Section 5: Radiation Exposure Monitoring and Personnel Protection

Contents

5.1 General

The intent of the personnel radiation monitoring and protection program is to assure that sufficient precautions are taken to protect all individuals from unreasonable radiation exposure. Limiting the amount of time, increasing the distance between an individual and the radiation source and employing shielding are all recommended to minimize potential radiation exposures.  All procedures involving the use of ionizing radiation must be carried out in such a manner to maintain exposures as low as reasonably achievable.

This Section of the Handbook provides details of the University’s radiation monitoring program, limits for occupational exposures and exposures to members of the public, details regarding occupational exposure records and histories, and information about radiation-related respiratory protection.

5.2 Occupational Dose

An occupational dose of ionizing radiation is a dose received by an individual in the course of employment in which the individual’s assigned duties involve exposure to sources of radiation.  Individuals who receive or have the potential to receive an occupational dose are considered occupationally exposed and are subject to the occupational dose limits prescribed in 10 NYCRR Part 16.6 (Section 5.5 of this Handbook).  Doses received from background radiation, medical examinations and practices, voluntary participation in medical research programs, or as member of the public are not considered occupational doses.

(i) Occupational Radiation Exposure Monitoring

An individual at Syracuse University will be monitored for occupational exposure if:

  • there is a potential for the individual to receive, in one year, a dose from external radiation sources in excess of 10% of the occupational dose limits established by NYSDOH in 10 NYCRR Part 16.6(a);
  • there is a potential for the individual to receive, in one year, an intake in excess of 10% of the applicable Annual Limit on Intake (ALI) listed in 10 NYCRR Part 16, Appendix 16-c, Table 1, Columns 1 and 2;
  • the individual is a declared pregnant woman who is likely receive a dose from external sources in excess of 10% of the limits for external exposure established in 10 NYCRR 16.6(h) or a committed effective dose equivalent, in one year, in excess of 0.05rem; or
  • deemed necessary by the RSO or RSC

(ii) Prospective Evaluation

The Prospective Evaluation of occupational exposures is the basis for determining an individual’s personal occupational exposure monitoring needs.  Potential occupational exposures may be evaluated according to: 1) the process contributing to the potential exposure; 2) categories of workers exposed to similar radiological conditions (i.e. job classifications); and/or 3)specific conditions. This evaluation will consist of any or all of the following:

  • review of historical exposures (for an individual and/or laboratory groups)
  • air sampling analysis results
  • environmental/area monitoring results
  • process review

A prospective evaluation of occupational exposures will be performed by Radiation Safety staff and review by the RSO, prior to January 1st for each calendar year.  If an individual’s radiation exposure conditions change during the course of the year, his/her need for monitoring will be re-evaluated.  Records of prospective reviews will be maintained by EHSS.

5.3 External Radiation Monitoring

External radiation doses result from exposure to sources of ionizing radiation, outside the body.  Gamma rays, x-rays, high energy beta particles and neutrons are considered “penetrating radiation” and present an external exposure hazard. Conversely, low energy beta particles and alpha particles are relatively “non-penetrating” and present less of an external radiation exposure hazard.

External radiation exposure can be limited by the use of “Time, Distance and Shielding” concepts.  The following steps are recommended to  limit the amount of external exposure received:

  • Limit the time spent in the vicinity of the radiation source.

Exposure = Exposure Rate X Time

  • Maximize the distance between the individual and the radiation source. The intensity of radiation is inversely proportional  to the square of the distance (i.e. increase the distance by 2, decrease the intensity by 4).
  • Use shielding to reduce the amount of radiation reaching the individual. The type of shielding used depends on the type of radiation (i.e. lead for gamma, plexiglass for beta).

(i) Methods of Monitoring External  Radiation Exposure

The film badge is the most common type of external radiation monitor used at the University.  Film badges are generally used to monitor whole body deep and shallow exposures and  are  sensitive to penetrating radiation (gamma rays, x-rays and medium to high energy beta particles). Thermoluminescent dosimeters (TLDs) are used at Syracuse University to monitor extremity exposures.  TLDs are also  sensitive to penetrating radiation.  The detectable energy range of the film badges and TLDs currently used at the University is approximately 15 KeV to 3 MeV for x-rays and gamma rays and 250 KeV to 1.5 Mev for beta particles.

