ML20059G780

Id State Univ Radiation Safety Policy Manual

ML20059G780
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Site:	07001374
Issue date:	04/30/1992
From:	IDAHO STATE UNIV., POCATELLO, ID
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26 l

IDAHO STATE UNIVERSITY RADIATION SAFETY POLICY MANUAL i

Prepared and issued under the auspices of l

TIIE RADIATION SAFETY C05BIITTEE l

i l

l For additional information, contact TIIE RADIATION SAFETY OFFICER t

Radiation Safety Division f

Technical Safety Office i

Idaho State University Box 8106 Pocatello. Idaho 83209 (208) 236-2311 Approved by the Radiation Safety Committee April 1992 W

Chair, Radiation Safk{ Committee t

'\\4 k,,'%

- ' ' Radiation Safety Officer l

l 9311090085 931015 P

PDR ADOCK 07001374 1

B pyg y

Record of Revisions Revision /Date Affected Pages Entered On By 1

1

TABLE OF CONTENTS PURPOSE...........................................

1 ENIERGENCY PROCEDURES

.............................1 BASIS FOR RADIATION PROTECTION POLICIES...............

3 3

Radiation-Induced Health Effects Principles of Radiation Protection 4

Radiation Doses and Risks..

4

.5 Individual Dose Limits ALARA Policy 6

RES PONS IBILITIES....................................

6

.7 Radiation Safety Committee Radiation Safety Officer..

.8 Radiation Safety Division of Technical Safety Office

.9 Radiation Users.

9 Responsible User 10 RADIATION S AFETY TRAINING........................... I1 CONTROL AND AIONITORING OF EXPOSURES TO EXTERNAL RAD IATION SO URC ES................................. 12 X-ray Machines 12 Radioactive Materials 13 Exposure Evaluation and Monitoring 13 Personal Dosimeters (Badges) 13 CONTROL AND 310NITORING OF INTAKE OF RADIOISOTOPES.... 14 Handling Precautions 15 Contamination Suneys 15 Airborne Activity 16 Bioassays 16 S ERVIC E FEES......................................

17 l

Extraordinary Costs 17 Optional Senices 17 Page i

t 1

LABORATORY EVALUATIONS; SURVEYS AND AUDITS 17 CALIBRATION OF INSTRUMENTS

........................19 SEAL.ED SOURCE LEAK TESTS...........................

19 l

TRANSPORTATION AND SHIPMENT OF RADIOACTIVE MATERIALS. 19 1

RADIOACTIVE WASTE MANAGDIENT.....................

20

}

BIBLIOGRAPHY

.....................................20 l

1 G LO SS ARY.........................................

22 i

Acronyms and Abbreviations

....................22 Areas...

.........................................22 Monitoring and Surveying................................

23 Quantities and Units..

...........................23 Users...............

.............................26 ACKNOWLEDGDIENT 27 i

l i

l t

I Page ii i

...,,_,.___m...

RADIATION SAFETY POLICY MANUAL PURPOSE l

This manual conveys the official policies of Idaho State University for the control of all sources of, and exposures to, ionizing radiation that are within the jurisdiction of the University. The manual defines responsibilities of individuals and organizations for radiation control, it specifies the policies that guide specific decisions on radiation control matters, and it provides general safety mies and procedures that are obligatory for all users of mdiation sources. Requirements and procedures not included in this manual are developed, promul-gated and enforced as necessary to implement the overall philosophy and policies for radia-tion protection as presented herein.

Federal and state regulations require a written radiation protection program, which includes provisions for keeping doses As Low As Reasonably Achievable (ALARA). All radiation users must be included in the program and must be informed of the prognm and of their individual responsibilities. This manual is intended to satisfy these regulatory requirements.

El\\ERGENCY PROCEDURES 4

Radiation Emercency Any accident, injury or loss of control of a radiation source that could cause an excessive or uncontrolled radiation exposure to any individual is referred to as a radiation j

I emergency. The proper response to any radiation emergency depends upon a thorough understanding of the magnitude of risks, priorities for action and the application of common sense. Each user of radiation sources should be familiar with the basic emergency responses listed below and methods for applying them in his or her own work area.

Protect People!

ine first consideration in any emergency is to assist injured persons and to prevent any funher injury. If the situation involves a radiation producing rpachine, the machine should be tumed off to prevent unnecessary exposure to the injured individual or to individuals providing assistance. For medical assistance, dial 8-911 immediately and report the nature of the illness or injury. Inform the 911 dispatcher that the injured individual may be contaminated with radioactive material. If you are qualified to render first aid, do so without regard to the presence of radioactivity. There are no radioactive sources at the University that produce radiation exposure risks large enough to prevent giving first aid! Notify University Security, at 236-2514 or 2515 of the situation. Security will provide RADIATIOfJ SAFETY POLICY MAfJUAL (4/92) - PAGE 1

.l t

I assistance and will aid in directing emergency response personnel to the scene. Except for i

the usual precautions for moving an injured person, individuals should immediately leave the room or area until the extent of the radiological hazard has been evaluated. However, all l

individuals should remain available in the vicinity until checked for contamination or exposure.

Get IIelo!

Each individual using radiation sources j

should know in advance who to call in case of a radiation emergency. If fire, injury or other EMERGENCY TELEPHONE emergency conditions, m addition to radiation E SERS l

are involved, first call the appropriate numbers listed on page 1 of the Campus Directory.

Fire, ambulance, or Then call the Radiation Safety Division of the medical assistance:

l Techmcal Safety Office: extension 2311 dunng nomial office hours; extension 2514 or 2515 '

8-911 and 236-2515 (Security) during off duty hours.

l Radiation Safety Division.

t When reporting any emergency, be sure of Technical Safety to state the exact nature of the emergency; then Office give your name and the phone number from j

which you are calling, the exact location of the Normal business emergency (building, room, nearest entrance, hours: 236-2311 etc.) and the name of the Responsible User, if l

known. Do not hanE uD! Let the person Other than nonnal called end the conversation after all pertinent us ness houn:

infonnation is clearly understood.

j ecur y:

r 515 l

Contain the IIazard!

Any of the following actions appropriate to the situation should be performed provided they can be carried out safely:

1.

Turn off radiation producing machines.

2.

Cover containers of radioactive materials.

3.

Place absorbent material on spilled liquids.

4.

Close the sash on fume hoods, but do not tum off hood exhaust fans.

5.

Close doors to the area and post signs or guards to prevent unauthorize 30 ALIs Monthly l

j 1-30 Alls Each bioassay interval 1

< 1 ALI Semi-annually

]

Inactive""

Annually 3

Monthly average durmg interval.

See text.

f l

RADIATION SAFETY POLICY MANUAL (4/92) - PAGE 18

CALIBRATION OF INSTRUhENTS Ponable radiation survey instruments in active service are calibrated semi-annually, or following repair, by personnel of the Technical Safety Office Department using procedures in

" CALIBRATION AND USE OF PORTABLE SURVEY INSTRUMENTS" RPR $2).

1 Instmments for measuring exposure rates are calibrated for linearity of response on all useful ranges. Instruments used for contamination surveys are calibrated for detection efficiencies for various nuclides, as well as for linearity of response.

SEALED SOURCE LEAK TESTS Sealed sources of radioactive material shall be tested for leakage at regular intervals to verify the integrity of the source containment and, in the unlikely event of failure, to detect the escape of radioactive material before serious contamination of facilities, equipment or personnel occurs. The frequency of leak tests, and the sensitivity of detection of escaping radioactivity, shall comply with the regulations or license conditions specified by the agency authorizing the possession of the source. Leak tests are to be performed using procedures approved by the Radiation Safety Officer. Records of sealed source leak tests are maintained by the Radiation Safety Division of the Technical Safety Office.

I TRANSPORTATION AND SHIPMENT OF RADIOACTIVE MATERIALS Radioa. tive materials of any kind may be transponed on public roads on or off University propeny only if packaged and labeled in compliance with U.S. Depanment of l

Transponation (DOT) regulations. Radioactive materials may be shipped from the University to another organization or individual only after verification by the RSO that all transfer packaging, labeling and transponation requirements have been met.

To assure that all requirements for shipment are met, and that appropriate records are maintained, a written authorization form and one or more check lists must be prepared by the l

individual responsible for the shipment and approved by the RSO before the shipment is l

made. The instmetions and forms for various applications are contained in Radiation Procedures and Records related to those applications. Instmetions for " SHIPMENT OF LIMITED QUANTITIES OF RADIOISOTOPES" are contained in RPR 14. For all other transfers or shipments, the instmetions and forms are contained in " TRANSPORTATION OF RADIOACTIVE MATERIAL" (RPR.55).

RADIATION SAFETY POLICY MANUAL (4/92) - PAGE 19 I

I RADIOACTIVE WASTE MANAGEMENT l

Radioactive wastes (radwastes) shall be collected, stored, packaged, shipped and disposed of in accordance with all peninent state and federal regulations. The RSO shall prepare and maintain pn>cedures for handling radwastes that will ensure the protection of the i

employees involved in such duties and keep all radiation exposures ALARA. Specifications i

for segregation and packaging of radwastes shall be based on specific regulations or regu-latorf guidance, and include a record-keeping system that will allow complete tracking and l

accounting for all radwastes shipped to a disposal site or disposed of locally. Refer to l

" RADIOACTIVE WASTE MANAGEMENT" (RPR 54).

BIBLIOGRAPHY International Commission on Radiological Protection (ICRP):

l Recommendations of the ICRP, Publ. 26 (1977).

i LimitsforIntakes ofRadionuclides by Workers, Publ. 30 (1979-88).

3 l

General Principles ofMonitoringfor Radiation Protection of Workers, Publ. 35 l

l (1982).

I Radionuclide Transformations: Energy and Intensity ofEmissions, Publ. 38 (1983).

l Indisidual Monitoring for Intakes of Radionuclides by Workers: Design and Interpretation, Pub "988).

National Council on Radiation Protection and Measurements (NCRP):

Review ofNCRP Radiation Dose Limitfor Embryo and Fetus in Occupationally Erposed Women, Repon 53 (1977).

Protection of the Thyroid Gland in the Event of Releases of Radioiodine, Repon 55 (1977).

Operational Radiation Safety Program, Repon 59 (1978).

Management of Persons Accidentally Contaminated with Radionuclides, Repon 65 (1980).

Operational Radiation Safety - Training, Repon 71 (1983).

1 J

RADIATION SAFETY Poucy MANUAL (4/92) - PAGE 20 4

Radianon Protc' don and AfeasurementforLow Voltage Neutron Generators, Repon 72 (1983).

General Conceptsfor the Dosimetry ofIntemally Deposited Radionuclides, Repon 84 (1985).

Use of Bioassay Proceduresfor Assessment ofinternal Radionuclide Deposition, Repon 87 (1986).

Recommendadonsfor Limitsfor Erposure to Ionizing Radiation, Repon 91 (1987).

U.S. Nuclear Regulatory Commission, Code ofFederal Regulations, Title 10 (10 CFR):

Notices, Instructions and Repons to Workers; Inspections, Pan 19.

Standardsfor Protection Against Radiadon, Pan 20.

Rules of General Applicability to Domestic Licensing ofByproduct Afaterial, Pan 30.

Specipc Domestic Licenses of Broad Scopefor Byproduct Afatenal, Pan 33.

Human Uses of Byproduct Afaterial, Pan 35.

Packaging of Radioactive Afaterialfor Transport and Transportation ofRadioactive Afaterial under Certain Conditions, Pan 71.

Idaho Department of Health and Welfare, Rules and Regulations Idaho Radiation Control Regulations, title 1, Chapter 9 l

RADIATIOtJ SAFETY POLICY MATJUAL (4/92) - PAGE 21

I e

i GLOSSARY ACRONDIS AND ABBREVIATIONS ALARA: The basic premise of radiation protection, i.e. that all radiation doses should be kept _As _IAw As Reasonably Achievable, taking into account social and economic consid-erations, through the application of sound radiation protection practices, procedures and engineering controls.

ALI: The Annual Limit on Intake is the quantity of any radionuclide which, if taken into the body, pmduces an effective dose to internal organs that is equivalent in risk to the annual whole body dose limit of 5 rems. Because of differences in physiological transport mechanisms, the ALIs vary depending on the ruute of intake. For purposes of contamination control and bioassay procedures, the ALI for ingestion is used, since that is the most common route of accidental intake in research laboratories.

RSO: The Radiation Safety Officer (RSO) is the individual specifically appointed and named on the radioactive materials licenses, to establish and enforce such procedures as are necessary to assure compliance with applicable regulations and license conditions, and to ensure effective implementation of the policies and rules established by the Radiation Safety Committee. Depending on the context, "RSO" may also refer to any individual designated to act on behalf of the RSO.

l AREAS Controlled Area: Any area to which access is limited for any reason. X-ray rooms and -

accelerator rooms are controlled administratively by the personnel who operate the equipment. Radioisotope laboratories are controlled by posting and locking for the purpose of preventing unauthorized removal of radioactive materials. Exposure to radioactive materials is prevented by controlling the materials, not by limiting normal access to the laboratory when it is open and attended.

l Iliah Radiation Area: Any accessible area in which an individual could receive a dose equivalent exceeding 100 miem in I hour at 30 cm (1 ft) from the source or from any surface the radiation penetrates.

Radiation Area: Any accessible area in which an individual could receive a dose equivalent l

exceeding 5 mrem in I hour at 30 cm (1 ft) from the source or from any surface the radia-l tion penetrates.

I Radioisotooe Laboratorv: Any room or area in which 10 or more Reference Quantities of unsealed radioactive materials are stored or used.

RADIATION SAFETY POUCY MAfJUAL (4/92) - PAGE 22

Restricted Area: Any area to which access is limited for the purpose of protecting individuals against undue risks from exposure to radiation and/or radioactive material. The mere presence of any radiation source, if adequately controlled to limit potential exposures, does not necessitate a restricted area designation. Areas containing sources with the potential for producing significant exposures require specific authorizations and procedures or posting for access control and are designated as restricted areas.

University Facility: Any real property permanently or temporarily owned by or under the control of the University.

MONITORING AND SURVEYING j

j Bioassav Interval: The bioassay interval for a particular radioisotope is the maximum time that may elapse betweea bioassays tiat will assure detection of the verification level for a given assay method. The bioassay interval for a particular radioisotope is determined by its physical and metabolic characteristics, and by the instmmentation used for the measurement.

i See BIOASSAYS FOR INTERNAL RADIOACTIVITY (RPR 12).

Contamination Survev: A systematic investigation to detennine the presence, or to verify i

the absence, of radioactive materials in unwanted locations, e.g. on the body or personal i

clothing, on surfaces of objects that may be touched or handled, on equipment or materials to i

be removed from a restricted area, etc.

l Exposure Survev: A systematic investigation to determine extemal radiation exposure mtes at specific locations where individuals may be present ar potentially exposed.

e i

Nonnenetrating Radiation: Ionizing radiation from extemal sources that is not likely to deliver significant doses to organs or tissues more than I cm deep in the body, e.g. beta particles and low energy photons, i

Penetrating Radiation: Ionizing radiation from external sources capable of delivering i

significant doses to organs or tissues more than I cm deep, e.g. x or gamma rays and j

neutrons.

Wine Test: The detection and evaluation of removable contamination by measurement of radioactive material wiped from the surface onto an absorbeni material such as a filter paper.

QUANTITIES AND UNITS Ahsnrbed dose is the mean energy per unit mass imparted to any matter by ionizing radiation. The common unit of absorbed dose is the rad, defined as an absorbed energy of 100 ergs per gram of material. The new international standard unit is the gray (Gy), defined as an absorbed energy of 1 joule per kilogram of material; I Gy = 100 rads.

RADIATION SAFETY POLICY MANUAL (4/92) - PAGE 23 i

,..,.,--.----c

I i

l I

l i

Activity: A quantity of a radionuclide specified by the mean rate of spontaneous nuclear

{

transformations which it undergoes. The common unit of activity is the curie (Ci), defined as the quantity of radioactivity which decays at the rate of 37 billion transformations per second.

Quantities of mdioactivity of biological or environmental interest are commonly expressed in j

submultiples of the curie:

I millicurie (mci) = 3.7 x 10's

2.2 x 106 min ~' (dpm)

I microcurie ( Ci) = 3.7 x 10's-'

=

I nanocurie (nCi) = 37 s = 2,220 dpm i

i picoeurie (pCi) = 0.037 s-* = 2.22 dpm j

i The new intemational standard unit for activity is the becquerel (Bq) 1 Bq = 1 transformation per second.

f Committed dose eauivalent (Hrso) means the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual i

during the 50-year period following the intake.

Committed effective dose eauivalent (Hs.50) is the sum of the products of the weighing factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.

Deen dose eauivalent (H,), which applies to external whole-body exposure, is the dose equivalent at a tissue depth of I cm (1000 mg/cm ).

2 Dose: used in this manual refers either to absorbed dose or to dose equivalent, depending-i upon the context and the units used.

Dose eauivalent (Hr) means the product of the absorbed dose in tissue, quality factor, and I

I all other necessary modifying factors at the location of interest. The units of dose equivalent are the rem and sievert (Sv).

Effective dose eeuivalent (H ) is the sum of the products of the dose equivalent to the organ t

or tissue (Hr) and the weighing factors (W ) applicable to each of the body organs or tissues 1

that are irradiated.

4 i

RADIATION SAFETY POLICY MANUAL (4/92) - PAGE 24 4

-,,. _,.... _, _..,. _ _ _.. _. _,,, _ -. _.... _. _ _ _. ~..,. _... _..

Exposure usually refers to any condition which creates the potential for any individual to receive a radiation dose, either from external irradiation or from internal contamination with radioactive materials. For radiation measurements, " exposure" refers to the intensity of x or gamma irradiation, specified by the ionization produced in air. The common unit of

)

exposure is the roentgen (R). An exposure of 1 R delivers almost I rad (0.869 rad m air or 0.93 rad in soft body tissues). Submultiples of the roentgen are normally combined with time units to express exposure rates, e.g., milliroentgen per hour (mR/hr), etc.

i Extremity means hand, elbow, arm below the elbow, foot, knee, and leg below the knee.

Eve dose eauivalent applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm ).

Interval Inventory: The total quantity of radioisotopes introduced into the lab each month, averaged over the bioassay interval, expressed in ALIs.

Radiation Machine: Any device capable of producing ionizing radiation except those which produce radiation only from radioactive material.

Radioactive Material: Any solid, liquid or gaseous substance which spontaneously emits any type of ionizing radiation.

l l

Radiation Source: Any " Radiation Machine" or " Radioactive Material" emitting or capable of producing ionizing radiation.

t Radioisotope: As used in this manual and related procedures, a " radioisotope" is any j

radioactive nuclide used in unsealed or dispersal form. This terminology is used primarily to I

characterize the form of the material and the nature of the use.

l l

Reference Ouantitv: A quantity of any radioisotope related to its relative hazard potential and used to prescribe requirements for handling, monitoring, labeling and disposal.

i Sealed Source: Radioactive material that is permanently bonded or fixed in a capsule or matrix designed to prevent release and dispersal of the adioactive material under the most severe conditions which are likely to be encountered in normal use and handling.

Shallow - dose eauivalent (Hs), which applies to the external exposure of the skin or an l

2 extremity, is taken as the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm )

j averaged over an area of I square centimeter.

j B

I RADIATION SAFETY POLICY MANUAL (4/92) - PAGE 25

)

1 l

l l

1

1 Weiching factor (W ), for an organ or tissue (T) is the proportion of the risk of stochastic 7

effects resulting from irradiation of that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. For calculating the effective dose equivalent, the values of W are:

r Organ Dose Weighing Factors Orean or Tissue lL Gonads

. 0.25 Breast 0.15 Red bone marrow 0.12 Lung.

. 0.12 Thyroid 0.03 Bone surfaces 0.03 Remainder 0.30' Whole Body..

1.0 06 Footnotes:

• 0.30 results from 0.06 for each of 5 " remainder" organs (excluding the skin and the lens of the eye) that receives the highest doses.

• For the purpose of weighing the external whole body dose (for adding it to the intemal dose),a single weighing factor. W =1.0, has been specified.

r USERS t

Radiation user: Any individual whose official duties or authorized activities include handling, operating, or working in the presence of any type of radiation source is classified as a radiation user. For purposes of evaluating radiation protection requirements, radiation users may be considered as belonging to one of the following sub-groups:

Alternate responsible user: An individual authorized by the RSC (or temporarily authorized by the RSO) to assume the duties of the responsible user in the absence of the later. The alternate responsible user will normally be required to possess the same qualifications as the responsible user.

Normally exposed users are those who may be expected to receive doses exceeding 10% of the occupational limits. Radiation doses to these individuals are individually monitored.

RADIATIOtJ SAFETY POLICY MANUAL (4/92) - PAGE 26

t f

Minimally exposed users are those who are unlikely to receive any radiation dose greater than 10% of any occupational limit. This category includes individuals who do not work routinely with radiation sources, but whose of6cial duties may occasionally bring them into l

areas where adiation exposures may occur, e.g. emergency, security, maintenance, receiving i

and shipping personnel, custodial and housekeeping staff. Radiation training and monitoring for these users are conducted and recorded on a group, rather than an individual, basis.

Potentially exposed users are those who are unlikely to receive a dose greater than 10% of any occupadonal limit, but who work with sources that could produce large accidental doses, e.g. accelerators or therapy units. Radiation doses to these users are individually monitored.

l Responsible user: An individual authorized by the Radiation Safety Committee to acquire and use specific radiation sources, and to supervise their use by others, in compliance with peninent regulations and imder conditions approved by the Committee. Responsible users must demonstrate, to the satisfaction of the Committee, competence in the safe use of radiation sources by vinue of appropriate training and experience. Responsible users must j

assume full responsibility for all mdiation sources under their control.

J l

ACKNOWLEDGEl\\ENT i

i This manual was prepared by Morris Hall under the direction of Thomas Gesell and reviewed by the ISU Radiation Safety Committee. It is based in pan on the radiation policy manual of the University of Utah. Dr. Keith Schiager, Radiation Safety Of6cer of University of Utah and President-elect of the Health Physics Society, gave freely of his time and expenise during the preparation of this policy manual. His contribution and that of his staff is greatly appreciated. The contributions of Ken Whitham and Jennifer Buchanan are l

also appreciated.

t 1

4 d

RADIATION SAFETY POLICY MANtJAL (4/92) - PAGE 27

7 RADIATION SAFETY I

i PROCEDURES AND RECORDS (RPRs) l i

i i

FOR RADIOISOTOPE USERS

~

l RADIONUCLIDE DATA (RPR 10)

RADIOISOTOPE LABORATORY SAFETY PROCEDURES (RPR 11)

BIOASSAYS FOR INTERNAL RADIOACTIVITY (RPR 12)

RADIOlSOTOPE ACQUISITION AND DISPOSITION (RPR 13)

SHIPMENT OF LIMITED QUANTITIES OF RADIOISOTOPES (RPR 14)

HOUSING AND HANDLING OF RADIOACTIVE ANIMALS (RPR 15) m n

l 7

LIQUID SCINTILLATION MEDIA Fluors containing non-hazardous, non-toxic (NHNTI solvents are required unless a specific exception is obtained from the RSO or the Radiation Safety Committee. Examples of such fluors are:

• NEfficienc/

Flow *

'llEfficienc/

Flow

• Fluor (mfor.)

meen i SD fu)

(sec)

Fluo:- (RFer.)

Mean 2 SD (N)

M BCS (AMER)

Betaanx-ES (ICN)

Ecoltage (ICN)

Ecolite(+) (ICW) tytoscint-ES (ICN) universol-ES (ICN)

(pti-Fluor (PACK) 39.7 2 5.5 (24) 3.2 opti-Fluor o (FACK)

Poly-Fluor (FACK) ultian Gold (PACK) 43.1 s 2.1 (24) 5.5 Ready safe (BECK) 40.6 s 4.2 (24) 7.2

= Trititsu counting efficiencies are based on 0.1 mL samle in 4.0 mL fluor; " Flow" represents the time for a fixed -

voltane to flow from a pipette and is inversely proportional to viscosity; data from Klein, RC and Gershey, EL,

'Biocegradable' liouid scintittation counting cocktails, Health Physics 59:461-470, 1990.

AMER = Amersham Corp., Arlington Heights, IL 60005 800-323-9750 i

SECK = Beckman Instruments, Fullerton, CA 92634 800-742 2345 I

ICN = ICN Radiochemicals, Irvine, CA 92713 800-854-0530 PACK = Packard Instrtsment Co., Downers Grove, IL 60515 800-323-1891 1

ICN Radiochemicals, Irvine, CA 92713 800-854-0530 j

Solvent-Free, Isolab, Inc., Akron, OH 44321 800-321-9632 Bio-Safe II and sio-safe NA Research Products International Corp., Mount Prospect, IL 800-323-9814 Ecoscint A (aqueous samtes), Ecoscint o (organic samtes)

National Diagnostics, 1013-1017 Kennedy Blvd.

1 Manville, NJ 08835 2031 800-526-3867 i

Fluors containing toxic or flammable solvents may not be purchased without prior approval from the RSO.

5 Examples are:

i Beckman:

CP, MP, HP/b, EP, MP, NA, Ready Micro, Ready Solv, Ready Protein, Ready Get, Ready Value, Peady Organic, Reacy Flow II, Ready Flow !!!

3CN:

Universatt NEN:

Aguasol. Aquasot-2, Econofluor, Econottuor-2, Formula 963, Liquifluor, onnifluor, Atomlight, Aquasure, Biofluor, Riefluor, and att "NEF= r u bers Packard:

Insta-Get xF, Scint-A XF, Pico Aoua, Pico-Fluor 15, Pico-Fluor 40, Hionic Fluor, Filter-Count, Pico-

[

Fluor LLT, Insta-Fluor, Permafluor V, Monophase 5, Flo Scint I, II,11!, IV, and V, l

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y m_

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y,..

p<..m, r,.,.--..,r,,

e..-,.-,m,-.

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RADIATION USER PERSONAL DATA 07-i 1

PURPOSE I

documentation stating they have received radiation This procedure specifies the personal data that must safety training (RPR 1B), as specified by the RSO.

be provided by each radiation user. The user shall Radiation users that will be individually monitored provide a summary of training and experience with for radiation exposure are required to provide radiation sources (RPR 1 A) and, if neCe-ssary, a form Certain personal information (RPR 1 A) to the TSO.

(RPR 1B) to request radiation exposure or radiation safety training records from previous employers.

The required information includes:

i

[

The confidentiality of personal data, and the right of i

individuals to review their own records and to (1) primary ioentification data, e.g. full name, obtain written summaries of radiation exposures are also specified.

birth date, sex, and social security number.

(2) previous training and experience with radiation sources.

DEFINITIONS l

" Radiation User" is any individual whose official (3) current employment status, including job duties or authorized activities include handling, title or description, department, supervisor, and work location.

operating, or working in the presence of, any type of radiation source, whether or not such use is confined to a restricted area.

Personal records of radiation users will also contain r

the scores obtained on tests taken to demonstrate "Normally Exposed" radiation user is an individual knowledge of radiation safety procedures, data 4

who could receive more than one tenth (10%) of obtained from monitoring of extemal and internal radiation exposures, and reports on any injuries or the occupational radiation dose limit in any calendar abnormal incidents related to the use of radiation quarter. This category includes individuals who

{

sources.

normally receive more than 100 mrem per quarter, i

as well as some who rarely receive more than 100 mrem in a quarter, but who work with sources that Individual radiation user records are treated as i

could produce a significant dose accidentally.

confidential and are available only to individuals 4

with a legitimate need for the information. An "Potentially Exposed" radiation user is an individual individual may review the contents of his or her personal radiation user file at any time. All who is unlikely to receive a dose greater than 10%

personnel will receive a copy their radiation of any occupational limit, but works with sources that could produce large accidental doses,;e.g.

monitoring record at the end of the monitoring year, accelerators and nuclear reactors. Radiation doses to these individuals are individually monitored.

