2 before release of room for use

Caution Radioactive Material

each area or room in which there is used or stored radioactive material >10 times the material in Appendix C of 10 CFR part 20

Caution Radiation Area

An accessible area with radiation levels 5 to 100 mR/ hr at 30 cm from the radioactive source

High radiation area

dose rate is greater than 100 mR/hr 30 cm from radioactive material

Title 10 CFR 19.12 "Instruction to Workers" requires training to be provided to individuals who in the course of employment are likely to receive in a year an occupational dose in excess of 100 mrem.

true

What is the title of Appendix M in NUREG-1556 Vol. 9, Rev 3?

Model Procedures for an Occupation Dose Program

Notices to radiation workers and instructions to workers fall under which part of 10 CFR?

part 19

The US Nuclear Regulatory Commission has jurisdiction over all byproducts of fission.

true

Bq

becquerel

TEDE

total effective dose equivalent

RSO

radiation safety officer

NRC

nuclear regulatory commission

NVLAP

national voluntary laboratory accreditation program

PET

positron emmission tomography

RG

regulatory guide

RSC

radiation safety committee

DOT

department of transportation

TLD

thermoluminescent dosimeter

code of federal regulations

official legal print publication containing the codification of the general permanent rules published in the Federal Register by the departments and agencies of the Federal Government, divided into 50 titles then into chapters

10 CRF 19

establishes requirements for notices, instructions, and reports by licensees and regulated entities to individuals participating in NRC licensed and regulated activites and options available to these individuals in connection with Commission inspections

19.11- posting of notices to workers

outlines specific documents which must be posted: NRC license, operating procedures applicable to the license, notices of violations and response by licensee, NRC Form 3 Notice to employees

19.12- Instructions to workers

outlines the site specific instructions to workers, including info on storage, transfer, or use of radiation and/ or radioactive material, health protection problems associated w/ exposure, precautions or procedures to min. exposures, improving protection of personnel, worker responsibility to report violations

19.13- Notification and Reports to Individuals

outlines radiation monitoring of radiation workers, dosimetry reports, exposure limits for radiation workers

19.15- Consultation with workers during inspections

inspectors may request private discussions w/ workerss, as well as individuals requesting private discussions with inspectors

19.16- Requests by workers for inspections

if a worker believes a licensee is in violation, the worker may request an inspection from the NRC

19.32- discrimination prohibited

no persons shall on the grounds of sex, be excluded from participation, license, or subjected to discrimination under the NRC programs or activities

10 CFR 20

standards for protection against radiation

20 Subpart A

general provisions: establishes standards of protection against ionizing radiation resulting from activities conducted under NRC licenses, control receipt, possession, use, transfer, and disposal of licensed material by licensee in a manner that the total dose to an indv. dose not exceed stds for protection

20 Subpart B

radiation protection programs requirements: to develop, document, and implement a radiation safety program appropriate to the licensed activities

20 Subpart C

occupational dose limits: outlines the annual exposure limits for radiation workers, compliance of the requirements, dose determination of internal and external exposures, dose equivalents to a fetus

20 Subpart D

radiation dose limits for indv members of the public

20 Subpart F

surveys and monitoring personnel such as dosimetry reqs

20 Subpart H

respiratory protection and controls to restrict internal exposure in restricted area: requires licensee to provide adequate resp. protection by use of containment, decontamination/ ventilation

20 Subpart K

waste disposal: methods and reqs including decay in storage, transfer, sewage release, burning reqs

20 Subpart M

records required: reports include theft, loss of material, excess exposure, notification of incidents, spills

20 Subpart L

reports recording: radiation safety programs, survey records, waste records

Appendix B to Part 20

ALIs and derived exposure, effluent concentrations, concentrations for release to sewerage, includes calculations and tables to evaluate limits for intake, exposure, sewage

Appendix C to Part 20

Quantities of licensed material requiring labeling table with radionuclide and the limit for each for labeling purposes

10 CFR 35

medical use of byproduct material

35 Subpart A

general info: reqs and provisions for use of byproduct material and issuance of specific license authorizing the medical use of this material

35 Subpart B

general admin reqs: rad safety program-authority, responsibilities, & changes, written directives, training reqs for RSO and AUs

35 Subpart C

general technical reqs

35 Subpart D

unsealed byproduct material-written directive NOT required: use of unsealed byproduct material for uptake dilution and excretion, imaging and localization, training reqs

35 Subpart E

unsealed byproduct material written directive required: safety instruction and precautions, training for use of byproduct material requiring a WD, training for oral admin or I-131 in all conc, parental instructions for byproduct material req a WD

35 Subpart G

sealed sources for diagnosis: use and training for sealed sources used for diagnosis

35 Subpart L

records recordkeeping: radiation safety protection programs, authority and changes, WD, procedures for admin or materials req WDs, instrument calibration, leak tests, exposure survey records

