ML19345H138
| ML19345H138 | |
| Person / Time | |
|---|---|
| Site: | 07001207 |
| Issue date: | 03/18/1981 |
| From: | NAVY, DEPT. OF |
| To: | |
| Shared Package | |
| ML19345H137 | List: |
| References | |
| 18820, NUDOCS 8105010029 | |
| Download: ML19345H138 (69) | |
Text
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APPLICATION FOR RENEWAL OF SNM-1147 1
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U.S. Department of the Navy 2
Naval Surface Weapons Center White Oak, Silver Spring, Maryland 20910
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18 March ~1981 i
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TABLE OF CONTENTS Page Number Headings 1
License Number 1
Docket Number Expiration Date
_1 1
Location of Use 2
Maximum Quantity of Material which Licensee may Possess 3
Authorized Use 5
Administration and Organization 8
Inspections Radiation Detection and Measuring Instruments in Use 9
by the Health Physics Branch Method, Frequency, and Standards Used in Calibrating 10 Instruments General Radiological Safety Procedures 10 Collection and Disposal of Radioactive Wastes 13 Solid Wastes 13 Liquid Wastes 14 Ultimate Disposal Contamination Limits 14 Internal 14 Surface Air and Water Contamination 14
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Criticality Precautions Unsealed Quantities of Special Nuclear Material 15 Sealed Sources 16 Dscontamination Area Decontamination 16 Equipment Decontamination 16 Personnel Decontamination 16 Leak Testing Procedures Techniques Employed 17
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Counting Methods 17 Monitoring 18 Procedures for Issuance and Processing of Film Badges 18 Special Requirements Governing the Purchasing, Receiving, and Shipping of Radioactive Material 20 Radiation Safety Training 20 Energency Action 21 ALARA Concept 21 Appendix A - RSO Resume l
l Appendix B - Radiological Safety Manual 4
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APPLICATION FOR RENEWAL OF SNM-1147 U.S.. Department of the Navy Naval Surface Weapons Center White Oak, Silver Spring, Maryland 20910 License Number:
SNM-1147 Docket Nunber:
70-1207 Erpiration Date: 31.0ctober 1979 Location of Use:
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The general storage area for Special Nuclear Material is building 321, the Naval Surface Weapons Center (NSWC), White Oak Laboratory (WOL).
The sealed sources are to be used at NSNC WOL under the direction of the Radiatien Safety Officer (RS0).
The uranium-235 is used in building 343 radiochemistry laboratories, building 4 (Van de Graaff facility); the depleted uranium is used i
principally in the environmental laboratory in building 20, PU-238 l
microspheres project is used in radiochemistry laboratories in building 343.
239 The 239 Pu-Be sealed sources and the 760-gram Pu
- p. sealed 4
source are used for calibration of radiation detection instruments, shielding measurement studies, and instrument development research at buildings 2, 4, 10, 71, and 343, and other authorized places of use at I
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Maximum Quantity of Material which Licensee may Possess:
1.
NRDL Source No. 2 - 79.93 grams PuBe M-232' Mound Laboratory Monsanto Chemical Company Miamisburg, Ohio No Serial Number 2.
NRDL Source No. 4 - 760 grams pup 4 Hanford Atomic Products Corp.
General Electric Company Richland, Washington 3.
NRDL Source No. 5 - 80 grams PuBe
~800-H-14 Nuclear Materials and Equipment Corp.
Apollo, Pennsylvania 4.
NRDL Source No. 6 - 16 grams PuBe SNM 414 - SNM 35-1 Nuclear Materials and Equipment Corp.
Apollo, Pennsylvania 5.
3.3 milligrams Pu 239 as resin deposited sources 6.
20 grams Pu 239 as contained oxide 7.
21 grams Pu 238 in any form 8.
U-233: 10 grams as nitrate 9.
U-235: 50 grams as oxide or foil l
10.
thorium and natural and/or depleted uranium 68.1 KG 11.
Pu-238: 3.3 milligrams 12.
U-235: 60 grams in any form,
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~~ Authorized Use:
Authorization is requested to receive, possess, and store the materials listed below:
1.
3.3 milligrams Pu-239 as resin deposited sources; 20 grams Pu-239 as contained oxide; and 21 grams Pu 238 in any form 2.
10 grams U-233 as nitrate 3.
50 grams U-235 as oxide of foil 4.
10 grams of U-235 in any form.
Authorization is requested to receive, possess, and use the following materials:
1.
,180 grams Pu-239 encapsulated as Pu-Be neutron sources 2.
760 grams Pu-239 encapsulated PuF neutron source 4
3.
Pu-238 3.3 milligrams 4.
U-235: 50 grams in any form
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5.
68.1 KG uranium depleted in the U-235 isotope 6.
thorium and natucal and/or depleted uranium, 68.1 KG.
The special nuclear material such as uranium enriched and the l
isotope U-235 will be used for radiation in National Bureau of Standards (N3S) nuclear reactors, NSWC's linear accelerators, cyclotrons, and Van de!
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Graaff machines.
The special nuclear material will be irradiated with) neutrons, thus causing fission of the uranium-235 isotope.
Maximum
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amount of special nuclear material per sample for irradiation is about 50 milligrams of the enriched uranium-235 isotope.
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The irradiated samples of uranium-235 will be used for counting measurements.
Radiochemical analysis wi11 also be performed on the
. irradiated uranium samples.
The 238 plutonium dioxide in the form of microspheres in a prior use was subjected to a sea-water environment in an exposure chamber where the effect of the ocean could be determined l
by observation and measurement, i
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Uranium depleted in the U-235 isotope in microgram to gram amounts is to be used as follows:
a.
standard source b.
fragmentation studies c.
radiochemistry d.
Van de L aaff targets for investigating the stopping power of heavy particles.
In addition, small amounts of depleted uranium are to be used in investigation of metallurgy and stress corrosion cracking tests.
The uraniun in cylinder form will be used while mounted under tension in an environmental chamber operated under control conditions.of l
temperature, moisture, and effluent direction.
Thorium is utilized in compounds of metals with metalloids for experiments measuring their magnetic and non-magnetic properties.
Thorium is also used in making of compounds.
-Administration and Organization:
The Radiation Safety Committee meets semi-annually or upon request when deemed necessary.
The Committee consists of the Radiological Safety Officer, the Medical Officer, a nuclear chemist, a nuclear physicist, and two chemical engineers and is responsible for reviewing and approving radiation safety policies for the NSWC, as well as requests for*use of Nuclear Regulatory Commission license material.
The Committee msobers have academic degrees in related fields of science and/or engineering with years of experience in th'e use and handling of radio-active materials and radiation producing machines.
