ML20149J904
| ML20149J904 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 07/31/1990 |
| From: | TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | |
| Shared Package | |
| ML19317C540 | List: |
| References | |
| PROC-900731, NUDOCS 9707290144 | |
| Download: ML20149J904 (106) | |
Text
{{#Wiki_filter:. O PROCEDURE MANUAL FOR THE USE OF RADIOISOTOPES AND RADIATION PRODUCING DEVICES OFFICE OF RADIOLOGICAL SAFETY TEXAS A&M UNIVERSITY July, 1990 ' g. i i p
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9707290144 970722 PDR ADOCK 05000059: c p PDR
INTRODUCTION-1. 1
- 2. RESPONSIBILITIES 2 I
2.1 RADIOLOGICAL SAFETY BOARD 2 2.2 RADIOLOGICAL SAFETY OFFICER 5 2.3 OFFICE OF RADIOLOGICAL SAFETY 6-2.4 SUB-LICENSEE RESPONSIBILITIES 7 3. APPLICATION FOR SUB-LICENSES UNDER 10 i UNIVERSITY BROAD LICENSE
- 4. i PULES FOR THE USE OF RADIOISOTOPES 11 4.1 ORDERING OF RADIOACTIVE MATERIAL 12 4.0 RECEIPT OI RADIOACTIVE MATERIAL 12 4 ~. 3 TRANSFERS 14 4.4 STORAGE OF RADIOACTIVE MATERIAL 14 4.5 !
TRANSACTION PROCEDURES 14 l 4.6 DISPOSAL 16
- 5. RULES OF PRACTICE 20
- 6. INSPECTIONS AND SURVEYS 23
- 7. SPILLS AND ACCIDENTS 24
- 8. PERSONNEL MONITORING 25
- 9. BIOASSAYS 26
'10. EMPLOYMENT OF MINORS 26
- 11. FIELD EXPERIMENT RULES 26 l
- 12. RESEARCH FACILITY 28 l
- 13. SURVEY INSTRUMENTS 28 i
- 14. RADIOGRAPHIC OPERATIONS 29
- 15. ANNEXES TO PROCEDURE MANUAL (List) 31 11 !
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TEXAS A&M UNIVERSITY I OFFICE OF RADIOLOGICAL SAFETY - 0 l PROCEDURE MANUAL FOR THE USE OF RADIOISOTOPES AND RADIATION PRODUCING DEVICES l l I
- 1. INTRODUCTION >
These procedures define the Radiological Safety Program and l the responsibilities thereof for Texas A&M University and support to designated parts of the Te::ss A&M University System covered by l letters of agreement. These procedures are to be followed by all University personnel, and.those personnel of other organizations utilizing University facilities or coming under the licensed n)' responsibility of the University who receive, possess, use, transfer, own or acquire any source of radiation or radiation producing device covered . by one or more of 1 the University Radioactive Material Licenses. j Revised July 1990 Page1 I
Tha Prasident of Texas A&M University, as tha rnsponsiblo , officor, has authorized the following organizational structure (Annex A) to ensure compliance with all regulations, controls and 4 l b) y safety aspects pertaining to radiation safety: establishment of a Radiological Safety Board (RSB), appointment of a University Radiological Safety officer (RSO),
- and establish a Office of i
Radiological Safety (ORS) with a professional staff to support j the University Broad License. ! The President of Texas A&M.Univer-sity or his designated representative may enter into' letters of agreement with other parts of the TAMU System. The function and responsibilities of these components are further explained in the j following text. i 4 1 ! 2.1 RADIOLOGICAL SAFETY BOARD l Members of the Radiological Safety Board (RSB) (Annex B) and its chairman shall be appointed by the President and shall serve until their successors are named. Board membership will normally include representatives from various user groups. Ex-officio members of the Board shall consist of a representative from each l i
! l j of the following groups:
i k University Systems Safety and Health office University Health Center University Office of Radiological Safety (Radiological Safety Officer) The Radiological Safety Board'(RSB) shall function as an overview board to the University Office of Radiological Safety. Revised July 1990 Page 2
It is directed to assist in the dnvolopannt. of guidelines and procedures as necessary to ensure compliance with regulations of the Texas Department of Health, Bureau of Radiation Control (BRC) and U.S. Nuclear Regulatory Commission (NRC) as they apply to the University licenses.
, The RSB shall serve as the sub-license approval authority for the Broad License.
2.1.1 Review of Sub-license Applications Three selected members of the Board shall review from the j standpoint of their safety analysis, and approve or disapprove all sub-iicense applications submitted by University per-sonnel or staff members of organizations covered by the Univer- l i sity license. The following educational, training and/or experience standards are established to satisfy sub-license requirements. A. Formal course in radioisotope techniques, B. One year of experience and training under the super-vision of a licensed staff member, or l C. Having held a Radioactive Material License issued by l the USNRC or an agreement state for similar work. D. A sub-license applicant may be exempt from require- ) ments of para. A, B and C if the requested material is
- 1. less than 100 uCi of 14 C or 3 H, or
- 2. less than 10 uCi of activity of non alpha emitter:
2.1.2 University Regulations The RSB shall assist the University RSO in the develop-ment of rules and procedures to ensure safe practices with Revised July 1990 Page 3
2.1. 3 - Appnals l The RSO may impose operational conditions, restrict !
! work, or require immediate termination of work in a radioisotope lO
(,/ laboratory or facility using radioactive material or radiation producing devices under a sub-license. Such situations could i result in a request by the sub-license for a waiver or exemption from existing regulations. In such cases the request will be ! reviewed by the RSB and a written reply of recommended actions s
- will be forwarded to the RSO and the sub-licensee.
) The RSB shall review items of non-compliance which may i } have resulted in a hazard to health and safety of individuals, g loss of equipment and/or facilities due to radioactive contamina-tion or conditions / situations which are in non-compliance with a-the Bureau of Radiation Control or USNRC rules, whichever are i applicable. The review shall include analysis of the actions i Q V taken by personnel of the ORS, and the individual sub-licensee. j Actions to be taken pertaining to such non-compliance activities {_ shall be presented to the sub-licensee. Actions required by the t ]. ORS to allow " exception to Rule" (should this be a viable ap-
.proach for the continuation of the work) shall be defined and
[ submitted for Board approval. The Chairman of the University Radiological Safety Board i shall forward a copy of Board actions to the University President .i or his duly appointed representative following review of viola-tions of severity level I and II. 2.1.4 Radiological Safety Program Evaluation The Board shall meet at least semiannually for the purpose Revised July 1990 Page 4 1
of being briofed on tha status of thm rcdiction cafety program. Tha agenda shall includa but not bn limitrd to tho following:
- a. changes of the Board membership
- b. changes of the ORS staff
- c. changes in regulations, policies, and procedures
- d. review of incidents or accidents
- e. proposed research programs
- f. future requirements of the ORS 2.1.5 Field Work i
Field studies involving the use of radioactive material require approval by the RSB. An experiment protocol shall be submitted to the ORS for review and then to the RSB for approval. Written approval must be received by the sub-license prior to the initiation of those field experiments. 2.2 RADIOLOGICAL SAFETY OFFICER CT O The University Radiological Safety Officer shall act under the authority of the University President and is charged to l direct the Radiological Safety Program for Texas A&M University I and supported agencies The Director of the Office of Radiological Safety shall be the RSO and shall be responsible for all administrative duties associated with this position. The University RSO is responsible for ensuring that a staff of professional health physicists and technicians is maintained and capable of performing the surveillance and administrative duties of the program. Revised July 1990 Page 5
1 of a budget which meets the fiscal rsquircmints of tha program . and is in accordance with fiscal directivaa. Such budgets shall G be presented to the administration with a full explanation of the requirements and expenditures. The RSO shall advise and assist University personnel in establishing educational and training programs. Safety aspects of experimental programs will be discussed with the researcher, with special attention'to those phases of the work which might lead to personal and environmental radiation health hazards. The RSO or his designee (s) shall be responsible to ensure compliance with all applicable rules and regulations and safe practices. The RSO is empowered to impose conditions of work, the restriction of work and the termination of work if sufficient cause is determined. h V 2.3 OFFICE OF RADIOLOGICAL SAFETY The Office of Radiological Safety shall 'oe the administra-tive office for the program. As such, the office shall serve as the depository for the following records, reports, and documents: 2.3.1 Texas A&M University NRC Special Nuclear Material Licenses, NRC By-product Material Licenses, Bureau of Radiation Control Radioactive Material License, and such other licenses or registration which the University may acquire. 2.3.2 Records of personnel radiation exposure for the University including NRC Forns 4(Annex D) or TRC Forms 21-2 and 21-3, re-spectively. V) Revised July 1990 Page 6 4
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1 radiation producing-devices. Thras sub-lictnssa are isnund and . amanded by.the ORS with approval by ths RSB/RSO and current
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copies of these are filed at the ORS. 2.3.4 Records of radioactive material accountability, inventor-ies and transfers, (Annex E). 2.3.5 Reports of surveys of the University facilities. 2.3.6 Reports of disposal of radioactive material, (Annex F). 2.3.7 Reports of incidents and accidents. 2.3.8 Reports of leak test of sealed sources, (Annex G). 2.3.9 Calibration reports. 2.3.10 Records of orders and receipts of radioactive material. The ORS shall also perform the necessary office and adminis-trative duties for the RSO and the professional staff. 2.4 SUB-LICENSEE RESPONSIBILITIES + {} A sub-licensee is at all times responsible for all licensed operations, training of personnel, procedures and techniques used in all laboratories operated under his sub-license. This respon-sibility extends to the actions of all employees, including employees and students performing work in these facilities opera-ting under the sub-license. To ensure adequate control of work with radioisotopes and definition of work responsibilities each sub-licensee shall main-tain a current list of radiation workers under his/her sub-license. A copy o'f this current employee / student worker / student researcher listing shall be sent to the ORS each September, January, and June. Revised July 1990 Page 7 1
'The sub-licensen is responsible for dnvolopment of proca- I dures specific to the experimental protocols used in his or her research.
Procedures should be in written form and revised as l necessary to be maintained current. In addition, safety aspects, do's and don'ts, and emergency responses should be included where applicable. Requirements for conducting and documenting postwork I and routine surveys of personnel and work areas should also be included in procedures, where applicable. General training for laboratory workers, including sub-licensees, is offered by the ORS twice annually. This training includes broad-based instruction on (1) radiation physics, units and terms; (2) radiation monitoring instrumentation, wipe test-ing, and decontamination methods; (3) applicable regulations, policies, and procedures; (4) general laboratory safety with regard to use of radioactive materials, emergencies, and spills;
.and (5) biological effects of radiation , internal vs external exposures, radiation risk vs benefit, and prenatal exposure.
As stated above, the primary responsibility for laboratory worker training rests with the sub-licensee. While the ORS training course is offered to anyone wishing to attend, any sub-licensee may conduct and document training for personnel in their laboratories. A copy of the outline used in the ORS course (Annex P) in included to provide a guide to the sub-licensee to ensure that all appropriate information is covered in personnel ,, training. Handouts used for the ORS course are available from i 4 the ORS to augment such laboratory training. { Revised July 1990 Page 8
a proccdures spccific to their facilitics and experim:ntal proto-l cols. An outlino is providad in Annnx Q which would be used by all sub-licensees to ensure that adequate specific training is V provided to all laboratory personnel. Appropriate training, both general and specific, must be completed prior to commencement of work activities involving radioactive materials. The sub-licensee shall maintain a file documenting internal , training of his or her laboratory personnel. Documentation should include subject matter, date of training and names and social security numbers of those in attendance. l l Each sub-licensee shall be required to acknowledge his/her I responsibility for the safe operation of all laboratories opera-ted under his/her sub-license in writing. The statement form shall be prepared by the ORS for signature and the signed form shall become a part of the sub-license records at the ORS. (]J It is the policy of the Texas A&M University Radiological Safety Board and the .. University ORS who administers the radio-active material broad Jicense under which Texas A&M University operates, that multiple-names on sub-licenses will not be autho-rized. This means that all permanent faculty and staff members using radioactive materials and who are qualified by training and experience should hold an individual sub-license rather than one group sub-license for a department or section. The basis for this policy is that the holder of a sub-license is held respon-sible by the RSO through the ORS for all activities under that sub-license, including ordering isotopes, record keeping, invan-tories, training of users on the sub-license, and adherence with (Q Revised July 1990 Page 9 LJ
safo laboratory procedures. If a single sub-licanso covers large I numbars of laboratories and users no single individual can effec- ' tively supervise the work.
) Sub-licensees who are planning to be physically una' ail-able to their laboratory facilities (e.g. out-of-town, vacations, conventions, consulting trips, or sabbaticals) shall be respons-ible for obtaining the assist.ance of another TAMU sub-licensee to 1
provide oversight for their active facilities and experiments during their absence. Sub-licensees shall also be responsible i for advising the ORS of their absence and the sub-licensee to be named as the responsible individual. 4 I I 3. APPLICATION FOR SUB-LICENSES UNDER UNIVERSITY BROAD LICENSE 2 A faculty or staff member of Texas A&M University or sup- ) ported agency may make application for a Sub-License author-izing the use of radioactive materials or radiation producing I \/ devices by preparing the University standard license application-form (Annex C) in duplicate and submitting these to the Office of Radiological Safety. The application will be reviewed by the l 4' 4 06::, staff to ensure all items are completed and adequate informa-tion is provided for a thorough understanding of the proposed a work. If personnel of the ORS are not familiar with the re-
- ferenced facilities, an inspection of the proposed work area will j be made. Inspection of the facilities should be documented via the Office of Radiological Safety Applicant Review Form (Annex 0). This form should be attached to the completed application for sub-license prior to review of the application by the Radio-i i
l 1 i (V3 Revised July 1990 Page 10 t i 4
then be forwardLd to tha RSB membLrs for tpproval or disapproval. RSB requests for cdditional information cra coordinated by the I
, Office of Radiological Safety staff. Application forms for sub-V) licensing are available from the Office of Radiological Safety upon request. Sub-licenses are issued for 2 years, and a written j renewal request is required for the continuation of the sub-license.
Amendments to sub-licenses should be submitted in writ-ing to the University Radiological Safety Officer (RSO). Re- l quests for amendments are acted on by the RSO, but if sufficient l change is noted from the work programmed in the original sub-license, then Committee approval may be requested. l
- 4. RULES FOR THE USE OF RADIOISOTOPES ALARA, As Low As Reasonably Achievable, is a concept which l
applies to minimizing doses received by any individual as well as l .O to releases of radioactive materials to the environment. Each k i GI individual must be aware of the need to keep his or her own ex-posures ALARA. Each sub-licensee must employ the ALARA principles of time, distance and shielding to reduce personnel doses when designing and conducting experiments. It is not the intent of these rules or other ORS actions to hinder efficient performance of the work. Rather, it is to emphasize the responsibility of each individual to do his part toward the protection of individuals and the institution through maintaining proper working conditions and records. This As Low As Reasonably Achievable (ALARA) concept shall be foremost in all decisions of the ORS staff. O Revised July 1990 Page 11 LJ
6y (Ebla ORS arn for the purpose of minimizing the hazards of personnel exposuro and exposure to contamination. There is an equally real, though of ten unappre-ciated, legal liability risk associated with the presence of radioactive materials on the University premises and the require-ments for the restriction of access, monitoring records, etc., are for the purpose of minimizing this risk. Safety in a laboratory using radioisotopes requires rigorous and careful observance of normal laboratory safety requirements, their common sense extension to fit the special case of radio-activity, and the important requirement that each individual be competent, informed, and responsible. i l 4.1 Ordering of radioactive material ! i Purchase requisitions for radioactive material shall be l l routed through the ORS for approval. i Upon receipt of the purchase requisition, the ORS staff will check the order against; I (1) the individual sub-license, and (2) the University license to ensure coverage. The material ordered will then be assigned a 1 code number called the RSO number which will hereafter denote the material in this individual radioisotope order. Phone orders for radioisotopes shall be cleared through the ORS prior to being placed. The procedures listed in the preceding paragraph apply to phone orders also. i 4.2 Receipt of radioactive material All radioactive material packages received during normal l working hours shall be surveyed, opened and inspected for damage and/or leakage within three (3) hours after receipt. If received i Page 12
- 'O Revised July 1990 l
process is oighteen (18) hours.