PROCEDURE

" Minimally Exposed" radiation user is an individual who is unlikely to receive one tenth (10%) of the Each radiation user shall submit a completed "RADI-occupational radiation dose limit in any calendar ATION USER TRAINING & PERSONAL DATA" form (RPR 1 A) to the TSO before starting work with any quarter. This category includes individuals who radiation sources. If any previous employment routinely handle only small quantities of radioactive materials, and others exposed only intermittently, involved potential exposure to ionizing radiation, a e.g. dental hygienists, emergency and security

" REQUEST FOR RADIATION EXPOSURE HISTORY personnel, maintenance, receiving, custodial and AND/OR TRAINING VERIFICATION

• form (RPR 1B) housekeeping personnel.

shall also be completed for each previous employer.

POLICY 4

Before a radiation user is allowed to use radiation sources or radiation producing machines, they must 4

partiicipate in radiation safety training, or provide ll RPR 1. FTRsoNAL DATA (12s2F1 5

)

RPR 1 A. RADIATION USER TRAINING & PERSONAL DATA (Please type or print legibly)

Last name:

First name:

Middle int.:

Previous (maiden) or other surnames known by:

'f Soc. Sec. No.:

Sex: Male Female I

Birth date: Month Day Year i

Job Title or Duties:

1 i

Department:

Room Numb'er:

Phone:

l Responsible User:

or Instructor:

l Program Number:

i Date of first radiation use at Idaho State University:

}

i Required radiation safety training includes the following topics:

i' (1) nature of radiation sources, (2) biological effects and risk estimates, 1

(3) risks to the unborn and control of prenatal exposure, (4) ALARA principle and minimizing exposure, (5) correct use of protective devices, (6) provisions of regulations and licenses, (7) response to radiation emergencies, (8) responsibilities and rights of radiation users, and, for radioisotope users only:

r (9) safe handling and storage of radioactive materials.

1) Have you received the handouts on " Radiation Safety For Minimally Exposed Personnel" and i

l Basics Of Radiation Safety".

}

i Yes _ No _

f

2) Have you had previous work experience involving occupational radiation exposure?

l Yes No

3) Have you received training on ej,L of the topics listed above at another institution? -

{

Yes _ No __

\\

If you checked "Yes" for items 2 or 3, complete a" REQUEST FOR RADIATION EXPOSURE HISTORY ANDIOR TRAINING VERIFICATION" (RPR 1B;for each such institution or employer.

The information above is accurate and complete. I understand that i may communicate directly, in confidence and without prejudice, with the Radiation Safety Officer or the U.S. Nuclear Regulatory Commission on any matter concerning radiation protection.

Signature:

Date:

RPR 1. PERSONAL DATA (12/92F2 2

l

i i

RPR 18. REQUEST FOR RADIATION EXPOSURE HISTORY and/or TRAINING VERIFICATION (Please type or print legibly) j r

L Organization:

t

)

)

Address:

i t

i l

l Attention:

f Radiation $sfety officer (if known) of Supervisor (indicate wtuch).

l l

l To whom it may concem:

l l

l Please send the following to the address indicated below:

j f

_. My radiation exposure history.

__ Verification that I received radiation safety training appropriate for independent work with radioactive materials and/or radiation sources.

I i

Last name:

First names:

i 5

l Soc. Sec. #:.

Birth date: Mo:

Day:

Yr:

i i

Inclusive dates of work with radiation (m/yr to m/yr):

to Please send the requested information to:

Idaho State University Technical Safety Office Box 8106 Pocate!!o, Id. 83209 Signature:

Date:

RPR 1. PERSONAL DATA (12/92)-3 '

3 l

/

RADIATION USE APPLICATION 1

r PURPOSE INFORMATION TO BE SUBMITTED This procedure specifies the requirements that must All applicants for authorization to be a responsible be met and the information that must be provided user must submit:

to the Radiation Safety Committee in support of an application to use regulated ionizing radiation 1

RADIATION USER PERSONAL DATA (RPR 1) sources of any kind at Idaho State University.

2 RESPONSIBLE USER'S TRAINING J

POLICY EXPERIENCE RPR 2A)

The Radiation Safety Committee is the governing Applicants for unsealed, dispersible radicactive i

body for all aspects of radiation protection within materials not to be used in or on humans must the University, including all affiliated research, submit:

clinical, instructional and service units utilizing

(

)

radiation sources in facilities owned or controlled by 3

RADIOACTIVE MATERIAL USE APPLICATION the University. Each proposed use of radioactive (RPR 2B) materials, x-ray or other radiation generating

{

machines must be submitted to the Committee, yjg Applicants forradiation generating machines or self-the Radiation Safety Officer (RSOL for review shielded irradiators not to be used on humans must '

l before implementation. Specific forms and data to submit:

be submitted are prescribed in the attachments to this procedure. The descriptions of facilities and 4

RADIATION MACHINE USE APPLICATION equipment, the training and experience of the user, (RPR 2C) and the operating or handling procedures shall be 1

provided in sufficient detail to permit the Committee Applicants for use of any source of radiation on or to evaluate the safety of the proposed use.

in humans must subrnit:

a j

5 CLINICAL RADIATION USE APPLICATION (RPR l

INITIAL APPLICATIONS 2D' A first-time applicant to become a responsible user An applicant for research use of any radiation should obtain a copy of the Radiation Safety Policy Manual from the Technical Safety Office. The must &st W ammved as a respnsMe user Qe aa n ae mm ee; use w em a@ca-index to all current Radiation Procedures and

=

n un is most apWate. W use of Madon Records included in the Manual should be reviewed to identify any that may be applicable to the as n t m W & nz W at planned radiation use; these should also be tate Unimstm obtained from the Technical Safety Office.

REVISIONS TO AUTHORIZATIONS After becoming thoroughly familiar with the pertinent requirements, the applicant should complete the appropriate checklists and forms Any desired revisions to an authorization should be attached to th,s procedure and submit them to the discussed with the RSO via the Technical Safety i

Offia If W RSO heim h h WW revision does not involve any change from the initial safety evaluation, and is within the intent of the initial authorization, the revision may be approved by the RSO without further Committee action. The RSO may, however, require additional information before granting approval. The RSO is required to brief the RSC of all program changes at the next Radiation Safety Committee meeting.

1 RPR 2. RADIATloN USE APPLICAT!oNs (9/93)+ 1

. - - _. - ~ _ - _. _, - _ _ -_

~

If a proposed revision to an initial authorization involves significant changes, in the opinion of the a

RSO, in sources or conditions of use from those specified initially, the proposal must be resubmitted to the Committee for authonzation.

To assure that all records related to radiation sources, users and conditions of use are accurate and up to-date, the RSO may require that parts or all of the application be verified or resubmitted periodically. If the updated information includes changes that are significant to safety, the application will be submitted to the Committee for reauthorization.

l r

i 4

6 e

1 i

i i

4 RPR 2. RADtATION USE APPLICATIONS (9/93)- 2

I l

RPR 2A. RESPONSIBLE USER'S TRAINING & EXPERIENCE l

(Please type or print legibly)

?

f Last name:

Initials:

Soc. Sec. No:

f Trainina in Basic Radiation Sciences:

Tvoe & Hours of Trainino Formal Supervised Courses On-the Job i

Subiects Location & Dates (hours)

(hours]

l Nature of radiation i

l sources Biological effects

(

& risk estimates j

l ALARA pricciple

& minimizino exoosure Correct use of

)

orotective devices Provisions of regulations

& licenses Response to radiation emeroencies Responsibilities

&richts of Radiation users Experience in Usina Radiation: List radiation sources used personally; list nuclides and quantities, description of machines, dates and nature of each use. (Attach supplemental sheets if necessary.) For each location where experience was obtained, complete one

• REQUEST FOR... TRAINING VERIFICATION" form (RPR 1B).

l 1

j l

The information above is accurate and complete.

Signature Date RPR 2. RADIATloN USE APPUCATioNS (9/93)- 3

~

l 1

i l

RPR 28. RADIOACTIVE MATERIAL USE APPLICATION (FOR UNSEALED OR DISPERSIBLE MATERIALS NOT USED IN OR ON HUMANS)

Maximum Order _

Nuclide All Monthly Use Nuc!;de Physical / Chemical Form mQj How Oftent (mci)*

(No. of Alls]

l l

l

• See *RADioNUCLtOE CATEGORIES AND DATA' (RPR 1cA)

In addition to the RESPONSIBLE USER'S TRAINING & EXPERIENCE (RPR 2A), the PERSONAL DATA form (RPR 1 A), submit the following:

1 1

l

_ RADIATION USER TRAINING & PERSONAL DATA" forms (RPR 1 A) for all other individuals who will work l

in the same location (faculty, staff).

i

_ Brief description of experimental objectives and methods, with justification for the specific radionuclides and quantities.

_ Description of facilities where radiation sources will be used and stored, including building, rooms, fume l

hoods, shielding, security arrangements; include diagram of layout if appropriate.

l

_ Description of radiation survey instruments that will be readily available for contamination and exposure control, and analytical instruments that will be used for determination of radioactivity in wipe test papers or urine samples.

_ Animals to be used, if any, including number, individual doses, holding facilities and handling methods,

_ Brand names of liquid scintillation fluor (s) and tissue solubilizers, if any, that will be used. Written justification must be provided for any fluors other than *NHNT" and vials larger than " minis". See " LIQUID SCINTILLATION MEDIA" on next page.

i i

_ Description and estimated quantities of radioactive wastes to be generated, if any radioactive wastes will also contain any hazardous materials, as defined by the EPA, provide wntten justification for producing them.

I have read the University's Radiation Safety Policy Manual and understand the conditions and regulations contained in it. With respect to the requested radiation sources and proposed uses, I acknowledge and accept the responsibility for:

(a) radiation protection instruction for allinvolved personnet; (b) acquisition of the equipment, supplies and/or services necessary for radiation protection; (c) security to prevent misuse or theft of radioactive materials; (d) maintaining occurate records of acquisitions and dispositions; (el regular contamination and/or exposure surveys and records; (f) notification of the RSo of any accident or abnormal encident; (g) arranging for authorization of another individual to assume the preceding responsibilities, of to suspend or terminate all radiation uses, pnor to any extended absence, Signature of Responsible User:

Date:

l RPR 2. RADIATION USE APPLICATIONS (9/931 - 4

._t l

4 t

LIQUID SCINTILLATION MEDIA i

i Fluors containing non-hazardous, non-toxic (NHNT) soIVents are required unless a specific exception is obtained from the RSO or the Radiation Safety Committee. Examples of such fluors are:

'M Efficiency

• Flou*

'Al Efficience Flow

• Fluor (Mfar.)

Nean e SD (N) iste]

fluor (Nf ar. )

Mean

• SD (N)

(see) i BCS(AMER)

Betasuna-ES(ICN) 45.127.9(6)'

2.6 l

Bio-Safe II(RPI) 38.1 2 5.2 (24)'

4.1 Bio-safe NA(RPI) 43.9 9.8 (6)'

2.5 Cytoscint-ES(Ich) 43.7 4.0 (24)'

3.7 Ecolite(+)(!CN) 32.1

• 5.1 (24)'

5.3 Ecoltame(ICN) 36.6 2 6.0 (24)'

4.9 Ecoscint A(kAT) 40.2 s 4.5 (24)'

3.7 i

l Ecoscint N(NAT) 45.8 2 5.0 (24)*

2.7 Ecoscint o(NAT) 45.126.7(6)'

2.8 Envirosafe(ANOR) 35.4 2 4.6 (24)*

4.2 Mano Flow 5(NAT) 35.6 2 3.7 (24)'

2.7 Opti-Fluor"(P ACK) 39.725.5(24)*

3.2 organicSolv 3(ANOR) 42.2

• 9.7 (6)'

2.5 Ready Safe (BECK) 40.6 s 4.2 (24)*

7.2 Ultima Gold (PACK) 43.1

• 2.1 (24)'

5.5 Fluors containing toxic or flammable solvents may not be purchased without prior approval from the RSO. Examples are:

CP, HP, HP/b, EP, MP, NA, Ready Micro, Ready Solv, Ready Protein, Ready Gel, Ready Value, Ready Organic, Ready Flow II, Ready flow !!! (BECK)

Universall (ICN)

Betafluor, Hydrofluor, Liquiscint, Monoflow 4, Ultraflow (NAT)

Aoussol, Aguasot-2, Econofluor, Econofluor-2, Fornuta 963, Liquifluor, Omnifluor, Atomlight, Aquasure, Biofluor, Riefluer, and all "kEF" numbers (NEN)

Insta-Get XF, Scint-A XF, Pico-Aqua, Pico-fluor 15, Pico* Fluor 40, Hionic Fluor, Filter-Count, Pico-Fluor LLT, Insta-Fluor, Permafluor V, Monophase S, Flo Scint I, !!, !!!, IV, and V (PACK)

Tritim counting efficiencies are based on 0.1 mL sample in 4.0 mL fluor; " Flow" represents the time for a fixed voltrne to flow from a pipette and is inversely proportional to viscosity; data from Klein, RC and Gershey, EL, l

'Blodegradable' liquid scintillation counting cocktails, Health physics 59:461-470, 1990.

1 Non-aqueous cocktail 2

Multipurpose cocktail AMER = Amersham Corp., Arlington Heights, IL B00-323 9750 ANOR = Anorak Scientific, South Hackensack, NJ BECK = Beckman Instruments, Fullerton, CA B00-742-2345 ICN = ICN Radiochemicals, Irvine, CA B00-854-0530 ISO = !solab, Inc., Akron, OH 800-321-9632 i

NEN = DuPont-NEN Products, Boston, MA B00-551-2121 NAT = kational Diagnostics, Manville, NJ 800-526-3867 j

i PACK = Packard Instrment Co., Downers Grove, IL B00-323-1891 RP!

s Pesearch Products International Corp., Mount Prospect, IL 800-323-9814 l

RPR 2. RADIATION USE APPUCATIONS (9/93)- 5

RPR 2C-1. RADIATION MACHINE USE APPLICATION (X-RAY. MACHINES, PARTICLE ACCELERATORS AND SEALED-SOURCE IRRADIATORS NOT TO BE USED ON HUMANS) in addition to the RESPONSIBLE USEP.'S TRAINING & EXPERIENCE (RPR 2A), the PERSONAL DATA form (RPR 1 A), submit the following l

_ RADIATION USER TRAINING & PERSONAL DATA" forms (RPR 1 A) for all otherindividuals who will work i

in the same location (faculty, staff, students).

_ Detailed description of irradiators or radiation machines including safety devices, e.g. open beam, closed -

beam, iriterlocks, warning lights, shutter indicators (open-closed) x-ray tube status (on-off).

i

_ Description of facilities where radiation machines or irradiators will be used, including building, rooms, shielding, security arrangements, etc.; include diagram of layout as appropriate.

_ Description of any available instruments for radiation surveys or monitoring.

_ Step by step operating procedures to be used by all personnel while operating equipment.

_ Outline of instruction to be given to all users addressing items such as possible hazards, significance of safety devices, operating procedures, symptoms of acute localized exposure, and procedures to be followed I

in reporting suspected or actual exposure. (No person will be permitted to use equipment without this 1

instruction).

I have read the un#versity's Radiation Safety Manual and understand the conditions and regulations contained in it. Wth respect to the requested radiacon sou ces and proposed uses, I acknowledge and accept the responsibihty for:

r (a) radiation protection instruction for all involved personnet; (blacquisition of the equipment, supplies and/or serwces necessary for radiation protection; I

(c) notification of the RSo of any accident or abnormalincident; (d)arrariging for authorization of another indtwdual to assume the preceding responsibihties, or to suspend or terminate ailradiation uses, pnor to any ertended absence.

Signature of Responsible User:

Dete:

l RPR 2. RADIATION USE APPUCATioNS (9/93) 6

1 RPR 2C-2. ANALYTICAL X-RAY MACHINE APPLICATION CHECKLIST Responsible user Phone:

I Location (Bldg. & Room)

Installation date:

l t

Tvoe and use Manufacturer Model Serial No.

i

_ Open beam Control unit:

l

_ Fully enclosed Icx1 l

i

._ Diffraction [xcl Number of ports available:

In use:

i

_ Fluorescence [xri Target material Max. kVp Max. mA l

Accessory equipment (powder cameras, goniometers, etc.)

i i

Application date FACILITY RE4111REDENTS

" CAUTION - X-RAY EQUIPMENT" (or equivalent) sign at entrance?

Yes No

" NOTICE TO WORKER $" (NRC form 3) posted conspicuously?

Yes No f

X-RAY EQUIPeENT REEKl!REDENTS Safety Devices i

~

b Reg.rired on open beam units - a device that prevents any portion j

of the body from entering the primary beam, or a device that terminates

(

the beam if obstructed.

Yes No IF "NO", has exenption been filed?

Yes No

{

Signs arul Labels j

" CAUTION: HIGH INTENSITY X-RAY BEAM" - on source housing?

Yes No l

" CAUTION - RADIATION. THIS EQUIPMENT PRODUCES RADIATION WHEN ENERGIZED"

- near switch used to turn on unit?

Yes No Warning Lights or Devices - All Units I

"X RAY ON" light - near any switch that energizes and near any X-ray port.

Yes No The warning light (s) shall be fail-safe.

Yes No Additional Warning Devices Recpired for open beam Units X-RAY TUBE STATUS, "0N/0FF" - located near the radiation source housing, and at or near the port, if the primary beam is controlled in this manner.

Yes No Shutter Status "0 PEN / CLOSED" - located near each port on the radiation source housing, if the primary beam is controlled in this manner.

Yes No All warning devices must be fail safe.

Yes No Ports and Shutters unused ports on radiation source housing shall be secured in the " closed" position in a manner that will prevent casual opening, i.e. without the use of tools Yes No On equipment installed 'af ter Novenber 1983, open beam units shall have ports equipped with a shutter that cannot be opened unless a local conponent has been connected Yes No OPERAT!NG REEEHRBENTS RPR 2. RADIATION USE APPLICATIONS (9/93)- 7

Are written operating procedures available to att users of x. ray egai ment?

Yes gr P

l f

i J

d RPR 2. RAO(ATION USE APPLICATIONS (9/93). 8

.. ~

i i

I l

4 RPR 2C-2. ANALYT! CAL X-RAY MACHINE APPLICATION CHECKLIST (cont'd)

)

PERSONNEL RECJIREENTS Nave all persons eperating x-ray equipment received both Institutional Analytical X Ray and on-the-job instruction and demonstrated adequate knowledge of:

radiation hazards associated with use of equipment; Yes No significance of raciation warning and safety devices; Yes No eperating procedures; Yes No symptoms of acute localized exposure; and Yes No procedure for reporting actual or suspected exposure?

l Yes No Personnel Monitoring For open-Deam systems, have personal monitoring device:: (ring badges)

Yes No been issued?

l If "Yes", are they used in conpliance with University requirements?

Yes No RADIATION SURVEY EQUTPENT Radiation survey meter (s) available at facility:

"ake/Model:

ser. No.

Calibration Date:

Make/Model; Ser. No.

Calibration Date:

l Upon completion, send this application checklist to:

Technical Safety office Box 8106

)

RPR 2. RADIATION USE APPLICATIONS (9/93)- 9

7

~

RADIONUCLIDE DATA j

PURPOSE Dose Rates (mrem / hour):

This procedure provides a ready reference to radiation Penetrating - the dose rate from photons at 1 protection data for commonly used radionuclides.

meter from a point source of 1 millicurie, as-Data for nuclides not listed herein may be obtained sumed to be proportional to the inverse of the from the RSO.

square of the distance between the point source and the receptor.

POLICY Skin doso - dose rate to the basal epidermal cells from contamination on the skin, expressed in 2

Radionuclide data used for radiation protection microcuries per unit area of skin ( Ci/cm ) over 2

calculations shall be obtained from regulatory authori-an area of at least 1 cm,

ties or reputable scientific advisory organizations.

In research facilities, application of the ALARA REFERENCES principle dictates that no removable contamination shall be tolerated indefinitely. Whenever contamina-International Commission on Radiological Protection, tion is detected, it must be removed promptly to Recommendations of the /CRP, Publ. No. 26,1977.

prevent its spread and the possible exposure of other individuals. The responsible user must assure that Ibid., Limits for/ntakes o/ Radionuclides by Workers, the necessary monitoring is performed, recorded and Publ. No. 30,in 4 parts with supplements, f 979-66.

reported.

US Environmental Protection Agency, Limiting of DEFINITIONS Radionuclide /ntake and Air Concentration and Dose Conversion Factors for Dose Conversion Factors for Annual Limit on intake (All): The quantity of a

/nhalation, Sr/bmersion, and /npestion, Federal Guid-radionuclide (expressed in millicuries) which,if taken ance Report No.11, EPA-520/1-88-020, September into the body, produces an effective dose equivalent 1988.

in risk to the annual whole body dose limit of 5 rems.

Because of differences in physiological transport Health Physics Journal, Volume 53, Number 2, mechanisms, the Alls vary depending on the route August 1987. D.C. Kocher and K.F. Eckerman, E/-

of intake. For purposes of contamination control and ectron Dose-Rate Conversion Factors For External bioassay procedures, the All for ingestion is used, Exposure Of The Skin from Uniformly Deposited since that is the most common route of accidental Activity On The Body Surface.

intake h1 research laboratories.

U.S. Nuclear Regulatory Commission, Code of Federal Reference Quantity (RO): A quantity of a radio-Regulations, Title 10, Part 20. Standards ForProtec-nuclide (expressed in microcuries) related to its tion Against Radiation.

relative hazard potential and used to presenbe re-quirements f or handling, monitoring, labeling and dis-posal. Reference quanities are obtained from 10CFR-20, Appendix C.

Removable Contamination Limit: A basic limit for removable surf ace contamination, specified in

• CON-TAMINATION LIMITS AND ACTION LEVELS" (RPR IcB).

RPR 10. RADIONUCUDE DATA (7/92)- 1

.--,1

,ma e+

W 1

RPR 10A. RADIONUCLIDE CATEGORIES AND DATA l

(For data on radionuclides not listed below, contact the RSO.

Half-lives in bold l

indicate radionuclides that are stored for decay for waste disposal purposes.)

Dose rates farem/ hour) l Reference Penetrating Skin dose

.l Quantity Ingestion At 1 meter at 0.07 mm

~

Nuclide Half-life (uCi)

ALI (mci) from 1 mci per uC1/ca"

'LO-BETAS * - low-energy beta or electron emitters with negligible external exposure potential and ALI's a 1 millicurie.

H-3 12 yrs 1000.

80.

0..

1200 C-14 5730 yrs 1000.

2.

Of 1

S-35 87 days 100.

6.

O.

1300 i

Cl-36 3x10' yrs 10.

2.

O.

7200 I

Ca-45 165 days 100.

2.

O.

I Cr-51 28 days 1000.

40.*

0.02 Fe-55 2.7 yrs 100.

9.

O.

Ni-63 100 yrs 100.

9.

O.

Tc-99 2x10 yrs 100.

4.

O.

5 Pm-147 2.6 yrs 10.

4.

O.

i

'HI-BETAS" - high-energy beta emitters with negligible gamma emission but capable of I

1 significant bremsstrahlung production if not properly shielded. Emphasis is on control of doses to extremities and prevention of intake.

P-32 14.3 days 10.

0.6 0.

8900 Rb-86 18.7 days 100.

0.5 0.05 l

Sr-90 28.6 yrs 0.1 0.03 0.

2

" IODINES * - radiciodines are treated as a separate category for exposure evaluation.

Emphasis is on prevention of intake by ingestion or inhalation.

I-125 60 days 1.

0.04 0.07 I-129 6x10' yrs 1

0.005 0.13 I-131 8 days 1.

0.03 0.22 6300

• GASES * - noble gases present minimal exposure potential or waste disposal problems.

Kr-85 10.7 yrs 1000.

NA

.O.

Xe-133 5.2 days 1000.

NA 0.1 i

" NATURAL" - naturally occurring nuclides, primarily alpha emitters. Emphasis is on prevention of intake by ingestion or inhalation.

l

\\

Th-232 (nat) 14x10' yrs 100.

0.0007 0.

U-238 (nat)

4. 5x10' yrs

100, 0.2 0.

l 4

The AU s not appbcab6e to macrospheres, wtuch are lugh!y mooluble particles, typically greater than 0.01 mm dameter. They requus external exposure control and motutormg, but are not readdy absorbed from the gestromtestmaJ tract. If mbaled, beemume of ther size, they are most likely to be depasnad in the upper respuntory trset.

from m tuch they would be cleared by the mucous transport and swallowed.

RPR 10. RADIONUCUDE DATA (7/92)- 2 l

1

~

. ~...,.

Dese rates (mrem / hour)r Reference Penetrating Skin dose Quantity Ingestion At 1 meter at 0.07 mm Nuclide Half-life fuCil ALI fmCi) from 1 mci nor uCi/cm2

• GAMMAS * - gamma emitters with ALI a 1 millicurie; emphasis is on external exposure control and monitoring.

Na-24 0.625 days 100.

4.

1.89 Mn-54 312 days 100.

.2.

0.51 Co-57 271 days 100.

4.*

0.15 290 Ga-67 3.3 days 1000.

7.

0.11 1100 Ga-68 68 min 1000.

20.

0.54 Ge-68 288 days 10.

5.

0.06 Sr-85 64.8 days 100.

3.*

0.75 55 Nb-95 35 days 100.

2.*

0.48 970 Mo-99 2.8 days 100.

1.

0.11 Tc-99m 0.25 days 100.

80.

0.12 890 Ru-103m 39 days 1000.

2.*

0.33 2400 m

In-111 2.8 days 100.

4.*

0.5 1400 Sn-113 115 days 100.

2.*

0.18 I-123 0.542 days 100.

3.

0.28 Gd-153 242 days 10.

5.*

0.17 460 Au-195 183 days 10.

5.

0.09 Hg-195m 1.7 days 100.

2.

0.1 Hg-197 2.7 days 1000.

3.

0.07 Au-198 2.7 days 100.

1.

0.29 T1-201 3 days 1000.

20.

0.09 970 Pb-203 2.2 days

~1000.

5.

0.68 ALL OTHER NUCLIDES not included in one of the above groups are assumed to have g

significant potentials for both external and internal exposures and must be evaluated individually.

Na-22 2.6 yrs 10.

0.4 1.33 7200 Sc-46 84 days 10.

0.9*

1.17 5100 Fe-59 44.6 days 10.

0.8 0.66 4600 Co-60 5.27 yrs 1.

0.2 1.37 Zn-65 244 days 10.

0.4 0.33 Se-75 118 days 100.

0.5 0.86 360 Ru-106 367 days 1.

0.2 0.

Cd-109 453 days 1.

0.3*

0.18 Ir-192 74 days 1.

0.9 0.59 Hg-203 47 days 100.

0.5 0.25 The AU e not applicabis to 1_.

2, wtuch are highly inschable pernelse, typkully granter than 0.01 mm dameser. They roquare externs) exposure control and mondorms, but are not readily shmorbed from the gastro-f tract if abaisd. bemuse of their sue, they are most likely to be deposimi a tbs upper respiratory truct, from wtuch they e onki be cisared by the mucous transport and swallos ed.

RPR 10. RADIONUCLfDE DATA (7/92). 3

RPR 10B. CONTAMINATION LIMITS AND ACTION LEVELS' NUCLIDE CATEGORY REMOVABLE CCPTAMINATION LIMIT (RCL)*

Electron and/or photon emitters:

with ingestion ALI al mci

-1.

nCi (2,000 dpm; 40.

dps) per 100 c:tf 2

with ingestion ALI <1 mci 0.1 nCi (200 dpm; 4.

dps) per 100 cm Alpha-particle emitters:

0.01 nCi (20 dpm; 0.4 dps) per 100 cm' LOCATION QUANTITY REQUIRED ACTION Skin or hair Any Immediate removal by gentle washing

>l RCL Immediate removal and bioassay' within normal interval

>10 RCL Immediate removal and bicassay' within 5 days Clothing, personal

>l RCL Do not remove clothing from the lab wash in or protective the lab or store for oecay of activity Skin contact likely

>10 RCL Bioassay' within five (5) days Skin contact unlike-

>10 RCT.

Bioassay' within normal interval ly Surfaces or obiects

>l RCL Until decontaminated, isolate, cover, label, that are readily etc. to ptevent personnel contact; indicate accessible or location and activity in sturvey record.

normally touched,

~

e.g. bench tops, handles, etc.