The Medical Officer has also had advanced training in radiological health protection.
Primary responsibility for radiation safety control at NSWC is assigned to the Head, Health Physics Branch.
Health Physics is responsible for the promulgation and enforcement of required safety practices pertaining to the use of radioactive materials and radiation sources.
The Health Physics Branch is an organized part of, and is administered by, the Safety Division, Command Support Department of NSWC.
It consists of the RSO (Branch Head), a Safety Engineer, and a part-time Health Physics Aid.
The Commander of NSWC has authorized the immediate hiring of two health physicists (one at a GS-5/7/9 level and one at a GS-9/11/12 level).
One candidate has been selected,.is in the process of being
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hired, and will report approximately 1 April 1981.
An application has been received for the second position and the applicant is coming to NSWC for an interview on 23 March 1981; hopefully to be hired and on-board by 1 May 1981.
The two health physicists will assist in providing _ - _
surveillance, surveys, and monitoring in areas where radiation sources are used and/or stored and will enable the Health Physics Branch to give greater radiation safety coverage.
All work in this Branch is done under the direct supervision of the RSO, who is the Branch Head.
The Health Physics Branch maintains inventories of all radioactive materials within WOL.
Inventories are inclusive of byproduct, special nuclear, and source materials.
These materials are governed by the following regulations issued by the NRC: Title 10 CFR - Parts 19, 20, 21, 30 - 36, 40, 70, and 71.
Health Physics is also responsible for accountability control over certain unlicensed materials.
These materials include both ionizing and non-ionizing sources of radiation.
It is mandatory that all authorized users inform the Health Physics Branch with regard to the
' location and uses of such materials and equipment.
Tae RSO has the overall responsibility for the NSWC radiological i
safety program.
The Head of the Health Physics Branch is the RSO for
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the NSWC.
The Commanding Officer of the NSWC WOL is responsible for compliance with Federal regulations and Navy Department directives in the procurement, control of storage, handling, use, safety aspects, and disposal of radioactive material under his jurisdiction.
The Commanding Officer l
takes such action as deemed necessary to establish uniform practices and procedures and to assure compliance and implementation of the Federal Regulations, Department of Defense directives, and Department l
of the Navy directives.
He implements periodic inspections to assure compliance with the applicable directives.
He also ensures that all applicable provisions of the licenses and of litle 10, Code of Federal Regulations, are complied with in the use of these sources.
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The RSO provides consultation and advice ragarding the implementa-tion of controls for the hazards associated with radiation sources and the effectiveness of these measures.
He is responsible for promulgating and supervising the radiological safety program.
He is directly responsible for the adequate and effective controls which prevent spread of contamination and for decontamination techniques and procedures.
This individual is technically qualified by virtue of education, military training, and/or professional experience to supervise the storage, issue, operation, and disposition of radiation sources, and has a thorough knowledge of applicable regulations pertaining to the control of radio-activity.
The duties and responsibilities of the RSO include:
serves as the licensee's liaison officer with the a.
Nuclear Regulatory Commission
'b.
maintains control of procurement and disposal of licensed material develops and maintains up-to-date operating and c.
emergency procedures d.
establishes and maintains a personnel monitoring program procures and maintains radiation survey instruments e.
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establishes, conducts, or chooses instructors for l
the training of Health Physics personnel, users, and others concerned with handling radioactive material's establishes and maintains storage facilities g.
h.
maintains expos re devices and associated equipment -
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establishes and maintains the leak test-ing program j.
establishes and maintains the internal inspection system k.
performs source replacement and source tagging operations 1.
conducts quarterly inventories and maintains utili:ation
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logs m.
establishes and maintains a survey instrument calibration
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program n.
establishes and maintains the licensee's record-keeping system o.
reviews and ensures maintenance of those records kept by others p.
assumes control and institutes corrective action in emergency situations q.
investigates the cause of incidents and determines necessary preventativg action.
Inspections:
Inspections are conducted, documented, and filed by the Health Physics Branch for review.
The frequency of these inspections range from daily to monthly.
Command inspections are conducted throughout l
the Laboratory bi-annually with users and/or Health Physics personnel accompanying the team to areas in which radioactive materials are used and' stored.
The Health Physics Branch, however, must of necessity inspect and/or conduct surveillance of any area in which radioactive materials 1
l are used or stor2d in the interest of radiation safety.
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l ItADI ATION DliTI!CTION AND MUASullING INSTitUMl!NTS IN USE BY Tile IIEALTil Pi!YSICS BRANCil Instrument Type No. Available Range Use 0
a/# Detector 5
0 - 2x10 CPM contamination and personnel (s ta tionary)
- monitoring, leak testing, air and water, sampling 6
a Detection and 3
0 - 10 CPM contamination monitoring Monitoring (portable)U Neutron Detectors 1
0, 2000 mr/hr.
dose rate monitoring 5
h) 2 0 - 8x10 CPM dose rate monitoring (portabic)O Air Samplers 7
25 CFM aerosol / sample collectors i
3 1.7 CFM aerosol / sample collectors (portable)U Stationary instruments calibrated every six months / standardized daily.
O Portabic instruments calibrated every 90 days.
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Table 1 i
Method, Frequency, and Standards Used in Calibrating Instruments:
Alpha and neutron radiation detection instruments are serviced on a regular basis, or as required (i.e., instrument failure).
The olectronic components are checked quarterly and each instrument is calibrated at six-month intervals or every other time it is serviced.
In addition, each instrument is checked immediately before use with a small radioactive test standard.
Instruments taken from storage are checked and calibrated prior to use.
Electronic and calibration services for portable instruments are performed a't the local Radiac Repair Facility, Naval Electronic Systems Command, Navy Yard, Washington, DC.
Each instrument is calibrated in accordance with the conditions of the Radiac Repair Fa.cility's AEC License Number 08-03179-02.
The types of instruments used are described in Table 1.
Counter-scaler systems are checked daily with standards traceable to the NBS (and repaired) for electronic performance by instrument technicians at NSWC WOL.
Counting systems are calibrated by Health 1
Physics personnel for operating plateaus and are checked daily with calibrated standards for instrument performance.
Air sampling equipment are checked prior to use and occasionally thereafter, or as required to determine the air flow.
l General Radiological Safety Procedures:
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The control procedure for use of radioactive material requires the preparation of a Standard Operating Procedure (SOP) as described in the Naval Surface Weapons Center Safety Manual (PS100.5A) by the responsible supervisor.
The SOP is reviewed by the Division Head, and if approved, is forwarded to Health Physics for general review and l i
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consideration as to the adequacy of safety requirements.
After review and approval, the S0P will be forwarded to the investigator's Department Head for final review and approval.