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Packages will be routinely delivered to the ORS or may be l delivered to a health physicist stationed at the cyclotron (A y Institute, the College of Veterinary Medicine, or other University facility properly staffed and trained. Delivery direct to sub-licensees or their facilities on the main University campus is not authorized and should it occur immediate notification of the ORS is required. Direct delivery to outlying facilities is authorized. Survey dose rate limits are 10 millirem per hour at a dis-tance of three feet from the exterior surface of the package, or 200 millirem per hour on the exterior surface of the package. Removable contamination surveys results from the exterior of the package should not exceed 0.01 microcuries or 22,200 dpm per 100 cm 2 area. I Should radiation levels in excess of those listed above be noted, the ORS shall immediately notify the final delivering i carrier and the Bureau of Radiation Control, Texas Department of j Health by telephone, telegraph, mailgram, or facsimile. In ! addition, the ORS will notify the sub-licensee ordering the I material and ascertain if they will accept a contaminated sample. The carrier will be notified when required by regulations. ! Two copies of RSO Form 4 (Reca c.t Notice) (Annex S) will be prepared. One copy of the receipt form will accompany this shipment when delivered to the researcher. A second copy will be placed in the material accountability file for input into the ORS computer inventory file. This copy is then filed in the Revised July 1990 Page 13
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6criaf iaceived". .._. _... _ .._ ___ - - -- - - - -- ~^R file after the materials ara delivered and ! signed for. Radioactivo material will be signed for by the sub-licensee or a representative of the sub-licensee upon delivery. A 4.3 Transfers V Transfers of radioactive material between sub-licensees will be reported on a RSO Transfer Form (Annex H) or equivalent. It is the responsibility of~the transferring sub-licensee to ensure that the receiver is properly licensed to receive said material. l Transferred material will maintain the initial ORS number assign- ; ed by the ORS. The ORS will assign an additional code number as needed. 4.4 Storage of radioactive material It is suggested that individual storage facilities be utilized by each sub-licensee for the storage of his/her radio- l active materials. When joint or common storage is used, each container of material should be clearly marked to denote the owner or sub-licensee thus ' reducing possibilities of accidental loss or misuse of materials. Storage facilities shall be proper- } ly marked with radioactive material and radiation level signs as appropriate. Each storage area, whether it be a cabinet, bench drawer, well, refrigerator, etc., shall be equipped with a lock-ing device or be located in a room which remains locked when un-occupied. 4.5 Transaction procedures Operations involving use of isotopes on a sub-licensee's inventory are usually receipts, transfers, liquid waste dis-posals, or solid waste disposals. All such transactions shall be Revised July 1990 P ;c 14
cach inventory item (RSO number). Form 14 clso makes provision , for "other entries." The heading should be filled out in full, giving the sub-license number, the name of the sub-licensee, the I v sub-licensee's department, and the applicable RSO number. "RSO No." denotes the number issued by the ORS to eacht isotope re-ceived. It is found on the receipt form for each radioactive shipment. When a waste pickup by ORS is made, total activity for each waste classification should be calculated and noted by the sub-licensee, and the pickup date should be entered. References to a particular entry should be made by transaction date in the comments section. The columns or entries are to be used as follows:
- a. Entry Dates This is the date a particular transaction occurred.
For example, the first date entered is normally the date of p radioactive material receipt. Additional dated entries indicate V individual sub-licensee uses and/or disposals to the sub-licensee's waste containers.
- b. Disposal Form The solid, liquid, anc vials columns denote the physical form of the material for which the transaction entry is made. Simply enter an "X" or check mark denoting the form.
"Other" denotes entries for disposal transaction forms other than those described above. The purpose of the "Other" entry should be designated here (e.g., an isotope may be removed from an inventory after it has decayed to safe levels by entering " decay" in this column).
Q Revised July 1990 Page 15
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.-. .. . . . _ _ . ._..._._.__._.._...__..._._-_..________......_..._____m._.
1- C. Comments
- This column ' may be used to d: nota the chemical compound, the volume of compound used, or any other "information which may be of use to the sub-licensee in accounting for the radioactive material.
- d. Amount Disposed
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This column simply allows entry of amount of radioac-tive isotope (in millicuries) disposed .of in the referenced 1 transaction. ! ] e.- Remaining " Inventory" dehoted the quantity of radio- ! isotope for a particular ORS number remaining in the inventory of-the sub-license following each transaction. Decay need not be , considered and the quantity should be in millicuries unless otherwise designated.. Each sub-licensee shall make a physical inventory of the radioactive material covered by his license upon ' receipt of the periodic ORS inventory printout. Such inventory - data is normally distributed quarterly. A copy of the
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inventory ' shall be returned to the ORS after being checked with corrections noted. ' A 4.6 Disposal Properly prepared radioactive wastes including solids, bulk liquids, vials containing liquids, and special forms of waste (e.g. animal carcasses) will be collected by the ORS on request. 4.6.1 Waste Segregation
- a. Solid waste is classified into two categories - '
short half life (such isotopes with half lives of less than 300 days) and long-half life (such isotopes with half lives greater r Revised July 1990 Page 16
scintillation vials. Syringes, sharp objects, broken gicsa, and 1 razor and scalpal bladas will be placad in eturdy boxas bnfore
- being placed in the solid waste drum.
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( b. Bulk liquid waste should be separated by isotope. Liquid waste is further classified by separating aqueous and non-I aqueous wastes in separate containers. Liquid waste classified as aqueous should contain neither hazardous chemical materials (e.g. toluene, organic based scintillation cocktails, chloroform, i benzene, etc), nor bichazardous materials. c. i Vial waste is defined as glass or plastic i containers with liquid.
- Vials less than 20 ml in size can be accepted as vial waste.
The 20 ml and larger vials shall be separated with the liquid contants bulked into liquid containers l and the empty vials disposed of separately. 1 d. Animal carcass wasta can be defined as animals or O animal tissues that have been injected with radioactive mater-V lais.
- Contact the ORS before wcrk is begun to determine options
- for waste disposal.
1 Conditions for the incineration of biological j materials (e.g. animal tissue or carcasses) containing radioac-tive material are stipulated in the University Broad License or in the regulations. No incineration of such material is author-ized without approval of the ORE. Waste which contains both radioactive material and { bichazardous material shall be autoclaved, bleached, or otherwise treated by the sub-licensee to eliminate the bichazards associ-ated with the waste. This must be done before the waste pickup Revised July 1990 Page 17 V
ferred method for-olimination of bichazarda sirtee this method dons not generato additional volumns of hazardous wasta. 1 The ORS must be notified in advance of all disposals of ( liquid and soluble radioactive materials to the University sewer system and disposal of radioactive gases by venting to the atmos-phere. Limits on concentrations of liquid and gaseous disposals shall be those specified in the current Texas Regula-tions for Control of Radiation. 4.6.2 Each sub-licensee shall maintain a record of all dis- j posals under their license, including the following information: i l
- a. Method of disposal
- b. ORS No. of disposed material
- c. Radioactive isctope involved i l
- d. Quantity disposed
- e. Date of disposal I 4.6.3 For the discharge of radioactive materials into the sanitary sewer system, the following conditions must be ful-filled:
- a. Prior approval of the ORS must be obtained.
- b. An accurate record of the disposal must be main-tained.
- c. The radioactive material must be readily soluble in water and does not contain any regulated hazardous materials.
- d. The gross quantity released into the sanitary sewer system of the University must not exceed (1) curie per year; this cumulative total is maintained by the ORS and applies to the Broad license. l p Revised July 1990 Page 18 V
' 'dischargsd into the sanitary sewar system shall not exceed con- . centrations listed in Appendix 21A. Tsxas Ragulations for Con-trol of Radiation; it shall be considered good practice, how-ever, to al?.x 4 i safscy factor of 100 in diluting liquids for disposal in order to ensure that concentration limits are not exceeded and to conform to ALARA principles. All dilutions shall 4 be accomplished as the liquid enters the sanitary sewer system (i.e., the dilution by University or building sewage volume flow 4 i shall not be considered). f
- f. The ORS shall be notified in advance of any dis-i ;
charge. Necessary data to be supplied to the ORS are location, i ! isotope, compound, quantity to be discharged, dilution or concen-tration of liquid as it enters the sanitary sewer system, and location, date, and time of proposed disposal. This notification i may be in writing and must provide sufficient advance notice to allow the ORS to take appropriate action in order to prevent j simultaneous multiple disposals of large quantities. Telephone 1 l notification is adequate as long as a record of same is entered on the disposal record. 1
- 4.6.4 Radioactive gaseous waste may be discharged into the atmosphere provided the following conditions are met
- a. A suitable record of the disposal must be main-l tained.
i 4
- b. The gas is dispersed through a fuma hood or a
} i suitable pathway which has been inspected by the ORS and the flow
- rate determined. (For some hoods, this data is posted on the j hood).
Revised July 1990 Page 19 )
. _ . . - - - - - - - ~ - - . - - - - - - ~ --- ~"-~~~~~~~'
- c. Concentration of the gassous wasto shall ba '
- l. diluted to values that are less than those listed in Appendix ;
21A. Texas Regulations for Control of Radiation. The licensee ' i shall make every effort to ensure that the release is at a steady rate in order to obtain maximum dilution and dispersion. d. The ORS shall be notified in advance of any re-lease. Necessary data ' include: location, isotope, compound, quantity, dilution of effluent, flow rate of fume hood to be l used, rate of release of the isotope into the fume hood, and date and time of the proposed disposal. Notification me.y be by the l telephone or in writing but either must be sufficiently in advance of the disposal to allow appropriate action by the ORS. I A record of telephone notification shall be a part of the sub-license disposal records. i
- 5. RULES OF PRACTICE All radiation areas requiring special markings and control-led access will be denoted in accordance with the BRC Regula-tions. More specifically, for restricted areas, radiation areas (dose rate of >5 mrem /hr or a total dose >100 mrem in five !
consecutive days) will be marked with a " Caution Radiation Area" $ sign in accordance with appropriate regulations. High radiation areas, that is those areas in which the total dose could exceed 100 mren in any one hour shall be marked and controlled as required by BRC regulations. In unrestricted area (areas outside the control of the sub-license or where access is not controlled for the purpose of tG Revised July 1990 Page 20
%)
tiva material) radiation Icydis shall not ba parmitted to excacd - 1 any of the follcaing:
- a. 2 mrem in any one hour kJ b. 100 mrem in any seven consecutive days (168 hrs) or l
- c. 500 mrem any any one year i
- Any laboratory, room, or facility in which airborne radio-4 active material exists in concentrations exceeding those denoted l by TRC Appendix 21A Table 1, Column 1 or, if averaged over the number of hours in any week during which a person occupies the area, exceed 25% of the specified limits of TRC Appendix 21A Table I, Column 1, shall be posted with an " Airborne Radio-activity Area" sign.
b j All laboratories, rooms, and facilities in which radioactive , materials are stored, or used, shall be marked with " Caution Radioactive Materials" signs. Notice to Employees signs TRC 21-1 shall be posted in each C lab or sub-license facility in sufficient number so that they may be easily observed by personnel of that facility or lab. i Notices and signs are available from the ORS . Inspections by personnel from the ORS will ensure proper posting of signs and notices. Such general information signs as listed below shall be posted at the discretion of the ORS: Exclusion Area Film Badge Required Controlled Area No Smoking, Eating, or Drinking Area Revised July 1990 Page 21
._ ~ -- . . . - . . . -. - - _ - . . . - . -.
Emnrgency Responso Notice Protective clothing such as lab coats or aprons should be ' \ a worn when working with unsealed sources of radioactive material. ! h1 v Protective apparel such as lead lined aprons may be required under some conditions. Rubber or plastic gloves shall be worn i anytime unsealed radioactive material is handled. Use of respiratory protection equipment may be required by the ORS under certain conditions. Handling of radioactive materials will be by
- mechanical means (e.g. tongs) whenever possible to minimize hand 1
- exposure. Mouth pipetting of radioactive material will not be j tolerated.
j Any work with radioactive material likely to generate dusts i ! or vapors shall be performed in adequate fume hood, or glove boxes unless other safety procedures have been established and have been shown to eliminate the airborne problem. I J l NO FOODS OR BEVERAGES ARE TO BE PREPARED, STORED, OR i $ CONSUMED IN ANY RADIOISOTOPE LABORATORY WHERE UNSEALED 1 6 RADIOISOTOPES ARE USED, STORED, OR HANDLED. This shall include, 4 l but not be limited to candies, gums, and smokeless tobacco. l Facility. directors are requested to designate separate rooms for this purpose. Hands should be thoroughly cleaned prior to eating following work with radioactive materials. No smoking will be permitted in areas where unsealed radio-
. isotopes are used, stored or handled.
Maintenance and custodial personnel shall be instructed as to what areas may be worked in and under what circumstances. Each lab director or sub-licensee is responsible to ensure that Revised July 1990 Page 22
_____n_______ sp;cial labs. l
- 6. INSPECTIONS AND SURVEYS O
Routine unannounced visits are made to the laboratories by health physics personnel. In addition to the inspection visits the ORS will normally make a contamination survey each month in each sub-licensee lab. These surveys are for the ORS official records and do not relieve the sub-licensee of his or her re-sponsibility of timely checking for contamination and maintaining a clean lab. Radiological Safety Office survey reports are filed at the ORS. Copies of these reports are not routinely sent to the sub-licensee unless contamination levels in excess of allowable limits are detected. Upon detection of such conditions, copies will be made for the sub-licensee to aid in the decontamination process. Limits of contamination which are
]
w' normally considered acceptable are given in Annex I. Routine surveys conducted by the ORS do not relieve the sub-licensee of the responsibility of performing routine surveys of the laboratory and postwork surveys of work areas. The frequency of the routine surveys should be commensurate with the radioac-tive material work performed in the lab. Work areas found to be contaminated should normally be cleaned with soap and water and resurveyed. Contamination levels must be reduced to those found in Annex I or below. Surveys must be documented and be main-tained on file for inspection. Post-work surveys must include personnel contamination surveys (not required if only H-3 used). If personnel con- [] Revised July 1990 Page 23
%.J
tamination(s) are found, refer to applicablA portion of emargency procedures (Annex R). Outlying facilities will be visited on an "as needed" basis. The schedule of visits will be based on the hazard associated with the activities at the off-campus use sites. A guide to the schedule to be developed will be the inspection frequency of TRC Part 11 Appendix 11-C. < Incidents actual or suspected shall be immediately investi-gated by ORS staff personnel.
- 7. SPILLS AND ACCIDENTS Emergency notification of the ORS staff is made by calling 845-1361 during normal working hours,and 845-4311 after hours and on weekends. This is the emergency number for the University and a Health Physicist's assistance should be requested. Emergency procedures are included as Annexes Q and R. A copy of the O ~
b appropriate emergency procedures should be posted in each laboratory where radioactive material is used or stored. The ORS should be immediately notified of spills or 1 accidents. Primary responsibility for cleanup of such spills rests with the sub-licensee. Special equipment and clothing are available and ready for immediate use through the ORS. The personnel of the ORS will advise and assist the sub-licensee in decontamination, and should it be indicated, ORS personnel will take direct charge and perform the decontamination. The sub-licensee should ensure that his/her lab personnel are available to assist in the decontamination of the facility. Revised July 1990 Page 24
suitablo personnal monitoring drvices ara cupplied by thm , ORS to all University employces for whom their usa is required. p To receive dosimetry, an individual must complete a Request for Dosimeter Service form (Annex J) and return the completed form to the ORS. Additional monitoring devices may be employed as directed by the ORS, e.g. pocket dosimeters (ion chambers) and in-house TLD badges - each being capable of yielding immediate personnel dose data. Personnel dosimeters may not be required for some indivi-duals working in laboratories in which 3 H and/or 14 C are the only radioisotopes used, stored, or handled. These radioisotopes emit low energy beta particles which are not capable of being moni-tored by available personnel dosimeters. However, this determi-nation should be made by the Staff of the ORS rather than by the sub-licensee. O \,._/ When an employee suspects an overexposure, he/she should immediately report this to his superior and to the ORS. The employee's dosimeter will be immediately sent for processing and a phone report returned upon analysis. The employee shall not engage in activities that mignt in any way cause him/her to receive additional exposure until the special report is received. Any individual has the right to review his or her own radiation exposure records and is encouraged to do so. These records are maintained at the ORS and are available during normal { working hours. Upon employment termination, final reports of exposure will be prepared for the former employee (Annex K). Lost badges and p Revised July 1990 Page 25 v
1 Guida 5.7 (Ann x L). 9
- 9. BIOASSAYS v) Bioassays will be performed by personnel of the ORS in l
accordance with the conditions of the University License or when i ingestion of radioactive material is suspected. (See Annex M for bicassay procedures) i
- 10. EMPLOYMENT OF MINORS !