Other methods of monitoring (i.e. neutron dosimetry) may also be used at the University as necessary.

(ii) External Radiation Monitoring of Personnel

Syracuse University will monitor individuals for external occupational exposure if they are likely to receive a dose in excess of 10% of  the occupational exposure limits established in 10 NYCRR Part 16.6(a) or 10% of the exposure limits established for declared pregnant woman in 10 NYCRR Part 16.6(h).  The prospective review performed by the RSO will be used to determine  individuals who require external radiation monitoring.  In addition, some individuals who, based on the prospective review, do not require occupational monitoring according to regulations may also be issued a radiation exposure monitor at the discretion of the RSO.

Personal radiation monitors will be assigned to individuals upon completion of Stage One of the radiation worker training program. The dosimeters used at the University are provided and processed by an accredited, NVLAP approved, dosimetry service. They are exchanged on a regular basis (i.e. monthly, quarterly) and sent to the dosimetry service for processing.

Assigned whole body monitors must be worn whenever controlled areas are frequented, at the location of the body most likely to receive the highest exposure (i.e. chest, waist).  Assigned TLD rings must be worn on the extremity that is likely to receive the highest exposure whenever radioactive materials are handled.

Radiation Supervisors are responsible for keeping the RSO informed of individuals under their supervision requiring radiation exposure monitoring. They are also responsible for notifying the RSO of lost or damaged dosimeters and dosimeters that need to be canceled. This notification should be provided on a “Lost, Damaged or Canceled Dosimetry” form available from EHSS.

(iii) External Radiation Exposure Monitoring Rules

The following rules must be followed by all individuals monitored for radiation exposure. Failure to observe any of the radiation exposure monitoring rules may result in remedial and/or disciplinary action as deemed appropriate by the RSO.

  1. Radiation monitors must be worn by individuals assigned them at all times when frequenting or in close proximity to ionizing radiation.
  1. Dosimeters must be stored in an accessible, centralized location. This location must be free of possible irradiation, heat, humidity and direct sunlight.
  1. Individuals assigned dosimeters are responsible for the proper wearing, storage and timely exchange of their own monitors.
  1. The deliberate or unnecessary irradiation of a personal dosimeter (i.e. to test its accuracy) is strictly prohibited.
  1. Lost or damaged dosimeters must be reported to the RSO.
  1. Occupational exposure monitors must never be worn during non- occupational exposures (i.e. medical x-rays).

5.4 Internal Radiation Monitoring

Internal radiation exposure results from the ingestion, absorbtion, inhalation or injection of radioactive materials into the body.  Small quantities of radioactive materials which present an insignificant external hazard can result in an appreciable exposure when taken into the body.  Once inside the body, the radioactive material continues to irradiate the body until it has either decayed or been excreted.  The rate of decay of the radioactive material varies with the isotope’s physical halflife and can be anywhere from a few seconds to several thousand years.  Physical halflife is different from biological halflife which is rate of elimination from the body.  The elimination rate of the material depends on a number of different factors (i.e. chemical constituents) and can occur over a period of a few days or up to many years.

(i) Methods of Monitoring Internal Exposure

The assessment of internal exposure may be accomplished through one or a combination of the following methods. The type of assessment used is dependent on the radiological, chemical and biological characteristics of the material to which an individual was exposed.

  • Determination of the concentration of radioactive material in the air of the work area(s)
  • Determination of the quantities of radioactive material in the body
  • Determination of the quantities of radionuclides excreted from the body

Bioassays are the most common methods used at the University for evaluating internal exposure.  A bioassay is defined as the determination of the kind, quantity or concentration and location of radioactive material in the human body by direct measurement (in-vivo) or by analysis (in-vitro) of materials excreted or removed from the body. The types of bioassays used to monitor radiation exposure include urinalysis, thyroid uptake and nasal swabs.

