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1. Administrative Organization

1.1 President

1. Assumes institutional responsibility through the Radiation Safety Officer and the Radiation Safety Committee (RSC) for general radiation safety practices and their administration.

2. Works with, Deans, Directors, and Department Chairpersons, through the Radiation Safety Committee and the Radiation Safety Officer in establishing a program that provides for the safety of all personnel associated with laboratories using radioactive materials or radiation producing devices and meets the State of Maryland licensing/registration requirements.

3. Appoints the Radiation Safety Committee and delegates appropriate authority to that body in matters pertaining to radiation safety.

1.2 Radiation Safety Committee (RSC)

This Committee is responsible for establishing procedures and policies for the authorized procurement, protection, use, and disposal of radioactive materials and radiation producing devices; for the safety and protection of all personnel, on the University of Maryland Campus and all properties under its control, involved in any projects in which ionizing radiation is used. The Committee shall:

1. Provide technical and administrative guidance and aid in the interpretation of various regulations governing the use of sources of ionizing radiation.

2. Review and act upon all new, renewal applications and amendment requests for possession and use of radioactive materials and registration of radiation producing devices.

3. Determine the adequacy of training and experience of persons requesting permission to use or supervise the use of radioactive materials and radiation producing devices.

4. Determine the suitability of space, facilities, or equipment designated for use or storage of radioactive materials and the use of radiation producing equipment.

5. Receive and review periodic reports from the RSO on monitoring, contamination, and personnel exposure.

6. Meet, at the call of the Chairperson, or designated representative, to review alleged infractions of safety rules and regulations, incidents and emergencies concerning any radiation program or project on the UM.

1.3 Deans, Directors, and Department Chairpersons

1. Promote the safety policies of the Office of the Vice President for Academic Affairs and Provost as formulated by the RSC, State of Maryland and/or Federal agencies.

2. Hold faculty members or supervisors responsible for the implementation and enforcement of applicable safety procedures and safety requirements.

3. Authorize necessary expenditures for safety.

1.4 Radiation Safety Office (RSO) - Department of Environmental Safety

1. Advising the Director of Environmental Safety and the Office of the Vice President for Academic Affairs and Provost on the control of radiation hazards.
2. Directing all radiation safety activities on the UM Campus and satellite facilities.

3. Controlling all radioactive material and radiation producing devices.

4. Acting as executive agent for all State of Maryland licenses for the possession, use, storage, and disposal of radioactive material and radiation producing devices on the UM Campus and satellite facilities.

5. Providing advice, assistance, technical support, and supervision to all activities using radioactive material or radiation producing devices on matters of radiation safety.

6. Conducting and administering education and training programs in the safe use of radioactive materials, sources, and radiation producing devices.

7. General surveillance of all radiation safety activities, including both personnel and environmental monitoring.

8. Ordering (or authorize ordering), receiving, processing, and shipping all radioactive materials coming to or leaving the University of Maryland Campus and satellite facilities.

9. Ensuring calibration of all portable survey instruments in a timely manner.

10. Collecting, distributing and processing of personnel monitoring devices; keeping of records of internal and external exposure to personnel; notifying individuals and their Principal Users of unusual exposures or when approaching maximum permissible amounts of exposure, and assisting all personnel in keeping future exposure as low as reasonably achievable (ALARA).

11. Maintaining an around-the-clock emergency response for emergencies and incidents involving radiation, radioactive material, or personnel exposure.

1.5 Principal User

1. Planning and organizing an experiment or program keeping in mind the type and amount of radiation or radioactive material to be used and/or produced.

2. Providing for necessary engineering controls for the safe use of RAM by obtaining necessary funding, specifying equipment, and assuring that all equipment is installed and functioning properly.

3. Instructing those personnel who work under their authorization, in the safe use of radioactive materials or radiation producing devices.

4. Furnishing the RSO with information concerning individuals and activities in their areas; particularly, pertinent changes in personnel and procedures.

5. Contacting the RSO whenever major changes in operational procedures, rooms, alterations of facilities (e.g., shielding changes, removal or installation of radio-active material handling equipment) occur or when new operations which might lead to personnel exposure are anticipated.

6. Ensuring that all regulations governing the use of radioactive materials or radiation producing devices are complied with as established by the RSC, NRC, and the State of Maryland.

7. Equipping each laboratory complex with survey meters capable of detecting the types of radiation that might be encountered in the area as directed by the RSC. Ensure that the survey meters are functional and in current calibration. Deliver the instrument to the RSO if in need of repair.