Employment of minors (persons under 18 years of age) is not recommended by the ORS. Should, for some reason, a sub-licensee insist that a minor be employed in his lab, a letter of authorization must be on file at the ORS, signed by the parents
- or guardian of the minor that they are aware of the type of work 1
being performed, and stating under whose supervision this work is l (n) %J being performed. These conditions shall also be imposed on high school students engaged in summer institutes at licensed facili-l ties where potential for radiation exposure exists. Exposure limits for minors are listed as 1/10 that of adult radiation workers in the TRC Regulations (21.104). l
- 11. FIELD EXPERIMENT RULES Use of radioactive material in field experiments (exclusive of soil moisture and density gauges) are restricted as follows:
In order to use radioisotope in field experiments it is neces-sary to submit to the ORS an application with the following information: (this information will be submitted to the RSB for I.3 V J Revised July 1990 Page 26
approval). L
- a. A full dnscription of thn distribution of the human '
population and livestock population in and near the experimental l area.
- b. A statement concerning the relationship of the experi-l mental area to watersheds from which domestic water supplies are collected, together with a topographic sketch of the area.
- c. A description of the underground strata with reference l
to the likelihood of movement of water and fixation of activity by mineral components.
- d. A statement regarding the degree of control which can and will be maintained over the experimental area.
In addition to the requirements of Section 1 above, the RSB will require assurance that the following will be complied with before permission to conduct field experiments is given:
- a. All experiments involving the use of radioactive
\ materials in plots or fields will be carried out on land under the immediate control of the Universicy except as follows. If it is essential that land other than that owned or controlled by the University be used, an " agreement," duly signed by appropriate University authority and landowner, and definite description of l i
the site must be forwarded to the ORS before the experiment is undertaken. I l b. Plans must be agreed upon for restricting access to and marking of plots in which the radioactive material is used.
- c. The crop and wastes from the radioactive portions of the l
plot must be removed and stored or disposed of in accordance with
-- ( Revised July 1990 Page 27 I
- d. Undtr no circumstances will th3 crop ba psrmitted to
- 3. enter an animal or human food chain.
- 12. RESEARCH FACILITY The Cyclotron Institute operates under the regulatory con-trol of the Texas Bureau of Radiation control program. All aspects of isotope production, beam production, target handling and laboratory safety within the facility will be in accordance J
with TRCR Regulations and internal procedures of the facility. Procedures for operation and control are stated in. the Safety Manual of the facility. i 4 l' 13. SURVEY INSTRUMENTS i Each laboratory or facility in which radioactive material is utilized shall have available a survey instrument capable of p\_/ detecting the radiation emitted by the radioactive material in use '(tritium excluded). This instrument shall be utilized to detect contamination on personnel and within the facility. Facilities in which gamma or neutron emmitting material are used should have available instruments capable of reading dose rates in the range producible in the accessible areas of the source. Ion chambers will normally be used for gamma dose rate measure-ments whereas the standard BF 3 or boron-lined detectors or neutron sensitive scintillators will normally be used for neutron detection. Calibration of survey instruments will be performed by ORS personnel or other qualified individuals. This office has the capability of calibrating most GM, ion chambers and neutron A Revised July 1990 Page 28 V
cnnuclly. Tha ORS is not responsiblo for th3 lumintrnanca and rspair of survey instrunnnts and is not staffed for this service. l It is the responsibility of the sub-licensee to ensure that his survey instruments are properly maintained and submitted to I the ORS in operable condition for calibration. 1
- 14. !
RADIOGRAPHIC OPERATIONS l Procedures for the safe use and operation of X-ray equipment shall be in accordance with Parts 31, 32, and 34 of the Texas Bureau of Radiation Control Regulations. General operating procedures are contained in the regula-tions and are listed below for the types of installations in use at University facilities. Specific operating procedures must be posted and available to all X-ray equipment operators. X-ray equipment shall be p operated by individuals adequately instructed in safe operating d procedures and competent to safely use the equipment. Only those persons whose presence is necessary during the axposure shall be in the radiographic room during the exposure, and they shall be equipped with protective devices if they must work close to the useful beam. The useful beam shall be restricted to the minimum size possible to perform the desired exposure. Personnel monitoring shall be required for operators and personnel working in the radiographic room. Monitoring devices will not be worn under protective clothing. Monitoring devices shall be worn at the collar outside of the protective clothing. Operators of X-ray equipment shall utilize barrier shields or Revised July 1990 Page 29
raa %Wir raEaY1on exposure. In facilitics whero the controls are separated from the tube ' ' housing , a visual check . will be made prior to each n exposure to ensure all persons not required therein have been O cleared from the radiography room. X-ray units shall not be left on and unattended. Operators shall be present at the controls during all exposures. Protec-tive gloves and aprons shall be worn when using portable units. Care shall be taken to keep one's body out of the useful (primary) beam when holding animals or cassettes. Regulations applicable to use of diagnostic and therapeutic x-ray equipment are found in Part 32 of the Texas Regulations for Control of Radiation (TRCR Part 32). Regulations applicable to use of analytical x-ray equipment are found in TRCR Part 34. O V l l l Revised July 1990 Page 30
,. _ _ _ _ . . _ - . . _ _ _ _ _ _ _ . . . . . _ _ _ _ . . . . _ . . . . _ . _ _ _ _ . . _ , . . _ ...___..__...._..._m.
,. ANNEXES TO PROCEDURE MANUAL { $~
- i 1 l i '
! A. NEW ORGANIZATION CHART i B. RADIATION SAFETY BOARD MEMBERSIIIP LIST C. LICENSE APPLICATION 4 D. NRC -FORM 4 I I.
E. SAMPLE PRINTOUT OF INVENTORY l t 4 F. DISPOSAL FORM G. LEAKTEST FORM H. TRANSFER FORM i ! I. CONTAMINATION LIMITS J. FILM BADGE REQUEST FORM 1
- K. TERMINATION EXPOSURE REPORT L
L. DOSE ASSESSMENT FORM p M.- BIOASSAY PROCEDURES i N. APPLICANT REVIEW FORM l O. RADIOISOTOPE HANDLING-AND PROCEDURES TRAINING l P. INSTRUCTION' GUIDE FOR LABORATORY-SPECIFIC TRAINING FOR 4 RADIOISOTOPE OR RADIATION. WORKERS i j Q. _EMERGENC.Y PROCEDURES FOR RADIOGRAPHIC AND TELETHERAPY i' OPERATIONS ' R. EMERGENCY PROCEDURES FOR LABORATORY PERSONNEL
-S. RECEIPT FORM
!- l ( l I l
- - Revised July 1990 Page 31
)
- , + -
ORGANIZATION CHART - TEN AS A&M IINIVERSITY l l PRESIDENT (~T Dr. Ray M. Bowen j Y INTERIM EXECUTIVE VICE PRESIDENT AND PROVOST FOR
.- AC ADEMIC AFFAIRS Dr. J. Charles Lee VICE PRESIDENT FOR RESEARCH j AND ASSOCIATE PROYOST FOR GRADL' ATE STUDIES Dr. Robert A. Kennedy i OFFICE OF RADIOLOGICAL SAFETY AD\11NISTR A TlON ,
ADMINISTRATIVE DIRECTOR RADIOLOGIC.\L I l ASSISTANT Dn. Milton E. McLain SAFETY BOARD (')nis. Debbie K. Adkins f Dr. Michael % alker ASSOCIATE DIRECTOR Chairman Mr. Christopher TI. Meyer OFFICE OF RADIOLOGICAL SAFETY OPERATIONS CYCLOTRON INSTITUTE CAMPUS OPERATIONS MEDICAL PROGRN.lS SENIOR HEALTH PHYSICIST SENIOR IIEALTH PilYSICIST SENIOR HEALTH PilYSICIST Mr. Daniel I. Menchaca Mr. Douglas A. .lohnson Mr. Keith E. Carsten HEALTH PHYSICIST TECHNICI AN I Mr. Luis U. Rodriguez Ms. Latha Vasudevan ni:usi:i) .spni tw3 c.1xacs wonim ons oncesian i tx c { t G'
ANNEX B RADIATION SAFETY BOARD l MEMBERSIIIP Dr. Michael Walker Chairman Vet Radiology Dr. Milton E. McLain Ex-omcio Omce ofRadiological Safety l Dr. Julius W. Dieckert Ex-omeio Poultry Science Depanment ) Dr. Kenneth Dirks Ex-omcio Beutel Health Center : Dr. . Harry Stiteler Ex-omcio Systems Safety & Health ! Dr. J. Warren Evans Animal Science Department Dr. John A. McIntyre Physics Department Dr. John W. Poston Nuclear Engineering Dept Dr. Richard P. Schmitt Chemistry Department I I Rensed 4 95 C. demord nb-hst O'
~ . . . ..~.. . -. .-. . - - .- .. .
~ -- . - ~ ~ .- ~
- - - - . . 's- - --- - - -
Sept 1991 1 TEXAS A&M UNIVERSITY OFFICE OF RADIOLOGICAL SAFETY
- COLLEGE STATION, TEXAS 77843 3261 i
Application for a Permit for the Use of Radioactive - Material and Radiation Producing Devices at Texas A&M University i. Instructions: The completion of this form is required by all persons planning to use radioactive material and/or ' radiation producing devices at Texas A&M University. Only upon notification of approval of this application will work with radioisotopes and/or radiation producing devices be permitted. Questions in this regard should be directed to the Radiological Safety Oflicer. Original and one duplicate copy are to be completed and sent to the Office of Radiological Safety for approval.
- 1. Name, campus address, and telephone number of applicant (department, service, group, bldg. and room No.h 3
1 2.~ Address at which radioisotopes and/or radiation producing devices will be used (if different from department address given in question No.1):
/
l
- 3. Individual user (name and title ofindividual(s) who will use or directly supervise the use of the radioisotopes and/or radiation producing devices. Include names of technicians and students.):
l 1 1-
- 4. Previous Licenses or Permits held: USNRC, Agreement State, or University:
- 5. Radioactive material and/or radiation producing devices for which authorization is desired. (Give <pecifica-tion producing devices.):
v
- 6. Chemical and/or physical form of radioisotopes:
1 A V '
- 7. Maximum amount of radioactivity for each radioisotope, in millicuries, that you wish to possess at any one time:
- 8. Statement of use. (Describe the purpose for which the radioisotope and/or radiation producing device (s) will be used. If irradiation services are desired. state in detail if toxic compounds will be used and whether volatile materials will be involvedJ Use additional sheets, if necessary:
l 1 O
- 9. Describe procedures which will be used to minimize hazards from handling and storage of the radioactive material and control of radiation producing devices: 3 1
- 10. Statement of Training and Experience. (Include training in the field, isotope handling experience and the activity of material worked with, and the type of work performed.):
v)
- - . . _ - . -.- -. _ . =
- 11. Radiation .:urvey instruments. (List the type and number of survey instruments available, radiation detected by said instrumenLt and the sensitivity and range. Include specific location of monitoring instruments with respect to work area:
(*%
- 12. Facilities. (List the available facilities that will be used in this work, including working areas. fume hoods, storage areas, etc. Draw a detailed sketch of the facility and include it with this application. Use additional sheets if necessary.):
- 13. Describe radiation survey procedures and methods oflocating contamination:
p., J l
- 14. Signature of applicant:
i l (Signature) (Please pnnt or type name) (Title) PLI 3 RETURN COMPLETED FORhtS (in duplicate) TO THE OFFICE OF RADIOLOGICAL SAFETY, M .bma.61.
TO BE COMPLETED BY TIIE OFFICE OF RADIOLOGICAL SAFETY: . Date received by O.R.S. [^J\te
% referred to review committee Action of review committee hiember, review committee Comments hiember. review committee Comments hiember. review committee Comments (N,s A&M University Permit Number issued on \
ior) (milli)(micro) curies of (milli)(micro) curies of (milli)(niicro) curies of for radiation producing devices Notification of approval by O.R.S. Permit Conditions: l'~ b) Permit review date: (two years from date ofissuance)
U o TRC Form 21-2 PAGE OF (19934 l AGEtlCYl RADIOLOGICAL. SAFETY OFFICE CUMULATIVE OCCUPATIONAL EXPOSURE HISTORY h s Am unimmy College Station, Toxos 77843-3261
- i. NAM a ASr. ,tRST. uiDDiE IMnAu 2toENnnCAnONNUM.ER 3.Em ,y, ,g.,,o,,,,,,
4.SEK G . MONf TORING PERIOO ~ 7 tlCENSEE OR REQiSTRANT N AME F E M Al f 8 itCENSE OR REGSTRATION NtMBER
- 9. RfCORD 10. 8 0tJTINf E S tim A T E It. DOE 12 tDI I3 SOE. WB 14.SDE.ME NO RECORD PSE 15.CfDE 18.CDE 17.TfDt t3.TODE 8 MONtTORINO PfR100
- 7. LICENSEE OR REGISTRANT NAM {
- 9. LICENSE OR REQSTR ATION NUM8fR g RECORD 10. ROUTINE E S T'M A T E 11.00t 12 LDI NO RtCORD 13 SCE. WB 14 SDE. ME PSE 15, CIDE le CDE ti.TfDt IB.TODE 8 MONITORING PERIOD
- 7. LICfNSEE OR REGISTRANT N AME
- 3. tlCENSE OR REGSTRATION NUMBER S. PECORD 10. RotJTINI EST:M AIE 11.DDE 12 LDt NO RECORD 13 SDt. WS 14. SDE. ME PSE
- 15. CEDE 18 CDE 17.TEDE te.TODE e MONITORfNQ PEMOO F. tlCENSf f OR REGISTRANT N AME e LICENSE OR RIGISTRATION NUMBER g pfCORD 10. RotJ71NE E S TIM AT E 31.DDI 12.tDE 13. SDf. WB NO RECORD PSI
- 14. sot. ME 15. CEDE 10.CDt 17.TfDE 12.TODI S. MONtTORiNG PENOO
- 7. LICENSEE OR REQSTRANT N AME 3.teCENSE OR REGISTRATION NUMBER g, gggggg gg, ggg;ygg ES TIM AT E 18.DDE 12.LDE 13.SDE.WB NO RtCORD PSE
- 14. SOE. ME 15. CIDE 1s.CDE 17. TEDE 18. TODE
- e. MOMTOR'NG Pf RIOD 7.11CENSEE OR REGSTRANT NAME
- 3. LECENSE OR REGISTRATION NUM8f R
- 9. RECORD 10. ROUTINI ESTM AT(
II.DDE 12. LDE 13 SDE. WB 14.SDE.ME NO RECORD PSE 15.CIDI 14.CDE 17.TEDE 18. TODE 19 SIGN ATURE OF MONITORED tNDevtDUAt 20 DATf SIGNED 2 5. CER TIFYING ORGAN!ZATION
- 22. StGNATURE OF DIStGNEE
- 23. DATE SIGN (D
Licensa No.: Date: 05/09/9C Nama: ddress: TAMU RADIOLOGICAL SAFETY OFF. g~s COLLEGE STATION , TX 77843 Phone: 409-845-1361 i
\
A Licensed Materials: Amounts: Lic. Mod. ( mci / KG/MG ) Date: 3-83 100.0000 - 133XE 100000.0000 - 60C0 6000000.0000 02-88
-137CS 20000.0000 -
3H 0.0100 - 241AM 1500.0000 03-88 226RA 25.0000 03-88 RSO
- Date Isotope mp L/S Amount INVENT-'
R/D/T 0104 ( mC i / KG/MG ) 0 TRAN. 01-01-70 60C0 -NSC 207000.0000 R 20700C.; : THE AMOUNT ON HAND DECAYED TO TODAY 'S DATE IS 14144.1423 0 41 01-01-70 60C0 -OCDM (CYCLO.) 30.0000 R 30.::: THE AMOUNT ON HAND DECAYED TO TODAY'S DATE IS 2.0499
/~71 01-01-70 137CS -NSC 1000.0000 R 1000.00:
() THE AMOUNT ON HAND DECAYED TO TODAY'S DATE IS 624.6791 1156 10-15-70 13 7CS -NSC 10000.0000 R 10000.0C: THE AMOUNT ON HAND DECAYED TO TODAY'S DATE IS 6361.3164 2686 01-05-77 36CL -STD 0.1000 R 0.'-~ ! THE AMOUNT ON HAND DE AYEC TO TODAY 'S DATE IS 0.100C 967 01-05-77 997C -STD 5.0300 R 5.;2: THE AMOUNT ON HANC DECAYE TO TODAY 'S DATE IS 5.0298 10568 08c13-86 99TC - 0.0540 R 0.054 THE AMOUNT ON HAND DECAYED TO TODAY'S DATE IS 0.0540 DNT01 03-07-88 241AM -SEALED SOURCE 1000.000C R 1000.000 THE AMOUNT ON HAND DECAYED TO TODAY 'S DATE IS 996.5291 O
WASTE DISPOSAL REPORT FORM l Otope: Licensee: License No: V RSO#: onsconu14 nui m l Starting Amount (in mci): Entry Date Disposal Form (in mci) Amount Remaining Comments Disposed inventory "U- Animal Solid Liquid Vials (mci) (mci) Carcass J 1 2 3
-l l
5 S. l 6 i s 7 8 9 l t 10
- yt Te 13 14 15 16 Disposal: l l Certification of chemical composition for bulk liquid wastes and/or vial wastes listed above.