>?.3 RCL Decontaminate immediately; bioassay' required within normal interval for potentially exposed individuals Decontaminate immediately;lly exposedbioassay' required

>100 RCL within 5 days for potent 2a Individuals ment or

>l RCL Do not release until criteria are satisfied Equi 5ities to be fac1 r="*66';

released for

>10 RCL unrestricted use raed Other surfaces or

>l RCL Label the contaminated area or object; ob]ects (not readily indicate location and activity on survey accessible or record ner:nally touched) i l

l

>10 RCL DecentEminate within one week i

' Based on NRc Regulatory Guade 8.23. Rednesar Safety Surveys at MedicalInsuomons. Rev.1. Jan.1981.

All contammanon a presuened to be removable until proven otherwoe. The imuts are expreened as actavity por 100 aquare centsmeiers, rounded to one signaricant 8

figure. For all surfaces encept ebo the consnesnamon may be averaged over no more inan 300 cin' for desernusung the appropriate menon.

• A!! roquaremems for bionssays a stus table are for screenmg bmensays.

RPR 10. RADIONUCUDE DATA (7/92) 4 l

t

1 7

\\

\\

RADIOISOTOPE LABORATORY SAFETY PROCEDURES PURPOSE 2 following the instructions or procedures provided l

by the responsible user and the RSO, or provided i

This procedure provides criteria, reference data, and in the Radiation Safety Policy Manual.

specific instructions for safe handling of radioisotopes

{

in unsealed or dispersible forms, including contamina-3 survaying of gloves, clothing, equipment and work tion control and monitoring of exposures. It also area frequently during procedures in which more specifies the requirements for monitoring records to than 1 Allis manipulated, and surveying of hands be maintained by the users, and personal clothing before leaving the laborato-ry.

POLICY 4 providing a urine sample, or obtaining a thyroid j

count, et intervals specified by the RSO. Refer i

l Itis the responsibility of each radiation user to follow to

• BIOASSAYS FOR INTERNAL RADIOACTIVITY" I

safe work practices, to be aware of actual or poten-taen 12i.

tial radiation exposures, and to keep all exposures j

to levels that are as low as reasonably achievable 5 recording the results of all radiation surveys and l

(ALARA). Each person who handles unsealed radio-screening bioassays promptly, completely and l

isotopes is responsible for the control and contain-accurately.

ment of radioactivity and for performing regular j

i surveys of personnel, personal effects, equipment The responsible ur nr must ensure that:

l l

and work areas using methods that will assure the l

l detection of contamination before significant expo-1 all radiation users have received the required radia-1 sures occur.

tion safety instruction.

l in research facilities, application of the ALARA 2 the equipment, supplies and services necessary l

principle dictate's that no removable contamination for radiation protection are provided.

shall be tolerated indefinitely. Whenever contamina-

)

tion is detected, it must be removed promptly to 3 radioactive materials are secured against theft, i

prevent its spread and the possible exposure of other misuse and access by unauthorized personnel.

l individuals. The responsible user must assure that the necessary monitoring is performed, recorded and 4 radioactive wastes are segregated properly and l

reported. Routine evaluations of all radioisotope placed in appropriate containers. The containers laboratories, including surveys for contamination, are are to be provided by the user; labels and clear also performed byTechnical Safety Office personnel.

plastic bags are available from the RSO. Follow the instructions in 'RADIOlSOTOPE ACQUISITION l

RESPONSIBILITIES AND DISPOSITION" inen isi.

Each person who works with unsealed or dispersible 5 accurate records of acquisitions and dispositions radioactive materials is responsible for:

of radioactive materials are maintained. Refer to "RADIOlSOTOPE ACQUISITION AND DISPOSITION 1 knowing the basic properties of the radioactive

<RPR 131.

materials to be used, e.g. the half-life of the nuclide(s), the type (s) of radiation emitted, the 6 regular exposure and contamination surveys are j

annual limit on intake (All) and any shielding that perfurmed and recorded.

may be required. See *RADIONUCLIDE CATEGO-RIES AND DATA

• inen toAi.

7 the RSO is notified promptly of any accident or abnormalincident involving radioactive materials.

l RPR 11. RADLAB SAFETY (7/92).1 1

l

l l

8 prior to any extended absence, another individual surveys are not necessary and all contamination l

is authorized by the Radiation Safety Committee surveys may be made by means of wipe tests.

l (or temporarily authorized by the Radiation Safety Officer) to assume the preceding responsibilities, if an analytical instrument is to be used for counting or the use of radioactive materials is suspended urine samples or contamination wipe tests, the user I

or terminated.

must know the counting efficiency for each sample type and for each anticipated nuclide. The RSO will help the user to determine appropriate sample sizes POSTING OF RADIOlSOTOPE LABORATORIES and counting times for urine samples, and the results that would require verification.

Each room containing more than 10 reference quanti-ties (RPR 10) of all radioisotopes combined must be TROUBLE SHOOTING RADI ATION SURVEY METERS labeled with a " CAUTION RADIOACTIVE MATERI-ALS" label. This label should indicate the isotopes Instruments used for contamination surveys are not present, and the name and phone numbers (home and required to provide extremely accurate results.

office) of the responsible user.

However, they should provide consistent indications of the presence or absence of contamination. If a A

• NOTICE TO EMPLOYEES", available from the meter gives inconsistent or questionable results, i

RSO, must be posted where anyone entering the lab check the following conditions before sending it for can see it.

repair or recalibration.

If any dose rate exceeds 2 mrom/ hour at 30 cm (1 1 Check the batteryl Turn the selector to the

• Bat-ftJ from an accessible source or surface, the room tery" position for a minimum of 30 seconds to is a " Restricted Area" and must be posted to prevent verify that the battery is in good condition. If the entry of unauthorized individuals. If any dose rate battery is low, replace it.

exceeds 5 mram/ hour at 30 cm (1 ft.) from an acces-sible source or a surface, the room must be labeled 2 If the meter roads higher than its normal back-with a " CAUTION RADIATION AREA

• sign. If either ground, check for extemal contamination with a of these dose rates is exceeded, notify the RSO.

reliable meter. Contamination becomes a problem i

when users have neglected to monitor their hands j

l SURVEY INSTRUMENTS during the radiolabeling process. Meters should be included when performing both personal and The responsible user shall ensure that instruments area surveys.

used for determining exposure rates or for direct 1

detection of contamination are capable of responding 3 If the meter is contaminated, clean it carefully to appropriately to the kinds of radiation anticipated and remove the contamination. If the contamination have been calibrated within the past year. For most cannot be removed down to background, remove radioisotope laboratories, a thin-window Geiger-the betteries, label the meter with " CAUTION l

Mueller (GM) survey meter with an audible response RADIOACTIVE MATERIAL" tape, place it in a is best. For low-energy photon emitters, (1-125, Cr-labeled plastic bag, and set it aside for decay.

51. etc.) a thin-crystal scintillation detector, also with When the contamination has decayed down to audible response, is preferred.

background, the meter should be recalibrated.

The user must know the detection efficiency, e.g.

4 If discrepancies are observed between the readings cpm / dom, for each survey instrument and record it from two meters, first check the efficiencies with all survey results. The reporting forms attached indicatod on the calibration tabel. Small discrepan-to this procedure include provisions for recording all cies may represent actual differences in the sensi-l pertinent instrument data.

tivities of the instruments. If the discrepancies are not due to differences in efficiencies, the problem in laboratories where only tritium (H-3) or less than may be in the electronics or in the calibration of 1 ALI of low-energy beta emitters are used, direct one or both meters. First ask the Technical Saf ety RPR 11. RADLAB SAFETY (7/92)-2

_. _ _. _ _.. -. ~. _,, - -.. _ _, -. _

Office to verify the calibration; then obtain repairs, source with no shielding is approximately 200 mrem /-

if necessary.

hour per millicurie. Multiply activity handled at one time (mci) by the hand contact time (hours / quarter) 5 Before removing a meter from the lab, survey it by 200 to estimate the quarterly hand dose.

to assure that no contamination is present.

For P-32 or other high-energy beta emitters, a shield made of any plastic material 1 cm (3/8 inch) thick 6 If a meter has been sent in for repair, the meter will absorb the beta particles while generating little must be recalibrated by Technical Safety Office secondaryradiation. For millicurie quantities of P-32, personnel before being put back into use.

lead shielding approximately 3 mm (1/8 inch) thic'.

should be added to the exterior of the plastic to EXTERNAL EXPOSURE CONTROL absorb the more penetrating secondary radiation.

Careful planning of work, good handling techniques Ring badges ace issued to individuals whose hand or and thorough morntonng are all necessary to minimize finger doses could exceed 1,000 mrem per calendar i

i exposure. Adequate shielding and distance from quarter. The requirement for monitoring is based on sources are also important factors in reducing ex-the nuclide(s) used, and the activity (mci) handled posure. lodine-125 should be shielded with at least monthly by the individual. An individual who has 3 mm (1/8*) of lead. Other nuclides that emit higher been issued a badge is required to wear it whenever

(

energy gamma rays may require 5 cm (2") or more handling radioactive materials. The badge itself I

of lead. The shielding must extend entirely around offers no protection; however, it provides valuable l

the source; verify by making measurements of expo-information that is necessary to ensure that expo-l sure rates above, below, in back and at the sides of sures are kept as low as reasonably achievable l

storage locations.

(ALARA).

The potential quarterly gamma dose from each The ring badge should be wom so that the name label unshielded radionuclide used may be estimated as:

faces the source,i.e. toward the palm of the hand.

D = A*X*T(1/d'), where:

example, den MW W hm a Wal, h nno badge should be worn on the little finger of the D = estimated dose (millirem / quarter) hand holding the pipette with the name label facing the mouth of the vial. The dose rate at the mouth A = activity handled (millicuries) of an open combovial containing 1 mci of P-32 in 1 X = external dose-rate constant (mrem /hr-mC; at 1 MI of liquid may be as high as 400 mrem / minute.

m)

Values for X are given in RPR 10.

Exposure can be markedly reduced by not picking up tubes when radiolabeling.

T = exposure time (hours / quarter)

To avoid contamination of the ring badge, always 1/d' = distance correction wear it under gloves. Verify that it has not become

= 10,000 for contact hand dose contaminated by including it in your routine personal (d = 1 cm) and area surveys. Always store your badge away from heat, as well as radiation sources.

= 100 for hand dose using tongs EXPOSURE RATE SURVEYS (d = 10 cm)

= 10 for body dose during entire handling time A survey of exposure rates must be performed (d = 30 cm) whenever s urces of penetrating radiation are first acquired, when the quantities of these radionuclides are increased and when physical arrangements for i

handling or storage are modified. Additional surveys SPECIAL INSTRUCTIONS FOR P-32 USERS should be performed occasionally to assure that inadvertent changes in exposure rates have not occunei For high energy beta-particle emitters, e.g. P-32, the dose rate to the hands (1 cm distance) from a point RPR 11-RAoLAB SAFETY (7/02)-3

PREVENTION OF INTAKE OF A thorough survey of the entire laboratory must be i

RADIOACTIVE MATERIAL performed and recorded by the user in each radioiso-tope laboratory on a regular basis according to the Ingestion of radioactivity must be prevented by level of use, as indicated below. An evaluation of avoiding mouth contact with any items handled in the radiation protection status of each radioisotope a radioisotope laboratory (pipettes, pencils, etc.), by laboratory, including a contamination survey, will also prohibiting eating, drinking and smoking in radio-be performed by TSO personnel at the frequencies nuclide handling areas and by careful attention to given in

• RADIOISOTOPE LABORATORY EVALUA-personal hygiene.

TIONS" (RPR 50).

1 Gloves, lab coats, or other protective clothing, should The appropriate frequency for performing routine be available and worn to prevent contamination of laboratory surveys is determined by the ncture and skin and personal clothing. Lab coats and gloves quantities of radionuclides, and the conditions of use.

should not be worn to the cafeteria, library, class-The frequency of routine contamination surveys is rooms or home. Sandals or other open-toed shoes based on the "intervalinventory", expressed in ALis.

are not appropriate for work with radionuclides.

The intervalinventory is the total quantity (in ALIs)

Work, storage and waste areas should be provided of unsealed (dispersible) radioisotopes in the laborato-with secondary containers and covered with absor-ry averaged over the most restrictive bioassay inter-bent paper. Plastic trays and dish pans are suitable val. intervalinventories are determined by Technical for use as secondary containers. The potective Safety Office personnel when radioisotopes are covering should be replaced when it becomes exces-received.

j sively dirty or contaminated.

The nominal survey frequencies shown in the table Inhalation of radioactive materials must be prevented are to be interpreted as guidelines. In cases where

{

by performing all operations that release gases, contamination occurs regularly, the interval between 4

vapors or dusts in fume hoods. The4 ash of a fume surveys should be shortened, if the survey results i

hood is intended to serve as a shield to protect the obtained over a period of a year indicate no contami-l face from spatters, as well as to control air flow. To nation problems, the routine survey interval may be provide the proper protection, the hood must be free increased. In no case, however, should the interval of major obstructions to the flow of air and the sash be more than double the nominat interval in the table.

i should be set at the optimal height. It is the users responsibility to ensure fume hoods provide adequate Measurements of contamination by direct detection, l

air velocity.

wipe tests, or both, should be made of representative i

surf aces. An audible instrument response should be in emergency situations, filtered or supplied-air used during direct surveys because of the faster and respirators w e used to prevent inhalation of contami-more sensitive response and because it eliminates l

nants. Whenever the probability of airborne contam-the need to watch the meter constantly.

I ination is significant, the RSO should be notified and l

air sampling may be required.

To determine quantities of removable contamination, l

or to survey areas that are inaccessible to a survey l

instrument, wipe tests should be taken. An area of l

CONTAMINATION SURVEYS 100 -300 cm'should be wiped with absorbent paper for each test, if energetic beta emitters are involved, Surveys for contamination on the hands and clothing the activity on the filter may be measured directly must be performed immediately after working with with a thin-window GM survey meter. If tritium or radioisotopes to allow detection and removal before other low-energy beta emitters are involved, the wipe the material enters the body. Any radioactive materi-filter should be analyzed with a liquid scintillation al on the skin must be removed promptly by normal counter.

washing. If it cannot be removed easily, request advice from the RSO.

RPR 11. RADLA8 SAFETY (7/92) -4 1

[

l CONTAMINATION SURVEY DATA an exposure rate survey should be made as previ-ously described.

i 1 Unless the only nuclides used are tritium or small i

quantities (<1 All) of other low-energy beta 4 Atlocations with positive resultsfrom contamina-emitters, a direct survey should be made with a tion, or surfaces that are not accessible for a portable instrument. For each portable survey direct measurement, use a dry filter paper to take instrument used, record the make, model and a wipe of 300 (preferred) or 100 cm'. (A 300 cm' serial number (s) of survey meter (s) used for the area is any equivalent of a 7-inch square or a strip I

survey on the " CONTAMINATION SURVEY -

2 cm wide and 1.5 meter long; a 100 cm' area is l

PORTABLE INSTRUMENT

• form (RPR 11 Al. Indicate any equivalent of a 4-inch square or a strip 1 cm j

the calibration date and the detection efficiency wide and 1 meter long.)

j for the critical nuclide, i.e. the one with the largest l

number of ALis in use. Calculate the net response 5 Using the portable survey instrument in a low-rate expected from the instrument for the remov-background location, make a direct measurement able contamination limit (RCL). Note that all of of the contamination on the filter paper. Record the instrument response information needs to be the results according to the directions on the entered only once until the instrument is recali-survey form.

i brated.

l 6 If contamination from low-energy beta emitters, 2 With the audible response turned on, move the e.g. C-14, S-35, is detected at a level close to the i

detector slowly over all surfaces that might be RCL (RPR 108), the wipes should be kept and i

contaminated, holding the detector 1-2 cm from counted in a liquid scintillation counter.

I the surface. Record the highest net response for each object or location surveyed, following the 7 ff only tritium or small quantities of other low-instructions on the form under ' CONTAMINATION energy beta emitters are used, take wipe samples SURVEY RESULTS".

of all objects and surfaces that are normally touched or readily accessible.

l 3 At locations with positive survey results, first ascertain whether the reading could be penetrating 8 On the ' CONTAMINATION SURVEY - WIPE radiation coming through the surf ace, rather than TESTS

• form inPR tisi, record the data identifying

[

from contamination on the surface. If significant the counting instrument, the efficiencies for the penetrating radiation is detected, i.e. more than critical nuclide and the expected response for a i

0.2 mrem /hr (approximately 10 times background),

wipe with more than the RCL.

INTERVAL' RESPONSIBLE USER INVENTONY ROUTINE CONTAMINATION SURVEY FREQUENCY l

l

< 1 ALI Personal surveys EVERY DAY and laboratory surveys EVERY MONTH when radionuclides are in use.

1-30 ALis Personal surveys EVERY DAY and laboratory surveys EVERY WEEK when radionuclides are in 1

use.

>30 ALis Both personal and laboratory surveys EVERY DAY when radionuclides are actually in use.

Monthey evere0e dunng the beoassay enterval.

RPR 11. RAoLAs SAFETY (7/92) -5 I

i

i I

RECORDS i

All radioisotope disposition records must be kept up i

to date and returned to the TSO when the waste is picked up. Refer to " RADIOISOTOPE ACQUISITION AND DISPOSITION" tRm ias for instructions.

The results of radiation surveys are to be recorded i

and retained for a minimum of three years. They are to be made available for review and evaluation by the

]

RSO and the appropriate licensing agency. A suitable j

form for recording survey results is attached to this procedure; however, otherformats that provide com-parable information may be used.

l Personnel surveys should indicate the name of the individual surveyed and, if any contamination was found, the location on the body or on the clothing.

1 1

i e

4 i

i RPR 11. RADLAB SAFETY (7/02) -6

?

l RPR 11 A. CONTAMINATION SURVEY - PORTABLE INSTRUMENT Pege 1 of survey record initiated by inen=> on idei.:

User:

Bldg / Room (s):

)

Nuclides used:

Critical nuclide:

All: ___ mci Removab!o contamination limit (RCL):

dpm per 100 cm 2 SURVEY INSTRUMENT RESPONSE TO CRITICAL NUCLIDE Critical Expected Not Response Survev instrument (s) Used Nuclide to 1 RCL (com or cos)

Bkgd.

Efficiency

[1]

12]

-[3]

Calib.

Rate Point Wipe of Wipe of Make. modet.Ser. No.

Date (com)

Source Direct 100 cm' 300 cm' l

1.

2.

3.

l (1) and (21 RCL x Pomt Source Effecency 1313 m RCL x Pomt Source Eff.

f i

CONTAMINATION SURVEY RESULTS

{

i

!Al Repeated entnee for persone or locations met are surveyed regulerty may be edentifed by matiale or a code letter following a cieerty identifed entry

~

on the some or previous sheets.

[8]

Enter "D* for e direct measurement. *100* for a 100 cer/ wipe or *300* for e 300 cm' wape.

IC)

Net count rate of motor wrth probe neer the contammated surface or the wipe fitter.

IDI

1. f the count rate m re).e greet., then tr. expected respone. to i RcL. es heted above. enter the muetipio of the Ret

[A]

[B]

[C]

[D]

f Survey inst.

Object, Location in Room Area Net Rate Multiple Surveyed Date Used or Name of Person (cm )

(com) of RCL By

)

2

(

i l

t s

I 1

)

ALL SURVEY RECORDS MUST BE RETAINED FOR AT LEAST THREE YEARS i

i RPR 11. RADLA8 SAFETY (7/g2l -7 l

l

\\

i

RPR 11 A. CONTAMINATION SURVEY - PORTABLE INSTRUMENT Continuation sheet # _ of record initiated on to t.:

User:

Bldg / Room (s):

Nuclides used:

Critical nuclide:

All: _ mci Removable contamination limit (RCL):

dpm per 100 cm' (A)

(B)

[C]

(D)

Survey Inst.

Object, Location in Room Area Net Rate Multiple Surveyed

. qnf}_

(com) of RCL Bv

(

Date Used or Name of Person MM N

m mWN m

N 9969 W

N m

6me N

4 WW6 t

m m

m 6

i 1

N ALL SURVEY RECORDS MUST BE RETAINE.D FOR AT LEAST THREE YEARS '

RPR 11. RADLA8 SAFETY (7/92)-8 r

~_

d RPR 11B. CONTAMINATION SURVEY - WIPE TESTS Pege 1 of survey record initieted by tnemes on wete -

Us3r:

Bldg / Room (s):

i Nuclides used:

Critical nuclide:

A ll: _ m Ci 4

Removable contamination limit (RCL):

dpm per 100 cm' a

COUNTING INSTRUMENT DATA i

Type:

LSC _ Gamma _, Other Model, S/N:

i Program / Setup:

Preset:

minutes or

__ counts Units of Readout:

l Counting Channel:

(11 121 (31

Background:

Critical nuclide efficiency:

Expected Net Response to 1 RCL:

i WIPE TEST COUNTING RESULTS I

(Al Repeated entnes for persone or locations that are surveyed regulerty may be edentdaad by initiate or e code tetter efter e cieerty identified entry on the some or continuation sheets.

IBl Enter *100* for a 100 cm' wee or *300*7br a 300 cm' wepe.

4 tc1 Net re.pon.e m e.cn chann.iin some unite se recorded above.

(D]

If pnmary channel response e greater then that expected for 1 RCL, enter the mutteple of the RCL.

[A]

[B]

[C]

[D]

Survey Area Net Channel Resoonse Muttiple '

Surveyed l

Date Obiect or Location (cm')

111 (21 (31 of RCL Bv

+

l i

l i

b 1

1 i

l I

)

i ALL SURVEY RECORDS MUST BE RETAINED SOR AT LEAST THREE YEARS RPR 11. RADLAB SAFETY (7/92:.9 a

_., -.. _. +.

.,--.4

,,m.,

,.~,,...,-w,e,,

. - ~ - -

RPR 118. CONTAMINATION SURVEY - WIPE TESTS Continuation sheet # _ of record initiated on to.w User:

Bida/ Room (sh i

Nuclides used:

Critical nuclide:

All: _ mci f

2 Removable contamination limit (RCL):

dpm per 100 cm l

l f

[A]

[B)

[C]

[D]

l Survey Area Net Channel Resoonse Multiple

. Surveyed Date Obieet or Location (cm')

111 I21

._[21_

of RCL By i

i f

i i

l t

I f

r

[

\\

h h

I f

r ALL SURVEY RECORDS MUST BE RETAINED FOR AT LEAST THREE YEARS I

r RP9t 11. RADLAB SAFETY (7/92) -10

i l

l 7

i i

BIOASSAYS FOR INTERNAL RADIOACTIVITY PURPOSE by the nuclides used, are required from each user who handles more than minimal quantities of disper-This procedure specifies the requirements, responsi-sible radionuclides. A routine bioassay may be bilities and methods for performing and reporting waived when appropriate surveys for contamination, measurements for detecting and verifying the pres-conducted during and after each use of radioactive ence or absence of radioactivity in the body.

material according to recommended procedures, i

demonstrate that there was essentially no exposure to unconfined, dispersible radioactive material.

POLICY Although the emphasis of a radiation protection DEFINITIONS program is primarily on prevention of unnecessary j

exposures, measurement and evaluation of exposures All: The annuallimit on intake is the quantity of any is also necessary. Bioassay is the determination of radionuclide which, if taken into the body, produces the kind and amount (and possibly the location) of an effective dose to internal organs that is equivalent radioactive material in the human body by direct (b in risk to the annual whole body dose limit of 5 rems.

vivo) measurement or by analysis MMim of materials Because of differences in physiological transport excreted or removed from the body. Bioassay is an mechanisms, the ALis vary depending on the route important tool for evaluating actual or suspected h ofintake. For purposesof contamination controland vivo contamination with radioactive materials. Mon-bioassay procedures, the All for ingestion is used, itoring and dose assessment mu% be performed for since that is the most common route of accidental any individual with an annual intake of all nuclides intake in research laboratories.

combined of 0.1 ALI or more. To assure that this requirement is met in all cases, indrvidual intakes Removable Contamination Limit: A basic limit for must be detected and evaluated at lower levels. The removable surf ace contamination, specified in " CON-conditions requiring bioassavs, as well as the meth.

TAMINATION LIMITS AND ACTION LEVELS" (RPR ods and maximum intervals specified in this proce-T oB).

dure are designed to assure that an annual intake exceeding 0.05 ALI, whether as a single intake or as intake & Uotake: The total quantity of radioactive i

chronic or multiple intakes, is not only detected, but material entering the body is referred to as the intake, determined quantitatively.

whereas the quantity absorbed into organs, tissues or interstitial fluids is referred to as the uptake.

l Individuals who handle dispersible radioiodine com-pounds may be required to obtain h vivo measure-Discersible: In the context of bioassay requirements, l

ments of radiciodine in the thyroid, performed by the "dispersible" refers to radioactive materials in any l

RSO, at specified intervals. Individuals who handle form that could be taken into the body and potentially other radionuclides in dispersible forms may be transferred to body organs, tissues or fluids.

l required to perform assays of radioactivity in urine on a routine basis to document the absence of Bioassav interval: The bioassay intervat is the maxi-radioactivity in the body or to determine the magni-mum time that,may elapse between bicassays that tude of any exposure. Other types of assays may will assure detection of the verification level for a be utilized if, in the judgement of the RSO, such given nuclide and assay method. The bioassay assays will meet the intent of this policy more ef-interval for a particular nuclide is determined by its fectively.

physical and metabolic characteristics, and by the instrumentation used for the measurement. For most A bioassay is required whenever personal contamina-commonly used nuclides and typical analytical sys-tion or injury caused by a contaminated object tems, the bioassay intervalis 13 weeks (one calendar occurs, or if airborne radioactivity may have been quarter); for P-32, and a few other very short-lived inhaled. Routine bioassays, at intervals determined RPR 12. BloASSAY (7/92) 1 r

l

i I

nuclides, however, the bioassay interval is only one dispersible form of more than 0.5 ALI per month, j

month.

averaged over the bioassay interval, is considered to be potentially exposed to an annualintake of more j

Elaosed interval: The elapsed interval is the time than 0.05 ALI and must perform or obtain bioassays j

since an assumed intake of radioactive materials or, routinely unless the records of contamination surveys i

if the time of intake is unknown, since the last bioas-of both the user and the RSO verify that there was say without a positive result. The elapsed interval no exposure to unconfined radioactive materials is used to calculate the intake and the effective dose exceeding the levels specified below.

j from a positive bioassay result.

Screenino assav: A screening assay is one that is CONDITIONS REQUIRING BIOASSAYS performed simply to determine whether radioactivity i

may be present in the body, but without precise The optimum time for performing a bioassay is within j

quantification of activity or dose.

a few days after a potential exposure. Each user should perform a screening assay within a few days a

j Verification level: The verification level is a result after handling any unusually large quantities, or after of a screening bicassay that indicates a possible performing any procedure involving a greater than intake exceedmg 0.002 ALi multiplied by the elapsed usual opportunity for exposure. Subsequent routine 3

j interval in weeks. A screening assay result that bioassays would not be required again until the end

[

exceeds the verification level must be verified.

of another full bioassay interval unless another a

I unusual exposure situation occurred. The RSO will j

Verification assav A verification assay is one that notify users when a bioassay is due, i.e. the expira-is performed to obtain a reasonable estimate of the tion of the bioassay interval, but it is the respon-I actual quantity of radioactivity taken into or present sibility of the user to complete the bioassay promptly.

in the body. The verification assay is performed by, Since the last bioassay, if no work with radioactive or under the direction of, the RSO.

materials was performed, or if survey records verify that there was no exposure to contamination exceed-Dosimetric assav: A quantitative bioasTay performed ing the levels indicated below, this may be reported by an independent reputable laboratory to provide by checking the appropriate statement on the "URI-I data for annual dose determination is called a desi-NALYSIS SCREENING ASSAY"reportform(RPR12A).