8. Posting all areas under their control with proper radiation warning signs.

9. Ensuring that the personnel under their control discharge their individual responsibilities as listed in Section 1.6.

1.6 Radioactive Material and Radiation Equipment Users

1.6.1 Principal Investigators

1. Planning and organizing an experiment or program keeping in mind the type and amount of radiation or radioactive material to be used and/or produced.
2. Instructing those personnel, for whom they are responsible, and who will be working under their Authorization, in the use of safe techniques, operation of equipment, and in the application of approved radiation safety practices.
3. Furnishing the RSO with information concerning individuals and activities in their areas; particularly, pertinent changes in personnel and procedures.
4. Contacting the RSO whenever major changes in operational procedures, rooms locations, alterations to labs (e.g., shielding changes, removal or installation of radioactive material handling equipment) occur or when new operations which might lead to personnel exposure are anticipated.
5. Ensuring that all regulations governing the use of radioactive materials or radiation producing devices are complied with as established by the RSC, NRC, and the State of Maryland.
6. Equipping each laboratory complex with survey meters capable of detecting the types of radiation that might be encountered in the area. Ensure that the survey meters are in current calibration and deliver the instrument to the RSO if in need of repair or calibration.
7. Posting all areas under their control with proper radiation warning signs.
8. Ensuring that the personnel under their control discharge their individual responsibilities as listed in Section 1.6.4.
9. Ensuring that all necessary engineering controls are properly in place for use by personnel under their Authorization.

1.6.2 Authorized User

1.6.3 Individual User

1.6.4 Responsibilities of Users

1. Keep exposure to radiation as low as reasonably achievable (ALARA).

2. Wear the prescribed monitoring equipment such as a film badge, TLD, and/or pocket dosimeter while working with radioactive materials or radiation producing devices. Personnel who work with only pure alpha emitters and RSO specified low energy beta emitters will not be required to wear film badges. Dosimetry equipment must not be tampered with and must be protected from damage or abuse.

3. Use appropriate protective measures such as:
   1. Wear protective clothing whenever contamination is possible.

   2. Use protective barriers and shields whenever required and appropriate.

   3. Use remote handling tools such as forceps, tongs and pipettes to minimize personnel exposure.

   4. Use an approved hood or glove box while using or creating radioactive gases or volatile materials, such as welding on radioactive materials.

   5. Cover work surfaces with a plastic backed absorbent paper when using liquids.

   6. Use stainless steel or disposable fiberglass trays lined with absorbent paper to confine contaminating materials and to limit or collect spillage in case of an accident.

   7. Refrain from eating, drinking, smoking, chewing gum or tobacco, or applying cosmetics in an area where radioactive materials are used or stored. Do Not store or prepare food or drink in any area or equipment that is or has been used for radioactive materials, e.g., refrigerators, cabinets, glassware.

   8. Keep cleaning equipment (brooms, mops, buffers, buckets, etc.) used in radiation designated spaces from being used in other areas.

4. Mark and label all contaminated or potentially contaminated containers and equipment with radioactive marking tape and/or labels as required.

5. Wash the hands (including under the fingernails) thoroughly and survey the hands, shoes and body for radioactive contamination.

6. Utilize the proper radioactive waste procedures as set forth in Section 3.9.

7. Maintain a log of all meter and wipe surveys conducted by the user. The frequency of survey is dependent on the operation and/or radioactive isotope(s) in use. See Section 3.8. The RSO is available to help establish the survey and record keeping necessary to comply with the licensing requirements.

8. Carry out decontamination procedures when necessary and take the necessary steps to prevent the spread of contamination to other areas.

9. Report accidental inhalation, ingestion, or contamination involving radioactive materials to the Principal User or supervisor and RSO. Cooperate with the RSO to evaluate possible exposure if necessary.

10. Keep the laboratory neat and clean. The work area should be free from equipment and material not required for the immediate procedure.

11. Assure that freezer or refrigeration equipment (spark proof if required) is available for the preservation of radioactive solutions which decompose at normal room temperatures, and for storage of contaminated animal carcasses, plants, or other unstable material awaiting disposal.