35 Subpart M

medical event report and notification of dose to fetus/ embryo or nursing child

NUREF-1556, Vol 9, Revision 3

contains info to provide program specific guidance and assist applicants and licensees in preparing applications for materials, licenses for the medical use or byproduct material. Describes the info needed to complete NRC forms. Describes acceptable methods to implement NRC regulations and techniques

What does NUREF-1556 mean and how does it apply ti NucMed techs?

outlines the requirements and offers instructions for form completion to amend the license when necessary due to new and constantly emerging therapies and procedures, and new authorized users

specific license of limited scope

issued to applicants subject to limitations: radionuclide specified chemical and physical forms, possession limits, proposed use, RSO, authorized user, locations of use

broad scope specific licenses

authorize the possession and use of a wide variety of byproduct material, under control of an in-house RSC, mainly large institutions providing pt care and conducting research using radionuclides fro in vitro, animal, and medical procedures

master material license

multi-site, multi-regional, material license issued to a Federal organization with a centralized radiation control program with regulatory oversight responsibilities for a variety of material programs, uses an in-house RSC, NRC provides independent inspections, ie; all VA hospitals

mCi-MBq

1 mCi = 37 MBq

rem-mrem-mSv

0.001 rem = 1 mrem = 0.01 mSv

absorbed dose

the energy imparted by ionizing radiation per unit mass of irradiated material, units= rad, gray (Gy)

activity

rate of disintegration or decay of radioactive material, units= Ci, Bq

address of use

the building(s) identified on the license and where byproduct material may be received, prepared, used, or stored

airborne radioactive material

RA material dispersed in the air in form fo dust, fumes, particulates, mist, vapor, or gases

airborne radioactivity area

room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of licensed material exist in concentrations

annual limit on intake (ALI)

the derived limit for the amt of RA material taken into the body of an adult worker by inhalation or ingestion in a year

area of use

portion of address of use that has been set aside for the purpose of receiving, preparing, using, or storing byproduct material

bioassay

determination of kinds, quantities, or concentrations, and in some cases, the locations of radioactive material in the human body, whether by direct measurement or analysis and evaluation of materials excreted or removed from it

byproduct material

any RA material yielded in, or made radioactive by, exposure to the radiation incident to the process of producing or using special nuclear material

committed dose equivalent

the dose equivalent to organs or tissues of reference that will be received from an intake of RA material by an indv. during the 50 yr period following intake

committed effective dose equivalent

sum of the products of the weighting factors applicable to each other body organs or tissues that are irradiated and the committed dose equiv to these organs or tissues

constraint

a value which specifies licensee actions are required

controlled area

an area outside of a restricted area but inside the boundary, access to which can be limited by licensee for any reason

deep-dose equivalent

applies to external whole body exposure, DE at a tissue depth of 1 cm

derived air concentration (DAC)

concentration od a given radionuclide in air which is breathed by the reference for 2,000 hours under conditions of light work, results in an intake of ! ALI

discrete source

radionuclide that has been processed to its conc within a material has been purposely increased for the use of commercial, medical or research activities

dose equivalent

means the product fo the abosorbed dose in tissue quality factor, and all other necessary modifying factors at the location of interest units= rem, Sv

effective dose equivalent

sum of the products of the dose equivalent to the organ or tissue and the weighing factors applicable to each of the body organs or tissues that are irradiated

lens dose equivalent

applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 cm

occupational dose

the dose received by an indv in the course of employment in which their assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation

qualifying factor Q

the modifying factor that is used to derive dose equivalent from absorbed dose

radiation area

an accessible area in which rad levels could result in an indv receiving a dose in excess of 0.005 rem (0.05mSv) in 1 hour at 30 cm from the source

restricted area

access to which is limited by the licensee for purposes of protecting indvs against undue risks from exposure to rad and RA materials

shallow-dose equivalent

applies to the external exposure of skin of the whole body or the skin of an extremity, taken as the dose equivalent at a tissue depth of 0.007 cm

therapeutic dosage

dosage of unsealed byproduct material that is intended to deliver a radiation dose to a patient or human research subject for palliative or curative treatment

therapeutic dose

radiation dose delivered from a source containing byproduct material to a pt or human research subj for palliative or curative treatment

unit dosage

dosage prepared for medical use for admin as a single dosage to a pt or human research subj w/o any further manipulation the dosage after it is initially prepared

very high radiation area

an area accessible to indv which radiation lvls from radiation sources external to the body could result in an indv receiving an absorbed dose in excess of 500 rads (5 Gy) in 1 hour at 1 meter from a radiation source or from any surface that it penetrates

weighing factor

for an organ or tissue is the proportion of the risk of stochastic effects resulting from irradiation of that organ or tissue to the total risk of stochiastic effects when he whole body is irradiated uniformly