Chemical Cogituents
, Concentration (specify units)
' icensee (or designateo) signature Ponteo Name Date Neste Pickup Dy ORS: ') ate: By: Page of C3 DOCS \XLioRSFM14.XLS
WASTE CISP:DSAL REPORT FORM ' P 'o (+ ,) pe: 36 $ Ucensee: k%/f 6. kJe. Ucense No: b29 RSO#466Y~h OR FORM 14 Rev 10f94 StartinQ Amount (in mCD: .3 h h Entry Date Disposal Form (in mci) Amount Remaining Comments Disposed inventory
"' nimal ,
Solid Liquid Vials (mCO (mCQ Carcass
' #lMI96 01 02 2
030 .659 l Bldh< - ots . oss . ogo .z89 3
$G/4f .009 . ILO
./O9 4
.I15D ll2dl4S COI O/ .O// 16,9 s
zlwle .cos .oee . Ora, . Jos
? Il26l45 OI .D2 7
.OSo . O ?.3 Gy )qq- .pjg .03 5 . O Sg ,9g5 8 S/g//jf . 00 3 ,oE
.OE3 C-9 10 11
.)
13 14 15 16 i sposal: %//g/Qgl ,.p Y l .Z hh l_ _ . . ... l '...,n., . . . . . ' __ _ .12 .. ;
~
..J.3 f, h.~.._ ..h Cemfication of chemical comoosition for bulk licuid wastes and/or vial wastes listed above.
Chemical Constituents l Concentrat:0n (specify units) 4DTi2 Q-n mnw m s 0 7n a'
$ 6sr>/1, v' $}r ,Y
'nsee (or cesignateo) signature b4/8/A?s1 0/A7// S Pantea Name
$/0/9f Date ite Picxup cy ORS:
, . ;.,. ; .c . ;:, ., g,;,g .
n _ . . . .- . . . . .....u... _ B1 L -==. =....g..g ,
,.g g .g.g ,., .7.q..gg',-p ... ,,
. =-. U -. . '" ~ .-
. . .<- : .~.
Page / of ad C UUORsFM14 XLS
- l 1. Sublic-aNo. j i
ji Descriptive location of source stomge: 3. Deparrmerre-4 ,.aildine Room i
- 4. Sublirmee- l i
- 5. Name ofni** cone j
- 6. Phonenumber(s): _
(use this block for ndA! tin _a=1 r===drA j Isotope Activity Isotope Activity Isotope l Activity ) j Manufacturer SIN of source Manufacturer SIN of source Mamem ner SIN of sourc t j --
- In. w S/N Instrument S/N f= % sm Source DPM %eff Source DPM %erY Source- DPM %eff MDA(pCI)
MDA(uci) MDA(gCI) Cnt rnrmn=rion(pCI) C.~. ... . .lon(gCI) 1 Conenmmation( Ci) 'r Initials Review Datednitials Review _ Date4mnals Review i-_ -t S/N Instrument i= S/N w S/N Source DPM %eff Source DPM %etT Source DPM %erT M D A( Ci) MDA(pci) MDA(gCI) Contammnrion( Ci) Conenmmarion( Ci) _ Cantummarian(pCi) 3 ate / Initials Review Date/ Initials Review Date6mriale Review ! nstrume.nr S/N Instrument S/N I- S/N I i ource DPM %eff Source i DPM %eff Soince DPM %eff fDA( C1) , MDA( Ci) MDA(gCI) i onrnmmation(pCi) Conenmmnrion(pCI) E- - = =:on(pCI) , atednitials Review Date/ Initials Review Datednitials Review strument S/N Instrument S/N Is.= h S/N
<urce DPM %eff Source DPM %eff Source - DPM 5eff DA(pCi) MDA(pCi) MDA(pCI) maation(pCi) Conenmmation(pCl) Contannnation(pCI)
Review Datednitials Review DatdInitials Review
!OTICE: The contammarion limit is 0.005 C1. .eierence: Reg. Guide 5.1. TRCR 11.- File: 1.eadest Cet
1 RADIOACTIVE MATERIAL TRANSFER FORM !o MATERIAL TRANSFERED FROM: 1 Sub-Licensee Name 4 i Sub-Licensee Number Date of Transfer RSO Number Was this material originally transfered to you from another Sub-Licensee? Yes No if"Y", please give the name of the Sub-Licensee, and the date. from which the material j-was originally received. Isotope / Compound Quantity of Material Transfered (uCi, mci) 4 MATERIAL TRANSFERED TO: Sub-Licensee Name i l Sub-Licensee Number RSO Number (Office Use Only) ! 1 APPROVAL SIGNATIIRES: Sub-Licensee "FROM" Sub-Licensee "TO" croocs won 06ons iso rnaxs o<x-
ACCEPTABLE SUFSACE CCITIAMINATION LEVELS NUCL2 dea AVERAGEb f MAXIMUMbdf REMOVABLE bcef U-nat, U-235, U-238, and 5,000 dp= alpna/ 15,000 dp alpha / 1,000 dp= alpha / tssociated decay products 100 c=2 100 c=2 100 c=2 except Ra-226, Th-230, Ac-227, and Pa-231 Transuranics, Ra-226, 100 dp=/100 =2 300 dp:/100 c=2 20 d p/100 c=2 Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-129 Th-nat, Th-232, Sr-90, 1,000 d:=/100 =2 3,000 dp:/100 c=2 200 dp=/100 =2 Ra-223, Ra-224, U-232, I-125, I-126, I-131, I-133 Bata gmm e=i:ters (nuclides 5,000 dp= be:a, 15,000 dp= beta, 1,000 dp= be:2, with decay modes other than ga ca/100 =2 ga::ra/100 c=2 alpna e=tssion or spontaneous E m /100 c=2 fission) except Sr-90 and others noted above. 4here surface conta=ination by both alpha and beta gn==a e=i::ing nuclides exists, the li=its established for alpha and beta ga==a e=i::ing nuclides should apply independently. b As used in this table, dp= (disintegra:i:ns per =inute) =eans the rate of e=ission by radioac:ive =aterial as deter =ined by corre::ing :ne ccants per =inute observed by an appropriate detector for background, ef ficien:y, and gec=etri: factors associated witn :he l ins t ru=en ta tion. l C Measure =ents of average conta=ina: ion level snould not be averaged over =cre than one scuare
=e te r. For objects of less surface area, :ne average should oe derived for eacn object.
d Ihe =axi:su= conta=ination level applies :o an area of not =cre than 100 c=2 8 Th2 amount of re=ovable radioac:ive =sterial per 100 :=2 of surface area should be deter-mined by wiping that area with dry fil:er or sof: absorbent paper, applying =oderate pr2ssure, and assessing the a=ount of radioac:ive =sterial on the wipe with an appropriate ins tru=ent of known efficiency. Wnen re=ovacle centa=ination on objects of less surface area is determined, the pertinent levels sneuid be recuced proportionally and :ne entire surface should be wiped. I Th2 average and =axi=u= radiation levels asso:iated with surface conta=ination resulting from beta ga==a e=itters should not exceed 0.2 = rad /hr at I c= and 1.0 = rad /hr at I c=, respectively,
., m
=easured through not = ore nan 7 =illigra=s per square centi =eter of :ocal
/ sorber. L]
2/94 ANNEXJ l l TEXAS A&M UNIVERSITY OFFICE OF RADIOLOGICAL SAFETY ; REQUEST FOR DOSIMETRY SERVICE i
'c complete Sections I and II. Return completed form to the OfIice of Radiological Safety, TAMU, College Station. TX 77
- 61. Any questions. call (409) 845-1361 (FAX: 845-1348).
SECTION I: PERSONA L TNFORMATiON (please print or type) Full Name: Last First Middle (Maiden) Social Security Number: (If you do not have a SSN, please notify this office as soon as you receive one.) Date of Birth (Month / Day / Year): Sex: M F Permanent Address: License Holder (Name of Your Employer. NOT TAMU): TAMU Department: Pan 22.13 of the Texas Regulations for control ofRadiation requires that a report of radiation exposure be furnished to each individual aher termination of emplovment or association involving exposure to radiation. Please list an address where such a will reach you upon termination of employment. (If same as above. indicate SAME) { O ess: LJ SECTION II: RA DIATION EXPOSURE HISTORY (please print or type) YES NO 1. I have previously been monitored for radiation exposure at TAMIIS (internal via bioassay or external sia radiation dosimeter (s)).
- 2. I have previously been monitored for radiation exposure while employed ELSEWHERE. internal or external.
Ifyou answered "YES" to question number 2, please provide a copy ofyour up-to-date radiation exposure records to the ORS. Mail Stop 3261, Signature Date FOR OFFICE USE ONL Y DO.NOT WRITE HELOW TillSIINE M:nitoring Required: Internal: External: B ( d: (list isotopes) (list badges) Stan Date: Account #: Reinstate Date: Panicipant #: Order Date:
l 1 j April 2, 1991 4
- TO: &NAME& ,
& ADDRESS 1/O&
4 ADDRESS 2/O&
& CITY &
FROM: RADIOLOGICAL SAFETY OFFICE TEXAS A&M UNIVERSITY REPORT OF RADIATION EXPOSURE DURING & WEAR-PERICD& IS i ON PERMANENT FILE AT THE RADIOLOGICAL SAFETY OFFICE. FOR YOUR l PERSONAL RECORDS, THE ACCUMULATED DOSE ACQUIRED DURING THIS ! PERIOD IS RECORDED AS & DOSE &. i THIS REPORT IS FURNISHED TO YOU UNDER THE PROVISIONS OF THE' TEXAS STATE DEPARTMENT OF HEALTH REGULATIONS, T.R.C, PART 22, ENTITLED, " STANDARDS FOR PROTECTION AGAINST RADIATION." YOU O SHOULD PRESERVE THIS REPORT FOR FUTURE REFERENCE. Accompanied with individuals NRC Form 5/TRCR Form 22.13A or equivalent form O I
BUREAU OF RATIATEN CONTROL
' DOSE ASSESSMENT REPORT Pinse Print ce Type ALL infirm .tirn
. Name of Etnoloyee 2. Date of Birth 3. Social Security Number I >
- 4. Name of Licensee or Resistrant 5. License of Registration No. 6. Dose Recorded l l
l
- 7. M:nstoring Period i1 Type of Personnet Monitortn3 und i 1. Type of Radiaian Measured
- 8. Pirsonnes Monitortn3 Supplier Thermoluminescent Dosimeter Beta
- 9. PIrsonnel Monitoring Equipment Wintification Number Other
- 12. Ins tstigation Results i
l l A i
%)
Corrscrive actions taken. if any-t 3. Assesseo Dose and Metnoc of Calculation m. L Date Sl5natureof RaotationSafetyOfficer Date Sqnitute of Emplove, racta mai 4 4 ss.
Bioassay Procedures for Tritium When working in a radition environmant it is possible that - one may inadvertantly (or accidentally) intake a radioactive
)
material either by inhalation of a radioactive gas, by ingestion ( of a radioactive material in liquid or solid form, by absorption of a radioactive material in gaseous or liquid form, or by injection of a radioactive material into a wound. In the event intake occurs bicassay techniques are employed to determine the types (radioisotope) and quantity of material in the body. It should he noted that the intake, retention or elimination rate is dependent on each individual, the element, the chemical compound and its physical state. Thus some gases such as noble gases may be inhaled and nearly totally exhaled while tritium in the form of HTO is readily absorbed in the lungs. Other heavy
)
metals may not readily go into solution and thus pass through the i _ GI tract and have a high elimination rate. Should a Health Physicist suspect a case of ingestion the first checks would be 1) nose swabs, 2) saliva sample, and 3) breath sample. On the other hand inhaled and absorbed materials are eliminated from the body th"ough the urine and thus a urinalysis indicates the time dependent removal rate. Fecal analysis is usually used to ascertain the rate of removal for recently ingested materials and thus may indicate the exposure and effects on the gastrointestinal tract. The bicassay analysis will yield only the activity and identification (radioisotope) present in that sample at that , time. It does not give any additional information. Therefore it is necessary to either know when the ingestion occured or the O
- 4
, , - . -m ,~ w , - e ,
1%F9D results of soveral bicassays taken over a cpacified timn frama. - Ideally both are desired. By having several samples the Health Physicist can determine the individuals elimination rate and correctly determine the total dose or infinity dose due to the ingestion. The following procedure outline the steps the Health Physicist should follow to analyze for 3 H in a urine sample and to calculate the infintly dose D assuming the intake was HTO. PROCEDURE:
- 1) Prepare five LS counting vials with approximately 10 ml cocktail each. Number the vials 1 thru 5. Into viel no. 2 add .5 ml H2O vial No. 3 add 1 ml H20, vial No.
4 add 1.5 ml H2O and vial No. 5 2 al H20.
- 2) Now add 10 ul of HTO standard to each of the five vials.
- 3) Count the vials and generate a curve of H2O content vs.
efficiency. :
- 4) Generate a 2nd curve of the Quench ratio vs.
1 Efficiency.
- 5) Collect urine sample (approximately 50 ml required.)
- 6) Remove 15 ml urine and place in centrifuge tube, add 1 !
cc charcoal, mix and centrifuge for approximately 5 minutes.
- 7) Fill 2 LS vials with 10 ml cocktai, add .5 ml raw urine to 1 vial and mark U; add .5 ml decolorized urine to 2nd vial and mark CU.
- 8) Add 10 ul HTO standard to 15 ml raw urine sample, mix O
' " - " *~ ' - - " - ' - '-
wage 3 wall. Extract .5 cc and placa in LS vial, Edd 10 ml - cocktail and mark vial U+HTO. Add 1 cc charcoal to 1 remainder of sample, mix and centrifuge. Extract .5 ml i V("T ; and add to LS vial, add 10 ml cocktail and mark CU+HTO. Count all four vials. To calculate the tritium activity, use the following I equation. From steps 1 and 2 take vial No. 2 and use this as the standard. . Now for the untreated. samples: 1st Analysis 3 H activity = (No. 2 X U K 123 ( uci) (U+HTO - U x 2.22 x 106 liter i No. 2 = dpm of standard U = activity cpm of sample U 1 ( U+HTO = activity dpm of U+HTO sample ( (10 HTO added) 2nd Analysis I 3 H activity = (No. 2)-(CU) x 12 3 ( gqg) . (CU+HTO - CU) x 2.22 x 106 liter l No. 2 = dpm of standard No. 2 CU = activity of decolorized sample CU+HTO = activity of decolorized sample + 10 HTO input. O
Fage 4 Now using standard man as hAving 43 litsrs of H 0. - 2 l The D (infinity dose) is calculated as D = (51)(.01)(T) I 1/2 aff 4.3 x 104 (.693) T 1/2 eff = 11 days, I = total uci'3 in b doy D = (51(.01)(I)(11) = .205 mram/uci 4.3 x 10*(.693) s i t i f 1 i:' O i I ) l 1 O J
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_ - . . - - - - - . . . - = ~ _ - - . . . . - . - . 4 . DIOASSAY PROGRAM FOR INDIVIDUALS WORKING l WITH 12sI AND 132 7
- 1. INTRODUCTION 1.1 Because radiciodinated solutions and compounds undergo decomposition which may result in the volatill ation of radiciodine, individuals t working with these materials have a potential for accidental uptske of radioactive iodine. Once inside the body, the iodine concentrates ,
- in the thyroid, contributing to the radiation dose received by that i i organ. This bioassay program will enable the health physics staff to determine an individual's radiciodine thyroid burden, so that a thyroid organ-dose can be determined for those who have had an uptake. I
- ad-j dition the program will menitor the effectiveness of isotope handling procedures.