The Health Physics Branch is responsible for the protection of laboratory personnc1 and environment from radiological hazards.
This includes adequate radiological safety measures for all laboratory personnel who work in spaces where radioactive material is used and/or stored.
Special monitoring is performed on a case basis or when requested where any experimental or maintenance operation may involve an unusual radiological hazard.
Health Physics also conducts monitoring surveys and contamination wipe surveys of all areas where radioactive material is used and/or stored.
These services include special monitoring of fils badges, pocket dosimeters, and appropriate radioclinical examina-tions for evaluation of internal contamination.
These examinations will be conducted at the Naval Medical Center in Bethesda, Maryland, when required.
A supply of calibrated portable monitoring instruments, adequate to measure all types of radiation, are provided by the Naval Electronic Systems Command, Washington Navy Yard, Washington, DC 20390, for the Health Physics Branch, and for use by investigators for self-mohitoring purposes.
The 5nvironmental Laboratory in building 71, and building 70 (room 141), are designated as restricted areas and, as such, are provided with necessary locks and interlock systems, and are posted with appropriate radiation warning signs and other identifying Mforma-l tion.
All personnel who work in the area when radiological mate 123, l I
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is utilized are required to follow radiological safety procedures.
Film badges are worn by all personnel.
Monitoring by users of them-solves and work areas with portable instruments are carried out frequently.
Pocket dosimeters are read after use by users and' documented whenever they could receive an exposure to radiation of 100 mrem / week or more.
Whenever a dosimeter goes off scale (over 200 mr), the person will stop work and notify the Health Physics Branch immediately.
Health Physics will investigate the incident to determine if the exposure is accurate or a malfunction of the dosimeter.
If it is ascertained that the exposure is accurate, precautions will be instituted to prevent further exposure of this magnitude.
It is not anticipated that the use of tha listed sources wi1~
produce radioactive aerosol or waste.
Radiochemistry operations with small quantities of SNM material will provide a medium amount of radio-active waste, and in the event of a leak from a sealed source, any quantity of radioactive waste generated, as well as waste from its subsequent decontamination, will be placed in specially marked solid and/or liquid radioactive waste containers for all radioactive wastes.
Disposal will be to a licensed contractor.
Air samples will be collected should the possibility of gen 3 rating a radioactive aerosol be likely to occur.
An Automatic Gamma Alarm or a similar area monitor will be provided within a distance of 20 feet from the experimental set-up when large quantities (one Curie or more) of sealed sources are esed.
The alarm
~~-Ts set to be activated by radiation at 2 mr/hr.
This instrument is equipped with both an audible and visible alarm to indicate any increase in radiation background level.
No radioactive material will be moved within the Laboratory without prior approval and documentation by the Health Physics Branch personnel in accordance with this license application.
Collection and Disposal of Radioactive Wastes:
Solid Wastes _
Special waste containers with disposable liners are provided by the Health Physics Branch to the various departments utilizing licensed radioactive materials for the collection and temporary storage of low-level radioactive wastes.
These receptacles are yellow in color and contain the magenta radiation symbol and the wording " Caution - Radio-active Materials".
The Health Physics Branch is responsible for collecting the contents of these containers on a routine basis (monthly or more often as required).
Collected wastes are then placed in storage under i
the direct supe: vision of Health Physics prior to ultimate disposal to a commercial waste disposal company.
Liquid Wastes Special containers will be provided to laboratories employing liquid radioisotopes for the collection and containment of medium-level wastes.
These radioactive wastes will consist primarily of first-wash solutions.
Further washings of glassware will be restricted to certain designated sinks 1ccated in each of the laboratories using radioisotopes.
A.
1000 gallon capacity holding tank is situated approximately ten feet from the south wall of the radiochemistry building (building 343) for the retention of medium-level liquid wastes.
The contents of this tank will be periodically sampled for radioactivity by Health Physics personnel when the level reaches 850-950 gallons.
Ultimate Disposal Solid radioactive wastes and containers containing liquid wastes will ultimately be disposed of to a commercial firm through an inter-sorvice agreement between the Army and the NSWC.
Records will be maintained by the Health Physics Branch of the kinds, quantities, and dates of all radioactive disposals.
Contamination Limits:
Internal The Radioactivity Concentration Guides (RCGs), as recommended by the International Commission on Radiological Protection will serve as the Laboratory guide with respect to contamination internal to the body.
Surface The RCGs for surface contamination in radiation areas are listed below; Isotope Average Maximum Removable Alpha Emitters 500 d/ min -
1000 d/ min -
20 d/ min -
2 2
2 100 cm 100 cm 100 cm Beta-Gamma 0.2 mrad /hr 1.0 mrad /hr 200 d/ min -
at 1 cm at I cm 100 'cm2 Surface decontamination will be conducted when removable levels reach the amounts suggest_ed by the RCGs_above, or lower.
Air and Water' Decontamination I
The NSNC will comply with the[ requirements of 10 CFR 20, Appendix B, of the Nuclear Regulatory Commission with respect to air and water contamination limits.
" Driticality Precautions:
239F4 source with its containment has been deemed Although the Pu nuclear safe, the following additional precautions will be followed:
Experiments involving this special nuclear material will a.
be isolated from other such experiments.
To conform to the above, no other special nuclear material will be used or stored in these facilities (Environmental Laboratory, building 71; or room 141, building 70) during use or storage of this source.
A buffer distance of at least 12 feet will be required between other possible neutron sources within other areas of buildings 70 and 71.
b.
The basic configuration of the source shall not be altered in any way during use.
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Special precautions are required to assure that the inadvertent accumulation of a sufficient quantity of special nuclear materials (U233, U235, Pu239, or other fissionable material) necessary to create a critical mass with an attendant nuclear chain reaction will not happen.
Requirements are as follows:
Unsealed Quantities of Special Nuclear Material One " unit" is defined as 250 grams of any unsealed special nuclear l
material.
No more than one unit may be used in a room at any time.
No quantities of unsealed special nuclear material greater than one gram may be used in rooms adjacent to a room where one unit is being used.
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The Health Physics Branch must be notified in advance before gram quantities of unsealed special nuclear material may be moved from any room.
Quantities of special nuclear material greater than one gram not in use shall be l
l stored under the care of the Health Physics Branch in building 321.
I Because of the above precautions, an exemption is requested from the i
l' Code of Federal Regulations (10 CFR), part 70.24. l
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Scaled Sources The " sealed source" configuration must meet the criteria established in TID-7016, " Nuclear Safety Guide", for subcriticality by virtue of quantity, size, volume of dimension before procurement or use in the laboratory.
In addition, the basic configuration of the sealed source shall not be altered in any way during use.