12. Eliminate all unnecessary sharp objects from areas where radioactive material is used.

13. Do not handle the telephone, reports, etc., with contaminated hands or while using protective gloves.

2. Radiation Exposure Control

2.1 ALARA

2.2 Basic Radiation Protection Standards

2.2.1 Occupational Dose Limits

	  Exposed Area                         REM/Year  Sieverts/Year

  	Whole body - head and trunk;            5.0        0.050
  	gonads; arms above elbow,
        legs above the knee
	Extremities - hands and fore-          50.0        0.50
 	arms; feet and ankles, leg
        below the knee
        Skin                                   50.0        0.50
 Lens of eyes                           15.0        0.15

        Any Individual Organ or Tissue         50.0        0.50

        Embryo/Fetus (Entire Period)            0.5        0.005

The difference between whole body and skin of whole body is determined by the penetrating power of the incident radiation. If the whole body is exposed to radiation with a half value layer of less than 1 mm of soft tissue, then this is considered a skin dose. The dose to the extremities is radiation of any energy.

Note: Personnel working within a laboratory where radioactive materials are used or radiation devices are used, and badging is required, but who are not directly working with the material shall be considered an occupationally exposed person for control purposes.

2.2.2 Internal Exposure

2.2.3 Occupational Dose to Fertile Women

2.2.4 Occupational Dose to Minors

2.2.5 Exposure to Non-Occupationally Exposed Personnel (General Public)

2.2.6 Surface Contamination

Generally, a beta/gamma survey meter reading of twice background levels necessitates immediate decontamination.

                                   dpm/100 cm2
Item                            Alpha        Beta/Gamma
Skin, hair, clothing, shoes      100	        100

Cold areas (office, other        100            100
labs, etc.)

Equipment, lab surfaces,         100            100  *
floors, etc. in controlled
areas

      *  1000 dpm/100 cm2 for 3H

In those cases where surface contamination is found, but is not removable, the item must either be discarded as radioactive waste or the contamination permanently fixed to the item and the surface conspicuously labeled as contaminated. Clothing that cannot be decontaminated will be held for decay (if reasonable) or disposed of as radioactive waste.

2.3 Personnel Monitoring (Dosimetry)

1. An any individual is likely to receive in one year from sources external to the body, a dose in excess of 10 percent of the limits in Section 2.2.

2. An individual enters a high or very high radiation area.

3. An adult is likely to receive, in one year, an intake in excess of 10 percent of the applicable ALI(s) in 10 CFR 20, Appendix B. (Table 1, Columns 1 & 2).

4. A minor and declared pregnant woman is likely to receive, in one year, a committed effective dose equivalent in excess of 0.05 rem (0.5 mSv).

2.3.1 Dosimeter

1. The personnel dosimeter used for monitoring is the personnel monitor issued by the RSO. Dosimeter as defined in the Glossary is "A device that measures radiation exposure, such as a film badge, ionization chamber, or TLD", and is a device used to determine the dose received by a person exposed to beta, X, gamma and/or neutron radiation.

2. The dosimeter is used to provide the permanent radiation exposure history for the wearer. Therefore:
   1. It will be worn by only one person and by the person it is issued to. Care should be taken to avoid damage to the dosimeter.

   2. It will be worn in a location on your person (body trunk) where it is likely to receive the highest exposure on your whole body.

   3. Care must be taken that it not be shielded by other devices such as ID badges, pens/pencils, coins, or keys, etc.

   4. It must not be lost or damaged.

   5. It will be exchanged each month (usually on or about the 15th of the month). Badges older than 3 months cannot be processed and will be considered lost.

   6. It will not be used at locations other than at UM Campus and satellite facilities.

3. Wrist badges may be issued in cases where the extremities may be exposed to a significantly higher dose than the whole body, and are available upon a reasonable request.

2.3.2 Thermoluminescent Dosimeters (TLD)

The TLD must be worn on the finger, under the gloves, and with the portion of the ring holding the TLD chip toward the source of radiation.

2.3.3 Self Reading Dosimeters

1. Direct self reading dosimeters are available from the RSO.

2. Self reading pocket dosimeters may be worn by radiation workers in addition to, but not in lieu of, an assigned badge. Instances where this shall be a requirement is when entering areas where one may expect to be exposed in excess of 100 mrem at 30 centimeters from source or surface that radiation penetrates (High Radiation Area). The user can immediately determine an accrued exposure by periodically checking the dosimeter.

3. Short term visitors such as inspectors, casual visitors, and maintenance repair persons working on non-contaminated equipment in a radioactive material use area will be issued a self reading dosimeter in lieu of a film badge. A log of all personnel issued a dosimeter will be maintained reflecting the dose indicated by the dosimeter.