(ii) Internal Radiation Exposure Monitoring of Personnel

The Annual Limit on Intake (ALI)  is used as the basis for estimating the dose from radiation internally deposited in the body. A table of ALIs is provided in 10 NYCRR Part 16 Appendix 16-C, Table 1, Columns 1 and 2.   Syracuse University will make appropriate measurements to assess internal contamination if an occupationally exposed adult is likely to receive an intake, in one year, in excess of 10% of the applicable ALI, or a minor or declared pregnant woman is likely to receive a CEDE of 50 mrem in a year. The prospective review performed by the RSO will be used to identify individuals who require a routine internal exposure assessment.  In addition, certain situations/procedures may require an internal exposure assessment as deemed necessary by the RSO.

If an internal assessment is required, the appropriate method of  assessment will be determined by the RSO. The assessment may involve the collection of  urine sample(s), air sampling in the laboratory, an external survey of the body or a specific organ (i.e. thyroid), etc. Once the amount of radioactive material in the body has been estimated through the bioassay or other type of measurement, the estimated internal dose will be calculated and recorded. Radiation Safety staff must be contacted prior to the performance of any procedure anticipated to require a follow-up internal assessment.

(iii) Procedure Involving the Use of Volatile Radioactive Materials

Procedures using radioactive materials which are volatile or which represent the possibility of producing airborne radioactive contaminants must be performed in adequately functioning fume hoods or controlled release glove boxes. The breathing zones of individual users and exhaust air will be monitored during these procedures. This monitoring will be required at the discretion of the RSO to evaluate personal exposure and to ensure that air effluent releases are below NYSDEC limits. Volatile radioactive material procedures require 48 hour advance notification to the RSO. These experiments must be performed during normal working hours to assure the proper use of sampling pumps and data collection. In the event of accidental exposure to volatile radioactive materials or radioactive particulates notify the RSO immediately.

(iv) I125 and I131 Bioassays

Individuals using I125 or I131 are required to notify Radiation Safety staff and obtain a bioassay if any of the following conditions are met:

  • An individual uses, at any time on an open bench, a quantity of I125 or I131 which equals or exceeds 100 uCi;
  • An individual uses, at any time in an adequately functioning fume hood, a quantity of I125 or I131 which equals or exceeds 1 mCi;
  • An individual handles in open form, unsealed quantities of radioactive iodine that exceed 10% of those shown in Table 5-1 of this Section. The quantities shown in Table 5-1 apply to both the quantities handled at any one time or integrated as the total amount of activity introduced into a process by an employee over any 3 month period;
  • Actual surveys or calculations indicate that an individual had the potential to receive an intake in excess of 10% of the applicable ALI from Table 1 in 10 NYCRR Part 16, Appendix C;
  • The RSO has reason to suspect an individual was internally exposed; or
  • As required by State or Federal regulations or guidelines.

An I125 bioassay may include both an in-vivo and an in-vitro measurement.  The in-vivo measurement will be used to evaluate the radioiodine concentration in the thyroid through a thyroid uptake count. This procedure involves measuring background and the thyroid area with a low energy gamma detector. These measurements must be scheduled with and performed by Radiation Safety staff and must be performed within 48‑72 hours of the exposure. Bioassay results will be tabulated and included in the individuals occupational exposure records.

The in-vitro measurement to evaluate I125/I131 internal exposure is in the form of urinalysis.  This procedure involves the collection of urine samples within 72 hours of the radioiodine exposure. The preferred sample is a 50 mL collection of a first morning urine on the third day following the exposure.  A 24 hour total urine collection may also be necessary.  Sample collection containers are available from EHSS. The sample container must be labeled with the individual’s name, the time and date of collection and the isotope to which the individual was exposed and must be delivered to EHSS the morning of collection.

(v) H3 (Tritium) Bioassays

Individuals using Tritium are required to notify Radiation Safety staff and obtain a bioassay if any of the following conditions are met:

  • An individual uses, at any time on an open benchtop, a quantity of H3 that  equals or exceeds 10 mCi;
  • An individual uses, at any time in a adequately functioning fume hood, a quantity of H3 that equals or exceeds 100 mCi;
  • An individual uses quantities of H3 in a process or in processes over a one month period, that exceed 10% of the quantities shown in Table 5-2 of this Section;
  • Actual surveys or calculations indicate that an individual had the potential to receive an intake in excess of 10% of the applicable ALI established in Table 1 of 10 NYCRR Part 16, App. C;
  • The RSO has reason to suspect an individual was internally exposed; or
  • As required by State or Federal regulations or guidelines.