4
- 1.2 This program is designed to meet State and Federal Regulatory Agency l 4
125 I 333 l-A requirements for bioassay of and I. i ! 2. PP.0 CRAM PARTICIPATION \ < 2.1 All individuals who handic unsealed-quantities of 12s1 and 333 I in er.- cess of the qu:ntittes listed in Isble 1 and those individualt who werk close enough to such handling that uptake is possible (within a few ( meters) shall participate in this bioassay program. The quantities in i Table 1 apply to that amount handled either in a single usage or the L: total amount handled over a period of 3 consecutive months. l i, 2.2 It shall be the responsibility of individual licensees to notify the Radiological Safety Office of the names of those individuals working i under his/her license who require bionssay for radiciodine. L
- 3. FREQUENCY OF BIDASSAY
!' 3.1 Prior to beginning work with 12 51 or 12 I in quantities which require participation in the bicassay program, individuals shall be given a
.i o TABLE 1 O ACTIVITY LEVELS ABOVE WHICH BIDASSAY FOR
'"I OR I IS REQUIRED Activity Handled in Unsealed Form Type of Operation Volatile or Bound to Non-Dispersable Volatile Agent Processes in ooen room or bench, with possible escape of iodine from process vessels. 0.1 aci 1 mci Processes with possible escape of iodine carried out within a fume hood of adequate design, face velocity, and performance reliability. 1 mci 10 mci Processes carried out with gloveboxes, ordinarily closed, but with possible release of iodine from process and occassional exposure to contaminated box and box leakage. 10 mci 100 mci 2
"bccalina" or "preoparational" bionsecy. I
~ 3.2 A " routine" bionssay shall ba parformed within 72 hours (but not less
) ' O than 6 hours) on all individuals following commencement of work with I
quantities of radiciodine necessitating participation in this program. ) Bioassays shall continue on a hiweekly schedule as long as conditions j j exist which necessitate an individual's participation in the program. When work with radiciodine ir less frequent than every 2 weeks, a bio- l l assay shall be performed within 10 days of the end of radiciodine opera- -i tions. Individuals who work under conditions which present a high po-tential for uptake may be required to submit to bioassay more frequently than-biweekly. 3.3 Af ter 3 months of rou:ine biweekly bioassays the frequency of bicassay may be reduced to quarterly, at the discretion of the Radiological Safety I officer. I 3.4 An " emergency" bioassay shall be performed on any individual as soon as I O t possible following an incident in which that individual may have re-j ceived an uptake in excess of 0.5 pCi of 12sI or 0.14 pCi of I'l l. 3.5 All individuals who are required to participate in this program shall undergo a "posteperational" bioassay within 2 weeks (but not less than 6 hours) after' discontinuing operations with radiciodines. This bio-assay shall be performed prior to an individuals termination of employ-ment with or withdrawal from this university
- 4. ACTION LEVELS AND CORRESPONDING ACTIONS 4.1 Whenever the thyroid burden at the time of measurement exceeds 0.12 131 uCi of 123 1, 0.04 uC1 of I or a corresponding appropriate amount of a mixture of these two isotopes (see Appendix D), the following actions C' 4.1.1 An investigation of isotope handling procedures shall be conducter.
3
If this investigation indientes that o c:ntinuatien of current i Operations would ccusa furth:r uptake of radiciodine in excess ), of the above limits, operations using radiciodine in that lab 1 shall be discontinued until corrective actions can be imple-I i mented that will lower the potential for uptake. ! 4.1.2 Restrict the affect ~d individual from further work with radio-iodine until the thyroid burden is less than the above limits. l 4.1.3 Perform " diagnostic" bioassays on the affected individual at bi-weekly intervals until the thyroid harden is less than the above j limits. 4.1.4 Calculate the committed thyroid dose based on biological half- ; life deter =ined from follow up bioassays. 4.1.5 Make exposure record entries and notify State or Federal agenedes as appropriate. 4.2 In addition to the actions in 4.1, whenever the thyroid burden exceeds { 0.5 uCi 12s1, 0.14 uCi 33'I or a corresponding appropriate amount of a mixture of these two isotopes (see Appendix D), the following actions shall be taken: 4.2.1 Refer the case to appropriate medical consultation. ~ 4.2.2 Perform diagnostic hioassays at weekly intervals until the thy-roid burden is less than the values stated in 4.1. 4.3 If the affected individual and others working in the same area were on a quarterly bioassay schedule at the time the limits of 4.1 were ex-ceeded, reinstate biweekly bioassay schedule until it has been demon-1 strated that further exposures will not cause the limits of 4.1 to,be exceeded. 3
- 5. BIOASSAY PROCEDURE l
O s.1 Pr1or to commencem nt of oP <1o
- 1 1 of '"' o u 1
1 4 I I i
in exesco of thoaa listsd in Tcbla 1, licanssac chall notify tha , Radiological Scfaty Office of such cnd provide the names of those individuals who meet the criteria of 2.1. Licensees shall not per-mit any individual who meets the criteria of 2.1 to work with or near radiciodines until they have undergone a baseline bicassay. 5.2 The Radiological Safety Office shall contact these individuals and schedule baseline bioassays at a time and place convenient to both parties. 5.3 Individuals participating in this program shall notify the Radiological Safety Office following their initial contact with radiciodine to sche-dule the first routine bicassay (to be performed within 6-72 hours). Upon completion of this first bioassay, a bioassay schedule shall be established for the individual in accordance with 3.2 and 3.3. 5.4 Any individual involved in a radiological incident who may have exceed-ed the limits of 4.2 shall notify the Radiological Safety Office in-mediately. l 5.5 Any individual who is participating in this program shall notify the l Radiological Safety Office prior to terminating emp ayment with or ; otnerwise leavinE this university.
- 5.6 Eioassays shall be perfomed by individuals designated by the Radio-logien1 Safety Officer and shall be conducted in accordance with the detailed procedure contained in Appendix A.
S U 5
)
APPENDII A l
, i
, ((-J- BIOASSAY PROCEDURE A1. PRELIMINARY A1.1 Determine which isotope (s) of Iodine is used by individuals to be monitored. A1.2 Perform threshold calibration and efficiency determination for i { appropriate isotope in accordance with Appendix B or C. ' A1.3 Obtain all equipment necessary to perform bicassay. s A1.3.1 Ludlum Model 2200 Portable single channel analyzer (with I power cord) l 4 A1.3.2 Ludlum Model 44-3 NaI detector (for 12sI ) or Model 44-2 NaI t detector with shield (for 181 1)(with H.V./ signal cable) 1
- A1.3.3 Cotton tipped swabs
~ D A1.3.4 Alcohol
- [O A1.3.5 Detector positioning rig A1.3.6 Bionssay Record Sheet A2. PROTOCOL
~
' i A2.1 Insure that all control settings are appropriate for isotope to be ; i monitored. A2.2 Maasure background in area where bioassay is to be perfor=ed. g This area should be a low background area. Record on Bioassay Record Sheet. A2.3 Check for surface contamination on neck of individual to be moni-tored. A2.3.1 Swab neck in area between thyroid cartilage (" Adam's Apple") and clavicles with alcohol soaked cotton tipped swab.
\-' A2.3.2 Count swabs for 1 minute approximately 1/2" from surface of A-1
, datsctor. If n2ck io found to bn crntaminated. hava indi- .
vidual wash neck and re-check for contamination. Record on Bioassay Sheet. A2.4 MEASURE THYROID UPTAKE A2.4.1 Seat individual at a desk if possible. A2.4.2 Tilt head back at 45* angle. A2.4.3 Position detector face in contact with center line of the neck midway between thyroid cartilage (Adam's Apple) and 2 clavicles (collar benes). A2.4.4 Obtain a 1 minute count. Record on Bionssay Record Sheet. A2.4.5 Move detector to a position 3" away from and perpendicular to point of contact measurement. A2.4.6 Obtain a 1 minute count. Record on Bioassay Record Sheet. A2.4.7 With individual standing, place detector in contact with front of thigh, 3" above knee. V A2.4.8 Obtain a 1 minute count. Record on Bioassay Record Sheet. A2.4.9 Move detector to a position 3" away from and perpendicular to point of contact measurement. A2.4.10 Obtain a 1 minute count. Record on Bioassay Record Shect. A2.5 DETERMINATION OF THYROID BURDEN - Single Isotope Present. A2.5.1 Determine net contact CPM (C e
) by subtracting thigh contact CPM from neck contact CPM. Record on Bioassay Record Sheet.
A2.5.2 Determine net 3 inch CPM (Cs) by subtracting thigh 3 inch CPM from neck 3 inen CPM. Record on Bioassay Record Sheet. A2.5.3 Determine COUNT RATIO by dividing C e by C3, Record on Bio-assay Record Sheet. A2.5.4 Use COUNT RATIO obtained above to find effective thyroid [ depth from Figure 1 (125I) or Figure 2 (3311). Record on Bioassay Record Sheet. A-2
- i A2.5.5 Uso offectiva thyroid dspth to find UCi/CFM corraction fac- , -{
" 1 4
tor (CT) from Figure 3 (12sI) or Figure 4 (2st I). Record I on Bioassay Record Sheet. l v A2.5.6 Calculate thyroid burden. Record on Bioassay Record Sheet. ; Thyroid Burden = (C )(CF)(SECF*) A2.6 DLTERMINATION .0F THYROID BURDDI - Both Isotopes Present. A2.6.1 Determine 181 1 thyroid burden (steps A2.1 thru A2.5.6) 123 A2.6.2 To deter =ine I in the presence of 2si I one must account for.the 183 1 contribution in the 115 I energy window: (a) perf orm A2.1- A2.4.4, A2.4.7 and A2.4.8 using Ludlum l Model 44-3 detector as for 12s7, (b) determine combined net contact CPM (C ') by subtracting thigh contact CPM from neck contact CPM. Record on Bio-1 assay Record Sheet. j l
- (c) using the effective thyroid depth obtained from Figure
('~'\
\w- 2 during the 131 I measurement, obtain CFM/pci 183 I
e interference rate (IR) from Figure 5. Record on Bio-I assay Record Sheet. (d) CPM 231 I interference = (IR)(pCi 331 I Thyroid Burden) - a Record on Bionssay Record Sheet. 123 I thyroid burden. A2.6.3 Determine j ^ I3I (a) subtract CPM due to I obtained in A2.6.2(d) from com-bined net contact CPM (C ') obtained in A2.6.2(b). This resulting value is the CIM due solely to 12 sI (C ") . Record on Bioassay Record Sheet. (b) using the thyroid depth obtained from Figure 2 during 131 I measurements, obtain the corresponding pCi/ CPM Ca- *Sec Appendix B or C for SECF - A-:
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125 I correction fcctor (CF) from Figura 3. Racord en . , Bioassay Record Sheet. ? l l' (c) 12 s1 thyroid burden = (Ce ")(CF)(SECF 12sI).* Record 1 ? on Bioassay Record Sheet. i 4 1 3 1 J 1 s . E ! i } 1 1 1 l i i I i l i i s it l I l i I ! 5 4 4 4 1 1 i I 4 l i ( l 1 1
- f. *See Appendix B 4
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,G I Figure 1 ( WI ColmT RATIO Vs. EFFEC *IVE THYROID DEPTH CURVE A- 5
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APPLICANT REVIEW FORM - f-Name of Applicant Date: Department: Radioisotopes Requested Activities Requested FACILITIES REVIEW Performed By: Date:
)
- 1) Facility / laboratory location (s),
- 2) Fume hood (s) operational and propely marked to indicate i acceptable sash position o obtain proper face velocity (100 ft/sec). Attach fume nood survey form. Comments:
's, O,
- 3) Sinks, refrigerators, storage locations, etc. properly i marked. Comments:
TRAINING AND EXPERIENCE !
- 1) Number of persons to be working in laboratory: '
- 2) Persons allowed to work with radioactive materials:
Name Social Security No. i
- 3) Documented training to be provided by sub-licensee / ORS (circle one) i I
m guw. b) onn year of experienco and training under the cimenrisinn of a licensed staff membsr, or c) Having hold a Radioactiva Material Licenso issued by the USNRC or an agreement state for similar work. d) Exemption from a, b, and c above may be granted by the board if the requested radioisotope is lO V i) less than 100 uCi of 14 C or 3 H, or j ii) less than 10 uCi of activity of non alpha emitters. I h v i 4 l 2 O
RADIOLOGICAL SAFETY OFFICE RADI0 ISOTOPE HAlELING SHORT COURSE - TEXAS A&M UNIVERSITY [ SESSION NO. 1 A. Atoms, Elements, Isotopes, Radioisotopes, Nuclear Stability
- 1. Periodic Table
- 2. Isotopes
- 3. Radioisotopes
- 4. Nuclear Stability B. Definitions
- 1. Radioactivity
- 2. Radioactive Material
, 3. Radiation
- 4. Contamination
- 5. Half-life
- 6. Curie (C1)
- 7. Becquerel (Bq) *
- 8. Specific Activity
- 9. .. Electron Volt (eV)
C. Radiation and Interactions
- 1. Alpha Particles
- 2. Beta Particles i 3 t. Gamma and X-Rays !
[ 4. Neutrons A]4. Exposure and Dose 1
- 1. Exposure
- 2. Dose
- 3. Dose Equivalent
. E. Background Radiation
- 1. Natural Background
- 2. Man-made RAM in our environment
- 3. Medical Radiation Exposure
- 4. Calculation of one's own radiation dose SESSION NO. 2
- A. Theory of Operation of Radiation De'tectors
- 1. GM survey meters
- a. uses
- b. limitations
- 2. Ion chambers
- 3. Scintillation and other special detectors 4
V
B. . Survey Methods
'C. Demonstration of. Instrument Use and Operation .
D. Dosimetry 1 SESSION NO. 3
'A. Laboratory Procedures From a Radiation Safety Standpoint ;
(Demonstration)
.B. 'Special Techniques
- 1. Contamination control
- 2. Spills C. ALARA SESSION NO. 4 A. University Policy and Procedures Manual Revier
- 1. Sub-license application
- 2. Ordering of-isotopes
- 3. Obtaining film badges (film badge request form)
- 4. Receipt of radioisotopes
- 5. Transfer of material to others (transfer form)
- 6. Waste management (disposal form) )
- 7. Packaging and shipping off campu's
- 8. ' Bioassay for I-125 and H-3
- 8. Federal.and State Regulations
- 1. Introduction
( 2. Radiation exposure limits
- 3. Signs and-labels
- 4. Responsibilities of users
'5. Responsibilities of Radiological Safety Office SESSION NO. 5-A. -Biological Effects of. Radiation
- 1. Critical organs
- 2. Internal vs. External exposure 3; Radiation Risk vs. Benefit
- 4. Pre-natal exposure B. Film Presentation v
s
BIGASSAY RECORD . i, 1-i
- Name: Social Security No.: - -
Isotope (s) Used: (circle) 12s I - Last Used: Time - Date - 1:1 I - Last Used: Time - Date - i Licenses: License No.: ) Type of Biaassay: (circle one) Baseline, Diagnostic, Emergency, Postoperational, l l Routine. j 1. SINGLE ISOTOPE OR 831 I IN PRESENCE OF 12sg i Instrument: Model - S.N. - , Detector: Model - S.N. - p Room Bkg: CPM Neck
Contact:
CPM 3" from Neck: CPM 3 Neck Swab: CPM -Thigh
Contact:
CPM -3" from Thigh: CPM 2
- Net Contact (Cc )
- CPM Net 3" (Cs): CPM Count Ratio = (Cg )/(C3 ) = Effective Thyroid Depth: em Conversion Factor (CF): ,uC1/ CPM SECF:
Thyroid Burden = (C,)(CF)(SECF) = UCi lasy 1:1 I (circle one)
- 2. 125 1 IN PRESENCE OF I31 1 Instrument: Model - S.N. - j Detector: Model - S.N. -
)
Room Bkg: CPM Neck
Contact:
CPM Neck Swab: CPM ~
-Thigh
Contact:
CPM CPM NetContact(C[): _ 133 I Interference Rate (IR): CPM /uci ) 1:1 133 I Interference = (IR)(llCi I Thyroid Burden) = CPM Net 125 I CPM (C) =[(C') - (13 *I Interference CPM) = CPM Conversion Factor (CF): UC1/ CPM SECP: ! Thyroid Burden = (C")(CF)(SECF) = uCi 12s7 l
- 3. REMARKS:
9 O' . l Bionssay Performed By: Date: Time: A-10
4 APPENDIX B 4 ^
/ CALIBRATION OF LUDLUM MODEL 2200 SCA AND MODEL 44-3 DETECTOR FOR DETECTION OF 22s g Bl. CALIBRATE THRESHOLD AND WINDOW TO 10 kev / TURN.