4. Self reading dosimeters must be handled with care. A sharp blow, such as when dropped, discharges the dosimeter causing it to go off scale. In this case, an evaluation of the exposure must be made and the dosimeter recharged. The dosimeter must also be recharged at intervals given in the manufacturer's instruction manual.

2.3.4 Issuing Dosimetry

2.3.4.1 Temporary Personnel from Other Facilities

2.3.4.2 University of Maryland Personnel Visiting Other Facilities

2.3.5 Exposure History

2.3.5.1 Lost or Damaged Dosimeters

1. Obtaining the individuals work history for the period in question and evaluating the exposure taking into consideration the work performed and past exposure history.

2. Averaging the recorded doses for the previous three periods.

2.3.6 Bioassay Program

1. An adult is likely to receive, in one year, an intake in excess of 10 percent of the applicable ALI(s) listed in Appendix B, 10 CFR 20. (Table 1, Column 1 & 2).

2. A minor, or declared pregnant woman is likely to receive, in one year, a committed effective dose equivalent in excess of 0.05 rem (0.5 Msv).

Some radioisotopes which require bioassays are listed on the Authorization for Possession and Use of Radioactive Materials issued to the Principle Investigators. Instructions for the appropriate bioassay is provided with the Authorization. All isotopes listed that will be used at or in excess of the listed value require a baseline measurement prior to use, and will be followed by regular analysis thereafter.

3. Radioactive Materials - Policy and Procedures

3.1 Personnel Authorization

3.1.1 Principal Investigator (PI)

3.1.2 Under 18 Years of age

3.1.3 Undergraduate Students

3.1.4 Graduate Students

3.1.5 Post-Doctoral Faculty or Research Personnel and Classified Employees

3.1.6 Non-University Personnel

3.1.7 Casual Visitors

3.1.8 Special Student Programs

3.2 Authorization Procedures

3.2.1 Application for Possession and Use of Radioactive Materials and Radiation Producing Devices

3.2.2 Training and Experience of Radioactive Material and Radiation Equipment Users

3.2.3 Processing the Application

Based on the application, pre-authorization survey, and review by the RSO, the Radiation Safety Officer and/or the Chairman of the RSC may issue an interim approval prior to the full review by the RSC. This entire package is then presented to the RSC for review. If approved, a formal authorization is issued by the Radiation Safety Officer

Figure 3.1

Authorization Procedure Flow Chart

3.2.4 Renewal of Authorization

3.3 Possession, Receipt and Inventory of Radioactive Material

3.3.1 Ordering Radioactive Materials

3.3.2 Receipt of Radioactive Materials

3.3.3 Inventory Control

3.3.4 Transfer of Possession

1. Outside Agencies - Before material may be released to anyone not directly associated with the University of Maryland, the RSO will be notified of desired transfer. The RSO will contact the recipient and request a copy of their current appropriate Federal or State license to insure that the recipient is licensed to possess such material. This is necessary for compliance with UM license and to avoid potential legal prosecution. A documented record of all such transactions will be maintained by the RSO per regulations.

2. Interdepartmental - Internal transfer of radioactive material will be approved by the RSO. The recipient will have a current authorization for the same radioactive material (specific isotope) proposed to be transferred. Receipts of such transfers will be maintained by the parties involved and by the RSO.

3.4 Use Of Materials In Spaces Not Listed In The User's Authorization - On or Off Campus

Movement of material to be used by a UM authorized user at a site other than assigned laboratory, i.e., research sea cruises, requires five day notification to the RSO for in state moves, and thirty day for out of state movements. State approval for in state/out of state, and NRC approval of out of state moves are required.

These actions are particularly important when the material will be used at, and transported to, a facility not under the UM Campus license. Use of material in an unauthorized space on campus only jeopardizes the UM Campus license, whereas transport to and use at another facility will jeopardize their license as well.

3.5 Transportation of Radioactive Materials

3.5.1 Hand Transport

3.5.2 Vehicle Transport

3.5.3 Transport Between Authorized Areas

1. Both rooms or areas are listed on the user's authorization.

2. Proper shielding, if required, is utilized to keep exposure ALARA.

3. The package is labeled with suitable radiation labels.

4. The package is capable of containing all the material, in case of an accident, in order to avoid contamination.

5. The package is moved expeditiously via the most direct route and is in the physical possession of the transporter at all times.

3.6 Storage

3.6.1 Unsealed Sources of Radiation

1. If the material is of a composition requiring refrigeration, the refrigerator will be plainly labeled for radioactive material storage only, and no food or drink will be stored in the unit.