A Tritium bioassay generally consists of a urinalysis. This procedure involves the collection of a urine samples between 4 to 72 hours of exposure and every 24 hours following, until contamination is cleared from the body (H3 has a biological halflife of approximately 10 days). The preferred sample is a 50 mL collection of a first morning urine on the next day following the exposure. A 24 hour total urine collection may also be necessary.  Sample collection containers, available from EHSS, must be labeled with the individual’s name, the time and date of collection and the isotope to which the individual was exposed and must be delivered to EHSS the morning of the collection.

Table 5-1

Activity Levels Above Which An I125/I131

Bioassay Is Necessary*

        Activity Handled In Unsealed Form Making A Bioassay Necessary*

Type of Operation Volatile/Dispersible* Bound/NonVolatile*
Processes in open room or bench, with possible escape of iodine from process vessels 1 mCi 10 mCi
Processes with possible escape of iodine carried out within a fume hood of adequate design, face velocity and performance reliability 10 mCi 100 mCi
Processes carried out within gloveboxes, ordinarily closed, but with possible release of iodine from process and occasional exposure to contaminated box and box leakage 100 mCi 1000 mCi
*Quantities may be considered the cumulative amount in process handled by a worker during a 3 month period; (i.e. the total quantity introduced into a chemical or physical process over a 3 month period, or on one or more occasions in that period, by opening stock reagent containers from which radioactive iodine may escape). Quantities in the right-hand column may be used when it can be shown that activity in process is always chemically bound and processed in such a manner that I125 or I131 will remain in non-volatile form and diluted to concentrations less than 0.1 mCi/mg of non-volatile agent. Capsules (such as gelatin capsules given to patients for diagnostic tests) may be considered to contain the radioiodine in a non-free form, and bioassay would not be necessary unless a capsule were inadvertently opened (i.e. dropped or crushed). However, certain compounds where radioiodine is normally bound are known to release radioiodine when the material is in process, and the left-hand column may then be applicable. In those laboratories working only with I125 in radioimmunoassay (RIA) kits, the quantities of I125 are very small and in less volatile forms; thus bioassay requirements may be judged from the right-hand column. In field operations, where reagent containers are opened outdoors for simple operations such as pouring liquid solutions, the above table does not apply; bioassay should be performed whenever an individual employee handles in open form (i.e. an open bottle or container) more than 50 mCi at any one time.

Operations involving the routine use of I125 or I131 in an open room or bench should be discouraged. Whenever practicable, sealed bottles or containers holding more than 0.1 mCi of I125 or I131 should be opened at least initially within fume hoods having adequate face velocities of 0.5 m/sec or more.

*Adopted from the NRC’s Regulatory Guide 8.20, September 1979

Table 5-2

Activity Levels Or Concentrations Above Which A 

Tritium Bioassay Is Necessary*

Type of Operation HTC(b) & Other Tritiated Cmpds Including Nucleotide Precursors Tritium (HT or T2(c) Gas in Sealed Process Vessels(d) HTO Mixed w/ More than 10kg of Inert H20 (eg: In Reactor Coolant(e)
Processes in open room or bench, with possible escape of iodine from process vessels 0.1 Ci 100 Ci  0.001 Ci/Kg
Processes with possible escape of iodine carried out within a fume hood of adequate design, face velocity and performance reliability 1.0 Ci 1000 Ci  0.1 Ci/Kg
Processes carried out within gloveboxes, ordinarily closed, but with possible release of iodine from process and occasional exposure to contaminated box and box leakage 10.0 Ci 10,000 Ci  1 Ci/Kg
(a) Quantities (<10Kg) of substances containing tritium that are present during operations may be considered to be either the amount processed by an individual at any one time (when accidental intake is more likely) or the amount of activity that entered into the process (throughout) during any one month (when routine handling of repeated batches is the more likely source of exposure).

(b) HTO is the symbol for a water molecule in which a tritium atom (T) is present in place of a normal hydrogen atom (H).