[

metric assay. The need for a dosimetric assay will j

be determined by the RSO, but it is generally required 1

A bioassay is required within 5 days for each 1

for any individual whose cumulative annual intake individual having contamination of the skin or hair ex-is likely to exceed 0.1 All.

ceeding 10 RCL.

j investication level: An assay result that indicates a 2

A bioassay is required within the normal bioas-

[

j possible intake of 0.05 ALI or more will be investigat-say interval for any individual having skin or hair ed by the RSO to determine the cause of the expo-contamination exceeding 1 RCL.

l sure and corrective measures to prevent or reduce j

exposures in the future.

3 A bioassay is required within 5 days for each individual involved in a spill, or other uncontrolled Minimativ exoosed: A radiation user who handles a release, of >0.5 All of radioactive material outside cumulative quantity of radioactive materials in dis-of a properly functioning fume hood or > 5 ALIinside persible form of less than 0.5 All per month, av-a hood.

I eraged over the bioassay interval, is very unlikely to 1

experience an annualintake of 0.05 ALI and does not 4

A bioassay is required within 5 days for each require routine bioassays. If exposed to contamina-individual who was present in an area during a time tion exceeding the levels specified under " Conditions when removable contamination exceeding 100 RCL Requiring Bioassays", however, a nonroutine bioassay was present on any readily accessible surface, i

will be required.

~

5 A bioassay is required within the normal bioas-Potentiativ exposed: A radiation user who handles say interval for each individual who was present in j

a cumulative quantity of radioactive materials in an area during a time when removable contamination i

RPR 12. BloASSAY (7/92).2 l

.... ~.

l exceeding 10 RCL was present on any readily acces-listed, the action levels must be obtained from the sible surface.

RSO.

6 A bioassay is required within the normal bioas-The sample volume and minimum cour. ting time must say interval for each "potentially exposed" radiation be selected so as to achieve a lowerlimit of detection user. The determination of the cumulative quantity (LLD) at least equal to the required veiification level.

I handled will be based primarily on records of receipts The " BIOASSAY GUIDELIN ES" provide examples for

{

and disposals of radioactive materials, with adjust-several common nuclides and liquid scintillation ments for individual work assignments as defined by counting conditions, and may be used, if appropriate.

the responsible user. Routine bioassays may be The minimum counting time may be calculated as waived at the discretion of the RSO if the records of illustrated later in this procedure or it may also be i

contamination surveys of both the user and the RSO requested from the RSO.

verify that there was no exposure to unconfined l

radioactive materials exceeding the levels specified For urinalysis by liquid scintillation counting, select

[

above and no incidents of personal contamination a fluor that is suitable for large aqueous samples; i

since the last bioassay.

Cherenkov counting may be used for P-32 or other high-energy beta emitters.

1 RADIOIODINE ASSAYS For urinalysis by gamma counting, as well as by liquid l

scintillation counting, proceed as follows:

The preferred bioassay method for i

gamma-emitting radiciodines is by b vivo measure-1 To assure adequate sensitivity of the measure-ment of the thyroid gland. These assays are per-ment, use the largest vial and sample volume that formed by the RSO at preannounced locations on a the counting system can accommodate.

regular schedule. It is the responsibility of the user to obtain the thyroid assay whenever appropriate.

2 Prepare urine and distilled water samples of Records of the results of these assayrgre maintained equal volumes. Count both the urine and the distilled by the RSO, but are available to the monitored water samples for the same times.

)

individuals upon request.

i 3

Record the sample data and results on the

)

• URINALYSIS SCREENING ASSAY" form (RPR 12A).

I SCREENING UR9fALYSIS Calculate the activity concentration (dpm/mL) in the urine sample, using a nominal counting efficiency (as i

A screening assay is one performed simply to deter-provided by the vendor) for the nuclide of greatest mine whether radioactivity is present in the body, but concern.

without precise quantification of activity or dose.

For radionuclides other than iodines, routine bioas-4 Compare the assay result with the venfication says are most easily performed by h yitrg. analyses level for the nuclide(s) of interest, based on the of urine. The same instruments that are used to elapsed interval since last use (or last negative bioas-measure radioactivity in research samples may be say). If the assay result is less than the verification used to detect the same radioisotopes in urine level, send the signed form to the RSO. If the assay samples. Routine screening assays are to be per-result exceeds the verification level, perform a formed by or for each potentially exposed individual

" Verification Assay".

and reported to the RSO on the " URINALYSIS SC-j REENING ASSAY" form (RPR 12A).

VERIFICATION ASSAYS I

For the nuclides used recently, determine the verifica-If the result of a screening assay indicates the possi-tion level (dpm/mL of urine) for the elapsed interval.

ble presence of radioactive materialin the body, at For several commonly-used nuclides, the " BIOASSAY least one additional assay must be performed to GUIDELINES" that follow list the action levels for verify the result. A verification assay for a urine various elapsed times up to the maximum elapsed sample involves spiking the urine and distilled water interval. For other nuclides, or for elapsed times not samples with a known amount of activity to obtain the true efficiency of the counting system for the RPR 12. BloAssAY(7/92) 3

samples. Follow the steps on the " URINALYSIS VERIFICATION ASSAY" form (RPR 12B). If the bio-assay result exceeds the investigation level or in-dicates a potential annualintake exceeding 0.1 All, the RSO will determine appropriate corrective mea-sures.

I t

REFERENCES i

International Commission on Radiological Protection:

i General Principles of Monitoring for Radiation

\\

Protection of Workers, ICRP Publ. 35,1982.

I i

Limits for intakes of Radionuclides by Workers, ICRP Publ. 30, Parts 1,2 and 3 with Supple-l ments,1979-82.

Evaluation of Radiation Doses to Body lissues from Intemal Contamination Due to Occupation-al Exposure, ICRP Publ. 10,1968.

j An Assessment of Intemal Contamination i

Resulting from Recurren t or Prolonged Uptakes, i

ICRP Publ.10A,1971.

l National Council on Radiation Protection and Mea-l surements:

l General Concepts for the Dosimetty ofIntemally i

Deposited Radionuclides, Report No. 84,1984.

i Use of Bioassay Procedures for Assessment of internalRadionuclide Deposition, NCRP Report No.87,1987.

I i

U.S. Nuclear Regulatory Commission:

Acceptable Concepts, Models, Equations and Assumptions for a Bionssay Program, Reg.

(

Guide 8.9,1973.

Applications of Bioassay for 1-125 and 1-131, Reg. Guide 8.20, Rev.1,1979.

Information for Establishing Bioassay Measure-ments and Evaluations of Tritium Exposure, NUREG-0938,1983.

l RPR 12. BloASSAY (7/32)-4 l

I I

l

l MINIMUM COUNTING TIME CALCULATION The lower limit of detection (LLD) for which the risks of false negative results and of false positive results are each 5% is defined as follows:

LLD = 4.66(SD,1/Eff where:

disintegrations in sample in time T = VL x Vol x T LLD

=

l 4.66 = the product of the distribution parameters needed to establish the 5% error limits i

S D, =

standard deviation of the background (distilled water) count N,* * = (R,xT)"

=

N, = total background ccants in time T R, =

background count rate, in epm detection e$fciency, in counts / dis Eff

=

(a nominal efficiency may be used for screening assays, whereas it should be determined experimentally for verification assays) i VL = venfication level for elapsed interval since last bioassay, in dpm/mL Vol = volume of urine in sample, in mL T=

minimum counting time required, in minutes 1

R,(4.66/VL x Vol x Eff)2

=

i l

RPR 12. BIOASSAY (7/92) -5 l

l

BIOASSAY GUIDELINES I

1 i

~'

FOR URINALYSES FOR SELECTED RADIONUCLIDES

• Assumed Values Minimum Values Elapsed Action Levels Bkgd.

Count Sample Count Interval (dem/mL)

Rate Effic.

Volume Time Nuclide (weeks)

Verif.

Invest.

(com)

(t)

(mL)

(trin) i i

l H-3 1

5,800 145,000.

<25

>30%.

0.2 2

l 8

1,500 4,800 0.2 2

l maximum: 13 220 420 0.2 10 i

C-14 1

1 47 NA NA maximum: 8 6

20

<30

>40%

1.0 100 l

i l

P-32 1

16 400

<60

>80%

08 20 l

2 13 160 1.0

'20 i

3 10 87

1. 0' 20 maximum: 4 7

48 1.0 40 i

l S-35 1

64 1,600

<30

>40%

0.2 30 l

4 100 660 0.2 10 8

65 200 0.2 30 l

maximum: 13 25 48 0.8 20 t

l w.

i Cl-36 1

270 6,700

<30

>50%

0.2 2

4 250 1560 0.2 2

l i

8 71 220 0.2 20 t

maximum: 13 10 19 1.0 30 l

l l

Cr-51 1

130 3,300

<25

>30%

0.2 10 l

l 4

48 300 0.4 20 8

19 60 1.0 20 t

maximum: 13 9

17 10 80 I

FOR TNYROID MOnitOkING FOR RADIOIODINEE Elapsed I-125 Action Levels I-131 Action Levels l

Interval (nCi in thyroid)

(nci in thyroid)

(weeks)

Veri fv Investicate Verify Investicate 1

21 530 9.4 235 2

38 470 9.9 120 4

59 370 5.4 34 8

72 230 0.8 3

13 64 120 0.05 1

• If the auchdois) you work enh are act hated above. or af your cousnes -

bas a eissufiandy different backgroiad count ruse or counung smceeney from that Istad above, contact the RSO for appropruas======= meervais, ensapie voksnee and cousnas immes.

RPR 12. B10 ASSAY (7/92)-6 I

l

l RPR 12A. URINALYSIS SCREENING ASSAY Name:

Soc Sec. No.

Department:

Work Location:

)

Radionuelides used since last bioassay Action Levels Nuclide How Much?

How Leno Aco?

Verification Investication mci weeks dpm/mL dpm/mL mci weeks dpm/mL dpm/mL Check here if all records of contamination surveys, both by the user and the RSO, indicate no personal contamination and no exposure to unconfined radioactive materials exceeding the levels specified under

" Conditions of use that require bicassays" in the procedure.

l Check here if you have used no dispersible radioactive materials since l

your laet bioassay.

If you have checked either of the above exemption statements, provide the signatures i

and return the form to the RSO.

Assay Data: Sample collection date:

Date counted:

Instrument used (make, m8 del, S.N.):

?

Sample:

mL Fluor:

mL Count time:

minutes l

Total counts from samples -

Urine:

Distilled water.:

i Nominal counting efficiency for the assay counts / dis j

=

l Concentration in dos /sL:

(Urine samole counts) - (Distilled water samole counts)

(Sample volume, mL) x (Count time, min) x (Efficiency, counts / dis) dpm/mL Less than verification level?

Yes No

=

If less than the verification level, sign the form and obtain the signature of the authorized user; then send the form promptly to the RSO.

If the result exceeds the verification level, proceed with a verification assay, using the following form (RPR 12B) for reporting.

Sienatures:

Counted by:

Responsible User:

1 RSO verification of survey data:

(Analyst or RSO) l RPR 12. BIOASSAY (7/92)-7

l l

i RPR 12B. URINALYSIS VERIFICATION ASSAY 1

i Name:

Soc. Sec. No.

Sample collection date:

Date counted:

Instructions:

1.

Complete the " Screening Assay" procedure.

2.

Add a known activity of the nuclide of greatest concern to each sample (urine and distilled water) and count again to determine the true efficiency.

(NOTE: The volume of the spike must be small enough so that it does not change the original counting characteristics of the sample.)

If the appropriate nuclide is not available in a solution of known concentration from which a spike can be cbtained, discuss the requirement with the RSO.

3.

Calculate the counting efficiency and convert the final results to disintegrations per minute per milliliter of sample (dpm/mL).

Assay Data: Instrument used:

Sample:

mL Fluor:

mL Count time:

minutes Activity added to sample for efficiency determinttion:

Source: Inventory No.

Concentration:

dpm/mL Volume added:

mL Activity:

dpm Total counte obtained from samples:

Untreated Soiked N

Urine samples:

Distilled water samples:

Efficienev in counts /dise (Sciked urine sa:=cle counts) - (Untreated urine samole counts)

(Count time, min) x (Spike activity, dpm) counts / dis

=

i Concentration in den /mL:

(Untreated urine samole counts) - ' Untreated distilled water samole counts)

(Sample volume, mL) x (Count time, min) x (Efficiency, counts / dis) dpm/mL Less than investigation level?

Yes No

=

If less than the investigation level, complete the signatures and mail the fem to the RSO.

If the result exceeds the investigation level, confer with the RSO to detemine appropriate follow-up assays.

Sienatures:

Counted by:

Responsible User:

RPR 12. BIOASSAY (7/92)-8

r RPR 12C. THYROID MONITORING REPORT-i Name:

Soc. Sec. No.:

i Instructions:

l 1.

Record successive counts for one individual until the sheet is filled, or until a verification assay is required,as long as the same instrument is used and the calibration is still valid.

2.

Use the same counting time for all counts.

3.

Ccnvert to thyroid activity if counts exceed an action level.

)

Instrument and calibration data:

t Scaler - model:

Ser. No.

j Detector - model:

Ser. No.

I Calibration date:

Count time:

min or see Efficiency (net counts /nCi):

I 125:

I-131:

l I-129 check source ID:

Net counts in phantom:

(

Screenino assay data:

j Elapsed Verif.

Phantom Thyroid Data Nuclide Interval Level Counts Gross Net i

l Date Used (weeks)

(nCi)

Bked.

I-129 (cts)

(Ct s)

(nCi)

By i

l 1

l l

l Submit the form for filing after the above spaces have been filled, or after one verification assay'has been recorded, whichever comes first.

Verification assay data:

j I

If screening assay exceeds the verification level, make a measurement on the thigh i

to determine contribution from blood pool. Use the thigh measurement as the background l

to determine net activity in thyroid:

1 (Total counts from thyroid) - (Total counts from thich) nCi

=

(Efficiency, net counts per nCi)

If the verification assay result does not exceed the investigation level, submit the form although no further action is required. If the investigation level is exceeded, report to the RSO and initiate an investigation.

Reviewed by:

Date:

RPR 12. BloASSAY (7/92)-9

l

\\

l l

RADIOISOTOPE ACQUISITION AND DISPOSITION PURPOSE requests for radioactive material from the Physics Department shall also be treated as a normal I

This procedure specifies measures tar the contro of purchase of radioactive material. All request must j

radioactive materials from initial acq sisition to fsnal be submitted to the TSO on Form RPR 13F.

disposition by the responsible user. I t describes the prerequisites for acquiring radioactive matsrials. It Each user of radioactive materials shall maintain a specifies the procedures and forms for surveying complete record of all acquisitions, uses, transfers i

and reporting the receipt of radioactive materials, and disposals of such materials and provide this i

for maintaining radioactive inventory records, and data to the TSO in a timely manner. Before any for reporting all transfers. and disposals of radioactive materials can be transferred to another radioactive materials. Radioactive waste categories responsible user, or to another organization, are described, along with acceptable methods for authorization shall be obtained from the TSO.

segregation, packaging, labeling and reporting the disposal of such wastes. A separate procedure, Radioactive waste materials must be segregated by RPR S4 covers waste management by the Technical nuclide and all radioactive material labels removed Safety Office (TSO) and the responsible users.

by the responsible user prior to collection for disposal by the TSO. For the safety of all personnel involved in radioactive waste disposal, responsible POLICY users must take all reasonable precautions to deactivate, detoxify and neutralize biological waste l

Radioactive materials may be used for any materials.

legitimate educational, clinical or research purpose.

I However, they shall be purchased, or obtained, by individuals specifically authorized by the Radiation DEFINITIONS Safety Committee (RSC). The use of radioactive r

materials is conditional upon compliance with

" Animal" waste means carcasses or parts of specific procedures established by the RSC.

animals administered radioactive materials; it also includes collected excreta and combustible bedding The permission of the Radiation Safety Officer materials, e.g. shavings or sawdust.

(RSO) or a designated alternate, shall be obtained, j

l before any radioactive materials can be obtained by

" Assay Date" is the date that the manufacture i

a responsible user. The receipt of any radioactive certifies the activity of the isotope.

l material that is not obtained through the RSO,

~

should be reported promptly to the TSO.

" Aqueous" means a liquid that is soluble or readily j

dispersible in water and which contains no The College of Engineering's reactor program is chemicals classified as toxic or hazardous; except

)

allowed, under its resctor license, to produce for limits on radioactivity, aqueous liquid wastes are radioactive materials; Subsequently, all requests for those which may be discarded to the sewer.

j radioactive material, from the reactor program, shall be treated as a normal purchase of radioactive

" Dry" waste means any solid, nonputrescible, dry material. All requests for radioactive material from waste, e.g. paper, plastics, glassware and metals, the reactor program shall submitted to the TSO on that does not contain any compressed gases, a " Radioactive Material Request Form" ( RPR 13F).

pyrophoric or other hazardous materials, including If the request is for an authorized material it will be lead.

processed promptly; However, if the request is for an unauthorized material it will be returned to the "LS media" means any mixture of solvents and user until proper authorization is obtained.

fluors used for liquid scintillation counting.

The Physics department'has two accelerators that "NHNT" means nonhazardous, nontoxic, non-are capable of producing radioactive isotopes. Any flammable aqueous liquid.

j l

RPR 13. ISOTOPE ACQutSmoN & DISPoSmoN (12/92)- 1

~~

" Pathogenic" means any material potentially RPR 138 will be placed in the " Isotope Inventory containing pathogenic organisms, toxins, infectious Book." RPR 13C, which contains the same serial agents, etc.

number and identification data as 13A and 138, is j

forwarded with the package to the responsible user.

l A fourth form RPR 13D DISPOSAL LOG is available l

to the user as a supplement to RPR 13C. When the PURCHASING PROCEDURES radioactive material is retumed to the TSO as radioactive waste, forms RPR13A,13B, and 13C l

All purchases of radioactive materials and those are joined together and placed in the appropriate materials that are obtained from the reactor or section of the " Radioactive Waste Log" (see RPR 54).

accelerator programs must be initiated on a i

" Radioactive Material Purchase Permit" (RPR 130 and submitted to the TSO. If the order is for an authorized isotope and quantity, it will be processed RECEIPT AND VERIFICATION (RPR 138) promptly. If the user is not authorized to posses j

the isotope type or quantity ordered, the request Each new acquisition of radioactive material is i

will be held, by the TSO, until proper authorization reported on the " RADIOISOTOPE RECEIPT AND is obtained. The requisition shall contain the name VERIFICATION" form (RPR 138). In accordance with of the responsible user and an accurate description 10 CFR 20.1906.c, all radioactive material shall be of the radioactive material, including the isotope surveyed by the TSO not later than three hours of and the total activity, e.g. millicuries, not just a its arrival on the ISU campus, if the package was catalog number.

received during normal working hours.

If the package arrives at the ISU campus after normal working hours, then the package shall be surveyed not later than three hours from the beginning of the j

RADIOACTIVE MATERIAL CONTROL RECORDS next working day.

Any discrepancies in the package contents are to be noted on the form. The A serialized, multi-part form (RPR 13A.B & C) is used survey data and verification of the package for tracking of all radioactive material, from the time contents are to be retained by the Technical Safety it arrives at the University until it is transferred or Office in the " Isotope inventory Book." When the disposed of as radioactive waste. For radioactive material is returned to the TSO as waste, RPR 13B materials acquired through normal purchasing will be attached to RPR 13A and placed in the channels, the reactor program, or the accelerator appropriate section of the " Radioactive Waste Log."

program, the forms for reporting the contamination survey of a package, verification of u contents, Additionally, the TSO will recalculate a new and for reporting the disposition of the material will

" Bioassay interval" (RPR 12) and a new " Laboratory be initiated by the TSO. For materials acquired by Evaluation Interval" (RPR 50) for each new isotope any other means, the user is responsible for shipment.

promptly notifying the TSO and providing the information necessary to initiate the form.

DISPOSITION RECORD (RPR 13Cl All dispositions of radioactive materials are to be PACKAGE ARRIVAL REPORT (RPR isA, s & c) recorded, by the user, on the " RADIOISOTOPE DISPOSITION RECORD * (RPR 13c).

To avoid incomplete records and possible oversights, the Technical Safety Office:

disposition of material should be recorded either directly on the disposition form (RPR 13C) or on a When radioactive material is received, the TSO will

" DISPOSAL LOG" sheet (RPR 13D) at the time it is initiate the record by entering the identification of placed in a waste container. However, the material the user, the material, and the results of the will not be removed from the isotope Inventory external survey of the package on forms RPR 13A, Book until the disposition form is returned to the 13B, and 13C. RPR 13A when completed, will be TSO. When the material is returned to the TSO as placed in section 1 of the " Radioactive Waste Log."

radioactive waste, RPR 13C will be attached to l

l RPR 13. LSoToPE AcQu!SmoN & DisPoSmoN (12/92F 2 I

6

forms 13A and 138 and placed in the appropriate

• LOCAL TRANSPORT OR SHIPMENT OF SMALL section of the " Radioactive Waste Log" (see RPR OUANTITIES OF RADIOISOTOPES."

54) i To minimize errors in calculation of the activity used TRANSFERS TO NON-UNIVERSITY USERS or disposed of at various times, dispositions should be reported, on RPR 13C, as percentages of the The user who wishes to send radioactive material to 1

original quantity without regard to the radioactive another institution must notify the TSO of the j

decay or subsequent dilutions. Quantities may be intended transfer. The user will not transfer any l

reported as actual activities, e.g. microcuries or material until specific approvalis received from the j

millicuries, but care must be taken to avoid errors.

TSO. In accordance with 10 CFR 30.31.c. the TSO The reported dispositions must account for the must obtain written confirmation of the other original quantity within a reasonable degree of institution's license before the transfer is made:

i accuracy or the form may be returned to the user Additionally, the TSO must verify that the material l

for correction.

is shipped in accordance with the regulations of the US Dept. of Transportation. A user planning on shipping material to another institution, should refer to " LOCAL TRANSPORT OR SHIPMENT OF SMALL

[

DISPOSAL LOG OUANTITIES OF RADIOISOTOPES" (RPR 14) or l

"TR ANS PO RTATION OR SHIPMENT OF j

The " DISPOSAL LOG" (RPR 13D) is an optional form RADIOACTIVE MATERIALS" (RPR 55) for to aid radiation users in accounting for frequent instructions.

disposals of small quantities of radioisotopes. Each

" DISPOSAL LOG" sheet should be used for only one disposal method or waste container.

When EMPTY CONTAINERS frequent disposals are made to the same waste container, the quantities may be summed for If an empty ' radioisotope container is not 1

periods of up to a week for entry on the contaminated, it should be disposed of as i

"RADIOf SOTOPE DISPOSITION RECORD" (RPR 13C).

nonradioactive trash. All radiation symbols and The total activity placed in each waste container warning labels must be obliterated before an empty must be recorded on its " RADIOACTIVE WASTE container is discarded. Discarded lead containers TAG" (RPR 13E). This form should remain with the must be kept separate, but will be picked up, by the Radioisotope Disposition Record.

TSO, for recycling or disposal.

i UNCONTAMINATED DRY WASTES TRANSFERS TO OTHER UNIVERSITY USERS i

Whenever possible, potentially contaminated waste Radioactive materials may be transferred between materials, e.g. gloves, absorbent paper, etc., should responsible users provided that the user possessing be surveyed before disposal. If the absence of the material has checked with the TSO to verify the radioactive contamination can be verified by direct receiving user is allowed to posses the isotope and survey, remove or obliterate all radiation labels and that the transfer is reported properly. The first user discard the material as ordinary trash.

must record the transfer on the original

" RADIOISOTOPE DISPOSITION RECORD * (RPR 13ci Since tritium '(H-3) cannot be detected by direct and the receiving user must request a new form survey, materials potentially contaminated with from the Technical Safety Office on which to record tritium must be assumed to be contaminated. For the disposition of the material.

other low-energy beta emitters, e.g. C-14, S-35, etc., direct surveys can detect contamination only Radioactive materials transferred by vehicle on directly accessible surfaces. For high-energy between buildings must be packaged and labeled in beta (e.g. P-32), x ray (e.g.1-125) or gamma (e.g.

accordance with US Department of Transportation Na-24) emitters, direct surveys with appropriate regulations. Follow the instructions in RPR 14, instruments can detect contamination beneath surface layers.

RPR 13. ISOTOPE ACQutSmoN & DISPoSmoN (12/921-3 l

l

.q f

criteria specified above are to be segregated and DRY RADIOACTIVE WASTES collected by the waste generator for disposal by the TSO. Separate containers are to be obtained for I

Solid wastes that do not contain putrescible or materials which would be incompatible if placed in i

pyrophoric materials, compressed gases or free the same container, e.g. aqueous solutions and liquids are collected and handled as dry radioactive organic solvents, as well as for different nuclides.

waste. Wastes containing only short-lived nuclides (half-lives of less than < 65 days), will be packaged Liquid waste containers are to be unbreakable, e.g.

separately and disposed of by radioactive decay.

plastic jugs or metal cans, and are to be placed in a Radioactive waste that contains long-lived nuclides secondary container of sufficient volume to collect (half-lives >65 days) will be packaged by the TSO all of the liquid in the event of a leak in the primary for disposal to a licensed disposal facility, container.

Syringes, needles, pipettes, etc. must be placed in Aqueous wastes must be neutralized to prevent standard

" sharps" or other puncture-proof violent chemical reactions when the wastes are containers.

The user shall provide a covered transferred. Organic solvents and other hazardous garbage can of an appropriate size (nD larger than materials must be clearly and completely identified l

25 gallons); the RSO provides labels and plastic bag to permit safe handling and disposal. No solid liners. As materials are added to the container, the objects are to be placed in any liquid waste con-isotopes and quantities should be recorded on a tainer and the materials must be sufficiently fluid to

" DISPOSAL LOG" (RPR 13D) or the "RADIOlSOTOPE be poured from the container, even after storage for DISPOSITION RECORD * (RPR 13C).

decay.

j Labels shall be removed from all radioactive material Biologically active materials are to be deactivated or that is placed inside a radioactive waste container.

detoxified at the time they are placed in the waste containers. A chlorine disinfectant (e.g. Chlorox i

brand liquid bleach) should be added to putrescible DISPOSAL TO THE SANITARY SEWER SYSTEM liquid wastes to retard putrification; the quantity depends on the concentration of organic material in Liquid radioactive wastes may be released by the the waste.

TSO to the sanitary sewer, in accordance with RPR 54, if they meet one of the following criteria:

Frequent disposals to liquid waste containers may be recorded and summed on a " DISPOSAL LOG" 1 Small quantities of radionuclides that are readily (RPR 13D).

Transfer the totals to the soluble or dispersible in water, and contain no toxic

" RADIOISOTOPE DISPOSITION RECORD * (RPR 13C) or hazardous substances, may be released to the at least weekly and to the

• RADIOACTIVE WASTE l

sewer by the TSO. The sink used by the TSO for TAG" (RPR 13E) before final disposa!.

sewage disposal of radioactive materials shall be identified with a

• CAUTION RADIOACTIVE MATERIAL" label on the drain trap as well as on the LIQUID SCINTILLATION MEDIA AND VIALS top of the sink.

Users are required to use "NHNT* LS media and to 2 Waste water from washing of contaminated minimize the quantities of LS media used, to the persons or equipment may be released to the sewer maximum extent that is compatible with research provided that the TSO is informed prior to the requirements. The use of flammable LS media or release and that the total activity to be released is standard vials should be justified in writing and verified with reasonable accuracy and recorded in approved by the Radiation Safety Committee.

the responsible users program file.

Used vials are to be segregated, according to the LS medium and the radionuclides they contain, into one LIQUID WASTE COLLECTION AND SEGREGATION of the following categories:

Any radioactive liquid wastes that cannot be released to the sanitary sewer system under the l

RPR 13. tSoToPE ACQUISmoN 86 DISPostTioN (12/92)- 4

i 1 Vials containing only "NHNT* media, H-3, C-14 LABELING OF RADIOACTIVE WASTES i

and/or short-lived nuclides, (half-lives of less than 65 days).

All containers in which radioactive wastes are collected must be labeled " CAUTION -

2 "NHNT" media containing long-lived nuclides RADIOACTIVE MATERIAL" or " CAUTION (half-lives > 65 days) other than H-3 or C-14.

RADIOACTIVE WASTE".