2. If the material poses a possible airborne hazard, storage space shall be found in a working hood. As in all cases of storage, the container and shielding will be plainly marked as radioactive.

3. If the material requires neither 1 nor 2 above, then a relatively inaccessible storage space such as a cabinet, locker, or drawer may be utilized. The outside of the storage container, as well as the source and shielding within, will be plainly marked as radioactive.

3.6.2 Sealed Sources of Radiation

3.6.3 Special Cases

3.6.4 Radioactive Waste

3.7 Signs, Labels, and Signals

3.7.1 General Requirements

1. Radioactive Materials, Radiation Areas, High Radiation Areas, Very High Radiation Areas, Airborne Radioactivity Areas, shipping containers and vehicles will be marked or posted as required by various regulations. The RSO will assist in providing the necessary information, signs, and/or labels.

2. All signs, labels, and signals will be posted in a conspicuous place.

3. All radiation control areas, including Radiation Areas, Contamination Control Areas, and Airborne Radioactivity Areas will be established by a barrier. Walls, fences, rope, or tape may be used to define the boundaries of a controlled area.

3.7.2 Radiation Area

3.7.3 High Radiation Area

In addition to this posting, all such entrances shall:

1. Have a control device which upon entry into the area will cause the radiation level to be reduced below the level at which an individual might receive a dose of 100 mrem in 1 hour, or

2. Have a control device which will activate a conspicuous audio or visual alarm in such a manner to alert the individual entering the area and the supervisor of the facility of the entry, or

3. Be kept locked except during periods when access to the area is required with positive control over each individual entry. Keys for entry will be available to authorized personnel only, or

4. Be under direct surveillance if the High Radiation Area is to be established for a period of less than 30 consecutive calendar days, and does not have control devices indicated above.

3.7.4 Very High Radiation Area

In addition to the posting requirements, each entrance must be equipped with entry control devices which:

1. Function automatically to prevent an individual from inadvertently entering the area when very high radiation levels exist;

2. Permit deliberate entry into the area only after a control device is actuated that causes the radiation level in the area to be reduced below where it would be possible for a person to receive a deep-dose equivalent in excess of 100 mrem in one hour;

3. Prevent operation of the source in the area if radiation levels could result in a deep-dose equivalent to a person in excess of 100 mrem in one hour.

4. Provide additional control devices so that, upon failure of the entry control devices to function would:
   1. Reduce the radiation levels below that where a person could receive a deep-dose equivalent in excess of 100 mrem in one hour;

   2. Generate conspicuous visible and audible alarm signals to make an individual attempting to enter the area aware of the hazards and;

   3. Make at least one other authorized individual, who is physically present, familiar with the activity, and prepared to render or summon assistance, aware of the failure of the entry control devices.

5. When the source shield is liquid, provide means to monitor the integrity of the shield and automatically signal the loss of adequate shielding, i.e. water level.

6. Equip each area with devices that will automatically generate visible and audible alarms to alert personnel in the area before the source is put into operation; provide a clearly identified control device that will prevent the source from being put into operation and allow sufficient time for an individual in the area to operate the control device.

7. Provide administrative procedures to ensure that the area is cleared of personnel prior to each use of the source.

8. Test all entry control devices for proper functioning and document testing prior to initial operation on any day (unless operations were continued uninterrupted from previous day) and prior to resumption after any unintended interruption.

9. No operations will be conducted, other than those necessary to place the source in safe condition or effect repairs on controls, unless control devices are functioning properly.

   Figure 3.2

   Radiation Area Sign

   Caution

   Radiation Area

   Figure 3.3

   High Radiation Area Sign

   Caution

   High Radiation Area

3.7.5 Airborne Radioactive Area

3.7.6 Rooms or Areas

1. A Radioactive Materials sign (Figure 3.5) will be posted at all entrances to an area where unsealed sources of radiation are used or stored. This includes areas where radioactive waste is kept in an accessible condition.

2. If a room or area meets the conditions in Sections 3.7.2 or 3.7.3 and radioactive materials are used or stored, then the appropriate sign and the Radioactive Materials sign or a combination of the two signs (Figure 3.6) will be posted.

3.7.7 Containers and Labware

3.7.8 Sealed Sources

1. If the conditions of Section 3.7.2 or 3.7.3 do not exist in an area where sealed sources are stored, the entrance need not be posted, provided, that the radiation level 30 centimeters from the surface of the source container or housing does not exceed 5 mrem/hr, and the storage location (drawer, cabinet, refrig, room, etc.) provides adequate security for the source.