Additional quantities of special nuclear materials shall not be used or stored in the same or in adjacent rooms.
Dccontamination:
Area Decontamination Decontamirstion of a work area shall be done by personnel normally using the space or by the Public Works Department personnel, depending upon the type of effort required.
Health Physics personnel shall perform all necessary monitoring surveys, make recommendations for decontamination procedures and arrange for participation of other personnel, as necessary.
Equipment Decontamination For uncontrolled use it is mandatory that all equipment be decontaminated to final or standard clearance levels as shown above for alpha emitters.
Arrangements for equipment decontamination shall be made in accordance with controlled maintenance work as described above.
Personnel Decontamination First wash thoroughly with soap and water after working with radio-
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active materials.
General decontamination methods have been fairly _
successful and these are incorporated in the procedure which is posted
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in each skin contamination kit.
These kits art available from the Health.
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Physics Branch.
They are obtained by non-contaminated personnel or before operations start, as spelled out in the appropriate SOP.
The Health Physics Branch must be contacted whenever personal cor Tamination
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has not been completely removed by washing with soap and water.
In any work situation where removable radioactive material levels are above background gloves and lab coats shall be worn and are removed
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before leaving the laboratory.
Personal clothing that has become contaminated must be removed and then decontaminated.
In no case will
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contaminated clothing be worn away from the Laboratory.
The Health
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Physics Branch will be advised of all instances of personal contamination
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l and will recommend corrective action.
Lesk Testing Procedures:
All sealed sources will be leak tested by the Health Physics Branch three-month intervals in accordance with 10 CFR, part 70.
at Techniques Employed Filter paper wetted with alcohol (or other suitable solvent), or dry, will be rubbed over the source or the appropriately accessible surface of the storage container.
Cotton-tipped wooden applicator swabs, either wet or dry, will be t
l rubbed over the source or the appropriately accessible surface of the storage container.
f Counting Methods Each wipe or specimen will be counted for alpha and beta-gamma in <
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equipment of sufficient sensitivity to perform the test.
If any leak test reveals the presence of removable radioactivity in excess of ten percent of the limit of 0.005 microcuries (i.e.,.
5 x 10-4 microcuries), the source shall be immediately withdrawn from use and will be decontaminated or disposed of according to regulations.
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The NRC will be notified within five days of any leakage in excess of 0.005 microcuries.
Monitoring:
In order tc assure that adequate safety procadures are being followed in experiments with radioactive materials, the use is checked by Health Physics personnel.
Monitoring consists of surveys for radia-tion and contamination levels with portable radiation detection instruments and by the swiping of working areas for evidence of removable activity.
Air sampling is also conducted if there is a possibility of air-borne activity.
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Routine monitoring programs are conducted in spaces where radio-active materials are used and stored.
Areas immediately surrounding these spaces shall also be surveyed to determine any egress of radio-f active materials, i
Procedures for Issuance and Processing of Film Badges:
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1.
Film badges (gamma and neutron) are furnished on a routine monthly
. frequency by the Health Physics Branch to individuals designated by
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their supervisors as persons working in areas where ionizing radia-tion producing sources are used and/or stored.
The film badge used at NSWC-WOL is a stainless steel and cadmium, multi-filtered film
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holder which contains a two-film packet with a sensitivity range 1
of 1 x 10-2 Rem to 1 x 10 Rem beta-gamma and x-ray and 1 Rem to
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\\ 1 x 10 Rem gamma and x-ray.
A neutron film is inserted in the 3
\\film badge for those individuals who work with and/or around low,
1 level neutrons; its range is from 3 x 10-2 Rem to 1 x 10 Rem.
These badges are read and evaluated on a monthly basis.
Persons 1:orking in areas of neutron exposure are provided special TLD badges that are read and evaluated on a six-week frequency.
Each film badge is dated to show the period covered.
2.
The Radiological Safety Officer reviews all film badge reports ind checks for any high or unusual results (50 m-Rem when previous exposures in the same area were lower).
The individual involved and his supervisor will be informed of film badge findings.
If high and/or unusual radiation exposure is revealed, the individual and his/her supervisor are informed immediately of the film badge findings.
Health Physics Branch then conducts an investigation to determine the cause of the exposure and the necessary precautions to prevent a reoccurrence.
3 3.
If the exposure level exceeds.5 Rem, the individual shall be i'
referred to the WOL Medical Depar,tment for medical examination.
This is required by NAVMED P-5055.
4.
Personnel working in high radiation areas and/or any other place that a person could receive a whole body exposure of 100 mr/hr are required to wear two pocket dosimeters, in addition to film badges.
5.
Each individual working with neutron emitting sources will be issued a lithium fluoride thermoluminescent dosimeter (LIF TLD).
The range 5
of the LIF TLD is 00.005 to 1 x 10 Rem for gamma radiation and 5 Rem for neutron radiation.
The processing of 00.030 to 1 x 10 the LIF TLD is the same as for the regular film badges.
Special Requirements Governing the Purchasing, Receiving, and Shipping j
of Radioactive Material:
i All purchasing, shipping, and receiving shall be done in compliance
{
with the regulations of NRC and DOT.,
Radiation Safety Training:
New employees and students are given radiation safety training by the Radiation Safety Officer prior to use of licensed material.
All radiation safety training is documented and filed in the Health Physics Branch.
Training films and lectures are used to highlight specific
- areas of interest.
Basic fundamentals of health physics such as the use of portable instruments for radiological surveys, standardization and calibration of fixed instruments, sample preparation, and_ leak testing are stressed.
Training in mathematics is necessary to enable the employee to calculate source decay, the amount of radioactive material (in curies) in leak test samples, air samples, water samples, and wipe samples.
Retraining will be conducted as special occasions arise.
Radiological safety and health physics training for Health Physics I
personnel is provided by the Navy Nuclear Power Unit, Port Hueneme, California; Department of Health and Human Services,. 0ak Ridge National Laboratory; private and other Governmental training facilities.
The NSWC provides excellent self-development for its employees.
This training and retraining is offered on a regular basis and is open to all Health Physics personnel.
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Emergency Action:
In the event of an emergency such as' source positioner jamming, container hang-up, fire in room involving the source (s), or loss of power, the following immediate action must be taken:
a.
Evacuate all personnel from the immediate area to an area in which the radiation levels are less than two milli-roetgen per hour (mR/hr).
b.
Secure area and post a guard to prevent unauthorized entry.
Erect a sign stating the nature of the hazard and the operator's name and extension.
c.
Contact the RSO immedt.ately and other appropriate personnel as the situation deems necessary (i.e., fire department, WOL guard, safety office).