Packages in which radioactive wastes are stored or transported must 3 Any flammable solvent containing only H-3 be labeled with a " RADIOACTIVE WASTE TAG" (RPR and/or C-14 13E). The radioactive waste tag shall be filled out by the responsible user prior to pickup by the TSO.

4 Any flammable solvent containing only H-3, C-14 and/or short-lived nuclides, (half-lives <65 1 Each package may contain only one material days) should be further segregated by nuclides.

category of waste and must be labeled with its own tag.

5 Any flammable solvent containing long-lived nuclides other than H-3 or C-14.

2 Check one material category and one nuclide category contained in the package.

Used vials containing LS media should be placed in their original containers for collection. Standard 3 List the isotope and its activity in the spaces vials should be returned to their cardboard trays and provided. Enter the chemica' ~ trade nm of cartons; mini-vials should be placed in plastic bags any scintillation fluor, tissue solubilizer, or and I

of approximately the same capacity as the original chemical that may be classified as flammable, bags.

hazardous or toxic in the space provided. For such materials, attach a " Chain of Custody Record Sheet" (available from the TSO) to the

" RADIOACTIVE MATERIAL" labels should be waste tag.

removed from all vials, trays, begs and boxes of vials before they are transferred to the Technical 4 For liquid wastes, enter the volume (gallons) in Safety Office for disposal. The

• RADIOACTIVE a bulk container or the size of L.S. vials.

WASTE TAG" (RPR 13E) should be the only label indicating that the package contains radioactive 5 Verify whether the package contains any l

material.

" RADIO ACTIVE M ATERIAL" labels or tape; circle l

"YES" or "NO" (all labels should be removed i

Vials are to be securely capped; cartons are to be prior to placing any material in a radioactive j

securely taped and labeled to indicate the top, e.g.

material waste container).

"this side up" l

6 Enter the name of the Responsible User; date and sign the tag to indicate compliance with the l

SPECIAL WASTES waste generator's certification.

Any radioactive wastes not included in the above 7 The TSO will tie or tape the tag securely to the categories, or exhibiting unusual hazards, or waste packages.

requiring special precautions of any kind, are l

handled under special arrangements with the TSO.

Costs associated with handling, packaging, and/or WASTE COLLECTION disposal of abnormal radioactive wastes may be charged to the responsible user. Whenever unusual Responsible users should contact the Technical wastes are anticipated, the user should contact the Safety Office (236-2311) at least two days before TSO to plan for disposal before the wastes are a desired waste pick-up. All appropriate forms shall generated.

be filled out before the Technical Safety Office will -

accept custody of any waste.

RPR 13. isotope ACQUISmoN & DISPosmoN (12/92)- 5

(

The notice on the following page will be posted at radwaste collection locations to remind users of the requirements.

l When the isotope is no longer of use to the responsible user. the user should contact the TSO l

and schedule a waste pick-up. The Responsible Users should not accumulate waste in their laboratories.

l l

l 1

i l

l l

l i

i RPR 13. ISOTOPE ACQUtstTION & DISPCSITloN (12/92)- 6 I

RADIOACTIVE WASTE INSTRUCTIONS POST NEAR THE RADWASTE COLLECTION AREA ALL USE OF RADIOACTIVE MATERIALS IS CONDITIONAL UPON COMPLIANCE WITH THE FOLLOWING REQUIREMENTS FOR PACKAGING AND LABELING RADIOACTIVE WASTEE. NONCOMPLIANCE WILL NO BE TOLERATED, SINCE IT JEOPARDIZES ALL LEGITIMATE USES. WASTE PACKAGES ARE BEING INSPECTED; IMPROPERLY PACKAGED OR LABELED WASTES MAY RESULT IN IMMEDIATE CURTAILMENT OF THE USE OF RADIOACTIVE MATERIAL.

1.

ALL RADIOACTIVE WASTES MUST BE PROPERLY SEGREGATED - BY MATERIALS AND BY NUCLIDES.

2.

ALL SHARP OBJECTS MUST BE PLACED IN SEPARATE " SHARPS CONTAINERS" 3.

LEAD MUST BE KEPT SEPARATE, BUT WILL BE PICKED UP.

4.

THE RADIOACTIVE WASTE TAG MUST BE FILLED OUT COMPLETELY AND ACCURATELY, SIGNED AND DATED, BEFORE THE WASTE WILL BE ACCEPTED.

5.

THE ACTIVITY OF EACH NUCLIDE MUST BE ESTIMATED AS ACCURATELY AS POSSIBLE AND MUST BE CLEARLY SPECIFIED AS MILLICURIES OR MICROCURIES.

6.

IN ADDITION TO CHECKING THE APPROPRIATE CATEGORIES. THE WAS PE TAG MUST INCLUDE A DESCRIPTION OF THE WASTES.

7.

CHEMICAL CONSTITUENTS OF THE WASTE MUST BE IDENTIFIED BY N \\ME. SCINTILLATION FLUORS MUST BE IDENTIFIED BY BRAND NAME OR BY COMPLETE CHEMICAL COMPOSITION.

8.

IF ALL THE NUCLIDES IN A WASTE PACKAGE HAVE HALF-LIVES OF LESS THAN <65 DAYS, AND IF ALL " RADIOACTIVE MATERIAL" TAPE OR LABELS HAVE BEEN REMOVED OR OBLITERATED, ANSWER *NO" TO THE QUESTION ABOUT " RADIOACTIVE MATERIAL" LABELS; OTHERWISE, ANSWER "YES".

9.

CALL FOR WASTE PICKUP (236-2311) AT LEAST 2 DAYS BEFORE IT BECOMES URGENT.

I If you have any questions or problems, call the Technical Safety Office at 236-2311:

i RPR 13. ISOTCPE ACQUISITION & DISPOSITION (12/92b 7 l

i

~

I RPR 13A. RADIOISOTOPE PACKAGE ARRIVAL REPORT ll Inv. #

Program #:

Responsible User Dept.:

Location:

PO/Ref.'#:

Nuclide Initial activity:

millicuries Date:

==

Description:==

Assay Date:

Execsure Rate Survev Results:

Contamination Survey Results:

2

<0.5 mrem /hr at surface

<2000 net dpm/100 cm direct or:

mrem /hr at surface or:

net dpm/100 cm on wipe l

arem/hr at 1 meter Above results by survey meter.

If >SO at surface or Recipient to be notified by phone if

>1 a t 1 me ter, label if contamination is found on vipe should be Yellow II or III.

by liquid scintillation count.

1

" RADIOACTIVE

• vehicle placards required to transport packages with YELLOW III labels.

Ins truments*:

Model Ser. No.

Calib. Date Efficiency Contamination:

J Exposure rate:

Liquid Scint.:

j l

• (Instrument identification. calibration data and efficiency are on file in ISU Technical safety omce.)

Wipe results:

Count time Total count rate Backaround Net count rate

+

cpm

)

Survey meter:

cpm

+

cpm

+

J LS counting:

min epm cpm epm (all channels) l If incorrect labeling is suspected, or if any contamination is found on the package, notify the recipient promptly.

If personal or vehicle contamination is suspected, notify the Radiation Safety Officer j

iz: mediately. Any required notifications to the carrier or regulatory agencies is to be made by the RSO.

Package survey by:

Original - Initiated and retained by ISU Technical Safety Office Ccpies to send with the package (s) :

FADIOISOTCPE DISPOSITION (RPR 13C) for each package and/or item.

1

-l l

RPR 13. lSOTOPE ACQUISITION & DISPOSITION (12/92F 8

i l

I i

i RPR 13B. RADIOISOTOPE RECEIPT AND VERIFICATION l

t Inv. #

Program #:

Responsible User:

Dept.:

Location:

j i

PO/Ref. #2 Nuclides Initial activity:

millicuries Date:

==

Description:==

Assay Date:

i Ercosure Rate Survey Results:

Contamination Survey Results:

i 2

<0.5 mrem /hr at surface c2000 net dpm/100 cm direct

}

or: _

mrem /hr at surface or:

net dpm/100 cm a wipe 2

mrem /hr at 1 meter Above results by survey meter.

If >S0 at surface or Recipient to be notified by phone i

if

>1 at 1 meter, label if contamination is found on wipe should be Yellow II or III.

by liquid acintillation count.

t PACKAGE OPENING INSTRUCTIONS:

[

1.

Assume that container and packaging materials may be contaminated.

i 2.

Open in hood, if possible; wear gloves; work over absorbent paper.

3.

Use shielding and tongs for energetic beta or gamma emitters.

4.

Monitor thoroughly for contamination, including packaging materials, work area, clothing, hands, etc.

)

5.

Survey the inner container for removable contamination:

Wipe with a small piece of filter paper and check the paper for activity.

)

Use liquid scintillation counter for low-energy betas such as H-3, gamma counter for Cr-51, I-125 etc. or portable survey meter for energetic beta emitters such as P-32.

Report results below.

6.

Verify that the material description, nuclide and activity listed above a::e correct, or make corrections as necessary.

1 WIPE TEST RESULT:

not eps, by Survey Meter or Sample Counter PACKAGE RECEIVED IN GOOD CONDITION 7 Yes or describe DTSCRIPTION ABOVE IS ACCURATE OR HAS BEEN CORRECTED.

1 i

Opened, surveyed and verified by:

Date:

I l

RPR 13. ISOTOPE ACQUISmON & OtSPOSITION (12/92)- 9

~

._.. ~ -.... _. -,

1 I

RPR 13C. RADIOISOTOPE DISPOSITION RECORD Inv. #

Program #

Responsible User:

l Dept.:

Location:

)

PO/Ref. #t Nuclidet Initial activity:

millicuries i

1 Date:

==

Description:==

]

1 Assay Date:

i

(

1.

Record all transfers and disposals of the material listed above.

I Multiple disposals may be ca bined for periods not exceeding one week.

l 2.

EACM ENTRY SHOULD K EXPRESSED AS A PERCENTAE OF THE INITIAL euANTITY LISTED ABOVE.

Activity W)its may be used if decay corrected and specified clearly.

3.

For each disposal to a rachsmste cantainer or package, THE RADWASTE TAG IEssER 8EJST BE ENTERED AIC THE TYPE OF WASTE MATERIAL CIRCLED. The quantities reported on inventory disposition records will be checked against l

activities entered on redweste tags.

4 Transfer to another user or location must be approved in advance by the RSD and recorded below.

Categories:

S= Sewer; T= Transfer; A=Animmt; D 4 ry or sharps; I

F=Flammble Lipid; j

N 4NWT Li pid (bulk or vials)

Siyisture l

Circle One Waste Tag No. or (1st time)

I Date Category Nee of Recipient Amount Circle Units initials j

S T A D F W

% ACI mci S T A D F N

% ACI mci 5 T A D F N

% #Ci mci 5 T A D F W

% gCI mci S T A D F N

% ECl mci S T A D F W

% ACi mci S T A D F N

% ECi mci S T A D F N

% ACi mci S T A D F N

% gCi mci S T A D F N

% ACi mCl S T A D F N

% #Ci mci S T A D F W

% gCi mci 5 T A D F N

% #Ci mci S T A D F N

% ACl rnCi S T A D F N

% ACi mci S T A D F N

% ACi mci S T A D f N

% ACi mci j

$ T A D F N

% gCi mci For transfers: Name of recipient:

Location:

Date approved by RSD:

User SiFinture' Date:

When competed eign tre term one retum to asu Tecnruces betery othee bon a108.

l RPR 13. ISOTOPE ACQUISmON & DISPOSmON (12/92F 10

RPR 13D. DISPOSAL LOG Iristructiorts: Record individual disposals on this form. Transfer total for container to "RADICACTIVE WASTE TAG" (RPR 130 and tetal f or each inventory item to "RADICISOTOFE DISPOSITION RECORD" (RPR 13C).

Sink O or waste T.,s:

check cate, cry: O Dry or sharps O rt mnaete tiquid usuf tiquid 1 or

• rrorn RPR 13C 1 or

• rrte RPR 13C Date Nuclide ACi

% of InV. #

Initials Date Nuclide gCi Inv. f Initials J

RPR 13. ISOTOPE ACQUISITION & DISPOSITION (12/921-11

i RPR 13E. RADIOACTIVE WASTE TAG

~

{

+

CAUTION - RADIOACTIVE WASTE ONLY ONE NATERIAL CATE00RY ALLObED PER PACXA(El I

KEEP LEAD CONTAINERS SEPARATE FR(st MSTESI DRY, SOLID WASTE FOR LIOu!DS:

SHARPS (NEEDLES, P! PETS, ETC.)

Circle vist size:

ANIMAL OR OTHER BIOLOGICAL WASTE Mini Standard O NO -hazardous, uG= Toxic AQuE0uS trouiD Bulk Liquids F' AMMABLE, HAZARDOUS OR Tox!C LIQUID Cattons OTHER MATERIALS a

DESCRIBE MATERIAL - give names of chemicals and fluors:

!f any constituent is a " HAZARD (MS MTERIAL",

i.e. ignitable, corrosive, reactive or toxic (40 CFR 261),

1 conplete and attach a hAZl2005 MATERIAL DISP 0 GAL REaEST.

NUCliDES ACTIVITY CIEW EM CATEWY:

H-3 and/or C-14 Half-Life <65 days Other BETA-GAMMA Emitters O AtpHA E.itters or mass,2o4 DOES THIS PANM CXEITAIN ANY "RADt04CTIVE MTERIAL" LABELS?

Circle one: Yes No nASTE GENERATOR CERTIFIES THAT TIE CONTENTS ARE DESCRIBED ACQAATELYi Responsible User (Waste Generator):

Prepared by:

Rea M Catt-in Date TECHNICAL SAFETT OFFICE tJSE CEILY:

Accepted by:

Acceptance Date:

Storage Location:

Inv #:

Dry Waste Prepackaged drin Absorbed tiostabilized Process Date:

Container #:

Released Liquid OReteasedSotid other Exposure rate at contact:

mrem /hr Disposat Date:

By:

R8R 13E (2/92)

_t RPR 13. lSOTOPE ACQUIslil0N & DISPOSITION i12/92)- 12

l RPR 13F. RADIOACTIVE MATERIAL PURCHASE AUTHORIZATION l

l

1. All Radioactive Materials purchases requests must be cleared by the Technical Safety Office.

2.

Radioactive material purchases must be submitted at least three working days in advance.

I

3. All Radioactive Material Purchase Orders are to be a addressed as follows; Program Supervisors Name c/o Technical Safety Office l

Idaho State University l

Shipping & Receiving Dept.

I 638 E. Dunn St.

Pocatello, ID. 83209 4.

Forward this form to:

Technical Safety Office Box 8106 The attached requisition specifies the purchase of radioactive material under Idaho State Universities radioactive material license.

Responsible User:

Program #:

I' Dept:

l Authorized Isotone Chemical /obysi>:al form Possession limit I certify I am allowed to posses this material and that this l

purchase will not exceed my radioactive material possession l

limit.

1 l

Responsible User Signature:

Date:

This purchase request has been reviewed and verified by the Technical Safety Office.

Verified by:

I approve / disapprove this radioactive material purchase:

Radiation Safety Officer:

RPR 13. ISOTOPE ACQUISITION & DISPOSITION (12/92)- 13 I

l

I 1

2 l

7 i

ANALYTICAL X-RAY MACHINES i

1 PURPOSE prevents emergence of the primary beam, upon the f

failure of a safety or waming device.

l This procedure specifies requirements for analytical x-ray machines, including registration, physical safety "Open beam configuration". An analytical x-ray j

features, training and operational requirements for system in which an individual could accidentally users, and regular safety inspections.

place some part of his body in the primary beam path l

l during normal operation.

l POLICY A " radiation user" is any individual whose official

]

duties or authorized activities include handling, opera-

}

All operable x-ray generating machines used in Idaho ting, or working in the presence of, any type of j

State University facilities must be authorized by the radiation source, whether or not such use is confined

{

Radiation Safety Committee and must be registered to a restricted area.

i with the Idaho Radiation Control Agency (Idaho Department of Health and Welfare). All authori-A "normally exposed" radiation user is an individual l

zations and registrations shall be submitted to the who could receive more than one tenth (10%) of the Radiation Safety Officer (RSO) for review and pro-occupational radiation dose limit in any calencar f

f cessing. The RSO must also be notified before mov-quarter. This category includes individuals who j

ing, transferring or disposing of any x-ray machine.

normally receive more than 100 mrem per quarter, as well as some who rarely receive more than 100

)

The responsible user for each analytical x-ray ma-mrem in a quarter, but who work with sources that chine shall assure that detailed operating procedures could produce a significant dose accidentally, are available and that each operator has received appropriate training and understands Rnd follows the A " minimally exposed" radiation user is an individual j

correct procedures.

who is unlikely to receive one tenth (10%) of the occupational radiation dose limit in any calendar i

quarter.

j DEFINITIONS This category includes individuals who routinely i

]

handle only smallquantities of radioactive materials, t

" Analytical x-ray" refers broadly to machines or and others exposed only intermittently, e.g. dental i

systems used for research, for example to determine hygienists, emergency and security personnel, main-l the composition or microstructure of materials by tenance, receiving, custodial and housekeeping means of diffraction or fluorescence analysis or to personnel, j

l irradiate materials for testing. Specifically excluded I

are medical diagnostic or therapeutic units.

i REFERENCE l

" Beam-blocking device" means any part of an analyti-

[

cal x-ray machine or accessory that may be struck

" Radiation Safety Requirements for Analytical X-ray by x-rays, such as radiation source housings, ports Operations" IDAPA 16.01.9300, /daho Radiation and shutter assemblies, collimators, sample holders, Contro/ Regulations, Idaho Department of Health and camerc::, goniometers, detectors and shielding.

Welfare. Each responsible user should obtain a copy of IDAPA 16.01.9300, from the RSO and be f amiliar

" Exposed beam" means the operation of a normally with its contents.

enclosed analytical x-ray machine with any beam-blocking device removed and the x-ray beam on.

EQUIPMENT REQUIREMENTS

" Fail safe characteristics". A design feature which causes beam port shutters to close, or otherwise The requirements specified in regulation IDAPA 16.01.9300 apply to allof the University's analytical RPR 3o. ANALYTICAL X-RAY SAFETY (7/921 - 1

_ ~.-, _. _. -. _ _.

x-ray equipment. The important requirements are 4

any time a visualinspection reveals an abnormal itemized in " ANALYTICAL X-RAY MACHINE SAFETY condition.

INSPECTION" (RPR 30A). This record is to be completed by the responsible user at the time the machine is first registered and submitted to the RSO.

EXPOSURE MONITORING The inspection form is also to be used as a safety check list after any maintenance or mooitication that Users of open beam analytical x-ray units, and users requires disassembly.

of enclosed units who are approved to perform maintenance procedures with an exposed beam, are OPERATING REQUIREMENTS classified as normally exposed.

Each normally exposed radiation user of analytical x-ray equipment Each person who will operate or rr 4r. sin analytical must complete the

• RADIATION USER PERSONAL x-ray equipment shall first receive appropriate instruc-DATA" form (RPR 1 A). A finger dosimeter (TLD ring) tion and demonstrate competence on all topics will be issued within approximately one week after specified in IDAPA 16.01.9300.

the dats formis received by the RSO. The dosimeter must be worn whenever the x-ray machine is operat-Wntten operating procedures covering both normal ing and must be kept in an unexposed location at all and abnormal (emergency) conditions shall be avail-other times.

i able to, and followed by, all users of analytical x-ray equipment. The operating procedures sha!! include All dosimeters must be retumed promptly at the end detailed instructions for sample insertion and manipu-of the monitoring period.

lation, equipment alignment, routine maintenance by the user and recording of data related to radiation Users of enclosed x-ray equipment who are not safety.

specifically app.oved to perform maintenance pro-cedures with an exposed beam are classified as No person shall bypass a safety device without the minimally exposed and are not issued personal wntten authorization of the RSO. Individuals who dosimeters.

expect to perform maintenance thahrequires the presence of the primary beam when beam-blocking Experience has shown that accidental exposures from devices are removed must be authorized in advance enclosed (cabinet ) x-ray equipment have usually by the Radiation Safety Committee and must notify been to finger tips and were not accurately recorded the RSO that such work is expected.

even when dosimeters were worn. Furthermore, accidental exposures have often been so severe that biological effects appeared before the user dosimeter RADIATION SURVEYS was processed. Under such circumstances, dosime-ters contribute nothing to radiation protection or to The RSO will survey the radiation exposure rates in long-term exposure records.

accessible areas near an analytical x-ray machine at least once a year. The responsible user must re-Any suspected exposure to the primary beam of an quest, or perform and record, a radiation survey:

analytical x-ray machine must be reported promptly to the RSO.

)

1 following any change in the arrangement, num-ber or type of components, 2

following and maintenance requiring disassembly or removal of a component.

3 during any maintenance or alignment procedure that recuires the presence of a primary x-ray beam when a component is disassembled or removed, or I

l l

RPR 3o. ANALYTICAL X-RAY SAFETY (7/92)- 2 I

I

RPR 30A. ANALYTICAL X-RAY MACHINE SAFETY INSPECTION Responsible user Phone Location (Bldg. & Room) installation date Tvoe and use Manufacturer Model Serial No.

_ Open beam Control unit:

_ Fully enclosed X-ray tube (s):

_ Diffraction Number of ports available:

in use:

_ Fluorescence Target material kVp mA Accessory equipment (powder cameras, goniometers, etc.)

Inspection date -

FACILITY REQUIREMENTS

• CAUTION - X-RAY EQUIPMENT" (or equivalent) sign at entrance?

Yes No

" NOTICE TO EMPLOYEES" posted conspicuously?

Yes No Was the last radiation survey performed no more than 12 months ago?

Yes No Since the last radiation survey, have any of the following conditions occurred?

Removal or disassembly of anyNmponent that normally stops the primary beam?

Yes No Exposure of more than 1,000 mrem per quarter to any finger dosimeter?

Yes No EQUIPMENT REQUIREMENTS Safety Devices Required on open beam units - a device that prevents any portion of the body from entering the primary beam, or a device that terminates the beam if obstructed.

Yes No IF *NO*. has exemption beeri filed?

Yes No Signs and Labels

• CAUTION: HIGH INTENSITY X-RAY BEAM" - adjacent to housing?

Yes No

" CAUTION - RADIATION. THIS EQUIPMENT PRODUCES RADIATION WHEN ENERGlZED*

- near switch used to turn on unit?

Yes No

" CAUTION - RADIOACTIVE MATERIAL" - on housing, if appropriate.

Yes No Warning Lights or Devices - All Units "X-RAY ON* light - near any switch that energizes an x-ray tube.

Yes No Light must be illuminated only when the tube is energized.

Yes No if radioactive source - near any switch that opens a housing or shutter.

Yes No RPR 30. ANALYTICAL X-RAY SAFETY (7/92)- 3

I l

l On new equipment installed after December 1,1987 light shall be fail safe.

Yes No Additional Warning Devices Required for Open Beam Units X-RAY TUBE STATUS, *0N/OFF" -located near the radiation source housing, and at or near the port, if the primary baam is controlled in this manner.

Yes No Shutter Status *OPEN/ CLOSED * -located near each port on the radiation source housing, if the primary beam is controlled in this manner.

Yes No Control Panel interlock If an interlock device turns off the primary x-ray beam, it must not be possible to resume eteration without resetting the beam *0N* switch at the control panel.

Yes No Ports and Shutters Unused ports on radiation source housing shall be secured in the " closed

• position in a manner that will prevent casual opening, i.e. without the use of tools.

Yes No Beam Alignment Apparatus Any apparatus utilized in beam alignment procedures must be designed in such a way that excessive radiation will not strike the operator. Particular attention must be given to viewing devices, in order to ascertain that lenses and other transparent components attenuate the beam to an acceptable level.

Yes No OPERATING REQUIREMENTS Are wntten emergency procedures for radiation safety posted in a conspicuous location?

Yes No Do the emergency procedures contain the phone numbers of the responsible user and the the following actions to be taken in case of a known, or suspected, accident involving l

radiation exposure:

a) Notify responsible user and RSO (Technical Safety Office).

1 b) Arrange for medical examination. Additionally, the examining physician must be notified that exposure to low energy x-rays may have occurred.

Yes No Safety devices should be tested at least once per week, and must be tested at intervals not to exceed one (1) month. Have appropnate tests been performed and properly documented?

Yes No Are written operating procedures available to all users of x-ray equipment?

Yes No Has written approval been granted by the Radiation Safety Committee or the RSO for operation of the unit in a manner other than specified in the written procedure or for bypassing safety devices?

Yes No 1

l l

RPR 30. ANALYTICAL X-RAY SAFETY (7/92)- 4

PERSONNEL REoVIREMENTS Have all persons operating x-ray equipment received instruction and demonstrated adequate knowledge of:

radiation hazards associated with use of equipment:

Yes No significance of radiation warning and safety devices; Yes No operating and safety procedures; Yes No symptoms of acute localized exposure; Yes No procedure for reporting actual or suspected exposure; Yes No minimizing exposure (ALARA); and Yes No proper wearing of personnel monitoring devics, if applicable?

Yes No Personnel Monitoring Have personal monitoring devices (ring badges) been issued?

Yes No if "Yes", are they used in compliance with University requirements?

Yes No RADIATION SURVEY DATA Radiation survey meter (s) available et facility:

Make/Model:

Ser. No.:

Calibration Date:

Make/Model:

Ser. No.:

Calibration Date:

Radiation survey meter (s) used for thls survey, if different:

Make/Model:

Ser. No.:

Calibration Date:

Make/Model:

Ser. No.:

Calibration Date:

Survey results:

With machine operating at usual maximum Kvp and mA:

Maximum exposure rate within 5 cm from tube housing:

mR/hr is the dose rate less than 2.5 mrem /hr?

Yes No Maximum exposure rate within 5 cm from protective cabinet:

mR/hr is the dose rate less than 0.25 mrem /hr?

Yes No Maximum exposure rate at operator's position:

mR/hr Surveyed By:

Upon completion, send this inspection report to:

Technical Safety Office, Box 8106.

RPR 3o. ANALYTICAL X-RAY SAFETY (7/921 - 5

7 PARTICLE ACCELERATORS l

PURPOSE "Open beam" means any mode of operation in which any portion of the user's body could be placed into

{

This procedure specifies requirements for particle the primary beam.during normal operation if no 1

accelerators used in tesearch and education. Require-further safety devices or procedure were incorporat-ments include registration, physical safety features, ed.

training and operational requirements for users, and regular safety inspections. Accelerators used for the A " radiation user" is any individual whose official treatment of patients are excluded.

duties or authorized activities include handling, opera-ting, or working in the presence of, any type of radiation source, whether or not such use is confined POLICY to a restricted area.

All operable accelerators used in Idaho State Univer-A "normally exposed" radiation user is an individual sity facilities must be authorized by the Radiation who could receive more than one tenth (10%) of the i

Safety Committee and must be registered with the occupational radiation dose limit in any calendar l

Idaho Radiation Control Agency (Idaho Department quarter. This category includes individuals who l

of Health and Welfare). All authorizations and normally receive more than 100 mrem per quarter, registrations shall be submitted to the Radiation as well as some who rarely receive more than 100 Safety Officer (RSO) for review and processing. The mrem in a quarter, but who work with sources that RSO must also be notified before moving, transferring could produce a significant dose accidentally.

or disposing of any particle accelerator.

l A " minimally exposed" radiation user is an individual l

The responsible user for each accelerator shall assure who is unlikely to receive one tenth (10%) of the that detailed operating procedures are available and occupational radiation dose limit in any calendar that each operator has received appropriate training quarter.This category includes individuals who l

l and understands and follows the correct procedures.

routinely handle only small quantities of radioactive

~

materials, and others exposed only intermittently, e.g.

dental hygienists, emergency and security personnel, DEFINITIONS maintenance, receiving, custodial and housekeeping personnel.

[

" Accelerator" refers to machines or systems used to produce charged particles with energies up to 2 Mev for purposes of research and education. Accel-REFERENCE l

erators used for treatment of patients are excluded.