2. The outside of the storage container within such an area will be conspicuously posted with the sign in Figure 3.5.

3. In addition, if each sealed source is not permanently imprinted or embossed with the appropriate symbol and wording of any color, the label shown in Figure 3.7 will be affixed to each source.

   Figure 3.4

   Airborne Radioactivity Area Sign

   Caution

   Airborne Radioactivity Area

   Figure 3.5

   Radioactive Material Sign

   Caution

   Radioactive Material

   Figure 3.6

   Combined Radioactive Material and Radiation Area Signs

   Caution High Radiation Area Radioactive Materials Personnel Monitoring Required

   Radiation Area Radioactive Materials Authorized Personnel only

   Figure 3.7

   Radiation Materials Labels and Tags

   Caution

   Radioactive Material Isotope _________________ Amount __________________ Radiation _______________ Date ________ By ________ Do Not Remove This Tag Without Authorization of _____________________ Radiation Safety Office

   Radioactive Material

   Caution Radioactive Material
   Isotope Amount Date SP-RM 003

3.8 Surveys and Inspections

3.8.1 Radioactive Material Users

Since individual circumstances vary widely with regard to maximum activity, physical and chemical form of nuclide used, and to the various laboratory procedures in which radioactive material is employed, it is reasonable and prudent to attempt some classification of radioisotope facilities to determine the radiotoxicity of isotopes employed and how frequently they should be surveyed.

It is also recognized that radioactive materials are not in constant use in some laboratories on campus. Surveying laboratories for radioactive contamination during periods of infrequent use will be performed by the user. The RSO may be consulted to determine a reasonable and prudent survey frequency under such circumstances.

If for instance, such materials are used only for one laboratory a semester, only during the period of use would these guidelines apply. If the materials are placed in storage for the remainder of the year, surveys of the laboratory are unnecessary during the storage period. However, the storage site shall be surveyed during the storage period. An entry will be required in the wipe log to indicate that "no RAM was used" for each month of inactivity.

3.8.1.1 Classification

Users must first classify their laboratory areas, utilizing the attached two tables. Locate the isotope(s) used in Table 3.1 to determine the group classification to which the laboratory conforms. Then, utilizing Table 3.2, determine the appropriate survey frequency group, based on the amount per use.

For example:

An experiment is conducted employing a vial containing ¹²⁵I. The vial contains 5 mCi, and is opened to the laboratory environment while 1 Mci is removed. The vial is then resealed and returned to storage. First, locate ¹²⁵I in Table 3.1 in Group II. Then locate 5 Mci ¹²⁵I in Table 3.2 in Group II, Class II. The analysis indicates that the laboratory should be surveyed at least weekly while this level is employed. If it is a "one shot" only experiment, a survey should be done at the end of the experiment or at least once weekly which ever is shorter.

3.8.1.2 Survey Method

1. Initial Survey An initial survey will be conducted with an instrument, such as a GM tube or NaI crystal scintillation detector, to determine if contamination is present on a surface or in a particular area of a lab. The isotope employed shall determine the type of instrument that must be used in such a survey:

   Type 1 - For gamma and beta emitters of sufficient energy, a GM tube may be used; a scintillation detector for the appropriate emitter may also be used.

   Type 2 - For alpha emitters, an air proportional detector must be used. This device is available for a short term use from the Radiation Safety Office.

   Type 3 - For low energy gamma emitters, such as I-125, a NaI crystal scintillation detector must be used.

   Table 3.1

   Classification of Radionuclides According to Relative Radiotoxicity per Unit Activity

   

   Table 3.2

   Radioisotope Facility Classification

                        Class I        Class II            Class III
   
   Radionuclide     At Least Every      Weekly               Daily
       Group            30 Days
         I             < .01 mCi    .01 mCi TO 1.0  mCi  > 1    mCi
        II             < 1.0 mCi    1.0 mCi TO 10   mCi   > 1O   mCi
       III             <  1O mCi  .  10 mCi TO 100  mCi   > 100  mCi
        IV             < 100 mCi    100 mCi TO 1000 mCi   > 1000 mCi
   

   Note: Isotopes such as ³H, ³⁵S, and ¹⁴C are difficult to detect with a detector of any type currently available in the lab and will not be relied upon for detection of these isotopes. A wipe test will be used to determine any level of contamination when using these isotopes.

2. Wipe Test The final item of this method is the wipe test. Any time unsealed sources of radioactive materials are used in the lab, a wipe test will be conducted and the results posted in the wipe log book in the units of Disintegrations per Minute (DPM).