31.1 Initial Model 2200 control settings Bl.1.1 Window ON-OFT rwitch - 0FF I Bl.1.2 Rate meter range selector switch - % 10 Bl.1.3 Threshold dial - 3.50 (35 kev) B1.1.4 Window dial - 0.50 (5 kev) , Bl.1.5 High voltage - 0.00 Bl.1.6 Fast-slow response - F (fast) B1.1.7 Race meter function switch - RATE Bl.2 Energy Calibration Bl.2.1 Connect Model 44-3 detector to instrument. O)
\,, Bl.2.2 Turn power switch to desired power supply (LINE or BAT).
Bl.2.3 Expose detector to 12sI source. Bl.2.4 Increase H.V. setting until rate meter starts to respond to source. - Bl.2.5 Window ON-OFF switch - ON Bl.2.6 Increase H.V. until count rate peaks on rate meter (increase rate meter range as necessary). The threshold and window dials are now calibrated to 10 kev / turn. B2. EFFICIENCY DETE!LMINATION B2.1 Initial Model 2200 control settings B2.1.1 High voltage - as determined for threshold calibration of 10 kev / turn. B2.1.2 Set an energy vindow of 15-60 kev. [s_ ) B-1
, (c) thrrhold dial - 1.50" (13 kev)
- l. .
! (b) window disi - 4.50 (45 kev) i g B2.1.3 Window ON-OFF switch - ON t.') . B2.1.4 Time - as necessary for statistically significant counts. B2.2 Physical Set-Up B2.2.1 Obtain a set of 123 1 stsudards prepared in 30 ml polyethylene bottles. B2.2.2 Place bottle containing standard into the phantom carrier. 1 B2.2.3 Insert carrier into standard thyroid uptake neck phante=, Model 74-365, with bottle at front of phantom and red lines properly aligned. B2.2.4 Place Model 44-3 detector in ring-stand clamp so that the center of the detector face is in line with and perpendicular to the center of the standard solution and in contact with the front of the phantom. B2.3 Efficiency correction factor B2.3.1 Count each of the 12sI standards in the above geometry. B2.3.2 Count background (no standards in phantom) . B2.3.3 Correct the activity in the standard solutions for decay. . B2.3.4 Determine the average net UCi/ CPM. This value will be used to correct Figure 3 for detection system efficiency. B3. 125 CORRECTION OF uCi/ CPM I Vs. EFFECTIVE THYROID DEPTH CURVE (Figure 3). 33.1 Figure 3 is based on a system efficiency which yields 1.55 x 10~5 uCi/ CPM 12sI when the detector is in contact with the phant a (effective depth = 2.123 cm) as described above with energy window of 15-60 kev. B3.2 To correct Figure 3 for changes in system efficiency. l O ? Li B-2
33*2+1 Systemefficiencycarrsetdonfceter'= 'alun from B2.3.4 - (SECF) 1.35 x 10 * ! B3.2.2 Record SECT on Bionssay Record Sheet. i a i o i a i-l 4 s 1 i j i i 3 l t i i i l- 1 1 1 I l l 1
- i
? i 4 1 1 ! l l - 1 I-1 i l , 4 0 i i B-3
APPDIDIX C f ' V) CALIBRATION OF LUDLUM MODEL 2200 SCA AND MODEL 44-2 DETECTOR FOR DETECTING 131 7 C1. CALIBRATE THRESHOLD AND WINDOW TO 100 kev / TURN. C1.1 It.itial Model 2200 control settings C1.1.1 Window ON-OFF switch - 0FF , C1.1.2 Race meter range selector switch - X 10 133 C1.1.3 Threshold dial - 3.54 for I std (or 3.46 for 133 Ba stJ.) C1.1.4 Window dial - 0.20 C1.1.5 High voltage dial - 0.00 C1.1.6 Fast-slow response - F (fast) i C1.1.7 Rate meter function switch - RATE C1.2 Energy Calibration C1.2.1 Connect a Model 44-2 detector (with collimator) to instrument C1.2.2 Turn power switch to desired power supply (LINE or BAT) I'l 183 i C1.2.3 Expose detector to l-(or Ra) source a C1.2.4 Increase H.V. until rate meter starts to respond to source C1.2.5 Turn window ON-OFF switch to ON - 1 C1.2.6 Increase H.V. until count rate peaks on rate meter (increase rate meter range as necessary) i Threshold and window dials are now calibrated to 100 kev / turn. ! C2. EFFICIENCY DETERMINATION C2.1 Initial Model 2200 control settings 1 C2.1.1 High voltage - as determined for threshold calibration of 100 kev / turn. l C2.1.2 Set an energy window of 250-450 Kev.
>R !U C-1
l (c) thresholddial-2.3d . (b) window dial - 2.00 C2.1.3 Window ON-OFF switch - ON C2.1.4 Time - as necessary for statistically significant counts C2.2 Physical Set-Up I'l 133 C2.2.1 Obtain a set of l (or Bs) standards prepared in 30 ml l polyethylene bottles. C2.2.2 Place bottle containing standard into the phantom carrier. C2.2.3 Insert .:arrier into Standard Thyroid Uptake Neck Phantom (Model 74-365) with bottle at front of phantom and red lines on carrier aligned with red lines on phantom. C2.2.4 Place Model 44-2 detector in ring-stand clamp so that the center of the detector face is in line with and perpendicular to the center of the standard solution and in contact with the front of the phantom.
\ C2.3 Efficiency correction factor 183 133 C2.3.1 Count each of the I (or Ba) standards in the above geometry.
C2.3.2 Count background (no standards in phantom). - C2.3.3 Correct the activity in the standard solutions for decay. C2.3.4 Dec.ermino the average net UCi/ CPM. This value vill be used to correct Figure 4 for detection system efficiency. I38 1 Vs. EFFECTIVE THYROID DEPTH CURVE (Figure 4) C3. CORRECTION OF uCi/ CPM C3.1 Figure 4 is based on a system efficiency which yields 5.75 x 10~3 uCi/ CPM 131 I when the detector is in contact with the phantom (eff ective depth - 2.123 cm) as described above with an energy window of 250-450 kev. (This is equivalent to 5.00 x 10 s pC1/ CPM I3'Ba.) C-2
1
. C3.2 To corrsct Figura 4 for changsc in cyctam cfficiency.
2 - 383 C3.2.1 If I standards were used. System Efficiency Correction Factor = va ue r m C2. (SECF) 5.75x10-}.4 133 Ba standards were used.
- C3.2.2 If value from C2.3.4 l SECF
5.00 x 10-* C3.2.3 Record SECF on Bionssay Record Sheet. , I l l b (_ / , O C-3
APPENDIX D
.r CALCULATION OF ACTION LEVELS FOR MIXTURES OF 125 I AND 1sig 4
D1. INTRODUCTION Action levels listed in 4.1 of the bionssay program are equal to 25% of the maximum permissible organ burden (HPOB) of 12s l or 333 I. A 170B of either isotope, if continuously present in the thyroid, would result in an organ dose of 600 millirem / week (30 rem / year). If a mixture of both , isotopes is present, then one must calculate what activity of such a mix-ture would be equivalent to 25" of a MPOB for single isotope. D2. CALCULATIONS D2.1 A corresponding amount of a mixture (A ,f ) equivalent to the limits of 4.1 of the bioassay program is calculated by A,g, = [0.12X + 0.04(1-X)] uCi where X = fraction of mixture that is 12sg D2.2 Similar11y, for the purpose of 4.2 of the bioassay program A' ,1, = [0.5X + 0.14(1-X)] pCi D3. EXAMPLE
- An individual': thyroid burden is determined to be 0.10 pCi 12sI + 0.02 pCi 333 I.
X = 0.10/(0.10 + 0.02)
= 0.83 A,g = [0.12X + 0.04(1-X)] pCi
= [0.12(0.83) + 0.04(0.17)]
= 0.11 uCi
/
D-1 -
. . . .. . . . - - ~ _ . - . . . . . . . - . . _ - . . . _- .- . .. . _ . . - - . .. - . . - - . _ . - - . . - _ - -
3 Th2 thyroid burdsn of tha mixtura (0.12 pC1) is grastar than tha limit - for the mixture allowed in 4.1. l 2 A'mix = [0.5(0.83) + 0.14(0.17)]
= 0.44 pCi l The thyroid burden of the mixture does not exceed the limit for 4.2.
i l r i 1 i 1 ) 4 1 1 e D-2 . l 1
ANNEX-P Instruction Guide for Laboratory-Specific Training for Radioisotope or-Radiation Workers O \~ / The'following topics shall be covered by the Sublicensee in the training of his' staff and/or students who work with radio-active material and/or radiation producing devices under his license and control.
- 1) Area restrictions - where radioctive materials are to be used, designation of hot areas and cold areas within the labs and restrictions of use to include prohibited smoking, eating and drinking.
- 2) Location of material storage facilities and procedures for storage.
- 3) Proper posting of signs'and notices.
- 4) The requirement of personnel radiation dosimetry and r
availability of monitoring devices from the Radiological Safety Office.
- 5) Material usage - explanation of the research and levels of radioactive materials used in the labs and possible hazards from those materials. The use of radiation producing devices and hazards from exposure levels emit-ted from the device.
- 6) Special handling techniques to be used when handling radioisotopes or operating radiation producing devices to minimize exposures.
- 7) Protective equipment and clothing - use of lab coats, gloves, etc.
\s.
i waste material for disposal. '
- 4. .
i 9)' Responsibilities of the licenson and of the laboratory ! technicians. ;
- 10) Use of survey instrument for checking radiation levels j
i> and checking for contamination. < ?
- 11) Emergency procedures.to be followed if a spill or accident !
occurs. l i l
ANNEX Q EMERGENCY PROCEDURES for n k_) RADIOGRAPHIC AND TELETHERAPY OPERATIONS PURPOSE AND SCOPE This procedure is intended to provide guidance to personnel involved with radiographic or teletherapy operations (or other potentially high radiation output devices) in the event of an accident or a malfunction of any safety system. Applicable portions of this procedure (including notification of the Radio-logical Safety officer) should be followed regardless of whether or not significant hazards or injuries resulted. This procedure should be posted in a conspicuous location for ease of reference in an emergency. U,em PROCEDURE
- 1) Upon recognition of malfunction, accident, or violation of operating procedures, immediately eliminate the source of the radiation.
a) activate kill-switches or emergency-stop controls if available, or b) interrupt power to the device either at the appropriate power outlet or by using a circuit breaker as last resort.
- 2) DO NOT attempt to remove the object or target being irradi-ated, b
v l
- 3) Radiation survey msters mny b3 use:d to dstsct radiation levels in the nrsa duo to scatter radiction end to confirm -
that the device is in a safe shutdown condition. If you are (~h not familiar with the operation of the survey meter or \ms' confident of its reliability, do not attempt to use it.
- 4) Contact the Radiological Safety Officer or a member of the Office of Radiological Safety staff at 409-845-1361. For emergency assistance after normal working hours, holidays, or weekends, call 409-845-4311 (TAMU Physical Plant 24 hour operator) and request emergency assistance from the on-duty Office of Radiological Safety person.
- 5) Contact the sub-licensee or registrant for that device.
- 6) Prevent anyone from entering the hazard area or using the device until emergency assistance arrives.
- 7) Provide a thorough written description of the incident.
(
- }
/
r%
/
ANNEX R EMERGENCY PROCEDURES s for s RADIOISOTOPE LABORATORY PERSONNEL PURPOSE AND SCOPE This procedure is intended to provide guidance to persons working in or near laboratories where radioisotopes are used or stored in the event of an accident, spill, or other emergency (including lost or stolen sources). This procedure should be posted in conspicuous locations to ensure its availability in the event of an emergency. I PROCEDURES FOR SPILLS In the event of a spill involving radioactive materials, i ('N; many factors affect the determination of the appropriate re- ) V sponse. Factors such as activity, specific activity, form, com-pound, volume, and what was contaminated all must be considered in responding appropriately. All spills must be treated serious-ly and promptly to minimize the hazards and minimize the ensuring decontamination efforts required. The following general steps should be followed for any spill:
- 1) Stop the spill, prevent its spread.
a) If the spill is a liquid, eliminate the source of the spill and attempt to halt its spread. This may be accomplished by placing a leaking container inside of a bucket, barrel, plastic bag, etc. or by using an ab-O> V
7 rber to halt or retard its spread onca it h as spil-led. Special attention should be given to preventi ng ^ leaks from reaching other laboratory equipment , floor penetrations, or other places which might complicat e decontamination efforts or involve areas e the outsid control of the sub-licensee, b) If the spill involves a dispersible solid such as a powder, eliminate the source of the spill and contain the spilled material by use of dampened ab sorbent paper or other suitable cover material. c) If you or someone in the lab becomes contami nated, restrict that person from venturing farther from th e contaminated area than is necessary to keep a safe distance. Minimize the activities of that person to keep radioactive contamination from being spread t O) o clean parts of the facility. 2 Warn others. a) Warn others of the spill and the areas affected . This may be done verbally for those persons in the lab at that time. b) Post the contaminated area to warn anyone who may sub-sequently enter the lab of the hazard. 3) Inform appropriate persons. a) Contact the ORS at 409-845-1361 for assista nce. If the incident occurs after normal working hours , on week-ends, or holidays, contact the TAMU 24-hour operator at 409-845-4311 and request emergency radiol ogical assist-ance from the on-duty ORS person. D
sorbar to halt or rotard-its cprocd oncs it has spil-led .- Spncial attention should be givsn to provanting ~ 2 { 1eaks from reaching other laboratory equipment, floor
'( ) penetrations, or other places which might complicate decontamination efforts or involve areas outside the
' control of the sub-licensee.
b) If the spill involves a dispersible solid such as a l { powder, eliminate the source of the spill and contain r
- the spilled material by use of dampened absorbent paper l
or other suitable cover material.
- - )
c) If you or someone in.the lab becomes' contaminated, restrict thct person from venturing farther from the i contaminated area than is necessary to keep a safe H distance. Minimize the activities of that person to I keep radioactive.contanination from being spread to clean parts of the facility.
- 2) Warn others.
a) Warn others of the spill and the areas affected. This l may be done verbally for those persons in the lab at that time. b) Post the contaminated area to warn anyone who may sub- ! sequently enter the lab of the hazard.
- 3) Inform appropriate persons.
a) Contact the ORS at 409-845-1361 for assistance. If the incident occurs after normal working hours, on week-ends, or holidays, contact the TAMU 24-hour operator at 409-845-4311 and request emergency radiological assist-ance from the on-duty ORS person. O
i b) Contact tha sub-licansca responsible for that labora- l tory and that licensed material. i
,s c) Contact other persons that may have been contaminated i 5-) and left the lab without knowing of their contamina-tion. Request they either retrace their steps to the contaminated lab or remain at their present location until they can be surveyed for contamination.
- 4) Maintain a watch over the area from a safe distance until help can arrive.
PROCEDURES FOR PERSONNEL CONTAMINATION i Response to personnel contamination is highly dependent upon the location of the contamination, the compound, the radio-isotope, and the activity of the contaminant. Contamination of the hands or feet are the most common contamination incidents and /~D are normally the easiest to clean-up. However, no contamination V j is to be taken lightly and no person should be allowed to leave the laboratory with any identifiable contamination levels above background without the knowledge and approval of the ORS. To contact the ORS, call 409-845-1361 during normal work hours. l I Emergency assistance ,can be reached after normal working hours by calling the TAMU 24-hour operator at 409-845-4311.
=EAND CONTAMINATIONS
- 1) Wash hands with mild hand soap and water. The water temperature should be tepid (same as hand temperature). Hot and cold water are to be avoided initially to prevent open-O
ing or closing the pores in the skin.
- 2) Resurvsy hands to datormina rssulting contamination lovals. -
- 3) Repeat steps 1 and 2 until no further reductions in contami- i nation level are observed or until background levels are reached. This should not exceed 5 or 6 washings if the hands are scrubbed well each time.
- 4) Be aware that everything that the contaminated individual touches could be contaminated including faucet handle, tele-phone, door knobs, him- or her- self, etc. These areas should be surveyed carefully to ensure that contamination has not been spread elsewhere.
- 5) If it becomes necessary for the contaminated individual to use the telephone, use the restroom, or other task for which help is not available, the individual should don a clean pair of gloves to prevent contamination on the hands from
(_, contaminating clean objects in the lab. (~ 6) Contact the ORS for assistance. l SHOE CONTAMINATION
- 1) Remove the shoes immediately being careful not to step onto contaminated floors or other areas where contamination may have been spread. Use gloves to prevent hand contamination. ,
- 2) Wash the shoes in the hot sink using soap and water or bag the shoes for pickup by the ORS.