(c) A molecule of hydrogen gas contains two hydrogen atoms.  Either one of these atoms may be replaces with a T to form HT, or two T atoms may combine to form T2 gas.

(d) This assumes that adequate air monitoring has established that there is no tritium leakage or that no significant amount of tritium gas can be converted to HTO before intake.

(e) This column is applicable in place of the previous two columns in cases where tritium can be identified at measurable concentrations in large amounts of water or other substances, such as at nuclear power plants.

*Adopted from the NRC’s Regulatory Guide 8.32, July 1988

5.5 Radiation Exposure Limits

NYSDOH regulations set limits for radiation exposure received by occupationally exposed workers and minors, occupationally exposed pregnant women and members of the public. These limits take into account both the dose received from external exposure and the dose from internally deposited radioactive material. The terms “dose equivalent” and total effective dose equivalent (TEDE) are used in the established limits. Dose equivalent (H) takes into consideration physical and biological conditions and is the product of the dose received, the quality factor and all other modifying factors  related to stochastic biological effects. TEDE is defined as the sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalent (internal exposures).

(i) Occupational Dose Limits

Individuals who during their normal course of employment have a likelihood of receiving radiation exposure are considered to be occupationally exposed radiation workers.  NYSDOH, in 10 NYCRR Part 16, establishes limits for occupational exposure.  In every case, the dose should be kept as low as reasonably achievable and below the established occupational dose limits (with the exception of a planned special exposure as described in 10 NYCRR Part 16).

The annual limits for an adult radiation worker as established by NYSDOH in 10 NYCRR 16.6(a)  are as follows:

  • Annual limit, which is more limiting of :
  1. Total Effective Dose Equivalent of 5 rem

TEDE = DDE(external exposure) + CEDE(internal exposure)=  Hd + He,50; or

  1. The sum of the Deep Dose Equivalent and Committed Dose Equivalent  to any organ/tissue,other than the lens of the eye, of 50 rem  DDE(external) + CDE(internal) = Hd + HT,50
  • Annual eye dose at a tissue depth of 0.3 cm of 15 rem
  • Annual shallow dose at a tissue depth of 0.07 cm to any extremity or the skin of the whole body of 50 rem

No person shall transfer, receive, possess or use any radiation source which could cause any occupationally exposed adult at Syracuse University to  receive a dose in excess of any of the above stated occupational dose limits.

(ii) Occupational Dose Limits for Minors

Occupational dose limits for occupationally exposed individuals under 18 years of age are 10% of the adult occupational dose limits stated above.

(iii) Declared Pregnant Women – Dose Limits for Embryo/Fetus

A declared pregnant woman is a woman who has voluntarily informed the RSO, in writing, of her pregnancy and estimated date of conception. A woman is not required to provide medical proof when pregnancy is declared and may withdraw the declaration at any time. Pregnant workers are encouraged to inform the RSO as soon as possible of their pregnancy to ensure that steps are taken to monitor and minimize radiation exposure as necessary.

NYSDOH has established limits for radiation exposure to the embryo/fetus due to the occupational exposure of a declared pregnant woman.  NYSDOH requires that:

  • The dose to the embryo/fetus during the entire pregnancy not exceed 500 mrem.
  • Working conditions be adjusted to avoid a monthly exposure rate of more than 50 mrem to the declared pregnant woman.

The dose to the embryo/fetus is calculated by summing the Deep Dose Equivalent to the declared pregnant woman during the entire pregnancy  and the dose to the embryo/fetus from radionuclides in the embryo/fetus and radionuclides in the declared pregnant woman during the entire pregnancy.  If at the time of declaration of the pregnancy, the pregnant woman has already received a embryo/fetal exposure in excess of 450 mrem, the woman may still receive an additional 50 mrem total for the remainder of the pregnancy.

(iv) Dose Limits for Individual Members of the Public

The use, storage and disposal of radioactive materials and the operation of radiation-producing equipment should be such as to ensure that:

  • the dose in any unrestricted area from external radiation sources dose not exceed 0.002 rem in any one hour .
  • The total effective dose equivalent to individual members of the public dose not exceed 0.1 rem in a year.