ALARA Concept; When procedures are reviewed by the Radiation Safety Committee, the evaluation shall include a consideration that the procedure meet a commit-ment to reduce radiation exposures to as low as reasonably achievable.
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Appendix A RSO RESUME 6
8 6
RESUME Name:
William C. Cobbin Position:
Health Physicist Date of Birth:
19 August 1922 Education:
Fisk University - 1946-1949 Oakland City College - 1960-1963(A.A.)
Professional Experience:
9/80 - Present:
Head, Health Physics Branch, Safety Division, Comand Support
-Department, Naval Surface Weapons Center, White Oak Laboratory, Silver Spring, Maryland, and Radiation Safety Officer. Has primary resconsibility for radiation safety control at the White Oak Laboratory (WOL). Maintains inventories of all radioactive materials within WOL ' inclusive of byproduct, special nuclear, and source materials. Has overall responsibility for the WOL radio-logical safety program. Provides consultation and advice regarding the implementation of controls for the hazards associated with radiation sources and the effectiveness of these measures. Directly responsible for adequate and effective controls which prevent spread of contamination and for decontamination techniques and procedures. Duties and responsibilities include the following:
(1) serves as WOL liaison officer with the Nuclear Regulatory Comission (NRC); (2) maintains control of procurement and disposal of licensed material; (3) develops and maintains up-to-date operating and emergency procedures; (4) establishes and maintains a personnel monitoring program; (5) procures and maintains radiation survey instruments; (6) establishes, conducts, or chooses instructors for the training of Health Physics personnel, users, and others concerned with handling radioactive materials; (7) establishes and maintains storage facilitics; (8) maintains exposure devices and associated equipment; (9) establishes and maintains the leak testing program; (10) establishes and maintains the internal inspection system; (11) perfonns source replacement and source tagging operations; (12) conducts quarterly inventories and maintains utilization logs; (13) establishes and maintains a survey instrument calibration program; (14) establishes and maintains WOL's record-keeping system; (15) reviews and ensures maintenance of those records kept by others; (16) assumes control and institutas corrective action in emergency situations; and (17) investigates the cause of incidents and determines necessary preventative action.
11/79 - 9/80:
Health Physics Ionizing Radiation Safety Section, WOL. Duties and responsibilities consisted of general Health Physics support of NRC licenses held by WOL. Also provided support and consultation to users of radioactive materials as well as other ionizing radiation producing sources.
Developed and implemented a non-ionizing radia-tion safety program for WOL. Initiated an intensive training program including courses and workshops in Laser-Microwave Radiation Safety and Industrial Hygiene. Established long-range training goals for development in the area of non-ionizing radiation safety.
11/76 - 11/79:
Laser Safety Officer, Non-Ionizing Radiation Safety Section, WOL.
Developed and implemented a laser safety program for WOL consisting of inventorying, classifying, and labeling all lasers; determining risk category for employees potentially exposed to laser radia-tion; providing warning and/or caution signs and labels; conducting inspections; investigations of laser operations; and providing consultation to WOL laser users. Established eye safety program (medical surveillance) and procured the necessary eye examining equipment for WOL and the Dahlgren Laboratory to carry out the examinations as prescribed by the American National Standard for the Safe Use of Lasers.
8/69 - 11/76:
Health Physics Section, WOL. Responsible for radiation safety control at WOL. Maintained inventories of all rcdioactive materials within WOL. Responsible for the WOL radiological safety program. Provided consultation and advice regarding the implementa-tion of controls for the hazards associated with radiation sources and the effectiveness of these measures. Responsible for adequate and effective controls which prevent spread of contamination and for decontamination techniques and procedures.
6/66 - 8/69:
Health Physicist, Radiation Division, Physical Science Division, and the Nuclear Technology Division, U.S. Naval Radiological Defense Laboratory, San Francisco, California. Provided field operational health physics support to laboratory programs and to outside military activities.
3/57 - 6/66:
Investigator, Nuclear Technology Division, Technical Development Branch, U.S. Naval Radiological Defense Laboratory. Conducted experiments and participated in field-type expermental projects.
Planned and directed the experimental approach; data reductic.n; report writing; installing; operating and maintaining data collec-tion systems; fallout dispersal systems and reclamation equipment in the field.
I 1 l l
s WILLIAM C. COBBIN TRAINING Type of Training Where Trained Duration On-the-Job A
U.0'. Naval Radiological Defense Laboratory 1957-69 Yes San Francisco, CA B
White Oak Laboratory, Naval Surface Waapons Center,.
1969-Present Yes Silver Spring, MD Fundamentals of Non-Ionizing Radiation Protection 7/11/75 No (Government) SAT - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Industrial Hygiene for the Safety Professional 1/19/77 No (Non-Governmer.t) SAT - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i
General Safety Refresher Training 4/20/77 No (Government) SAT - 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Laser Safety (Non-Government) SAT - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 5/27/77 No h
Laser-Microwave Hazards Workshop 8/26/77 No (Government) SAT - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Safety Progranning "How to Do It" Safety Seminar 11/30/77 No (Non-Government) SAT - 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> Nuclea-Weapons Orientation Advanced Course 7/73 No (Government) SAT - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> CID Seminar Management, Optical Radiation Measurement 10/20/78 No (Non-Government)
High Energy Laser System Design (Government) 11/3/78 No SAT - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Seminar Moderate Disposal Lasers 10/78 No (Government)-8 hours
' WILLIAM C. COBBIN TRAINING (Centinued)
Type of Training Where Trained Duration On-the-Job Navy Occupational llealth Workshop 12/15/78 No
.(Government) - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Fundamentals of Non-Ionizing Radiation Protection 6/7/71 (Government) - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Laser Safet Training Workshop 9/20/79 (Government - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Member of FADCON Team 1972-75 i
Nuclear Wea ons Orientation Advanced Course 5/7/71 (Government 4
Fundamentals of Ionizing Radiation 6/70 (Government) - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> E
Radiation Safety Officers Refresher Course 2/1/80 (Government) SAT - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i
Radiation Protection Technology Home Study Course -
In Progress 4
4
]
i e
1
.i WILLIAM C. COBBIN RADIOACTIVE MATERIAL USED AND/0R HANDLED Maximum Duration of Type of Isotooe Amount Where Experience Gained Experience Use U235 10 Mci NRDL, San Francisco, CA 1957 -
R&D*
Pu233 760 gm NRDL, San Francisco, CA 1966-69 HP**
Pu233 10 Mci NRDL, San Francisco, CA 1966-69
_HP**
Co '
15000 ci NRDL, San Francisco, CA 1966-69 HP**
6 Np237 10 Mci NRDL, San Francisco, CA 1966-69 HP**
Csl37 120 ci NRDL, San Francisco, CA 1966-69 HP**
Mg 10 Mc ci NRDL, San Francisco, CA 1966-69 HP**
24 Lal43 100 ci NRDL, San Francisco, CA 1957-69 R&D-l Bal'- 3 100 ci NRDL, San Francisco, CA 1957-69 R&D Cd103 10 mc ci NRDL, San Francisco, CA 1957-69 R&D 10 mc ci NRDL, San Francisco, CA 1957-69 R&D I129 Sr '
10 mc ci NRDL, San Francisco, CA 1957-69 R&D 3
3 I 31 10 mc cf NRDL, San Francisco, CA 1957-69 R&D l
Aulii 10 ci NRDL, San Francisco, CA 1957-69 R&D Cdll5 10 mc ci NRDL, San Francisco, CA 1957-69 R&D Am:-l 2 ci NRDL, San Francisco, CA 1966-69 R&D l
Cm "
10 mc ci NRDL, San Francisco, CA 1966-69 R&D
(
2 H3 19 ci NRDL, San Francisco, CA 1966-69 R&D Co33 2000 ci NSWC, Silver Spring, MD 1979 HP Cf252 10 mc NRDL, San Francisco, CA 1966-69 HP j
Cf252 10 mc NSWC, Silver Spring, MD 1969-81 HP Tc ?