- 3) When shoe contamination is found, the entire floor of the laboratory (and any other area where the individual may have spread the contamination) must be considered contaminated until proven otherwise. Post the laboratory as a contamina-
/~N U
tion aras to warn others-than survsy othar psrsons in tha
' lab an soon cs.possible. -
- 4) Contact the ORS for assistance.
O OTHER PERSONNEL CONTAMINATION
- 1) Remove and bag contaminated clothing. Clean lab coats or ,
i
. coveralls may be donned'in place of contaminated clothing.
- 2) Contact the ORS for assistance.
3)~ Contaminated skin and hair may be washed with mild soap 'and tepid water as described for removdl or hand contamination.
- 4) Remain in one place until help arrives.
1 O l 1 1 O
ANN E S TEXAS A&M UNIVERSITY RADIOACTIVE MATERIAL CHECK IN AND DELIVERY - 4 ORS FORM 4 Rev 2/94 1. RSO No.
' ADMINISTR ATIVE
- 2. Date/ Time Processed 6. Permittee
- 3. Radioisotope 7. Permit No.
- 4. Form 8. Dept.
- 5. Activity Received pCi. mci 9. Use Location MONITORING EXPOSURE
- 10. Instrument (s) used: Type GM Make /Model Ludium 3 Serial Number
- 11. Package at 3 feet <0.1 mR/hr.
- 12. Package at surface <0. 5 mR/hr.
- 13. Primary container at surface mR/hr.
CONTAMINATION O 14. Instrument (s) used: Type
~
GM Make /Model Ludlum2200 Serial Number 13 4 6 8
- 15. MDA Calculation dom.
2
- 16. Surface of package < MDA dom /100cm.
- 17. Primary container < MDA dom /wice. I Note 1: If measurements exceed 10 mr/hr at 3 feet. 200 mR/hr at surface or 2200 dpm per 100 crE : contact ORS senior staff immeciately.
Note 2: Give copy of this form to user. retain original with user receipt signature. Note 3: Process within three hours of receipt.
Reference:
TRCR 21.906; TAMU Procedure Manual 4.2. X~ SURVEYOR Received by Laboratory O 1 1 >
~~' ~
RADIOACTIVE MATERIAL CHECX-IN AND DELIVERY 6 AMPLE MRS FORM 4 REV( 10/94) 1. RSO NO. k$0%W ADMINISTRATWE
- 2. Date/ Time Processed 2/It.//qc to:oo r 6. Permittee bW/Uutiu f/Ad/LS
- 3. Radioisotope - 56 5 7. Permit No. hgg
- 4. Form NfLN41%AJ 8. Dept. 0t'Aftes)&et4<r a / /
'5. Activity Received 3/p4 mCl
- 9. Use Location [//gr f)g'Al 0 729 MONITORING EXPOSURE
- 10. Instrument (s) used: Type GA Make/Model Lud 3 Serial No. 3MF/6
- 11. Package at 3 feet M mR/hr
- 12. Package at surface mR/hr.
- 3. Primary container at surface /8 mR/hr.
CONTAMINATION
- 14. Instrument (s) used: Type GA Make/Model Lud 2200 Serial No. 13468
- 15. MDA Calculation 3M dom.
2
- 16. Surface of package s dom /300cm.
- 17. Primary container demAvice.
Notts 1: If miasurements exceed to mR/hr at 3 feet from package. 200 mR/hr at surtace, or 22 cpm per em: contact ORS santor statt immectately.
- 2. Givs a copy of this term to the user. retain the eng:nal witn receiot signature.
- 3. Proc 2ss incoming packages within three nours of recciot.
R:;tirsnce: TRCR 21.90E TAMu Procecure Manual 4 2. j1n/h MiRVEYCR
/ 1 b'
Y
/ X /17w,w3 &k V Received by Laboratory ecx in 2/95 OAS
I GENERAL PROCEDURES O fer PERFORMANCE OF LABORATORY SURVEYS I. INTRODUCTION
- Laboratories in which radioactive materials are stored or used must be surveyed for radia-tion hazards at re gularintervals. The length of these intervals should depend upon the physical and/or caemical form of the isotopes used or stored in the lab, the activity-level of 1 the isotopes in the lab, and the frequency at which they are handled or used.
In REGULATORY GUIDE 3.3 the Texas Bureau of Radiation Controlissued regulatory guidance applicable to the use of radioactive materials at academic institutions. Tlie recommenilations contained in this guide have been augmented with good radiation safety ; practices in the following procedures to provide the Sub-licensee and laboratory personnel with a working document for use in implementing the radiation safety program for their laboratorv. 1 II. SCOPE
~
11is procedure includes instructions for conducting radiation field surveys. radioactive contamination surveys using portable radiation detection instruments. and surveys for removable radioacti'e contanunation using wipes. Also included are instructions to help laboratory personnel determine the type and frequency of surveys which are appropriate, the appropriate action levels and subsequent actions, and the necessary documentation / record-keeping requirements. Not all sections of this procedure are ap alicable to each laboratory. In fact, few laborato-ries exist on the TAMU campus that wil need to implement all portions of this procedure. Please refer to Section III, GUIDE TO CONTENTS, for assistance in determimng which specific survey procedures apply to your laboratory or facility. g.. OOffice of Radiological Safety March,1991 Page 1 of 13
)
l . III. GUIDE TO CONTENTS
- o
- Section Content Applicable - To Page k
IV.A Recommended Survey Frequency All Sub-licensees 3 IV.B Record-keeping Requirements All Sub-licensees 3 IV.C Radiation Field Surveys Users of P-32, I-125.1-131, 4 Using Portable Radiation Cr-51, & ~other gamma > I Detection Equipmem emitting radioisotopes i , p IV.D Radioactive Contamination All users of radioactive 6 i Surveys Using Portable materials in dispersible ] j- Radiation Detection forms, except tritium, Equipment - (powders, liquids. etc.) IV.E Radioactive Contamination All users of radioactive 10 Surveys For Removable materials in dispersible Contamination Using Wipe forms (powders. Tests liquids. etc.) O Page 2 of 13
' Office of Radiological Safety March.1991
I
V. PROCEDURE
S . IV.A. Recommended Survey Frequency . The materiafrefuency used'and ofthesurveys frequencyshould of work.depend ubon the amount and type of radioa e following are the smvey frequency requirements as dictated by state regulatory guides for radioactive contaminatioil:
- 1. Los Lcyc1 &cas - Not less than once per month for areas such as where in riim tests are performed, and analyzed, etc. (samples less than 100 microcuries each).
- 2. Medium Level &cas - Not less than once per week for areas where millicurie amounts of materials are used
- 3. High Level Areas - Not less than once per day for areas where curie amounts of activity are used or stored.
The Office of Radiological Safety performs monthly surveys in every laboratory where radioactive materials are known to be used or stored. Sub-licensees are expected to augment these surveys with surveys of their own when appropriate. Laboratories where cnly sealed sources are used or stored (such as the sealed sources used in gas chro'matographs, moisture-density gauges, etc.) are exempted from requirements of Sections IV.D and IV.E for performance of contamination surveys. Instead, users of most sealed sources must test those sources for leakage on a senii-annual basis. This program is organized by the ORS and is addressed in different procedures. O IV.B. Record-keeping Requirements
- 1. All surveys should be recorded on standard survey forms which should include the I following iriformation:
(a) type of survey; i (b) date performed (c) buildmg name/ room number; (d) name of Sub-licensee; (e) applicable instrument type, model, and serial number; (f) instrument background reading; (g) instrument efficiency; (h) probable radioisotope (s) to be detected: (i) sketch of the floorplan where survey is performed; l (j) results of the survey indicating each~ location surveyed and location of radioactive material work areas: (k) name of person performmg the survey; (1) signature of the Sub-licensee or designee as reviewer.
- 2. Records should be neat and legible.
- 3. Sub-licensees must keep records of com pleted surveys on-file for inspection by
. the Office of Radiological Safety and/or tae Texas Bureau of Radiation Control.
Records must be kept on-file "in' definitely" according to state regulations. O Office of Radiological Safety March,1991 Page 3 of 13
~
IV.C. Radiation Field Surveys Using Portable Radiation Detection Equipment
' 1. Required when... Radiation Field Surveys are only required when radioactive sources or radiation roducin O- 8 == -r vs rt i=p*ish- g r87 devices 8 t g rticies. existerwithin
=tre alaboratoLwhich
- s. vi s oree rc~es emit x-rays, which may require radiation field surveys be performed include x-ray machines, i
moisture-density gauges, electron microscopes, x-ray emitting sources such as Am-i 241, or gamma-rav emitting sources in quantities greater than 1 millicurie such as Co-60, C$-137, Cr-51, I-12$, I-131, Tc-99m, etc., or high-energy beta-particle emitting isotopes in quantities greater than 10 millicuries such as P-32, Sr-90, etc., or some combination of these radioisotopes which sum to these activity levels. I
- 2. Action Levels... When radiation field surveys indicate radiation levels greater-than or equal to 2.0 mR/hr contact the Office of Radiological Safety at 845-1361 to arrange a followup survey a,nd verification of adequate warmng signs.
i
- 3. Instrument Selection... Although most laboratories have only one type of instru-ment,if more than one type ofinstrument is available, the person pedorming the y survey must make the proper selection.
3 (a) GM or Geiger-Mueller detector. Most laboratories have only GM detec-1 tor (s) that have thin end-windows. These detectors can detect alpha. beta. gamma-ray and x-ray radiations. Although the response of GM detectors is 1 typically dependent upon both the type and energy of the radiation bein6 measured that is, they do not accurately measure radiation fields, radiation field surve,ys should be performed anyway. GM detectors are normally cali-i brated so that they will over-respond m radiation fields thereby resulting in conservatively high readings. (b) Ion-chamber detector. The ion-chamber detectoris capable of detectin x-ray and gamma-rav radiations and, by definition, responds to such radia g !. tions fields in an ene'rgy-independent manner, that is, the reading should be accurate (+/- 10% regardless of the source of radiation being measured. Therefore, the cion-)hamber detector is normally preferred to the GM l tor for radiation field measurements when both are available. 1 (c) Scintillation detector. The solid scintillation detectors used in portable radiation detectors are very sensitive to gamma-ray and x-ray radiations even
- at very low photon energie's. Although GM detectors are acceatable for l deteciion of I-125 gamma-rays, scintillators are the preferred c etectors for surveys in labs where significant quantities or I-125 are used or stored.
1 ! (d) Neutron detector. None of the above detectors are capable of detecting neutron radiation. Neutron detectors are required in very few laboratories or
- facilities since, other than nuclear reactors and accelerators, the only signifi-i cant sources of neutrons are found in moisture-density gauges, and Am-Be or Pu-Be sources. Since neutron instruments are expensive and rarely needed in most laboratories, and due to the relative complexity of performing neutron survevs. neutron-radiation surveys will not be addressed in this procedure.
Individuals desiring neutron radiation surveys are invited to request the ORS j to pedorm the survey using ORS instrumentation. i Office of Radiological Safety March,1991 Page 4 of 13 4
4 I .
- 4. Survey Procedures... Using a schematic dia, gram of the room or area being sur-veyed. number or otherwise mdicate on the d2agram the locations where radiation l measurements are made. On the diagram or on an attached sheet, record the
- p measurement reading for each survey location.' The following are hints and remind-
!V a ers to assist the surveyor in making a good survey: (a) On the survey form. record any and all pertinent information about the i survey and/or conditions which nught affect the results of the survey. Refer to it,em IV.B.1 on page 3 of these procedures for a listing of required infor-
- mation.
(b) Check the calibration tag on the instrument. If the instrument has not i been calibrated within the last 12 months, the instrument must be calibrated
- before the surve j cost to the user.Simply y is performed.
bring or shi The p theORS will calibrate instrument survey to the ORS officemeters to at no receive this service, or phone (409) 345-1361 for more information. ( (c) Check the batteries using the battery-check mechanism internal to the survey instrument. Most portable survey instruments have these capabilities built-in as standard eg,uipment. If your mstrument is not equipped with a i battery check mechamsm. attempt to verify that the survey meter will re-
- spond to radiation before each use it by observing its response to background .
or a known source. Routine battery checks using a voltmeter or routine i battery replacement should be insututed to maintain instrument reliability. 2 ! (d) The normal convention for radiation surveys is to hold the detector i approximately 1 meter (or approximately waist height) above the floor. i Other conventions may be adopted at any time: simply note the convention used on the survey form. Any survey recdin
- 3. ferent from the convention must be noted. g taken at heights or levels dif-4 l (e) Make a reading of the background radiation level and record this reading on the survey form. To make a background measurement, carry the instru-4
. ment to a location where you feel certain that the radiation reading is due ! solely to background radiation. For GM and scintillation detectors. this can l also serve as a check to ensure that the instrument is operable since the i needle of most GM and scintillation detectors should move at least slightly when reading only background radiation. h Make measurements at any and alllocations of possible interest. After } (f) the form is generated and fille'd out, addin g survey points is very simple and L quick. Special attention should be focuseo on radioactive material storag L areas such as refrigerators / freezers, cabinets, fume hoods, radioactive sm, ks e and sink traps, and radioactive waste containers both solid and liquid). In
- addition, surveys in places where radioactive ma(terials are not expec j often helpful id preventing future problems, e.g. student desks, refrigerators
- not normally used to store radioactive materia;s, and non-radioactive waste j contamers.
1 (g) Submit the completed survey form for review and approval by the re-sponsible Sub-licensee or his designated alternate. This review and approval
; must be indicated by signature and date.
O l Office of Radiological Safety March.1991 Page 5 of 13 i I .
IV.D. Radioactive Contamination Surveys Using Portable Radiation Detection Equipment J
- 1. Definitions... Radioactive contamination is defined as the presence of radioactive material where it is undesirable, harmful, or causes interference with normal activi-ties of, personnel. Radioactive contamination is commonly divided into two catego-L ries, " fixed" or "removabl:". Eimi contamination is that which is somehow incorpo-i j-rated into the surface or volume that it contaminates in such a manner that it cannot be removed by normal means such as rubbing or washing. Removable contamina-Iion is that which can be removed by wiping or washing a surface or volume. An example of fixed versus removable contanunation is a porous concrete floor on which a radioactive liquid was spilled. When someone walks on, touches, or mops or wipes the floor, radioactive contamination may be removed and carried elsewhere.
possibly contaminating a person or another area. If the floor is cleaned until radio- ! active material can no longer be removed by vigorous washing, wi or any other
- 4 practical means, but the radiation detector mdicates vity that radioacnpin I on the concrete floor, that remaining activity is regarded as fixed contaminatwn.
- Radioactive contamination surveys using portable radiation survey instruments detect both removable and fixed contammation. i.e. the detector cannot distinguish ~
i the difference.
- 2. Required When... Radioactive contamination surveys with instruments are neces-sary for monitoring personnel following completion of' work activities involving radioactive materials (excluding tritium), and for monitoring laboratory work benches. floors, sinks, hoods. and storage areas both routinely and follo' wing work with radioactive materials. Refer to Section IV.A for required survey frequencies.
These surveys are not required for laboratories using only sealed sources such as O moisture-density gauges or EC gas chromatographs.
- 3. Action Levels. Please refer to the table entitled ACCEPTABLE SURFACE CONTAMINATION LEVELS on the next page. These data are taken directiv from the Texas Regulations for Control of Radiatiori (TRCR Part 21). The columns entitled AVERAGE and MAXIMUM comain the values applicable to contamina-tion survey results obtained when using portable radiation detectors (i.e. total contamination). . If contamination levels renistered by the survey instrument exceed these levels (after background is subtracted') contact the ORS at 845-1361 immedi-ately.
- 4. Corrective Actions . When the results of instmment contamination surveys indi-cate that radioactive contamination exists, a wipe test or smear survey shoul'i be initiated to determine whether or not the contamination is removable refer to Section IV.E. page 10, of this procedure). If the contamination is remo(vable and is less than 10 times the applicable limits specified in the table entitled ACCEPT-ABLE SURFACE CONTAMINATION LEVELS commence decontamination 3rocedures. If decontamination efforts are successfulin reducing contamination evels to below 25% of the limit for REMOVABLE contamination, then document these efforts by performing a POST-Decontamination survey. If decontamination efforts are less successful or if the initial contamination levels exceed 10 times the applicable limits, contact the Office of Radiological Safety at 845-1361 for assist-ance.