" Radiation Safety Requirements for Particle Accelera-

" Beam-dump" means any part of an accelerator or tor Operations",lDAPA 16.01.9350,ldaho Radiation accessory that may be struck by the particle beam, Contro/ Regulations, Idaho Department of Health and such as radiation source housings, ports and shutter Welfare. Each responsible user should obtain a copy assemblies, collimators, sample holders, detectors of IDAPA 16.01,9350, from the RSO and be f amiliar and shielding.

with its contents. " Radiation Protection Design Guidelines For 0.1 - 100 MeV Particle Accelerator

" Exposed beam" means the operation of an accelera-Facilities", NCRP Report No. 51 and " Radiation tor with any beam-blocking device removed while the Alarms and Access Control Systems *, NCRP Report particle beam is on.

No.88.

" Fail safe characteristic" means a design feature which causes beam port shutters to close, or other-EQUIPMENT REQUIREMENTS wise prevents emergence of the primary beam, upon the failure of a safety or warning device.

The requirements specified in regulation IDAPA 16.01.9350 apply to the University's equipment.

l RPR 32.. PARTICLE ACCELERATOR SAFETY (7/92)- 1

}

l

The important requirements are itemized in " PARTI-EXPOSURE MONITORING CLE ACCELERATOR SAFETY INSPECTION" (RPR 32A). This record is to be completed by the respon-Users of accelerators are classified as normally sible user at the time the machine is first registered exposed. Each normally exposed radiation user of and submitted to the RSO. The inspection form is accelerators must complete the

• RADIATION USER also to be used as a safety check list after any PERSONAL DATA" form (RPR 1 A). A body dosimeter ma..n1ance or modification that requires disassem-will be issued shortly after the data form is received bly.

by the RSO. The dosimeter must be worn whenever the accelerator is operating and must be kept in an OPERATING REQUIREMENTS unexposed location at all other times.

[

Each person who will operate or maintain an acceler-All dosimeters must be returned promptly at the end I

ator shall first receive appropriate instruction and of the monitoring period.

demonstrate competence on all topics specified in j

IDAPA 16.01.9350.

Any suspected exposure to the primary beam of an accelerator must be reported promptly to the RSO.

Written operating procedures covering both normal and abnormal (emergency) conditions shall be avail-able to, and followed by, all users of the particle accelerators.

No person shall bypass a safety device without the written authorization of the RSO. Individuals who expect to perform maintenance that requires the presence of the primary beam when beam-blocking devices are removed must be authorized in advance by the Radiation Safety Committee and must notify the RSO that such work is expected. '

RADIATION SURVEYS l

The RSO will survey the radiation exposure rates in l

accessible areas near an accelerator at least once a l

year. The responsible user must request, or perform and record, a radiation survey:

1 following any change in the arrangement, num-l ber or type of components, 2

following any maintenance requiring disassembly or removal of a component, 3

during any maintenance or alignment procedure that requires the presence of a primary x-ray beam when a component is disassembled or removed, or 4

any time a visualinspection reveals an abnormal I

condition.

RPR 32. PARTICLE ACCELERATOR SAFETY (7/92) 2

i l

i RPR 32A. PARTICLE ACCELERATOR SAFETY INSPECTION Responsible user Phone Location (Bldg. & Room)

Installation date r

Tvoe and use Manufacturer Model Serial No, j

_ Open beam Control unit:

)

_ Enclosed beam inspection date i

FACILITY REQUIREMENTS

" CAUTION -X-RAY EQUIPMENT" (or equivalent) sign at entrance?

Yes No t

" NOTICE TO WORKERS" posted conspicuously?

Yes No j

" CAUTION HIGH RADIATION AREA" posted?

Yes No t

All radiation areas are conspicuously posted " CAUTION RADIATION AREA"?

Yes No i

l CONTROL AND INTERLOCK SYSTEMS Instrumentation, readouts and controls on the particle accelerator control console are clearly

~

I identified and easily discernible.

Yes' No

]

Are all target areas and other High Radiation Areas interlocked?

Yes No

{

When an interlock is tripped it is only possible to resume operation of the accelerator by manually resetting controls at the position where the interlock has been tripped, and l

l then at the main control console.

Yes No Each safety interlock is on a circuit which will allow its operation independently of all other safety interlocks?

Yes No All safety interlocks are designed so that any defect or component failure in the interlock system prevents operation of the accelerator?

Yes No Scram or Emergency stop button located and easily identifiable in all high radiation areas; button must include a manual reset so that the accelerator cannot be restarted from the I

accelerator control console without resetting the cutoff switch.

Yes No WARNING DEVICES Rotating or flashing warning light at entrances to high radiation areas?

Yes ' No Warning light is only operational when radiation is being produced?

Yes No Audible indication of system activation?

Yes No 15 sec prep cycle?

Yes No RPR 32. PARTICLE ACCELERATOR SAFETY (7/92) + 3

OPERATING PROCEDURES System secured from unauthorized use?

Yes No Copy of current operating and emergency procedures at the accelerator control panel?

Yes No Warning and safety devices are tested:

at least once every 3 months when in use?

Yes No upon start up?

Yes No Circuit diagrams available?

Yes No Switch on the accelerator control console used to routinely turn the accelerator beam on and off?

Yes No is safety interlock system being used to routinely turn the accelerator beam off?

Yes No VENTILATION CONTROL Where applicable is ventilation system adequate to ensure personnel are not exposed to air-borne radioactivity levels in excess of the limits specified in Idaho Department of Health and Welfare Rules and Regulations section 01.9110,03?

Yes No RADIATION SURVEYS / MONITORING REQUIREMENTS Appropriate portable monitoring equipment available at facility?

Yes No Equipment tested for proper operatidh daily?

Yes No Annual survey instrument calibration?

Yes No is continuous monitoring of radiation levels in all high radiation areas being performed?

Yes No Are the monitoring devices electrically independent of the accelerator control and interlock systems and capable of providing local readout at both the control panel and at entrances to high radiation areas?

Yes No Was the last radiation survey / facility evaluation performed no more than 12 months ago?

Yes No Are area surveys conducted in accordance with the written procedures established by the Radiation Safety Officer or a qualified expert?

Yes No Since the last radiation survey, have any of the following conditions occurred?

Yes No Removal or disassembly of any component that normally stops the primary beam?

Yes No Exposure of more than 1,000 mrem per quarter to any finger do'simeter?

Yes No When applicable, have periodic smear surveys been made to determine the degree of contamination in target and other pertinent areas?

Yes No Are records of all radiation protection surveys, calibration results, instrumentation tests, and smear results on file and available for review?

Yes No Shieldino and Safety Desian Reauirements RPR 32. PARTICLE ACCELERATOR SAFETY (7/92)- 4

i RSO or person designated by RSO consulted in the design of the particle accelerator installation and utilized to perform a radiation survey when the accelerator is first capable of producing radiation?

Yes No Installation provided with such primary and/or secondary barriers as are necessary to assure compliancs with Idaho Department of Health and Welfare Rules and Regulations sections l

01.9110,01.and 01.9110.05.

Yes No EQUIPMENT REQUIREMENTS Signs and Labels

" CAUTION: HIGH INTENSITY X-RAY BEAM" - on source housing?

Yes No l

" CAUTION - RADIATION. THIS EQUIPMENT PRODUCES RADIATION WHEN ENERGlZED"

- near switch used to turn on unit?

Yes No Warning Lights or Devices - All Units l

" BEAM - ON" light - near any switch that energizes the system Yes No l

On new equipment installed after December 1,1987 light shall be fail safe Yes two i

OPERATING REQUIREMENTS Are written operating procedures available to all users of x-ray equipment?

Yes No Has wntten approval been granted by the Radiation Safety Committee or the RSO i

for operation of the unit in a manner other than specified in the written procedure or for bypassing safety devices?

Yes No PERSONNEL REQUIREMENTS Have all persons operating x-ray equipment received instruction and demonstrated adequate knowledge of:

radiation hazards associated with use of equipment:

Yes No significance of radiation warning and safety devices:

Yes No i

operating, safety, and emergency procedures:

Yes No symptoms of acute localized exposure; Yes No procedure for reporting actual or suspected exposure; and Yes No use of related equipment including survey instruments?

Yes No Personnel Monitoring Have personal monitoring devices (ring badges) been issued?

Yes No i

If "Yes", are they used in compliance with University requirements?

Yes No RPR 32. PARTICLE ACCELERATOR SAFETY (7/92)- 5 l

r-m i

RADIATION SURVEY DATA Radiation survey meter (s) available at facility:

Make/Model:

Ser. No.:

Calibration Date:

Make/Model:

Ser. No.:

Calibration Date:

Radiation survey meter (s) used for this survey,if different:

Make/Model:

Ser. No.:

Calibration Date:

Make/Model:

Ser. No.:

Calibration Date:

Survey results:

1 With machine operating at usual kVp and mA:

1 Maximum exoosure rate within 30 cm from shield walls:

mR/hr is the dose rate less than 2.5 mrem /hr?

Yes No i

Maximum exposure rate at operator's position:

mR/hr is the dose rate less than 2.5 mrem /hr?

Yes No i

Surveyed By:

Upon completion, send this inspection report to:

l Technical Safety Office Box 8106.

I RPR 32. PARTICLE ACCELERATOR SAFETY (7/92) - 6 i

i

1

/

e l

RADIATION SAFETY TRAINING PURPOSE TRAINING CONTENT This procedure prescribes the training in radiation protection required for all individuals who may be All minimally exposed personnel must be instructed l

exposed to ionizing radiation in the course of their en specific conditions that could involve exposure, official duties. The content and frequency of training and proper procedures for avoiding unnecessary i

sessiens are specified for each category of radiation exposure. Such instruction must include:

l user.

• The nature and risks of exposure to ionizing radiation.

Recognition and meaning of radiation warning POLICY signs.

Precautions for avoiding unnecessary radiation Regulations governing the possession and use of

exposure, i

radioactive materials and other radiation sources

• Who to call for information or assistance on require that every individual working with or in the radiation exposure situations.

I presence of such sources be instructed in the applica-Responsibilities and rights of individual employ-ble provisions of regulations and license conditions, ees.

in the potential health problems associated with exposure to radiation, in the precautions and proce-All normally exposed radiation users must receive dures required for safe use of radiation, and in the instruction on the following topics:

i proper use of protective and measurement devices.

The extent of the training is to be commensurate Characteristics of radiation sources.

I with the potential risk of radiation exposure to the Interaction of radiation with matter.

individual.

Radiation detection and measurement.

1 Biological effects and risk estimates.

The primary responsibility for providing adequate Risks to the embryo / fetus and control of prenatal training for individuals who work routinely with exposure.

radiation sources rests with their responsible users.

AL. ARA principle; optimizing radiation protection.

For individuals who are only occasionally exposed to Proper use of protective devices, radiation, e.g. most dental hygienists, housekeeping, Provisions of regulations and licenses.

maintenance, and security personnel, the respon-Response to radiation emergencies.

sibility for training lies with their supervisors. Gener.

Responsibilities and rights of individual radiation ally, the responsible user or supervisor will fulfill this

users, responsibility by assuring that each person attends

• Availability of monitoring and inspection reports.

the appropriate training program offered by the University policy / procedures on radioactive Radiation Safety Officer (RSO). The supervisor or material purchases, responsible user may also provide the training and Individual dose limits to include dose limits to the submit a statement to the RSO listing the individuals embryo / fetus and concept of " declared" pregnant trained and the content of the training, woman.

The RSO is responsible for developing, conducting Users of x-ray machines (Radiographic Science and documenting training on radiation protection Students), will receive training from Radiographic applicable to all categories of radiation users. For Science instructors. Contents of training (lesson each category of users, the RSO shall establish an plans), exam results, and attendance records will be appropriate schedule or frequency and the minimal maintained by the TSO. In addition to the training requirements for content of the program. The RSO outlined for normally exposed radiation users, Radio-shall maintain appropriate records of training offered graphic Science students must also receive instruc-and completed to assure compliance with regulatory tion on:

requirements.

l l

Effects of machine attributes and usage on Instruction Conceming Risks from Occupational e

patient dose.

Radiation Exposure, Regulatory Guide 8.29, July Source and intensity of scattered radiation.

1981.

Proper use of gonadal shielding.

Placement of dosimeters for monitoring partial-Instruction Concerning PrenatalRadiation Exposure, body exposures.

Regulatory Guide 8.13, Rev.1, Nov.1975.

Proper use of special shielding devices.

Idaho Department of Health and Welfare. Idaho Users of analytical x-ray mechines and particle Department ofHealth and Welfare, Rules andRegula-accelerators, in addition to the training outlined for tions, Idaho Radiation Control Regulations title 1 normally exposed radiation users, must receive Chapter 9.

instruction on proper use of shutters, interlocks and l

other safety devices, and on the requirement for a safety survey following any modification or repair.

5 Users of soil densomiters, in addition to the training outlined for normally exposed radiation users, must ATTACHMENTS receive instruction on soil densomiter transport requirements and theory of operation.

1

• RADIOISOTOPE USERS TRAINING OUTLINE" is for all radioisotope users; separate handout materi-l Radioisotope users, will receive training as prescribe als are identified in the outline.

{

i in the

• RADIOISOTOPE USERS TRAINING OUTLINE *

(attachment 1 to this RPR).

2

" BASICS OF RADIATION SAFETY

• is a handout for groups of minimally-exposed personnelthat don't TRAINING FREQUENCY AND RECORDS need the entire Radiation Safety Policy Manual.

l Normally exposed radiation users are required to 3

• RADIATION SAFETY FOR EMERGENCY receive training priorto beginning work with radiation RESPONSE PERSONNEL" is a handout for fire fight-i sources. Training received at another institution may ers, police and security officers, and emergency j

be acceptable if it fulfills current requirements. The medical teams.

l RSO establishes procedures for verifying and accept-j ing training received elsewhere. The documentation 4

• RADIATION SAFETY FOR MINIMALLY EX-of training is retained in the permanent radiation user POSED PERSONNEL" is a handout for minimally-file for the individual.

exposed personnel.

Minimally exposed radiation users and others who 5

• RADIATION SAFETY FOR RECEIVING PERSON-may occasionally encounter radiaten sources, are NEL" is a handout for personnel in receiving.

offered radiation safety training periodically based on group needs. Training records for these personnel 6

• RADIATION SAFETY TRAINING ATTENDANCE are retained in the form of attendance sheets listing RECORD

• is for recording group training.

l the name of the group, the date, the instructor, any handout materials used and the attendees.

REFERENCES l

l National Council on Radiation Protection and Mea-surements, Operational Radiation Safety - Training.

NCRP Report No. 71,1983.

U.S. Nuclear Regulatory Commission:

Notices, Instructions, and Reports to Workers; Inspections,10 CFR 19.

RPR 44. TRAINING (9/92) 2

_, - _ _~

l t

l RADIOISOTOPE USERS TRAINING OUTLINE l

l l

Radiation users are encouraged to study the handout CONTROL OF RADIOACTIVE MATERIALS I

materials for this training, available from the RSO at (315-minute video presentations and 30-l l

any time.

minute lecture / demonstration)

Planning experimental procedures i

RADIATION SOURCES AND INTERACTIONS Preparation and use of fume hoods; bood air l

(Handout and 60-minute lecture) flow i

Basic dcfinitions; energy units Contamination control; secondary contain-f Interactions of charged particles (electrons) ment with matter Proper wearing of gloves, lab coats and moni-t Electron ranges and bremsstrahlung toring devices l

production Proper use of survey instruments; wipe tests

(

Interactions of photons with matter for contamination j

l Half-value layers for photons Opening and surveying packages; recording Radioactive decay modes and emissions changes to inventory l

1 Radioactivity units

• Response to radiation emergencies, e.g.

l l

l Radioactivity calculations: decay constant, spills, injuries, etc.

(

half-life

• - Units of radiation exposure and dose INDIVIDUAL EXPOSURE MONITORING Common sources of radiation exposure, natu-(30-minute lecture )

i I

ral and manmade Criteria for exemption from individual moni-tonng r

BIOLOGICAL EFFECTS AND RISK FACTORS Calculating potential external exposures (Handout and 25-minute lecture)

Bioassay intervals determined by All and Sources of information on radiation effects metabolism of nuclides and risks Bioassay measurements, screening and verifi-Non-stochastic (deterministic) effects of radi-cation ation Bioassay exemption based on absence of Stochastic effects of radiation contamination Somatic vs. genetic effects of radiation Confidentiality of dosimetry records and j

l Dose-response models; linear, non-threshold rights of individuals j

raodel i

ADMINISTRATIVE REQUIREMENTS PRINCIPLES OF RADIATION PROTECTION (30-minute lecture )

(Handout and 25-minute lecture)

Organization: radiation saf sty committee,

)

Justification of practices producing radiation RSO l

exposures Radiation Safety Manual and procedures Optimization of radiation protection (ALARA)

Responsible user definition and responsibili-Individual dose limits; annual limits based on ties lifetime risk; limits to embryo / fetus; concept of Procurement and security of radioactive ma-

• declared" pregnant woman terials Comparison of radiation risks with other com-Radioactive materialinventory and disposal mon risks records External radiation dose limits

• Waste segregation and labeling Annuallimits on intake (All)

EXAMINATION (multiple-choice; 40 minutes) i RPR 44. TRAINING (9/921 - 3 4

i BASICS OF RADIATION SAFETY 1

i r

RADIATION PROTECTION POLICIES RADIATION DOSES AND RISKS i

lonizing radiation is capable of producing biological Radiation doses are specified in units of millirems or i

effects that are detrimental to health. It is assumed sieverts (SI unit). One millisievert is equal to 100 that any radiation dose, no matter how sma!!, could millirems. The doses and related health risks pro-l produce some risk of an effect. The purpose of a duced by non-occupational radiation exposures may radiation safety program is to prevent unnecessary be helpful for understanding the risks from occupa-radiation exposures, and to control those that are tional doses. In the U.S., the annual average whole necessary.

body-body dose from cosmic rays and other natural l

l sources is 100 mrem, the effective dose from radon Each person who is exposed to radiation must be in homes is 200 mrem, medical examinations contrib-informed of the risks and of appropriate protection ute an average of 53 mrem and consumer products methods, and must accept persona! responsibility for and other manmade sources deliver another 9 mrem, using the available protection.

for a total of approximately 360 mrem per year.

i The risk of fatal cancer from all causes, averaged l

l RADIATION-INDUCED HEALTH EFFECTS over the entire U.S. population, is approximately 1 I

in 5, or 20% It is recognized, however, that certain l

l Health effects from exposure to ionizing radiation sub-groups, e.g. smokers or residents of large cities, may be stochastic (random in an exposed population) have cancer risks that are above average while other or non-stochastic (predictable for an individual).

groups have risks that are below the average. For most stochastic effects, a given dose of radiation is Non-stochastic effects may be observed in an ex-believed to increase the baseline risk for a population posed individual when a very large radiation dose, group by a constant fraction or proportiori.

l exceeding a threshold value, is received, usually in a rather short time. A dose smaller than the thresh-According to the most recent Academy of Sciences old value will not produce the effect. Once the thres-report, a continuous dose of 400 mrem per year to i

hold dose for a particular effect is exceeded, the the U.S. population can be estimated to contribute effect is almost sure to occur, but the severity of the 12% to the baseline risk of fatal cancer. The majority effect is proportional to the dose.

of radiation users receive occupational doses of much less than 400 mrem per year. An additional dose of f

Stochastic effects are those that occur randomly in 400 mrem per year for 20 years can be calculated an exposed population, usually after a long latent to increase the baseline risk by as much as 35 period. Since these effects cannot be distinguished from those that occur in an unexposed population, PRINCIPLES OF RADIATION PROTECTION the cause-and-effect relationship cannot be estab-lished on an individual basis, but only on a statistical Two basic principles apply to every individual that basis. For these effects it is assumed that there is may be exposed to radiation:

no threshold dose and that the probability of occurrence is proportionalto the dose. However, the 1

all radiation doses are to be kept as low as severity of the effect, if it occurs, is independent of reasonably achievable (ALARA), and the dose.

2 no dose to an individual shall be allowed to ex-ceed the appropriate individual dose limit.

1 1

RPR 44. TRAINING (9/92)- 4 m.

__~_. _._, _.

The ALARA principle is applicable even when the quarterly occupational dose limits based on Idaho potential dose is well below the individual dose limit State Regulations. These quarterly limits are:

because it is assumed that some risk is associated with any dose of radiation, no matter how small.

MILLIREM PER CALENDAR QUARTER ALARA also means balancing the benefits of dose reduction against social needs and economic consid.

1) Whole body; head and trunk; active blood-forming erations.

organs: lens of eyes:or goned.......................1250 Dose limits are intended to limit the individual's life-2)

Hands and forearms; feet and an-time risk of stochastic effects from small chronic kl e s.......................................................... 1 8 7 50 exposures as well as to prevent harmful non-stoch-astic effects from large doses.

3 ) S kin of wholo body.................................. 7 5 00 For individuals who are exposed to ionizing radiation The doso limits for minors (persons under 18 years as a direct result of their employment, individualdose of age) are 10% of the adult occupational dose limits.

limits are based on the philosophy that their total health risks should be no greater than the risks The dose limits for members of the general public, accepted by workers in comparable occupations or including all persons who are not classified as radia-industries who are not exposed to radiation.

tion users, is a total effective dose equivalent not to exceed 100 millirems per year. In addition the For anyone who does not receive a direct benefit, dose in any unrestricted area from external sources e.g. a salary or educational benefit, related to their cannot exceed 2 millirems in any one hour.

radiation exposure, the individual dose limits are much smaller than those for radiation users. These The embryo-fetus may be more susceptible to "non-occupational" limits are based on comparisons radiation effects than an adult and is, therefore, with the ordinary risks of living, rather than on risks subject to a lower dose limit. The dose limit for the due to employment.

embryo fetus is 500 millirems (5 mSv) during the entire gestation period. As a further precaution, it is advisable to keep the monthly doses below 50 INDIVIDUAL DOSE LIMITS millirems. This degree of protection for the embryo-fetus can only be achieved with the cooperation of

{

The primary annual adult (persons 18 yesrs of age the employee, who should notify her supervisor or i

or older) occupational dose limit is the more limiting the RSO as soon as the pregnancy is known.

of:

1) The total effective dose equivalent being equal to 5,000 millirems; or RADIATION USERS

2) The sum of the deep-dose equivalent and the A " radiation user" is any individual whose official committed dose equivalent to any individual organ duties or authorized activities include handling, opera-or tissue other than the lens of the eye being equal ting, or working in the presence of, any type of to 50,000 mi!!irems.

radiation source, whether or not such use is confined to a restricted area.

The annual limits to the lens of the eye, to the skin, and to the extremities are:

A "normally exposed" radiation user is an individual who could receive more than one tenth (10%) of the

1) An eye dose equivalent of 15,000 millirems, and occupational radiation dose limit in any calendar l

quarter. This category includes individuals who l

2) A shallow dose equivalent of 50,000 millirems to normally receive more than 100 mrem per quarter, i

the skin or to each of the extremities.

as well as some who rarely receive more than 100 l

mrem in a quarter, but who work with sources that in addition to the annual occupational dose limits, could produce a significant dose accidentally.

which are based on Federal Regulations, there are t

1 1

l l

RPR 44. TRAINING (9/92)- 5 I

A " minimally exposed" radiation useris an individual who is unlikely to receive one tenth (10%) of the occupational radiation dose limit in any calendar quarter.

This category includes individuals who routinely handle only small quantities of radioactive materials, and others exposed only intermittently, e.g. dental hygienists, emergency and security personnel, main-tenance, receiving, custodial and housekeeping personnel.

Any radiation user may communicate directly, in con-fidence and without prejudice, with the RSO or any member of the Technical Safety Office, the Idaho Department of Health and Welfare or the U.S. Nu-j i

clear Regulatory Commission on a y matter con-cerning radiation protection.

I l

RPR 44. TRAINING (9/92). 6

~ _.

l RADIATION SAFETY FOR EMERGENCY RESPONSE PERSONNEL-1 l

NATURE OF RADIATION SOURCES RADIATION DETECTION Radioisotopes used in many laboratories are easily Geiger-Mueller survey meters (" Geiger counter") are i

dispersed and may cause contamination of the skin very sensitive and excellent f or detecting contamina-l and may be taken into the body. The quantities tion. However, a Geiger counter may be swamped found in research laboratories are usually too small (saturated) by a high exposure rate and give a false to be of concern as an external radiation source, zero reading. To be safe, start reading the instru-during an emergency.

ment away from the source, then move nearer.

Sealed radionuclide sources are normally shielded and An ionization-chamber survey meter is not as sens-produce minimal risks. However, if the shielding is itive as a Geiger counter, but can measure the actual damaged or the source is otherwise exposed, high exposure rate, even at high intensities.

radiation intensities may be present. If the source capsule is ruptured, serious contamination is also EXPOSURE AND CONTAMINATION CONTROL j

possible.

Dose rates are reduced greatly by distance and l

X-ray machines produce radiation only when the shielding; don't linger near a source.

power switch is on; they do not produce radioactivity and there is no possibility of contamination.

Air contamination is not a concern unless fire or j

explosion occurs; avoid obvious smoke a,nd dust.

i DOSE RATES AND BIOLOGICAL. HARM Most personal contamination comes from direct l

contact; keep pedestrian and vehicular traffic out of For general use in emergency situations, the radiation area.

dose units of roentgen (R), rad and rem are inter-changeable. Dose rates are usually givenin milliroen.

Evacuation of the immediate area is justified in the i

toens (0.001 R) per hour (mR/hr).

event of fire or explosioninvolving a radiation source or radioisotope laboratory.

The dose rate depends upon the distance from the source and shielding.

Contamination should be detected and confined or removed as promptly as possible; keep potentially The dose received depends on the dose rate and the exposed persons in the aree until cleared by the i

total time of exposure, i.e.:

Radiation Safety Officer.

dose = dose rate x time.

{

i I

Detectable biological damage occurs only when a dose of more than 10 rem (10,000 millirem) is received in a short interval.

j RPR 44. TRAINING (9/92)- 7 i

l

.-._.,i

i RADIATION SAFETY FOR MINIMALLY EXPOSED l

PERSONNEL i

OBJECTIVES Contamination refers to any radioactive material that is not where it belongs, such as on the floor, on i

1 Know the difference between radiation exposure clothing or on the hands or body.

)

from contained sources, such as x-ray machines, and i

contamination with radioactive materials.

%DIATION AREAS I

2 Know the nature and risks of exposure to ioniz-The entrance to an area where an x-ray machine or ing radiation.

any other source of radiation can produce a signifi-i cant radiation exposure is labeled with a yellow and l

3 Know the restrictions on removing materials, magenta " CAUTION - RADIATION AREA

• sign. It including wastes, from radioisotope laboratories, is generally safe to enter such areas, but one should not stay in the area without good reason. Warning 4

Know what to do and who to call for help related lights on x-ray machines and other radiation sources i

to any radiation problem or emergency, are used to indicate that the unit is on.

i 5

Recognize radiation warning signs and their RADIOACTIVE MATERIAL AREAS meaning.

The entrance to an area where radioactive materials 6

Know the responsibilities and rights of individual are used is labeled with a yellow and magenta *CAU-

{

employees.

TION - RADIOACTIVE MATERIALS

• sign. You must

{

4 d

recognize these labels and follow the instructions for j

7 Know precautions for avoiding unnecessary such areas.

l radiation exposure.

i i

Containers of radioactive materials, including wastes, METHOD are identified with small yellow and magenta labels with the radiation symbol.

The training consists of a short oral presentation with ample opportunity for questions and answers. This Do not empty waste containers marked with radioac-outline and

• Basics of Radiation Safety" wil! be tive materiallabels. Do not remove empty boxes or l

provided as a handouts and the listed topics will be other containers with radioactive material labels

{

discussed in detail. Radiation warning signs and unless the label has been thoroughly obliterated, i.e.

labels will be displayed.

destroyed or covered.

i RADIATION AND RADIOACTIVITY RADIOACTIVE CONTAMINATION Radiation is energy transmitted through space.

Under normal conditions, contamination is not a Radiation may come from x-ray machines or from problem because radioisotopes are carefully con-radioactive material (radioisotopes). Radiation from tained. Small spills are to be cleaned up by the an x-ray machine stops when the machine is turned laboratory personnel who use the radioisotopes. Care off. Radiation from a radioactive material cannot be must be taken to avoid spreading the contamination.

1 turned off, but it can be confined.