10 mc NSWC, Silver Spring, MD 1957-81 R&D 9
ThlI3 10 mc ci NSWC, Silver Spring, MD 1957-81 R&D l --- --
' WILf.IAM C. COB 8IN RADIOACTIVE MATERIAL USED AND/0R HANDLED (Continued)
Maximum Duration of Type of Isotope _
Amount Where Experience Gained Experience Use Sr35 10 ci NSWC, Silver Spring, MD 1957-81 R&D Hg :23 100 mc NSWC, Silver Spring, MD 1966-81 ~
HP Pb210 10 mc NSWC, Silver Spring, MD 1966-81 HP Y90 10 mc NSWC, Silver Spring, MD 1957-69 R&D i
~
Sb zs 50 ci NSWC, Silver Spring, MD 1966-69
~
HP Sra9-90 10 mc NSWC, Silver Spring, MD 1957-69 R&D Zr95 1G mc NSWC, Silver Spring, MD 1957-69 R&D Nb95 10 cc NSWC, Silver Spring, MD 1957-69 R&D Lu176 20 ci NSWC, Silver Spring, MD
,1957-69 R&D Ra22s 25 me NSWC, Sf1ver Spring, MD 1957-69 HP
~
C14 100 mc NSWC, Silver Spring, MD 1957-69 HP Cf252 50 uci NSWC, Silver Spring, MD 1974-81 HP
HP Pml47 100 mei NSWC, Silver Spring, MD 1966-81 HP Csl37 130 ci NSWC, Silver Spring,MD 1966-81 HP Cd103 1 mci NSWC, Silver Spring, MD 1966-81 HP Coss 100 uci NSWC, Silver Spring, MD 1966-81 HP CoS7 100 uci NSWC, Silver Spring, MD 1966-81 HP' Pu239be 5 cf NSWC, Silver Spring, MD 1966-81 HP Krss 4 mei NSWC, Silver Spring, MD 1966-81 HP Na22 100 uci NSWC, Silver Spring, MD 1966-81 HP Na24 100 uci NSWC, Gilver Spring, MD 1966-81 HP -.
I WILLIAM C. COBBIN RADI0 ACTIVE MATERIAL USED AND/0R HANDLED (Continued)
Maximum Duration of Type of Isotope Amount Where Experience Gained Experience Use Mg55 100 uci NSWC, Silver Spring, MD 1966-81 HP A12s 100 uci NSWC, Silver Spring, MD 1966-81 HP Mn
Fe55 100 uci NSWC, Silver Spring, MD 1966-81 HP fos 3 100 uci NSWC, Silver Spring, MD 1966-81 HP Agi13 100 met NSWC, Silver Spring, MD 1966-81 HP Nb3" 100 uci NSWC, Silver Spring, MD 1966-81 HP Zr35 100 uci NSWC, Silver Spring, MD 1966-81 HP Rulos 100 uci NSWC, Silver Spring, MD 1966-81 HP Ni63 5 met NSWC, Silver Spring, MD 1966-81 HP Snll3 1 met NSWC, Silver Spring, MD 1966-81 HP Crs2 10 mei NSWC, Silver Spring, MD 1966-81 HP Ca45 10 mci NSWC, Silver Spring, MD 1966-81 HP Mixed 10 ci G.E. Vallecitos Reactor 1966-69 HP Fission Aerojet-General Reactor 1966-69 HP Products Research and Development Health Physics 4
Appendix B RADIOLOGICAL SAFETY MANUAL t
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18S20 I
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NOL' INSTRUCTION P5100.5A SAFETY MANUAL j'?
A i
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SAFETY MANUAL
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1 PART 1:. IONIZING. RADIATION d...,-
,+i NAVAL ORDN ANCE LABOR ATORY
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.i WHITE O AK, SILVER SPRING, MARYLAND c
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a r.
LY PART I:
IONIZING RA7IATION INTRODUCTION 9
1.
PURPOSE These procedures are intended to serve as a guide for Laboratory personnel engaged in operations involving the use of radioactive materials and other radiation producing' devices.
It also provides information on the activities and responsi-bilities of the Health Physics Division, the Medical Officer, and the Radiation Safety Committee, as they relate to the Laboratory Radiological Safety Program.
2.
POLICY The nob Radiological Safety Committee is responsible for reviewing and approving radiaticn safety policies of the Laboratory.
Primary responsibility for radiation safety control at
- NOL is assigned to the Chief, Health Physics Livision.
Fealth Physics is also responsible for directing and imple-menting nuclear policies and procedures approved by the Committee.
Laboratory policies governing the possession and use of-licensable nuclear materials are commensurate with the Atomic Energy Commission regulations.
It is the joint responsibil-ities of management, supervision and users of radioactive materials to comply with these regulations.
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E._
9 O
,9 CONTENTS-Page
)p; I.
1NTRODUCTICN.......................................
1 A.
Radiological Safety............................
1 B.
External Guides................................
1
(
b II.
EDIOLOGICAL SAFIrY ORGANIZATIONS AND RISPONSIBILITIES...................................
1 A.
Health Physics Division........................
1 D
f B.
Me di c al O f f i ce r................................
2 C.
Radiological Safety Committee..................
3 i%
III.
RADIATION SA?ErY PRACTICES.........................
4 A.
Accountability and Control.....................
4 B.
Collection and Disposal of Radioactive Wastes..