O Office of Radiological Safety March,1991 Page 6 of 13
..- - . - - - -.-.. ~ - - -....- .- - -..-.. .- -
4 PART 21
. 1 1
Appendix 21-C i 1 ACCEPTABII SURFACE COMIAMINATION IIVEI.S O
- NUCLIDEa AVERAGEb ef b MAXIMUMbdf REMOVABII cef l
4 U-nat, U-235, U-238, and 5,000 dpm alpha / 15,000 dpm alpha / 1,000 dpm alpha / 1 associated decay products 100 cm2 100 cm2 100 cm2 except Ra-226, Th-230, Ac-227,
- i. and Pa-231 I ,
{ Transuranics, Ra-226, 100 dp=/100 a=2
~
300 dpm/100 an2 20 dpm/100 c::2 l
- Ra-228, Th-230, Th-228, i
- Pa-231, Ac-227, I-129 ih-nat, Th-232, Sr-90, 1,000 dpm/100 cm2 3,000 dpm/100 cm2 200 dpm/100 c
- 2
. Ra-223, Ra-224, U-232, l I-125, I-126, I-131, I-133 l Beta gamma emitters (nuclides 5,000 dpm beta, 15,000 dpm beta, 1,000 dpm beta, I with decay modes other than gama/100 cm2 alpna emission or spontaneous sama/100 an2 gamma /100 c=2 i fission) except Sr-90 and others noted above. i a Where surface contamination by both alpha and beta gamma emitting nuclides exists, the { limits established for alpha and beta gamma emitting nuclides should apply independently. b As used in this table, dpm (disintegrations per minute) means the race of emission by raaloactive mater:.al as deter =ined by correcting the counts per minute observed by an j appropriate detector for background, efficiency, and geometric factors associated with the j instrumentation.
- .
- Measurements of average contamination level should not be averaged over more than one souare meter. For objects of .less surface area, the average should be derived for each object.
d The maximum contamination level applies to an area of not more than 100 cm 2, e The amount of removable radioactive material per 100 cm2 of surface area should be deter- ! mined by wiping that area with dry filter or soft absorbent paper, applying moderate i pressure, and assessing the amount of radioactive material on the wipe with an appropriate
, instrument of known efficiency. When removable contamination on objects of less surface i j
.. area is determined,' the pertinent levels should be reduced proportionally and the entire '
! surface should be wiped. j f The average and maximum radiation levels associated with surface contamination resulting i from beta gamma emitters should not exceed 0.2 mrad /hr at 1 cm and 1.0 mrad /hr at i em, respectively, measured through not more than 7 milligrams per square centimeter of total i s absorber. i Office of Radiological Safety March.1991 Page 7 of 13
l 5. Instrument Selection . Although most laboratories have only one type ofinstru- ~ j ment. if more than one type of instrument is available, the person penormmg the
- survey must make the proper selection.
! (a) GM or Geiger-Mueller detector. Most laboratories have oni GM detec-i- tor (s) that have thin end-windows. These detectors can detect al ha. beta.
! nmmn-ray and x-ray radiations at very low levels. Common G detectors
! c "annot detect tritium and are relatively insensitive to radiations from Car-bon-14 and Iodine-125. 4 l 4 (b) Ion-chamber detector. Ion-chamber detectors are an1 normally used to 1 detect or quantify radioactive contamination. Contamination leveis which i are detectable by" an ion-chamber detector are likely to be very high and must be investigated further immediately. 1 4 (c) Scintillation detector. Solid scintillation detectors may be used to detect i j very low contamination levels in many instances. Particularly, thin enstal l Nal detectors are excellent instruments for detecting I-125 contamina' tion and ZnS detectors are some of the most sensitive alpha contamination detec-l tors available. However, scintillation detectors are often very specialized ! instruments. For example, neither NaI detectors nor ZnS are often desi ' or operated in a mode that .would allow them to detect beta radiations. gned } NOTE: TRITIUM (H-3) CANNOT BE DETECTED WITH ANY OF THE i DETECTORS LISTED ABOVE. TRITIUM CONTAMINATION i SURVEYS MUST BE PERFORMED USING WIPE TESTING METH- ' ! ODS DESCRIBED IN SECTION IV.E BELOW. i 6. Stuvey Procedures... Using a schematic diagram of the room or area being sur-i veyed, number or otherwise mdicate on the diagmm the locations where radiation measurements are made. On the diagram or on an atached sheet. record the i measurement reading for each survey location. The following are hints and remind-j ers to assist the surveyor in making a good survey: 3 (a) On the survey form. record the name of the person performing the ! survey, the date, the room number and building 1dentification where the survey is conducted, the model and serial numbers of the radiation detector. and a'ny other information pertinent to the survey; l' (b) Check the calibration tag on the instrument. If the instrument has not been calibrated within the last 12 months, the instrument must be calibrated 4 before the survey is performed. The ORS will calibrate survey meters at no : i cost to the user. ' Simply bring or ship the instrument to the OltS office to i receive this service, or phone (409) 845-1361 for more information. t
- (c) Perform a battery check per Section IV.C.4(c) above.
i i ' (d) The normal convention for performing instrument surveys for radioac-tive contamination is to hold the detector (normally the thin ' window portion e of the detector) approximately 1 centimeter above the surface being sur-j . veyed. The detector should be moved slowly over the entire area or interest. i [ Office of Radiological Safety March 1991 Page 8 of 13 _ - __ ,_ _ .. . _ , _ _ _ . . - - ~ . .
HINTS: i) The surveyor should wear a glove on the hand holding the detector ~ to prevent hand contamination. If this is done, the fingers can extend lower than the end of the detector so that the fingers slide alon g the surface being surveyed thereby keeping the detector at a constant heig 1t above the surface. l ' In addition, this technique also arevents the detector from coming in contact i with the surface where it could become contaminated. ii) Use the audio function on the instrument,if available. For most people. l slight increases in count rate above background levels are more easty heard than seen via the needle deflections. Use of the audio also allows the sur-i veyor to follow the detector and the survey area with his/he eyes rather than having to watch the survey meter readout. l iii) Radiation sources, radioactive waste, etc. which is stored in the vicinity of the area being survey
'is not due to radioacn,ed may cause the detector to respond to radiation which ve contamination. The surveyor must be wary of such possibilities to avoid recording invalid survey results.
l (e) Make a reading of the background radiation level and record this reading 4 i on the survey form. To make a background measurement, carry the instru- ! ment to a location where you feel cenam that the radiation reading is due solely to background radiation. For GM and scintillation detectors, this can ' also serve as a check to ensure that the instrument is operable since the needle of most GM and scintillation detectors should move at least slightiv l (on,th,e most lowest or most sensitive scale) from reading only background
- radianon.
l (f) Make measurements at any and alllocations of possible interest. After ! the smvey form is generated a'nd filled out, adding survey points is very simple and quick so take ample measurements. Special attention should be i focused on radioactive material storage areas such as refrigerators / freezers, 4 O> ( cabinets, fume hoods. radioactive sinks and sink traps, and radioactive waste i ' containers (both solid and liquid). In addition, surveys in places where radio-active materials are not expected are often helpful in preventing future problems, e.g. student desks, refrigerators not normally used to store radioac- ! tive materiajs, and non-radioactive waste containers. i (g) Submit the completed survey form for review and approval by the re-sponsible Sub licensee or his designated alternate. This review and approval must be indicated by signature and date. O Office of Radiological Safety March.1991 Page 9 of 13
IV.E Radioactive Contamination Surveys for Removable Contamination Using Wipe Tests i
- ~f I
- 1. Required When Radioactive contamination surveys for removaale contamina-tion are necessary for monitoring laboratory work benches, floors, sinks, hoods, and i storage areas on a routine basis as well as to ensure adequate cleanup of spills, work l
- areas following completion of work when instrument surveys are not effective.
g Wipe test surveys should be used to determine whether the radioactive contamina-i i tion found during an instrument survey (refer to Section IV.D) is removable or fixed. Wipe testmg followed by wipe countmg using a liquid scintillation counter is i i the only acceptable method for monitoring for tritium contamination and the pre-ferred method for monitoring for C-14 and I-125 contamination. These surveys are not required for laboratories using only sealed sources such as moisture-density l gauges or EC gas chromatographs. M Action Levels... Please refer to the table entitled ACCEPTABLE SURFACE : i CONTAMINATION LEVELS. These data are taken directly from the Texas ! ! Regulations for Control of Radiation (TRCR Part 21). Pleas ~e note that the last i column of that table refers to REMOVABLE contamination. Wipe tests only- l monitor for removable contamination and. therefore, these values apply dire'ctly to' i j the results of the wipe test. 4 I
- 3. Corrective Actions... When the results of wipe test surveys indicate that radioac-i tive contamination exists and is less than 10 times the aaplicable limits specified in i the preceding table entitled ACCEPTABI E SURFACB CONTAMINATION
- IFVFT A commence decontamination procedures or discard as radioactive waste.
3 i If decontaminatiori efforts are successfulin reducing contamination levels to below i l 25% of the limit, then documentation of the success by performance of POST-i decontamination surveys shall be sufficient. If decontamination efforts are less successful or if the initial contamination levels exceed 10 times the applicable limits ! , in the following table, contact the Office of Radiological Safety at 845-1361 for
- assistance.
l 1 i i i
- 4. Instrument Selection... Instrument selection for quantitative analysis of the radio- !
activity present on a wipe must take into consideranon the radioisotope for which i i the laboratory is being surveyed. l L (a) Liquid Scintillation Counter. Wipe tests performed to identify the presence of tritium (H-3) contamination must be analyzed using a liquid scintillation counter. No other commonly available instrument exists for . monitoring tntium contamination on wipes. Li often the best instrument for Iodine-125 and (I-125) mostquid scintillation counters beta-emitting radioisotopes since these isoto aes are typically detected with high efficiencies i (usually greater than 50%). Although the LSC is more difficult to use than a L GM survey meter, LSC use may be simplified by using an open energy i window to detect any and all ra'dioactive contaminants regardless of ener Furthermore, conservative generic efficiency factors of 33% are recom gy. mended unless the radioisoto ae for which th'e survey is being performed is
- known. Refer to the attachec table for recommended efficiency factors for i
- use with various instruments.
- O Office of Radiological Safety March,1991 Page 10 of 13 l
I
i j (b GM Survey Instrument (with end-window detector). The GM survey
~
- ins)trument is the easiest and quickest means of quantifying i
collected on a wipe test. ' However, the GM survey instrument is relatively insensitive to low-energy gamma and beta radiations and is therefore rela-O~ tiv ivi trici =treroct cri==r di tie == rr -r diet etee ch c r8 - ! 14 (C ,14) and Iodine-125 (I-125). The GM survey instrument =isincapable of l detecung beta radiations from tritium (H-3). Refer to the attached table for L recommended efficiency factors to use with various instruments. (c) Scintillation Detectors. Solid scintillation detectors can provide highly i efficient detection of gamma-emitting radioisotopes such as Iodine-125 (I- ' 125). However, the solid scintillation detector should not be utilized for analyzing wipes possible contaminated with beta or alpha emitting radioiso-topes im ess the mstrument is specifically designed to detect those radiations, e.g., ZnS scintillation detectors for alpha radianon detection. Refer to the I attached table for recommended efficiency factors to use with various in-struments.
- 5. Wipe Selection... If a liquid scintillation counter is to be utilized for the analysis of the wi tissue.pe. the wipe must consist of something like a small piece of Kimwipe or fens This type of smear beenmes nearly transparent to the scintillator's light emissions when the wipe is thoroughly wetted by the cocktail. If a GM survey meter or scintillation detector is to be used t'o analyze the wipe, an acid-hardened, dry filter paper is recommended. For example, the 47 mm diameter Whatman paper filters !
are used for this purpose by the Office of Radiological Safety. !
- 6. Wipe Test Frequency... Refer to Section III above.
- 7. Wipe Test Procedures...
(a) Regulatoryguida ing an area of 100 .cmgee for performing wipe tests calls for wiping or sm glease note that the regulatory limits are also ex-pressed as dpm/100 cm . (b) Use a survey map or schematic diagram of the area to be surveyed to l indicate the locations where wipe tests are made. Include pertinent informa- l tion on the survey form which might aid in review orinterpretation of the 1 survev results. R'efer to Section IV.B.1 (page 3) of these procedures for a list-ing of the required information. We recommend that the stuveyor wipe any areas where radioactive contamination is suspected but not wanted and any ' other area where radioactive contamination is likely to have spread if l someone in the lab had become contaminated but had been unaware. For l example, wiae test the front of fume hoods, floors, lab benches, refrigerators l (especiall locations,y it istie handles), sinks, recommended etc. that the If contamination surveyor consider wipeistesting founddesks, in any of these telephones, door handles, floors in doorways which exit the " hot" area, etc. (c) Keep the wipes separated when practical. Allowing one wipe which might be contaminated to touch another could result in cross-contamination so that two areas are identified as being contaminated instead of one area. O Office of Radiological Safety March,1991 Page 11 of 13
(d) Forliquid scintillation counters, place each of the wipes into its own vial, - add at least 5 ml of LS cocktail to each vial (or enough to thoroughly wet and
- cover the wipe), cap the vials, and count each on the LSC in an open energy window for one mmute. Record the number of counts from the LSC as the
" gross" counts per minute, or " gross" cpm. ; (e) For GM survey meters and solid scintillation detectors, place the dirty or i
possible contaminated side of the wipe as close as practical to (but not more than 1 cm from the end-window (or most sensitive portion) of the detector and count for on)e minute. Record the number o
" gross" counts per minute, or " gross" cpm.
j (f) Determine a backgound count rate. For the LSC, place the same volume o4 cocktail as was usec with the wipes into a clean vial with an unused wipe i
- ~
and count on the LSC for one minute in the same way that the wipes were
- counted. Record this count result as the " background" count. Tlus value
! should be subtracted from each of the " gross" counts determined in (d) above and recorded as the " net" cpm. For the GM survey instrument and the solid i scintillation detectors, determine a background count rate by counting a wipe for one minute or longer. Record this value as the " background count 4 rate and subtract this value from the " gross" cpm readings from (e) above. Record these values as " net" cpm. 3 (g) Divide the " net" cpm values from (f) by,the appropriate efficiency factors i-from the following table entitled " Efficiencies of Various Detectors fo' r Common Radiogotopes" to calculate the appropriate contamination values ! in dpm/100 cm . Record these values for each survey location. s (h) Submit the com aleted form to the Sub-licensee or his/her designee for jJ 3 review and approval and signature. i l' ,
- 4 i
Office of Radiological Safety March,1991 Page 12 of 13 i
~
EFFICIENCIES OF VARIOUS DETECTORS FOR COMMON RADIOISOTOPES
-O V
NominalInstrument Response (%) End-Window Scintillators Isotope Radiation Energy GM NaI ZnS Liquid j H-3 Beta 19 kev 0 0 0 30 C-14 Beta 157 kev 1-5 0 0 60 S-35 Beta 167 kev 1-10 0 0 60 Ca-45 Beta 258 kev 10 0 0 80 P-32 Beta 1.7 MeV 25
- 0 80 I-125 Gamma 35 kev 1-5 20 0 80 Cr-51 Gamma 350 kev 5-10 30 0 50 Alpha 5.3 M e V 1-10 0 30 90 0 Po-210 Gamma 803 kev 5-10 30 0 30 Am-241 Alpha '5.4 MeV 1-10 0 30 90 Gamma 59 kev 1-5 20 0 80
- Variable but low due to the penetrating power of the P-32 beta particle and its ability to produce significant Bremstrahlung Radiation.
~
r\ bbffice of Radiological Safety March,1991 Page 13 of 13
~
1 Please complete the information requested below. This is to make our contact with you and your lab more 1 efficient. In other words, we will not be bothering the wrong people at the wrong time for the wrong reason!
. l If the same person handles all operations. list their first and last name and phone number in the first applicable blank (use the last name only in the other applicable blanks). Please PRINT legibly.
Yes, this may seem redundant, but please take the few minutes needed to fillit out and return to Radiological Safety Office (MS - 3261). Thank you.
................................=... ....................
Licensee: Lic. #: Dept.: l Mail Stop: Bldg Name: Mailing address (if off campus): i City: State: Zip: ' Room Number (s)- Lab: Office: Phone Number (s) - Lab: Office: i i Person to contact regarding:
- 1. LAB FUNCTION AND OPERATION in the absence of licensee:
Phone:
- 2. ORDERING OF ISOTOPES: Phone:
- 3. INVENTORY OF ISOTOPES: Phone:
- 4. DISPOSAL OF ISOTOPES: Phone:
- 5. DOSIMETRY BADGES: Phone:
1
- 6. PAPERWORK: Phone: l
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+
j 1 I
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