(v) Summary of Radiation Dose Limits

Occupational Dose Limits                                                                      Annual Limit

  • Whole Body (TEDE)                                                                                         5 rem
  • Skin (Shallow Dose Equivalent)                                                                      50 rem
  • Extremity (Shallow Dose Equivalent)                                                               50 rem
  • Eye (Eye Dose Equivalent)                                                                              15 rem
  • Organ /Tissue                                                                                               50 rem

(Deep + Committed Dose Equivalent)

Occupational Dose Limits For Minors (<18yrs of age)

  • 10% of the Occupational Dose Limits For Adults

Occupational Dose Limits For Declared Pregnant Woman

  • The dose to the embryo/fetus during the entire pregnancy                                 0.5 rem*
  • Working conditions be adjusted to avoid a monthly exposure rate of more than 50 mrem to the declared pregnant woman

Dose Limits For Members Of The Public

  • The total effective dose                                                                                   0.1 rem
  • The dose in any unrestricted area from external radiation sources                      0.002 rem* in any hour

 

* indicates that the dose limit is not an annual limit

5.6 Occupational Exposure Records

(i) Occupational Exposure Records

Syracuse University maintains occupational exposure records for each individual for whom radiation monitoring is required.   The records will be consistent in either SI or standard units and will  include, as applicable:

  • deep dose equivalent to the whole body
  • eye dose equivalent
  • shallow dose equivalent to the skin of the whole body
  • shallow dose equivalent to the extremity
  • estimated intake or body burden of radionuclides, CEDE assigned to the intake or body burden of radionuclides, and the specific information used to calculate the CEDE pursuant to 10 NYCRR Part 16.6(d)
  • TEDE when required by 10 NYCRR Part 16.6(b)
  • total deep dose equivalent and the committed dose to the organ receiving the highest total dose

A summary of an individual’s cumulative exposure for the past year will be sent out annually to each individual for their review. Since exposure monitors are not routinely provided solely for the measuring the exposure to the eye, eye dose equivalents will generally be derived from whole body film badge monitor.

Duplicate copies of occupational external exposure records will be provided to the laboratories upon receipt from the processing institution.  In addition, records and results of monitoring performed to evaluate internal exposure will also be maintained at EHSS. Records of an individual’s occupational exposure can be obtained from EHSS upon request from the individual. Records of occupational exposure will be maintained indefinitely at EHSS.

(ii) Radiation Safety Officer Exposure Review and Investigation

The Radiation Safety Officer will review all exposure reports. Any wholebody exposure greater than 50 mrem per exposure period will be investigated by the RSO or his delegate. Any extremity exposure greater than 500 mrem per exposure period will also be investigated by the RSO or his delegate. Any unexpectedly high or low exposures may also be investigated at the discretion of the RSO.

(iii) Multiple Employment

Doses received from all sources of occupational exposure, including those received at other places of employment, must be taken into account when considering whether an individual will exceed the allowable limits. NYSDOH requires that efforts be made to obtain information on doses received by employees who are also employed at other facilities. To comply with this, occupationally exposed employees are required to inform the RSO if they are being monitored for occupational exposure at another institution.  The RSO or his delegate will then make an effort to obtain their occupational exposure records from the institution.

(iv) Cumulative Exposure History/Prior Occupational Dose

Each individual who is monitored for radiation exposure at the University is requested to provided the RSO a list of all the facilities where they are or have been monitored for occupational radiation exposure.  This information may be provided on the Radiation Worker Sign-Up form and must include a contact person and address.  Radiation Safety staff will send a written request to the institution(s) listed to obtain the individual’s cumulative occupational radiation exposure records.  If an individual was monitored during the current year at another institution, but records are not obtainable, it shall be assumed that the individual  received 1.25 rem for each quarter for which records are not available and the individual was engaged in activities that could have resulted in an occupational exposure.