4 1.
Solid Wastes...............................
5 2.
Liquid Wastes..............................
5 3.
Ultimate Disposal..........................
5 C.
Contamin ation Limits...........................
5 1.
Internal...................................
5 2.
Surface....................................
5 3.
Air and Water Contamination................
6 D.
Criticality Precautions........................
6 1.
Unsealed Quantities of Special Nuclear Material...................................
6 2.
Sealed Sources.............................
6 E.
De contamin ation................................
7 1.
Area Decontamination.......................
7 2.
Equipment Decontamination..................
7 Personnel Decontamination..................
7 F.
Emergency Procedures...........................
8 G.
Environmental Monitoring.......................
8 1.
Routine Monitoring.........................
8 2.
Special Monitoring..........................
9 H.
Leak Tescing Procedures........................
9 1.
Techniques
- Employed........................
9 2.
Counting Methods...........................
10 I.
Maximum Permissible Exposure Limits............ 10 J.
Me dic al Examin ations........................... 11
~-7 1.
Radiological Health Examinations...........
11
[]l 2.
Radiological Accidents.....................
12 pp :
3.
Routine Urinalyses.........................
12 s) 4.
Spe cial Examinations....................... 12 5.
Visitors in Work Status....................
12 hi
[C!
K.
Monitoring Instruments.........................
13 1.
Dosimetric Devices.........................
13 2.
Film Badges................................
13 hh' l
3.
Pocket Ionizati on Chambers................. 13 Li i
C
CONTENTS Page L.
Personnel Monitoring...........................
14 g[~
1.
Radiation Received at NOL..................
14 a.
F ilm Badg e s....................... m 14 I
b.
Pocket Dosimeters......................
14 P#
2.
Individual Responsibility..................
15 3.
Visitors..................................
15 h
4.
Radiation Received Away from NOL...........
15 I
5.
Internal Contamination.....................
15 6.
Personnel Contamination....................
15 7.
Notification of Exposure...................
16 M.
Personal Protection............................
16 N.
P ro te ct ive Clo th ing............................
16 O.
Plutonium Safety Requirements..................
17 1.
Criticality................................
17 17 2.
Pyrcphoricity..............................
17 3.
Toxicity...................................
4.
Plutonium Storage and Fire Protection......
18 P.
Posting and Labeling...........................
18 Q.
Pro cure me nt Control............................
19 R.
Radiation Survey Procedures....................
20 S.
Relative Degrees of Radiation Hazards..........
21 23 T.
Remote Handling Equipment......................
23 U.
Special Warning Requirements...................
23 1.
Radiating Machine s.........................
23 2.
Sealed Sources.............................
3.
Contaminated Areas and Equipment...........
23 V.
Storing and Handling Radioactive Materials.....
24 W.
Tra ns f e r of Materi al...........................
25 X.
.Tr it ium S a f e gu ard s.............................
25 1.
Precautions................................
25 2.
Monitoring.................................
26 Y.
Work Performed After Regular Working Hours.....
26 Z.
Zone Precautionary Measures....................
27 1.
Zone Designations..........................
27 a.
Zone 1 - Radiation-Free Areas..........
27 b.
Zone 2 - Possible Contamination
[
Areas..................................
27 M
Ik c.
Zone 3 - Radiation Area................
27 b) l d.
Zone 4 - High Radiation Area...........
27 O
28 M
atoSsxRr................................................
tN Mn c.
iii l
e 4
m t.
.m Y
REFERETCES (a)
AEC Code of Federal Regulations, Title 10, Part 20, 7
" Standards for Protection Against Radiation."
(b)
NAVMED P-5055, Radiological Health Protection Manual.
h (c)
PCRACC, Vols I, II, III, Principles of Radiation and Contamination Control.
g (d)
TID-7016, Rev I, Nuclear Safety Guide, 1961.
(e)
Hazardous Materials Regulations of the Department of g
Transportation, Tariff No. 23, 1969.
g (f)
NOLINSTR PS100.5A, Safety Manual D
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RADIATION SAFETY L
~
I.
IN'"RODUCTION
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~
A.
Radiolocical Safety V
1.
The serious nature of radiation hazards requires I
that we observe most scrupulous precautions when working with
[
radioactive materials.
2.
No amount of radiation exposure should be incurred unless it is necessary and warranted.
Therefore, every indi-m-
vidual case of the use of ionizing radiation should be care-fully evaluated and used only if its use is considered more advisable than any other methods of investigation.
3.
Radiation will be confined at the source.
Pre-l cautions will be taken to ensure that utilization of radiation and radioactive sources do not jeopardize other experiments, operations or se -ivitie s.
4.
Although each individual must always be concerned and responsible for his own safety, supervisors at all echelons are directly responsible for the safety of all personnel and operations under their control.
B.
External Guides l
The Laboratory obtains and uses radioactive materials 1.
j under licenses granted by the U. S. Atomic Energy Commission (AEC).
Under these licenses, the Laboratory is subject to inspection and control requirements as outlined in the AEC l
Code of Federal Regulations, Title 10 (ref (a) ).
2.
Personnel working with radioactive materials must also comply with the requirements of NAVMED P-5055 (ref (b) ),
l and other cognizant Naval activities.
II. RADIOLCL,ICAL SAFETY O.EANIZATIONS AND RESPONSIBILITIES a
j A.
Health Physics Division The Health Physics Division is responsible for the b
overall bmplementation and supervision of the Laboratory's M
i l
Radiol ogical Safety Program.
Operating as a part of the f.'
Safety Department, the Division serves the entire Laboratory.
I Specifically, the functions of the Division are to:
((
I 1.
Interpret or modify existing radiological safety
(
regulations.
In addition, the Division will formulate new i
1 1
1
.V
radiological safety regulations for the safe handling, utili-g' zation and exposure to radiation, which will be submitted to
[
the Radiological Safety Committee for approval.
__W 2.
Provide consultative services to project leaders, q
scientists, investigators, technicians, and others, with 51 regard to safety in the care and use of radioactive material h
and radiation producing devices.
id 3.
Provide fihn dosimetry for all Laboratory per-gW sonnel and visitors who work with or near radiation sources.
Interpret and report results obtained from these devices and O'
forward them to the Medical Departreent for permanent filing.
4.
Review all requests for radioisotopes and irradiation services to assure that the proposals conform to licensing requirements.
5.
Maintain a central inventory of all radioactive end radiation producing equipment utilized in the Laboratory.
6.
Advise in the procurerent of special nuclear m'aterials.
7.
Provide advice in the planning for safe and legal disposal of radioactive waste and monitor actual operations.
8.