   DPM =          CPM         
         efficiency of detector
   

   Surface areas to be surveyed will be wiped with one inch discs of filter paper or parafilm, and the area per wipe will cover approximately 100 cm². These wipes will be placed in a vial containing standard scintillation cocktail and counted in a Liquid Scintillation Counter. If any reading exceeds 100 dpm, (1000 for ³H) that area will be considered contaminated and will be cleaned. The RSO will be notified of a contamination condition.

3.8.1.3 Typical Areas for Survey

Areas of concern include, but are not limited to:

Lab bench top and side surfaces;
Fume hood interior and exterior surfaces;
Floor area in front of benches and hoods;
Lab chairs and stools;
Light switches;
Drawer and other handles;
Bare hands, after glove removal;
Shoe soles, seats of pants, etc.

3.8.1.4 Records

3.8.2 Radiation Safety Office Surveys

1. Wipe Log: The monthly wipe test was not recorded in the laboratory wipe log; RSO personnel were unable to locate wipe log; the wipe log was not up to date.

2. Waste: Radioactive waste was found in an approved container but no entries were found on the container inventory card; waste containers were clearly labeled with proper radioactive material stickers/labels; radioactive waste was found in unapproved and unlabeled waste containers.

3. Film Badges: Individuals working with radioactive material requiring film badges and/or TLDs were not wearing their dosimetry; film badges in use were out of date.

4. Signs: Labels and signs appropriate for laboratories or equipment not found or missing.

5. Others: Other violations - as determined by RSO inspectors, and a numeric value given that is felt appropriate.

6. Score: Categories 1-4 are weighted for risk. The wipe log receiving the highest number of violations and the highest risk weight of 1.

   Score:   >3 : Weekly survey
           2-3 : Monthly survey
           1-2 : Quarterly survey
   
   Example: 3 Violations of the wipe log category in succession would
            result in a score of 3; an additional violation in category
            2 through 4 would result in a score >3 and indicate a 
            weekly survey schedule for the laboratory.
   

laboratories that use radioactive materials of significant energy levels that could potentially expose personnel to > 10% of the allowed exposure limits to the whole body or extremities will require a monthly survey frequency.

laboratories that use significant quantities of intermediate to high energy materials will require a monthly survey.

The purpose of the RSO survey is to help the user maintain a safe work environment and will include:

1. Meter and wipe surveys of work surface, floor, refrigerators, hoods, etc., to assure no contamination.

2. A check of fume hoods to assure that they are in working condition and have sufficient air flow for use with radioactive materials. A reading of 100 fpm or greater with the sash set at 12 inch opening is considered sufficient air flow.

3. A review of the wipe log.

4. An interview with the user and/or occupant to determine if there have been any new or unusual occurrences since the last survey and if the RSO may be of any assistance.

5. A written report of the survey. Any deficiency found will be noted and details sent to the user for corrective actions.

   Action will be taken at that time to correct the deficiency. Follow-up surveys shall be made at the time notification is received by the RSO that the deficiency has been corrected.

3.8.3 Restricted Areas

3.8.4 State of Maryland

3.9 Radioactive Waste

3.9.1 General Requirements

1. Ensure that sufficient and appropriate waste containers are obtained from the Hazardous Waste Management Office (HWMO) and that specific instructions for their use are fully understood.

2. Aqueous and non-aqueous liquids, vials, and solid wastes will be kept in separate containers.

3. Liquid and solid radioactive waste will be separated by isotope, except as authorized by the HWMO. Reactive chemicals must not be mixed.

4. Sharp objects will be disposed of in separate labeled containers or wrapped so that personnel who must later handle the waste are protected.

5. A running inventory will be maintained on the outside of each container by isotope, activity, and chemical composition for liquid containers.

6. All containers will be clearly labeled Caution Radioactive Waste or Caution Radioactive Materials.

7. Radioactive waste will never be placed in regular, non-controlled, non-radioactive designated containers.

8. All radioactive waste will be stored in a manner so as to prevent:
   1. Contamination of laboratory space and personnel;
   2. Generation of airborne hazards;
   3. Incompatible mixing of chemicals.
9. Radioactive waste will be stored separately from other types of hazardous waste or chemicals.

3.9.2 Solid Radioactive Waste

1. Solid radioactive wastes are all solid, dry, radioactive materials and laboratory waste such as gloves, absorbent paper, and used labware which is or may be contaminated with radioactive materials.