5.7 Respiratory Protection for Airborne Radioactive Hazards

Process and other engineering controls, such as ventilation and containment, must be implemented whenever feasible to maintain airborne radioactive material concentrations below those that define an airborne radioactivity area (see Section 6.3.5 of this Handbook).  When it is not feasible to apply these controls, exposure to airborne radioactive materials must be limited by:

  • controlling access to the area
  • limiting the duration of exposure, and/or
  • the use of respirators

If respirators are required, EHSS staff will evaluate the process and/or area to determine the type of respirator needed and estimate the potential exposure. The two basic types of respirators used are air purifying and air supplying.  Air purifying respirators mechanically filter, absorb or adsorb air contaminants onto a medium/media.  Air supplying respirators supply air to the wearer and are generally used in oxygen deficient and immediate danger to life and health atmospheres, in emergency situations and when the contaminant or concentration of the contaminant is unknown.  Respirators will be provided to University employees only at no cost to the employees. Non-employees, including students, will not be assigned respirators.  Additionally, special capabilities (i.e. visual, audio) will be provided to respirator wearers when needed.

All use of respirators at the University must comply with the University’s Respiratory Protection Program and associated OSHA and NYSDOH regulations.

(i) Radiation Hazard Evaluation

Areas/processes with a potential for airborne radioactive contamination will be evaluated by EHSS staff to identify the potential hazard and assess the need for respiratory protection. The evaluation (job analysis) will be conducted as outlined in the University’s Respiratory Protection Program.  The evaluation will consist of a process review and/or air sampling sufficient to:

  • identify the hazard
  • select the appropriate equipment selection (as necessary)
  • estimate the associated exposure potential

Any significant changes in evaluated processes/areas require notification to EHO and a re-evaluation as necessary.

(ii) Respirator Selection

Respirators used for protection from airborne radioactive contaminants must be tested and certified or have certification extended by the National Institute of Safety and Health(NIOSH) and the Mine Safety and Health Administration(MSHA). This respiratory protective equipment must also be used according to the equipment manufacturer’s expressed limitation for type and mode of use.

The selection of an appropriate respirator will be based on the results of the area/process evaluation and will take into account:

  • the physical and chemical properties of the air contaminants;
  • the physiological effects on the body;
  • the concentration of the contaminants;
  • the estimated exposure likely to be encountered;
  • the warning properties of the hazard (odor, irritant levels, etc.);
  • the respirator’s protection factor, limitations and fit; and
  • the oxygen level and immediate danger to life and health designation.

The selected respirator must be adequate to:

  • provide a protection factor greater than the multiple by which the peak concentration in the area is expected to exceed the derived air concentration (DAC) limit; and
  • result in a total effective dose equivalent ALARA

(iii) Emergency Use Respirators

In an emergency situation, where the presence and/or type or quantity of potential airborne contaminant(s) is unknown, self-contained breathing apparatus or other supply air apparatus must be used.  This equipment, specifically certified for emergency use by NIOSH and MSHA, must only be used by trained personnel and must meet the requirements for emergency use respiratory protection equipment established in the University’s Respiratory Protection Program. All emergency use respirators must be inspected monthly.  This inspection must be properly documented and the documentation maintained for a minimum period of three years.

(iv) The Use and Care of Respirators

An individual who is required to use a respirator for protection from airborne  radioactive contaminants must:

  • be an authorized radioactive material worker;
  • be evaluated by a physician initially and every 12 months thereafter, to determine if he/she is physically able to wear the respirator;
  • complete the Respiratory Protection Program Training provided by EHO; and
  • be properly fitted for the respirator (initially and every 12 months thereafter).

The use and care of respirators must comply with the requirements outlined in the University’s Respiratory Protection Program.  All respirators must be inspected before and after each use, and at least monthly if it is used for emergency purposes only.  This inspection, at a minimum, must include a check of the tightness of connections and the condition of the facepeice, headband, valves connecting tubes and canisters.  Rubber and elastic parts must be inspected for pliability and signs of deterioration. Replacement or repairs of damaged parts may only be made by experienced personnel.

(v) Airborne Radiation Exposure Evaluation

If an individual is required to use a respirator, the exposure likely to have been received by the individual during use will be estimated based on the results of air sampling and the protection factor of the equipment assigned. Air sampling will be conducted at the discretion of the RSO. Bioassays will be periodically performed on all individuals required to use a respirator to evaluate the actual intake of radioactive materials. The bioassay performed will be specific to the isotope and the physical and chemical components of the process(s) (see Section 5.4 of this Handbook for details on internal contamination assessments).

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