Each person involved in the spill must be monitored carefully to assure that no one leaves the area with l

A material that emits radiation is radioactive. Radio-contamination.

j active material can be spi!!ed, lost, or dispersed, but if contamination is found on clothing or on the body, j

it cannot be destroyed.

It must be removed promptly using ordinary washing, and the Radiation Safety Officer should be notified.

j RPR 44. TRAINING (9/92). 8

,,.. ~, _ _ _-,-. -

RADIATION EMERGENCIES Get Holo!

Any accident, injury or loss of control of a radiation Each individual should know in advance who to call i

source that could cause an excessive or uncontrolled in case of a radiation emergency. If fire, injury or radiation exposure to any individualis referred to as other emergency conditions in addition to radiation a radiation emergency. The proper response to any are involved, first call the appropriate numbers listed radiation emergency depends upon a thorough on page I of the Campus Directory. Then call the understanding of the magnitude of risks, priorities for Radiation Safety Division of the Technical Safety action and the application of common sense.

Office: extension 2311 during normal office hours; extension 2514 or 2515 (Security) during off duty Protect Peoplel hours.

I The first consideration in any emergency is to assist When reporting any emergency, be sure to state the injured persons and to prevent any further injury. For exact nature of the emergency; then give your name medical assistance, dial 8-911 immediately and report and the phone number from which you are calling, the nature of the illness or injury. If the person may the exact location of the emergency (building, room, be contaminated with radioactive material, inform the nearest entrance, etc.) and the name of the Responsi-911 dispatcher of the situation. If you are qualified ble User,if known. Do not hana uol Let the person to render first aid, do so without regard to the pres-called end the conversation after all pertinent infor-ence of radioactivity. There are no radiation sources mation is clearly understood.

at the University that produce radiation exposure risks large enough to prevent giving first aid! Except Contain the Hazardt for the usual precautions for moving an injured 1

person, individuals should immediately leave the room Any of the following actions appropriate to the or area until the extent of the radiological hazard has situation should be performed orovided they can be been evaluated. However, all individuals should carried out safely:

l remain available in the vicinity until checked for contamination or exposure.

Turn off radiation producing machines.

]

Cover containers of radioactive materiais.

EMERGENCY TELEPHONE NUMBERS Place absorbent material on spilled liquids.

Fire, Ambulance or Medical Assistance:

Close the sash on fume hoods, but do not turn off hood exhaust fans.

8-911 and 236-2515 Close doors to the area and post signs or guards to prevent unauthorized entry.

Radiation Division of Technical Safety Office Allow no one toleave the area without being checked for contamination.

Normal business hours: 236-2311 Follow-un Action Other than normal Any necessary decontamination or repairs required business hours:

after a radiation emergency shall be performed only under the direction of the Radiation Safety Officer Security: 236-2514 or 2515 (RSO) Reentry or re-occupancy must be authorized by the RSO.

RPR 44. TRAINING (9/92) 9

RADIATION SAFETY FOR RECEIVING PERSONNEL OBJECTIVES the outside of the package. This kind of package contains a very small quantity of radioactivity.

1 Know the difference between radiation exposure from contained sources, such sealed packages, and

" WHITE I" identifies a package that gives no external contamination with radioactive materials from leaking radiation exposure.

packages..

• YELLOW 11" identifies a package that produces a 2

Recognize radiation labels on packages and their very low external exposure.

meaning.

" YELLOW lil" identifies a package that produces an 3

Know the restrictions on transporting packages external exposure for which the total exposure time with " YELLOW 111" labels.

at a distance of less than 5 feet should be limited.

Packages with " YELLOW lil" labels must be trans-4 Know what to do and who to call f or help related ported in a vehicle with " RADIOACTIVE MATERIAL" to any radiation problem or emergency.

placards on all 4 sides. This is done by the Technical Safety Office.

5 Know that all shipments of radioactive material are conducted via the Technical Safety Office.

RADIOACTIVE CONTAMINATION METHOD Under normal conditions, contamination of packages is not a problem because radioisotopes are tightly The training consists of a short oralpresentation with contained. If any damage orleakage of a radioactive ample opportunity for questions and answers. This material package is discovered, notify the Radiation outline will be provided as a handout and the listed Safety Officer at once. In case ofleakage, care must topics will be discussed in detail. Radioactive pack-be taken to avoid spreading the contamination. Each age labels will be displayed.

person who may have been contaminated must be monitored carefully to assure that no one leaves the RADIATION AND RADIOACTIVITY area with contamination.

If contamination is found on clothing or on the body, Radiation is energy transmitted through space.

it must be removed promptly using ordinary washing, Radiation may come from x-ray machines or from and the Radiation Safety Officer should be notified.

radioactive material (radioisotopes). Radiation from an x-ray machine stops when the machine is turned RADIATION EMERGENCIES cff. Radiation from a radioactive material cannot be turned off, but it can be confined.

Any accident, injury or loss of control of a radiation source that could cause an excessive or uncontrolled A material that emits radiation is radioactive. Radio-radiation exposure to any individualis referred to as active material can be spilled, lost, or dispersed, but a radiation emergency. The proper response to any it cannot be destroyed.

radiation emergency depends upon a thorough understanding of the magnitude of risks, priorities for Contamination refers to any radioactive material that action and the application of common sense.

is not where it belongs, such as on the floor, on clothing or on the hands or body.

Protect Peoolel RADIOACTIVE PACKAGE LABELS The first consideration in any emergency is to assist injured persons and to prevent any further injury. If

" LIMITED QUANTITY" does not have a radiation the situation involves a radiation producing machine, symbol and is not required to say

• radioactive" on the machine should be turned off to prevent unneces-RPR 44. TRAINING (S/92)- 10

4 sary exposure to the injured individual or to individu-Office: extension 2311 during normal office hours; als providing assistance. For medical assistance, dial extension 2514 or 2515 (Security) during off duty 8-911 immediately and report the nature of the illness hours.

or injury. Inform the 911 dispatcher that the injured individual may be contaminated with radioactive When reporting any emergency, be sure to state the material, if you are qualified to render first aid, do so exact nature of the emergency; then give your name without regard to the presence of radioactivity.

and the phone number from which you are calling, I

There are no radioactive sources at the University the exact location of the emergency (building, room, that produce radiation exposure risks large enough nearest entrance, etc.) and the name of the Respon-to prevent giving first aid! Notify University Securi-sible User,if known. Do not hana upl Let ths other ty, at 236-2514 or 2515 of the situation. Security person end the conversation after all pertinent infor-will provide assistance and will aid in directing mation is clearly understood, emergency response personnel to the scene. Except for the usual precautions for moving an injured Contain the Hazardi person, individuals should immediately leave the room or area untilthe extent of the radiological hazard has Any of the following actions appropriate to the been evaluated. However, all individuals should situation should be performed orovided they can be remain available in the vicinity until checked for carried out safely:

contamination or exposure.

Turn off radiation producing machines.

Cover contairers of radioactive materials.

EMERGENCY TELEPHONE NUMBERS Place absorbent material on spilled liquids.

Fire, Ambulance or Medical Assistance:

Close the sash on fume hoods, but do not : urn off hood exhaust fans.

8-911 and 236-2515 Close doors to the area and post signs or guards to Radiation Safety Division of prevent unauthorized entry.

Technical Safety Office Allow no one to leave the area without being checked Normal business for contamination.

I hours: 236-2311 i

Follow-up Actior]

Other than normal business hours:

Any nncessary decontamination or repairs required after a radiation emergency shall be performed only Security: 236 2514 or 2515 under the direction of the Radiation Safety Officer (RSO). Reentry or re-occupancy must be authorized by the RSO.

Get Holo!

Each individual should know in advance who to call in case of a radiation emergency. If fire, injury or other emergency conditions in addition to radiation are involved, first call the appropriate numbers listed on page I of the Campus Directory. Then call the Radiation Safety Division of the Technical Safety RPR 44. TRAINING (9/92)- 11

i i

RADIATION SAFETY TRAINING ATTENDANCE RECORD Group:

Date:

I l

Scope:

Instructor:

i l

Handout:

On this date, the undersigned attended radiation safety training, received the listed handout material and were i

given an opportunity to ask questions pertaining to radiation risks and protection, l

l l

PRINT N AME LEGIBLY DEPARTMENT OR ORGANIZATION l

RPR 44. TRAINING (9/92)- 12

l l

RADIOISOTOPE LABORATORY EVALUATIONS i

PURPOSE If no work with radioisotopes is being done, and all radioisotopes are stored in a locked location conspic-This procedure provides instructions to Technical uously labeled with a sign that requires notification j

Safety Office personnel for performing radiological of the RSO prior to any further use of radioisotopes.

evaluations of radioisotope laboratories. It also con-the laboratory may be considered to be inactive and tains instructions and forms for recording and report-need be evaluated only annually, ing the results of such evaluations.

r The nominal evaluation frequencies given in the box POLICY are to be interpreted as guidelines, in cases where i

continuing contamination problems are found, the in-The RSO shall ensure that allareas where radioactive terval between evaluations will be shortened. If materials are stored or handled are inspected at evaluation results obtained over a period of a year

[

appropriate intervals to ascertain the radiological risks indicate no contamination or exposure problems, the f

and to evaluate the control mersures in use. Radia-routine evaluation interval may be increased. In no i

tion evaluations shall be perf ormed, when necessary, case, however, will the interval be more than double by Technical Safety Office personnel using in-the nominalinterval. To assure a realistic and inde-struments appropriate to the nature of the radioactive pendent evaluation of typical conditions, the schedule materials to be detected or radiation exposures to be for evaluations may be varied randomly.

measured.

i For radioisotope laboratories, i.e. those where dis-t t

l persible radioisotopes are used, the frequency of rou-l tine evaluations are based on the "inte?valinventory.

DEFINITIONS The " interval inventory" is the total quantity of i

radioisotopes in a laboratory each month, averaged

%sssey Interval: The maximum time that may l

l over the most restrictive bioassay interval, expressed elapse between bioassays that will assure detection in Alls. The routine survey frequencies for varicas of the verification level for a given assay method.

i average monthly inventories are shown in the box.

See

• BIOASSAYS FOR INTERNAL RAOlOISOTOPES" (RPR 12).

l TSO ROUTINE RADIOlSOTOPE LABORATORY EVALUATIONS Interval Inventorv' Nominal Freauency

> 30 ALis Monthly 1-30 ALis Each bioassay interval 1

< 1 All Semi-annually 1

Inactive *

• Annually Monthty everage dunng enterval.

see text.

RPR 60. l.A8 EvALuATroNS f7/e2)- 1 1

-. - - - - ~ -

- ~ -----~ I

Radioisotope Laboratory (Lab): Any room or area in specific authorizations and procedures for access and which 10 or more Reference Quantities of unsealed are designated as restricted areas.

radioactive materials are stored or used. Since the only laboratories referred to in this procedure are Radiation Area: Any accessible area in which an radioisotope laboraturies, they are referred to simply individual could receive a dose equivalent exceeding as " labs".

5 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm (1 ft) from the source or from any surface the radiation penetrates.

Reference Quantity: A quantity of any radioisotope related to its relative hazard potential and used to Hioh Radiation Area: Any accessible area in which prescribe requirements for hanelling, monitoring, an individual could receive a dose equivalent exceed-labeling and disposal. See *RADIONUCLIDE CATE-ing 100 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm (1 ft) from the GORIES AND DATA" tren icA>.

source or from any surface the radiation penetrates.

Interval Inventory: The total quantity of radioisotopes Airborne Redioactivity Area: Any room or enclosure in the laboratory each month, averaged overthe most in which airborne radioactive material exists in restrictive bioassay interval, expressed in Alls. See concentrations exceeding the derived air concentra-attachment "lNTERVALINVENTO RY WORK-SH EET" tions (DACs) or in which any individual could be ex-(RPR 50C).

posed to more than 0.5% of the Allin one calendar week.

To determine the interval inventory first obtain the j

quantity (in mCil of each radioisotope in the laborato-PRE-START EVALUATIONS ry. Next obtain the ALI for each radioisotope from RPR 10A. Convert mci amounts to ALis by dividing Before radioactive materials are introduced into a each quantity by its corresponding All. Next sum laboratory, a general evaluation is made by the RSO the results to obtain the total ALis on hand in the to ascertain that equipment, instruments and supplies j

laboratory. From RPR12 determine the most restric-necessary for controlling contamination and expo-j tive bioassay interval (in months) for the radioiso-sures are present or will be available when work with topes used in the laboratory. Divide'the total All radioisotopes begins. A floor plan map should be value by the most restrictive bioassay interval to prepared during the pre-start evaluation. This map determine the interval inventory in Alls, should be approximately to scale and should identify the locations of major radioisotope storage and work intervalinventories are calculated by TSO personnel areas, waste storage locations, hoods, sinks, etc.

when radioisotopes are recieved.

The authorized quantities and frequencies of radioiso-tope orders chould be reviewed and verified with the Controiled Area: Any area to which access is limited user.

Calculate the expected average monthly for any reason. Radioisotcpe laboratories are con-inventory, in Alls, and review with the user the trolled by posting and locking for the purpose of significance ot the inventory to the routine evaluation preventing unauthorized removal of radioactive mater-and bioassay requirements. If animals are to be used, ials. Exposure to radioactive materials is prevented review " HOUSING AND HANDLING OF RADIOAC-by controlling the materials, not by limiting normal TIVE ANIMALS" tRen tsi with the user, access to the laboratory when it is open and attend-l ed.

Procedures for handling and storing radioisotopes, for surveying ahd monitoring, for waste disposal and Restricted Area: Any area to which access is limited for record keeping should be discussed with the for the purpose of protecting individuals against responsible user. If an analytical instrument is to be undue risks from exposure to radiation and/or radio-used for counting urine samples or contamination active material. The mere presence of any radiation wipe tests, review with the user the counting source, if adequately controlled to limit potential efficiency for each sample type and for each antici-exposures, does not necessitate a restricted area pated isotope. Review with the user appropriate designation. Areas containing sources with the sample sizes and counting times for urine samples, potential for producing significant exposures require and the results that would require verification.

RPR 60. LAB EVALUATIONS (7/92t - 2 l

1

2

-e a.

---

,f i

f d

Prior to the start of work with radioisotopes in the 4

At locations with positive indications of exposure laboratory, waste containers are to be available and or contamination, first ascertain' whether the j

the necessary signs and iabels are to be posted. The reading could be penetrating radiation coming i

• LABORATORY EVALUATION CHECK LIST

• inPasoAi 3irough the surface, rather than from contamina-is used as a guideline for items to be evaluated and tion on the surface. If significant penetrating j

is retained in the RSO's files.

radiatian is detected, i.e. more than 0.2 mrem /hr (approximately 10 times background), an expo-ROUTINE EVALUATIONS sure rate measurement should be made, usually 4

at 30 cm (1 ft) from the surface. Record the i

Preparation results and post the area, if necessary.

l t

1 Review the emissions, energies and Alls of the 5

At locations with a positive indication of contam-isotopes used. Determine the removable con-ination, or surfaces that are not accessible for j

tamination limit (s) that apply to the isotopes a direct measurement, take a wipe with an ab-l

used, sorbent material, e.g. filter paper. If possible, wipe 300 cm';if not, wipe 100 cm'or the entire 2

Review the user's current radioisotope inven-surface. (A 300 cm' area is any equivalent of tory. Which isotopes are significant for con-a 7-inch square or a strip 2 cm wide and 1.5 l

tamination or exposure potential? What is the meter long; a 100 cm' area is any equivalent of interval inventory?

a 4-inch square or a strip 1 cm wido and 1 meter i

long.)

[

3 Review the previous survey results. Were there any problems? Were there recommendations 6

With the survey meter in a low-background e

that should be followed up on this time?

location, make a deect measurement of the i

contamination on the Filtr.r paper. Record these Exposure and Contamination Surveys results and converr Cem to multiples of the removable contamination limit (RCL).

1 Record the make, model and serial numbers of l

survey meters used for the survey on the " CON-7 If detected contamination could be from low-

[

TAMINATION SURVEY - PORTABLE INSTRU-ene gy beta emitters, e.g. C-14, S-35, etc., the

{

MENT

• form <am ti Ai.

Indicate the calibration wipes should be kept and counted in a liquid date and the appropriate detection efficiencies scintillation counter..The results should be i

for the entical isotopes.

recorded on

• CONTAMINATION SURVEY-WIPE l

TESTS

• mm itsi.

2 If the lab uses only tritium, the entire contam-(

ination survey must be done by wipe testing.

8 ff contamination is detected W the isotope is The results are to be recorded on the " CON-not known, the procedure in the following sec-j TAMIN ATION SURVEY - WIPE TESTS" form iara tion may be used to categorize the contaminant i

s i si.

for further analysis.

l 3

Unless the lab uses only tritium, the first priority Contaminant Evaluation should be a direct survey for contamination. For by Direct Measurement j

1-125, a thin-crystal scintillation detector is best.

Otherwise, use a thin-window G-M survey meter 1

Make a measurement of the contaminated j

4 l

with audible indicator. Move the detector slowly surface or of a wipe with the thin-window G-M j

over all surfaces that might be contaminated, survey meter.

holding the detector 1-2 cm from the surface.

if positive tabove background) responses are 2

Make a second measurement after placing a j

detected, stop and record the actual count rate.

sheet of paper over the contamination while Reference the recorded results to specific ob-keeping the meter in the same position relative jects or locations.

to the contamination. If the second resultisless than 1 % of the first, the most likely contami-RPR 60. LAB EvALuAT!oNS (7/92) - 3 i

j

~.

u nant is an alpha emitter. Use either the gas-vapors or dusts in fume hoods.The sash of the fume flow, internal proportional counter or a liquid hood is intended to serve as a shield to protect the scintillation counter to make a quantitative mea-f ace from spatters, as well as to control air flow. To l

surement.

provide the proper protection, the hood must be free

{

of major obstructions to the flow of air and the sash l

3 If the second resultis reduced to about 15% of should be set at the optimal height.The average f ace the first, the contamination is most likely a low-velocity should in the range of 80 to 150 fpm. If the energy beta emitter, e.g. C 14, S-35, or C-45.

desired hood velocity cannot be maintained the user Use a liquid scintillation counter to make a must make a::a gements for repairs or modifications.

quantitative measurement.

The fume hood should be visually inspected during each routine audit to assure that it is functioning and 4

If the second result is more than 50% of the being used properly.

I first., the contamination could be a high-energy beta and/or gamma emitter. Make a third mea-Contamination Control l

surement with a 1-mm thick piece of aluminum over the contamination.

Gloves, lab coats, or other protective clothing as needed for the work, should be available and worn t

5 If the third result is less than 20% of the first, in the lab. Lab coats and gloves should not be worn

}

the isotope is most likely a high-energy, pure-to the cafeteria, library, classrooms or home. San-l beta emitter, e.g. P-32. Use the appropriate ef-dals or other open toed shoes are not appropriate for ficiency for the portable survey meter to quanti-work with radioisotopes.

fy the result.

Liquids should be provided with secondary contain-6 ff the result obtained through 1 mm Alis more ment. Work areas should be covered with absorbent

{

than 50% of the first, the contaminant is a paper. Plastic trays and dish pans are suitable for gamma emitter. If it is important to identify the use as secondary containment. The protective isotope, take a wipe or sample pf the contami-covering should be replaced when it becomes exces-nation for spectral analysis with the Ge(Li) sively dirty or contaminated.

detector and multi-channel analyzer.

There should be no evidence of mouth or skin contact i

ROUTINE AUDIT with objects used in the radioisotope work areas.

Any signs of eating, drinking, smoking or mouth I

A radiation safety audit is a systematic review of all pipetting in the lab is considered @ f acto evidence

]

operational and administrative radiation protection of violationof thisrequirement. However,itisimpor-requirements in addition to a survey for exposure tant to watch for other perso uti contacts, e.g.

rates and removable contamination. An audit in-pencils in the mouth, application u.

akeup, etc.

cludes, but is not necessarily limited to, the following items:

Exposure Control Storaae and Security if isotopes that emit penetrating radiation are used, the appropriate use of shielding and distance should The regulations goveming the use of radioactive be reviewed. Phosphorous-32 should be shielded materials require that they be secured from unautho-with at least 8 mm (3/8*) of any low atomic number rized removal. To accomplish this, the lab entrance material, e.g. plastic or wood. lodine-125 should be and any cabinets, refrigerators or freezers in which shielded with at least 3 mm (1/81 of lead. Other radioisotopes are stored, must be locked when the isotopes that emit higher energy gamma rays may lab is unattended. This should be verified by noting require 5 cm (2") or more of lead. Make sure that j

that locks are available and by querying the users.

the shielding extends entirely around the source by making measurements of exposure rates above, Fume Hoods below, in back and at the sides of storage locations.

Inhalation of radioactive materials must be prevented Adjacent locations with elevated exposure rates by performing all operations that release gases, should not be regularly occupied. If any dose rate RPet 50. LAB EVALUATIONS (7/92) - 4

exceeds 5 mrem / hour at 30 cm from a source or a label should show the isotopes used in the lab, the J

surface, the room must be labeied with a " CAUTION -

name of the responsible user and his or her office and RADIATION AREA

• sign. If doses to the head or home phone numbers.

l trunk could exceed 100 mrem in a calendar quarter, body badges should be issued.

Personal Monitorina I

Review handling techniques and the use of tongs with the user. If doses exceeding 1,000 mrem per Observe and note whether dosimeters issued to lab calendar quarter to the hands are possible, ring occupants are being used. If they are not, bring this badges should be issued.

to the attention of the responsible user and the RSO.

Instruments Records Verify that appropriate survey instruments are avail-Review the records prepared and maintained by the able, operable and in use. Verify that no repairs or users. All inventory forms should be current and modifications have been made since the instrument should be forwarded to the RSO as soon as the was calibrated and that the calibration is not overdue.

inventory item is used up. All survey records should contain the identif5ation, efficiency and calibration if the user has a sample counting instrument used date of the instrument used. Personnel surveys for wipe tests or urine samples, venty the efficiency should indicate the name of the individual surveyed used for calculating activity in samples and the user's and, if any contamination was found, the location understanding of sample counting results.

on the body or on the clothing. If records are not complete and up-to-date, bring this to the attention Weste Containers and Storace Areas of the user.

Verify that radioactive wastes are being segregated Recommended Survey Frecuency properly and placed in appropriate containers.

Wastes must be segregated by material categories, As part of a routine audit, the frequency for routine e.g. dry, animals, scintillation vials, bulk liquids, etc.

lab evaluations should be reviewed. The default frequency should be followed for at least the first i

Dry waste containing isotopes with half-lives of less year. If contamination is found other than rarely, the than 65 days, and containing no " radioactive materi-intervals between surveys should be shortened. If al" labels or tape, should be segregated from other contamination has been well controlled, the survey dry waste.

interval should be lengthened. However, the interval i

shall not be increased by more than a factor of 2.

Scintillation vials containing only H-3, C-14 and/or isotopes with half-lives less than 65 days,in environ-mentally safe (NHNT) fluors, and with no " radioactive REFERENCES

{

materials

• labels or tape, should be segregated from j

other vials.

U. S. Nuclear Regulatory Commission, Standards for i

Protection Against Radiation,10 CFR 20.

Bulk liquids containing radiciodines should be segre.

gated from other isotopes.

Idaho Department of Health and Welfare, Rules and Waste containers should be conspicuously labeted Regulations, /daho Radiation Control Regulations, title in locations that do not create unnecessary exposures 1, Chapter 9.

to nearby personnel.

Sions and Labels The entrance to the lab should be posted with a

" CAUTION RADIOACTIVE MATERIAL" label. This PPR sO. LAB EVALUATIONS (7/02). 5

ATTACHMENTS l

A RPR 50A. LABORATORY EVALUATION CHECK LIST B

RPR 508. RADIOISOTOPE LABORATORY EVAL-UATION REPORT C

RPR 50C. INTERVAL INVENTORY WORK-SHEET D

RPR 11 A. CONTAMINATION SURVEY - PORTA-BLE INSTRUMENT E

RPR 118. CONTAMINATION SURVEY - WIFE TESTS i

RPR 60. LAB EVALUATIONS (7/92)- e l

l i

l i

i RPR 50A. LABORATORY EVALUATION CHECK LIST i

i Responsible User:

Date:

A Building:

Room (s):

s e

f Reason:_ Pre-start _ Contamination surwy_ Routme auda_ Special_ Cbse-out l

i j

Authorized Isotopes:

I l

Interval Inventory (Alls):

1 Combined interval inventory:

< 1 All 1-30 ALis

>30 ALis I

f Uses: Only in vitro?

If animals, what kind?

j l

How many?

Housed where?

i Storage & Security:

_ Room security?

-l 3

lsotope storage in lockable cabinet? _,,,

freezer? __ refrigerator? __

j t

i Fume Hood: Functional / utilized properly? _

i Contamination Control:

Gloves & lab coats available and used?

Trays, secondary containers, absorbent paper in use?

l 1

No evidence of eating, smoking, mouth pipetting, etc.?

Exposure Control:

Distance / shielding used?

i instruments:

For surveys (type, S/N)

Appropriate for isotopes used?

Operational test date For counting samples (type)

Efficiency known?

l RPR 60 LAB EVALUATIONS (7/92) 7

,1 i

i l

~

RPR 50A. LABORATORY EVALUATION CHECK LIST

)

Wastes:

Segregated by categories and required containers?

Short-lived isotopes in dry waste, NO LABELS 7 Other compactible dry wastes?

1 Aqueous bulk liquids?

Organic bulk liquids?

j Animals (kg/mo.); adequate freezer space?

)

LS vials, quantities and types of fluor?

l Signs & Labels:

Room entrance posted? _ Notice to Employees posted?

Refrigerator _ Freezer _ Sink _ Hood _ Waste containers _

4 i

i Personal Monitoring:

Body dosimeters issued? _ in use?

I Ring dosimeters issued? _ in use?

j Records:

Radioisotope inventory, uses, dispositions Area surveys Personnel surveys s

Personnel changes? No Yes (if yes, attach RPR 1 A or list of names and SS NosJ Evaluation by:

User Survey Frequency:

days Attachments:

onect survey este wipe test este survey map other Additional comments:

RPR 60. LAS EVALUATtoNS (7/92)

• 8

_., -... _. ~.. -.. _..

2

RPR 50B. RADIOISOTOPE LABORATORY EVALUATION REPORT To:

ineeponsibi. U. ort Program #: __

Building:

Room (s):

Reason:

_ cont min tion survey _ noutine ouder_ speciai/inc dent _ case-out

SUMMARY

OF SIGNIFICANT SURVEY RESULTS:

No removable contamination or significant exposure rates were found during this survey. We appreciate Your effort to keep it that way!

ontam at on must b r moved before work continues in the area.

The contamination has been cleaned up.

Unacceptable contamination (U) was found on:

Until it is removed, it must be covered, isolated, labeled, etc. to prevent contact by individuals in the area.

Low-level contamination [L1 was found on-Although this contamination poses no undue risk to personnel, it indicates that improvement in handling techniques is possible and desirable.

A screening bioassay is required promptly [P] (within 5 days) from each potentially exposed individual.

A screening bioassay is required within the normal bioassay interval [B) from each potentially exposed individual.

Significant exposure rates l>o.s mrom/ hour at ao cm) were found at:

Contaminated area categories:

Quantities (multiples of RCL) t

> 100 10-1Q0 1-10

<1 Skm, hair or clothme in contact with skin

_lS,P)

_{ S P!

_lS.Bl

_lul Readdy accessible surfaces; uncontrolled contact

_lS.Pl

_tS.Bl

_lul

_lL1 inaccessible surf aces: hmeted contact potential

_tVI

_lVI

_f L)

_lL1 OBSERVATIONS ON PROCEDURES, EQUIPMENT, RECORDS, ETC. < comment inciuded. is checkedi Contammation control Exposure control Survey instruments Area monstonn0 & records Personal surveys & tocortis Weenne of doesmoters Storage. secunty, stone and labele Weste eeDrogetu>n 6nventory and deposition records Surveyed by:

Date:

Attachments:

eneen het with comments survey date survey me, other RPR 60. LAs EVALUATloNs (7/92]- s

__.._-_ ~,_.--- _...._, -

.., -.. - ~ -.. _.