2. Materials which have become contaminated (and cannot be decontaminated) and contains any organic solvents such as benzene, toluene, or xylene, will be strictly segregated from other dry waste. Even a small amount of these organic solvents will cause the entire container to be classified as organic radioactive waste and the entire shipment will be rejected at the disposal site.

3. Containers for solid radioactive waste may be properly labeled trash cans or 55-gallon drums.

4. Waste containers for solid radioactive waste will be lined with a removable plastic liner.
5. No sharp objects, such as needles, knives, razor blades, pipettes, or glassware will be put in the plastic liner. Dry waste is normally compacted and must be handled by HWMO personnel.

6. Containers will be identified as to isotopes and a reasonable estimate of the activity of each isotope present in the container. A continuous listing will be maintained for all waste deposited in the container.

3.9.3 Liquid Radioactive Waste

1. All liquids, such as solvents, water, scintillation fluid, or other solutions, which contain or may contain radioactive materials are considered liquid radioactive waste.

2. Liquids will be segregated by type such as aqueous, organic solvent, scintillation cocktail, and by isotope except as authorized by the RSO. The techniques of waste preparation for final disposal vary greatly with each of these categories. The slightest solvent contamination causes the entire container to be classified as organic waste and disposal of this category is the most expensive.

3. Waste containers for liquid wastes are glass or polyethylene jugs and shall be stored in such a manner that should the container be damaged or break, the contents will be completely contained (i.e., within a secondary container).

4. Waste containers will be fitted with a securely fitting stopper or cover and must remain closed except to use or must be stored in an approved, operational hood.

5. No material other than liquids will be placed in liquid radioactive waste containers.

6. Water and solvents will be separated when possible.

7. Special consideration will be given to liquid wastes to ensure that mixing of liquids does not result in an altered Ph, unstable solutions, or the generation of gases.

8. Containers will be identified as to the isotope and a reasonable estimate of the activity of each isotope present in the container. A detailed chemical composition is also required. A continuous listing of this information will be maintained for all waste deposited in the container.

3.9.4 Radioactive Vials

1. Small scintillation type vials containing liquid samples will be treated separately from solid or liquid radioactive waste.

2. Vials may be plastic or glass containing 5 to 15 ml of radioactive liquid or scintillation fluid. Each type will be disposed of in separate containers.
   1. Aqueous - Vials containing isotopes with a half-life <90 days that contain aqueous biodegradable scintillation cocktail and no hazardous chemical will be poured from vials into a designated container for this type material only. Empty vials will be segregated into the appropriate dry solid containers and properly identified by isotopes and activity. Poured liquid will be segregated into the appropriate liquid container and properly identified by isotope, a reasonable estimate of the activity, and chemical composition.

   2. Organic - Vials containing isotopes with half-life >90 days ³H, ¹⁴C, etc.) and containing organic scintillation cocktail, and/or containing hazardous chemical waste not exceeding 0.05 uCi/ml will be accepted loose and do not have to be poured. Vials containing ¹⁰⁹Cd, ²⁶Cl, ²⁰³Hg, ¹²⁵I, ²²Na, ^32P, ³³P, and ³⁵S containing organic scintillation cocktail, and/or containing hazardous chemical wastes not exceeding the limits specified by HWMO are allowed and do not have to be poured.
      1. Remove vials from "egg crate" cartons and place loose into vial drum. Put carton in contaminated dry waste if contaminated and domestic waste if not.

      2. Ensure that the ³H and ¹⁴C vials are kept separate from the other nuclides.

3.9.5 Animal Carcasses

1. Animal carcasses which may contain radioactive materials will be separated from other radioactive waste and from other animal carcasses.

2. All animal carcasses contaminated with radioactive materials will be placed in watertight bags or wrapped and isolated from other wastes. Carcasses need not be individually wrapped.

3. Carcasses will be frozen.

4. All syringes, needles, knives, glass and/or other sharp objects will be removed before packaging.

5. Large animal carcasses may have to be stored in a special manner as prescribed by the RSO on an individual basis.

6. All packages of animal carcasses containing radioactive materials will be marked with appropriate radiation labels and identified to the isotope present and a reasonable estimate of activity.

3.9.6 Special or Unusual Waste

3.9.7 Disposal of Radioactive Waste

3.9.7.1 Removal by Department of Environmental Safety (DES) Personnel

3.9.7.2 Burial

3.9.7.3 Disposal into the Sanitary Sewer

3.9.7.4 Incineration

3.9.7.5 Final Disposal

3.10 Security

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