RPR 50C. INTERVAL INVENTORY WORK-SHEET

1. Determine the quantity (in mci) of each radio-Isotope Quantity (mCO isotope in the laboratory.

1.

2.

3.

4.

5.

2. Determine the ALI for each radioisotope from isotope All RPR 10A.

1.

2.

3.

4.

5.

RPR 60. LAB EVALUATIONS (7/921 10

RPR 50C. INTERVAL INVENTORY WORK-SHEET i

3. Determine the quantity in ALis by dividing each Isotope mci /ALI i

radioisotope quantity by its corresponding All.

1.

I 2.

i 3.

I 4.

5.

4. Sum the results of the ALI calculations from ALis Total block 3 to obtain the total numberTf ALis, i

i I

t l

1

5. Determine the most restrictive bioassay interval Most Restrictive Bioassay intervalin (in months) from RPR 12.

Months.

i I

l RPR 60. LAB EVALUATIONS (7/921 - 11 f

h i

... ~

RPR 50C. INTERVAL INVENTORY WORK-SHEET

6. Divide the total number of ALis obtained in ALis Total / interval l

l block 4 by the most restrictive bioassay interval obtained in block 5. The result is the interval To determine the recquired survey fre-l l

inventory expressed in AL!s.

quencies refer to the applicable table below.

TABLE 1 i

TSO ROUTINE LABORATORY EVALUATIONS i

interval Inventerv

• Nominal Frecuency

> 30 Alls Monthly 1-30 AL!s Each bioassay interval

< 1 ALI Semi-annually Inactive *

• Annually TABLE 2 RESPONSIBLE USER ROUTINE CONTAMINATION SURVEY FREQUENCY interval inventorv '

Nominal Freouency

> 30 ALis Both porsonal and icboratory surveys EVERY D AY when radionuclides are in use.

1-30 Alls Personal surveys EVERY DAY and laboratory surveys EACH WEEK when radionuclides are in use.

< 1 ALI Personal surveys EVERY DAY and laboratory surveys EVERY MONTH when radionuclides are in use.

• monthly average during the bioasssay interval

• see text RPR 60. LAB EVALUATIONS (7/92)- 12

1 1

i i

(

RPR 11 A. CONTAMINATION SURVEY - PORTABLE INSTRUMENT l

I Page 1 of survey record initiated by inem.: on idetal j

i User:

Bldg / Room (s):

Nuclides used:

Critical nuclide:

All: ___ mci l

Removable contamination limit (RCL):

dpm per 100 cm' l

SURVEY INSTRUMENT RESPONSE TO CRITICAL NUCLIDE Critical Expected Net Response i

Survev Instrument (s) Used Nuclide to 1 RCL. (com or cos)

Bkgd.

Efficiency Ill 121

[3]

Calib.

Rate Point Wipe of Wipe of Make. model.Ser. No.

Date (com)

Source Direct 100 cm' 300 cm2 l

1.

l 2.

i 3.

l 111 and (2) RCL x Point Source Efficency 1313 m RCL x Pomt source Eff.

CONTAMINATION SURVEY RESULTS t

iAl Repeated entnee for persons or locateone that are surveyed reguleny may be adentifed by initiets or a code letter followmg a cleerty identified entry on the some or previous sheets.

(B)

Enter *D* for e derect measurement. *100* for a 100 crd wipe or *300* for a 300 cm' wipe.

[Cl Net count rate of meter wrth probe near the contommated surf ace of the wipe fitter.

101 11 the count rete m (C) as Greater then the expected response to 1 RCL, as hated above, enter the multspie of the RCL.

[A]

[BI

[C)

[D]

Survey inst Object. Location in Room Area Net Rate Multiple Surveyed Datt Used or Name of Person (cm )

(com) of RCL Bv 2

I N

h ALL SURVEY RECORDS MUST BE RETAtNED FOR AT LEAST THREE YEAR $

RPR 60. LAB EVALUATIONS (7/921 - 13

- - > - ~ '

m ~

RPR 11 A. CONTAMINATION SURVEY - PORTABLE INSTRUMENT Continuation sheet # __ of record initiated on to.t.,

User:

Bldg / Room (s):

Nuclides used:

Critical nuclide:

All: _ mci Removable contamination limit (RCL):

dpm per 100 cm'

[A]

[B]

[C]

[D]

Survey Inst.

Object, Location in Room Area Net Rate Multiple Surveyed Date Used or Name of Person (em )

(com) of RCL By 1

I

~

i

~

s_

i I

ALL SURVEY RECORDS MUST BE RETAINED FOR AT LEAST THREE YEAR $

RPR 60. LAB EVALUATIONS (7/92)- 14

4 RPR 11B. CONTAMINATION SURVEY - WIPE TESTS i

l Pege 1 of survey record initiated by inemes on idetai User:

Bldg / Room (s):

Nuclides used:

Critical nuclide:

All: __ mci Removable contamination limit (RCL):

dpm per 100 cm l

2 t

COUNTING INSTRUMENT DATA Type: _ LSC _ Gamma _ Other Model, S/N:

Program / Setup:

Preset:

minutes or counts l

Units of Readout:

Counting Channel:

[1]

_121_

.. [3].

l

Background:

Critical nuclide efficiency:

i Expected Net Response to 1 RCL.

WIPE TEST COUNTING RESULTS I

'l (Al Repeated entnes for persons or locatens that are surveyed regulerfy may be sdentifed by mrtials or e code letter efter e clearfy identifed entry

[

on the some or contmusten sheets.

(B)

Enter "100" for a 100 cm' wipe or *300" dor a 300 cm' wipe.

IC)

Net response m each channel m same unns es recorded above.

[

101 if pnmow channel response e greater then that expected for 1 RCL enter the mutteple of the RCL.

{

[A]

[B]

[C]

[D)

{

Survey Area Net Channel Response Multiple Surveyed Date Obiect or Location (cm')

[1]

f21 f31 of RCL By 1

i ALL SURVEY RECORDS MUst BE RETAINED FoR AT LEAST THREE YEARS l

9 RPR 50. LAB EVALUATloN5 (7/921 - 15

RPR 118. CONTAMINATION SURVEY - WIPE TESTS Continuation sheet # _ of record initiated on rc t.i User:

Bida/ Room (sh Nuclides used:

Critical nuclide:

All: _ mci Removable contamination limit (RCL):

dpm per 100 cm'

[A]

18]

[C]

[D]

Survey Area Net Channel Resoonse Multiple Surveyed Date Obiect or Location (cm )

til 121

[3]

of RCL Bv 2

1 1

ALL SURVEY RECORDS MUST BE RETAlfdED FOR AT LEAST THREE YEARS t

RPR 60. LAB EVALUATIONS (7/92) 16

7 RADIOACTIVE WASTE MANAGEMENT PURPOSE not contain any compressed gases, pyrophoric or other hazardous materials.

This procedure specifies how radioactive waste will be collected, segregated, stored, processed and "LS media" means any mixture of solvents and packaged, shipped, and disposed of by the fluors used for liquid scintillation counting. "LS Technical Safety Office, media" must be segregated for disposal, based on the solvents and nuclides they contain:

1 "NHNT" refers to nonhazardous, nontoxic, l

Radioactive wastes (radwastes) shall be collected, nonflammable solvents.

stored, packaged, shipped and disposed of in accordance with all pertinent state and federal 2

Flammable or toxic solvents, e.g. toluene, regulations. The RSO shall prepare and maintain xylene, dioxane, pseudocumine, etc. shall not procedures for handling radwastes that will ensure be used except with special authorization from' i

the protection of the employees involved in such the Radiation Safety Officer.

duties and keep all radiation exposures ALARA.

l Specifications for segregation and packaging of radwas+es shall be based on specific regulations or SCHEDULING AND NOTIFICATION regulatory guidance, and include a record-keeping 4

l system that will allow complete tracking and Rer ast for waste pickups should be made by accounting for all radwastes shipped to a disposal phor. ') to the Technical Safety Office; a waste site or disposed of locally. Radioisotopes will not pickup request form (RPR 54A) must be filled out and

(

be mixed with hazardous materials. If there are any provided to the person collecting the wastes.

l questions about a material contact the Technical Waste pickups should be arranged, by the user at Safety Office.

least two days in advance.

DEFINITIONS PROTECTIVE CLOTHING AND DEVICES

" Animal" waste means carcasses or parts of animals administered radioactive materials; it also The minimum requirement for all phases of waste includes collected excreta and combustible bedding handling is the wearing of a lab coat and plastic or materials, e.g. shavings or sawdust.

rubber gloves. Lab coats and gloves used for waste handling will not be worn to the cafeteria or other i

" Ass:y Date" is the date that the manufacture public areas on or off the campus.

certifies the activity of the radioactive material.

During packaging or disposal of liquid wastes, a

" Aqueous" means a liquid that is soluble or readily plastic-lined lab coat and face shield or safety dispersible in water and which contains no chemi-glasses shall be worn. Check with the TSO if there cals classified as toxic or hazardous; except for are any questions regarding conditions that may limits on radioactivity, aqueous liquid wastes are require the use of additional protective devices.

l those which could be discarded to the sewer.

" Biological" waste means any biodegradable PICKUP OF WASTE materials, including

• animal" wastes.

The TSO will bring a thin-window GM survey meter

" Dry" waste means any nonputrescible, dry waste, on all waste pickups to survey waste containers for e.g. paper, plastics, glassware and metals, that does contamination or excessive exposure levels. The RPR 54 Radioactive Weste Menegement (9/92)- 1

, _ -I

TSO will verify that a radioactive waste tag (RPR 13Ei material to absorb potential leakage from the has been filled out properly and signed by the user primary container. Carefully J-seal the bag and tape before any waste will be accepted. The TSO will the user-prepared waste label on the bag. Next, not take any waste until it has been properly place the waste in the transfer drum. Remove labeled.

gloves and place them in a dry waste container, survey the waste in the transfer drum, and survey hands for contamination.

Packmaina of Dry Weste:

Resoonsible User:

Liauid Scintillation Vials:

i All radioactive labels must be removed from Liquid scintillation vials may be picked up and laboratory material before it is placed in a transported in plastic bags or the original cardboard radioactive waste container.

trays. Verify that they are properly segregated and g

labeled according to the nuclides and solvents Technical Safety Office:

present.

Remove the lid of the waste can and check the exposure rate. Visually check contents to ensure TRANSPORT OF RADIOACTIVE WAST E:

that only dry waste is in the container. Carefully J-seal the package and then remove the bag from the The vehicle used for transportirg wastes from on-waste container; inspect for protruding hypodermies site generators to the Radioactive Waste Storage needles, pipettes or other objects that may rupture room in the Physical Science Building must be i

the bag or cause injuries; also, check for leakage.

placarded on all four sides with

• RADIOACTIVE" Take swipes on the interior surface of the waste placards whenever radioactive materials are present container to determine if the waste container has in the vehicle. When radioactive materials are not been contaminated. Next, place the waste inside of in the transport vehicle, the " Radioactive

• placards a second bag, and remove gloves and place them should be removed or switched to the

• DRIVE inside of the second bag. Securely close the bag, SAFELY" position. A plastic cart or drum is used to I

with a J-seal, and place the bagged waste in the transport waste packages of all types to the waste transfer drum or cart. Swipe the outside of the transport vehicle.

i second bag and record the results on the waste tag.

Before leaving the lab, put a new bag in the waste When unattended, the transport vehicle will be kept container with top folded over the rim and replace locked at all times if it contains radioactive waste.

the container lid. Survey hands for contamination All radioactive materials will be removed from the j

survey the transfer drum to determine the exposure vehicle at the end of each work day.

If the rate and record the results on the waste tag.

transport vehicle is involved in an accident while transporting radioactive waste, the Campus Police Department (Ext. 2515) and the RSO (Ext. 23111 Packmaina Liouid Weste:

shall be notified as soon as possible. The RSO or i

his designee will determine if there is any l

Technical Safety Office:

contamination problem and supervise cleanup operations if necessary.

Check the exposure rate from the container. Lift the container out of its secondary containment and I

inspect for leakage and solid objects. If solid SORT!NG AND SEGREGATION OF RADWASTE objects are found return the container to secondary containment and inform lab personnel that the Dry Radioactive Weste:

objects must be removed before waste will be picked up. If no solids are observed, insure the lid All radioactive waste will be segregated by nuclide.

to the primary container is secure and then place Unless specifically noted, dry waste that contains the container in a plastic bag with some absorbent nuclides with a short half-life (<65 days) will be RPR 54 Radioactsve Weste Management (9/92F 2 i

held for decay (10 CFR 35.92), in the radioactive All disposals to the sanitary sewer will be performed waste storage room for 10 half-lives. Dry waste by the TSO. The sewer disposals will be performed with a half-life of >65 days will be packaged for in a sink specifically designated for this purpose, transport to a licensed disposal facility.

The sink used for sewage disposalis located in the Physical Science Building Rm-330.

Liould Radioactive Waste:

Biolooical Radioactive Waste:

All radioactive waste will be segregated by nuclide.

The TSO will employ three methods to dispose of Biological wastes containing radium or transuranics liquid radioactive waste as authorized by 10 CFR will be segregated for special packaging. Biological 20.2003. These disposal methods are: 1) Store for waste containing nuclides with a half-life <65 days decay, 2) Disposal to the sanitary sewer, 3)

(10 CFR 35.92) will be held in the radioactive waste Shipment to a licensed disposal facility. Aqueous handeling room for 10 half-lives and then disposed liquid radioactive wastes with half-lives <65 days of by inceneration. Notogical waste with nuclide will be held in the radioactive waste handling room half-life >65 days will be packaged for shipment to for ten half-lives and then be disposed of as a licensed disposal facilities.

uncontaminated liquid waste (10 CFR 35.92).

Aqueous liquid radioactive waste with half-lifes Once the biological waste has been decayed (10

> 65 days (excluding H-3 and C 14) will be held in CFR 35.92), it will be transfered to the Biological l

the radioactive waste handling room for as long as Science Animal Care Facility (ext. 3895) for l

practical (up to 10 half-lifes) and then disposed of incineration.

via the sanitary sewer. Radioactive waste storage time will be determined by the amount of space available in the waste handling room. Due to their Liouid Scintillation Vials:

long half-lives, aqueous liquid radioactive wastes that contain H-3 and C-14, will be disposed of to Representative vials from each package will be the sanitary sewer as soon as practical. There is no retrieved and counted using procedures outlined in appreciable benefit gained from on site storage of

• RADIOACTIVITY MEASUREMENTS * (RPR 53). The these materials.

results will be recorded on form RPR 54B. Any i

vials that contain toluene, xylene, dioxane, or pseudocumene will be set aside for packaging.

Sewaoe Disposal:

Packages containing only H-3 and C-14 in an NHNT solvent at less than 0.05 microCi/g will be placed in Prior to each disposal of radioactive liquid waste to a dumpster for disposal after completely obliterating the sanitary sewer, the TSO will determine the or removing all radioactive material labels (10 CFR activity of all nuclides to be discarded, their monthly 20.2005). Vials containing short lived nuclides average concentration, and the cumulative annual (half-life < 65 days)in NHNT fluors will be held for activity. Next, the TSO will calculate the average a period of ten half lives, then surveyed to assure l

monthly water flow through the Physical Science that the extemal exposure rate is not above Building. The average water flow is calculated by background; these packages may then be disposed averaging the water flow for the previous 12 of in a dumpster.as ordinary trash. Vials containing months and dividing the average by 10 to insure an long lived nuclides (half-life >65 days) in NHNT i

l adequate safety margin. This information will be fluors will be segregated for packaging.

recorded on RPR 541.

1 Once the nuclide quantities are determined to be within the limits specified by 10 CFR 20.2003, the radioactive liquid waste will be discarded into the sewer. All other liquid wastes will be segregated for packaging.

RPR 54 Radioactrve Weste Management (9/92)- 3

i I

1 l

l PACKAGING OF RADWASTES returned to the TSO as waste RPR 13A will be I

l removed from section 1, attached to RPR 13B & C I

l and placed in the appropriate section of the waste j

l Liouid Radwastes for Burial:

log (See Section Categories Below).

l 1

i Biological liquid waste to be sent to the U.S. DOE Section 2-Decay Storage:

Hanford Reservation for disposal will be packaged Section 2 contains a list of all material that is in compliance with requirements found in the currently held in the Physical Science Building Hanford Radioactive Waste Packaging manual.

Radioactive waste storage room for disposal by Liquids wastes to be sent directly to the commercial decay. RPR 54E is used to keep a record of all burial site will be solidified in accordance with material awaiting disposal by this method.

instructions in the US Ecology license. Before t

l absorbing, solidifying or packaging liquids for burial, Section 3-Shipment l

check the latest revisions of license conditions or Section 3 contains a record of all material that l

regulations to determine approved materials for is awaiting shipment to an off site radioactive l

absorption or solidification.

waste disposal facility. RPR 54F is used to trace all material in this section.

If nonreclaimable liquid wastes are sent to another broker for solidification, they should be packaged Section 4-Sewage Disposal:

for transportation the same as reclaimable liquids, Section 4 contains a listing of all material that is being held for disposal by dumping into the i

sanitary sewer. RPR 54G has a listing of all STORAGE OF PACKAGED RADWASTE material in this section.

i Sealed drums are to be placed on wooden stats and Section 5-Dead Fde:

remain covered at all times. The radioactive waste Section 5 contains a record of all rcdioactive handling room in the basement of the Physical waste that has been processed by the TSO.

Science Building must be posted with signs Records will be held for three years on material tu

" CAUTION - RADIOACTIVE MATERIALS" and kept has been decayed on site or dumped into t h e locked when not attended.

Waste shipments sewer. Records will be maintained in this section should be scheduled to prevent excessive for the life of the radiation safety programatlSUon accumulation of filled drums. If material is stored all material that has been shipped to a licensed for decay and subsequent local disposal, waste disposal facility. RPR 54H has a listing of all the drums only need to be marked with the container material in this section.

number, if the materials are in storage awaiting shipment to a disposal facility, RPR 54C should be Upon receipt of any radioactive material the TSO completed and the drums should be marked with all will fill out a

• Radioisotope Package Arrival Report" labels and markings required for shipment.

(RPR 13 A,B,&ci and assign three " Radioactive Waste Tags" (RPR 13E) to the responsible user. RPR 13A will be filled out and placed in Section 1 (active file)

RECORDS of the radioactive waste log. RPR 13B wili be filled out and placed in the isotope inventory Book. RPR Radioactive Weste Loa:

13C and three RPR 54Es will be delivered to the user along with the isotope.

The Radioactive Waste Log Consists of five sections. Each section is described below.

When responsible users are done with the isotope, they will contact the TSO and arrange for a waste Section 1-Activs File:

pick-up. The TSO will verify all the appropriate Section 1 contains form RPR 54D and the forms are filled out and the waste conforms to all completed form RPR 13A. RPR 54D allows the packaging restrictions before accepting custody of TSO to track the location of all radioactive material the waste. The completed waste tags will be that is received by the TSO. When is ot o p e is distributed as follows:

l RPR 54 Radioactive Weste Management (9/92)- 4 l

l I

I 1

l l

l 1

White copy: will be left with the responsible REFERENCES user for their records.

I U.S. Nuclear Regulatory Commission: 10 CFR 20 l

2 Yellow copy: will be attached to the completed and 10 CFR 61 10 CFR 71.

RPR 13C and placed in the appropriate section l

of the

• Radioactive Wasta Log.*

Hanford Radioactive Solid Waste Packaging, l

Storage, and Disposal Requirements, WHC-EP-l 3

Hard Tag: will be attached to the waste 0063, Westinghouse Hanford Companyi1988.

container and remain with the container untilit i s disposed of into the sewer or by decay. After the State of Washington, Radioactive Materials License waste has been disposed of, the hard tag will be issued to US Ecology, Inc.

l attached to RPR 13A and placed in section 5 of the l

waste log. The hard tag will remain with the waste t

l if it is shipped to a disposal facility.

Records will be kept _ that verify the exempt j

concentration of H-3 and C 14 vials (RPR 548).

I Radiation surveys of packages of vials containing, short-lived nuclides, e.g. P-32 and Cr-51, will also j

be recorded on RPR 54B.

1 i

Summaries of all radioactive waste disposals shall be generated at least annually by the Radiation Safety Officer. These summaries will be filed with l

the annual reports prepared for the records of the Radiation Safety Committee. The radwaste disposal l

l 100 will be used to summarize information required for waste shipment manifests, as described in "TR AN S PORTATION OF R ADIO ACTIVE l

MATERIALS" (RPR 56).

f L

i l

l i

I I

i j

RPR 54 Radioactive Weste Menegement (9/92)- 5

RPR 54A. RADWASTE PICKUP. REQUEST

]

This form is used by the Technical Safety Office to record requests for radioactive waste pickup, t

I i

RPR 54A RADWASTE PICKUP REQUEST i

i Responsible User:

Prgm #:

Phone:

I r

Location:

Room-Type:

Dry Sharps Animal Liquid Volume:

t.

MAKE SURE WASTE TAG IS READY l

Comments on back:

Date:

I i

i l

5 i

f 5

t l

l l

RPR 54 Radioactive Weste Management (9/92)- 6

)

I J

1 I

RPR 54B. SAMPLE DATA FOR L.S. VIALS The following 4"x6" card is used for recording counting data from j

representative samples of liquid scintillation vials..

i t

t RPR 54B SAMPLE DATA FOR L.S. VIALS 7/92 l

i Check one or both categories:

Pkg. ID #

l l[l Isotopes with half life < 65 days l

Sampling not require unless contains H-3 or C-14.

Held for 10 half lives? (Y) (N)-

i j

l[l H-3 and/or C-14, sampling required. (See back)

-j If H-3 and C-14 only, no other'nuclides detected.

l H-3 + C-14 < 50 microCi/g I

Package exposure rate at surface mR/hr

{

i Check only one category:

l[]

"NHNT" L.S. Vials;~ Released Solid Requirements for package _ release have been met.

I 1

I l

l[l Requirements for package release are not met.

1

)

Package placed in Container #

l J

Date Initial l

i i

f i

i i

l RPR 54 Radioactive Weste Management (9/92)- 7 i

4

.---r-

---

w

,-r,-.~

+

ro,--

..-,w,,.,.

w n -- t,-

t RPR 54B (BACK)

(H-3)

(C-14)

(Other) i No.

Chl, Ch2 Chl 1

I 2

3 4

5 l

6 I

7 8

[

t 9

i 10 Bkg.

Avg. Net cpm i

Eff.

Net nCi-cpm /(Eff.x 2200)

Vial size:

Std

- 15 g / vial Mini = 5 g/ vial Avg. Nci/g (Chi + Ch2 must be <50) i Ch3 must be zero!

RPR 54 Radioactwo Weste Management (9/92)- 8 i

I RPR 54C. RADWASTE CONTAINER DATA The following 5"x8" card is to be completed for every container.

(drum) of radioactive waste at the time it is packaged.. The card is to be delivered to the Technical Safety Office before the container-is listed for shipment.

FRONT-I RPR 54C (7/92)

CONTAINER #

(Last digit of year + 3 digits) l Size: __ 55 gallon or Type:

Spec. 7A or

" Strong,-tight" Weight:

lbs..

Physical Form:

Solid Vials Bulk Liquids Waste Description Code (see back. of card) :

l Solidified or Absorbent Media Code (see'back of card):

Contents / Chemical Form:

Paper, plastic, glass, rubber i

Scintillation fluor in vials Incinerator ash l

4 other 4

i Shiccine Catecorv:

LSA Dry Solids (LSA)

. LSA Vials. (LSA)

LSA Flammable Liquids (LSAF)

Type A Quantity (A) l Limited Quantity (LQ)

Special Form (SF)

OTHER

==

Description:==

i Preliminarv Survev:

Date:

By-Meter used:

Calib. Date:

Exposure Rate (mR/hr) at surface:

at 1 meter:

l l

RPR 54 Radioactive Weste Management (9/92)- 9 l

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1

{

f y

+.=-

t

~r-1

-mY

="w Tr"+

• * * ~ -

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RPR 54C (back) l Waste Descrintion Codes:

2. Dry Solid.

10. Absorbed Aqueous Liquid

3. Solidified Liquid

11. Absorbed Organic Liquid j

4.

Biological

12. Scintillation or Organic i

Liquid in Vials in Absorbent 7.

Filter Media

13. Aqueous Liquid in Vials in Absorbent

8. Dewatered Resins

14. Animal Carcasses in Absorbent 9.

Solidified Resins

99. Other Solidified or Absorbent Media Codes:

2. Speedi-Dry

10. Zonolite, Grades 2,3,4 l

3. Celatom (MP-78)

11. Dow Media

4. Floor Dry / Super Fine

12. Cement

5. Hi Dri

13. Asphalt

6. Florco or Florco X

14. Delaware Custom Media 7.

Instant-Dri

15. Envirostone

8. Safe-T-Sorb

16. Krolite i

99. Other 1

RPR 54 Radioactive Weste Menegement (9/92)- 10

RPR 54D WASTE LOG ACTIVE FILE INV #

Responsible Nuclide Activity (mci)

Assay Date Receipt Pickup User Date Date RPR 54 Radioact!ve Waste Menegement (9/32b 11

RPR 54E WASTE LOG ISOTOPE DECAY-SECTION 2 ItW #

Waste Tag #

Nuclide Activity Assay Decay Date Disposal Survey (mci)

Date (19 t -1/2)

Date Meter RPR 54 Radioactive Waste Management (9/92).12

e ta 3

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RPR 54G WASTE LOG SEWAGE DISPOSAL SECTION 4 INV #

Waste Tag #

Nuclide Activity (mC1)

Assay Date Disposal Date RPR 54 Radioactwo Waste Man ngement (9/92)- 14

e taD l

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N taD O

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s sA CE S

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RPR 54I SEWAGE DISPOSAL RECORD SHEET Date Average Nuclide Activity Monthly Total Annual Water Flow (mci /ml)

Activity Activity i

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RPR 54 Radioactive Weste Management (9/92F 16

- --- a r-

- -------m-a.

a.

m

ATTACHMENT E

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-JLockheed Env!mnmen!3; %its m

",~.: en

• Phone:(208)524 7322 Techr. ology Applications Olvision F AX:(208)524 9036 591 Park Avenue, Suite 202 Idaho Falls,ID 83402 September 16, 1993 Mr. Dave Clovis Reactor Supervisor College of Engineering Idaho State University P.O. Box 8060 Pocatello, Idaho 83209

Subject:

Plutonium Volatilization Test at ISU - PRP-147-93

Dear Mr. Clovis:

As you requested, I am enclosing Kirk McKinley's resume and a memorandum 01 understanding on payment for decontamination in case of an accident during the Pu Volatilization Test. I am also sending two VHS video recordings of the tests performed at Retech in Ukiah, California, using cerium as a plutonium surrogate. One tape shows activities outside the melter, the other is a view inside the melter showing the torch and the melt. Results of the cerium analysis will be provided as soon as they are available.

With respect to the Radioactive Material License for the Lockheed Soils Treatment Laboratory in Las Vegas, the license was issued by the Nevada State Health Division, license number 00-16-0112-02, expiration date: May 31,1995. Amendment 19 to the license, dated June 26,1991, authorizes the lab to have Plutonium 239 and decay products, in the form of solids as soil contamination, in the amount of 10 millicuries, for the purpose of research and development.

If you have any questions or need additional information about the license, please call me at (208) 524-7322.

Sincerely, V. V Harkins, r.

f Deputy Program Manager 1

1 l

ATTACHMENT F

1 4

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- ~ - _

~ ~ -

- ~ _.

WAAb 3AHO STATE UNIVERSITY TO WHOM IT MAY CONCERN:

Idaho State University issues this Statement of Intent Office of j

the Pnsident as a state government licensee of the Nuclear Regulatory Campus Box E310 Pocatello, Idaho G32094310 Commission.

The facilities for which the University provides (208) 236-3440 financial assurance and corresponding decommissioning costs are described in the University's application dated February

.b 10, 1992.

y will be available Funds up to the amount of $750,000 for decommissioning if and when necessary, i

The President is authorized by the State Board of if made, Education to execute contracts or agreements that funds.

'O/A

~

ficBrdL.4dwen ~

President Idaho State University

/

/c 92 Date