Measure and record the radiation levels and con-centrations of liquid and airborne radioactive materials being discharged within the L6boratory.
Periodic surveys in the 3
f orm of air and water samples are also performed to determine and con rol any release of radioactivity outside the confines of the Laboratory.
9.
Review and make reco=cendations on the rad-safe aspects of all new f acilities involving radiation machines or radioactive materials.
10.
Assis-in training and indoctrination of personnel in radiological safety.
11.
Perform evaluation and project development in the field of health physics for a sponsor.
This work should
~.
U be related to laboratory problems.
fj i-:
6L B.
Medical Officer wb The Medical Officer is responsible for the industrial 5.
health of Laboratory personnel.
Specifically, he performs the following functions related to radiological safety.
6
I-
~
l.
Reviews all instances of radiological exposure in excess of the permissible Ibnits (see Page 10) and pre-pares reports of such exposures for submission to the Bureau of Medicine and Surgery (EUMED).
2.
Investigates medical aspects of the radiological
[
safety program of the Laboratory.
E 3.
Conducts pre-employment and terminal physical examisations of all personnel who will be or have been exposed to radiation La their normal work function.
4.
Performs radiological. health examinations, as L*" -
required by NAVMED P-5055.
5.
Assists in the radiobiological assay program to i
determine possible internal exposure.
6.
Maintains records of personnel exposures and interpre tations.
7.
Compiles and interprets data from radioclinical laboratory analyses performed by the Health Physics Division.
He also recommends appropriate action as,. indicated.
C.
Radiolocical Safety Committee 1.
This Committee is responsible for performance of the following functions:
a.
Approve radiological safety policies and procedures for the, Laboratory.
b.
Review proposed procedures for operations, experiments, or tests involving 14diation and/or radioactive materials.
c.
Assist the Health Physics Division in the enforcement of radiation safety practices as set out in the NCL Radiological Safety Precedures.
sr-FI d.
Develop a criterion of evaluation for l
qualification of users of radioisotopes and other sources gf p
of ionizing radiation.
d C
e.
Approve or disapprove applications for senior users of radioactive materials.
f.
~ Consider and pass judgement on major equip-ment and f acility needs of the various users of radioactive materials at NOL.
3 I
e,
e
i-..
t c
n.
g.
Keep current on present and amended parts
?~
I of the Federal Regulations pertinent to the conduct of the radiation safety program.
h.
Maintain records of Committee action.
{
r; i.
Review plans for all new buildings and modification of existing structures where radioactive materials _
f are to be used.
M gations of radiological incidents and make appropriate j.
Serve as a reviewing committee for investi-igg ~
recommendations to management to include the Directorate, t'ae Technical Director and/or Commanding Officer.
2.
Membershio The membership of this Committee shall be as follows:
j a.
At least one member (or alternate) from each Department utilizing sources of radiation.
The Committee Chairman is selected from this group.
1 b.
The Radiological Safety Officer (represent-ing Health Physics).
Ex Officio Member and Recorder.
c.
The Medical Officer.
d.
Assistant for Nuclear Energy.
III.
RADIATION SAFETY PRACTICES i
A.
Accountability and Control The Health Physics Division maintains inventories of all radioactive materials within NOL.
Inventories are inclusive of byproducc, special nuclear, and souice materials.
J These materials are governed by the following regulations issued by the AEC:
Title 10 CFR Parts 20, 30 - 36, 40, and Es 70.
!T Health Physics is also responsible for accountability control over certain unlicensed materials.
These materials tj by include both ionizing and non-ionizing sources of radiation.
!!h It is mandatory that all authorized users infoon the Health
[y Physics Division with regard to the location and uses of such y) materials and equipment.
s_
B.
Collection and Discosal of Radioactive Wastes 4
- w 1.
Solid Westes-a.
1 Special waste containers with disposable liners p,
are provided by the Health Physics Division to the various ew Departments utilizing radioactive materials for the collect-E ion and temporary storage of low-level radioactive wastes.
d E
These recepticles are yellow in color and contain the magenta radiation symbol and the wording " Caution - Radioactive h
Materials."
The Health Physics Division is responsible for dC collecting the contents of these containers on a routine basis.
Collected wastes are then placed in storage under the fJ-direct supervision of Health Physics prior to ultimate dis-I'"-
posal to a commercial waste disposal company.
i 2.
Licuid Wastes Carboys will be provided to laboratories employing liquid radioisotopes for the collection and contain-ment of medium-level wastes.
These radioactive wastes will consist primarily of first-wash solutions.
Further washings of glassware will be restricted to certain designated sinks located in each of th9 laboratories using radioisotopes.
A r
1,000 gallon capacity holding tank will be situated approxi-mately 10 feet from the south wall of the Radiochemistry Building (Bldg. 343) for the retention of medium-level liquid wastes.
The contents of this tank will be periodically sampled for radioactivity by Health Physics personnel.
3.
Ultimate Discosal Solid radioactive wastes and carboys contain-ing liquid wastes will ultimately be disposed of to a commercial firm through an Interservice Agreement between the Army, Edgewood Arsenal and the Naval Ordnance Laboratory.
l Records will be maintained by the Health L
j Physics Division, of the kinds, quantities and dates of h
I measurement ~ of all radioactive collections and disposals.
fqi C.
Contamination Limits
- 1 L3 1.
Internal The Radioactivity Concentration Guides (RCG 8 s) b as recommended by the International Commission on Radiological h:
Protection will serve as the laboratory guide with respect (A
l to contamination internal to the body.
{j I
L j
2.
Surface f
The RCG's for surface contamination in radiation areas (see Section Y) are listed as follows:
l 5
i l
- w. en e.
- * =
e
l-Isotooe Averace Maximum Removab1_e.
g I-Alpha Emitters 500 d/ min -
1,000 d/ min -
20 d/ min -
L.
E hy 100 cm2 100 cm2 100 cm 5
Beta Gamma O.2 mrad /hr 1.0 mrad /hr 200 d/ min -
b at 1 cm at 1 cm 100 cm2 y
(For tritium, the removable limit is 10,000 d/ min - 100 cm,)
[
2 If any of the above maximum or removable values are exceeded, L:
b immediate action will be taken to isolate, contain and/or de-contaminate the area or personnel involved.
3.
Air and Water Contamination o
The Laboratory will comply with the requirements of 10 CFR 20, Appendix B, of the U. S. Atomic Energy Commission
~
with respect to air and water contamination limits.
D.
Criticality Precautions Special precautions are required to assure that the inadvertent accumulation g a sufficient quantity of special nuclear materials (U2
,U23S, Pu239, or other fission-able material) necessary to create a critical mass with an attendant nuclear chain reaction won't happen.
Requirements are as follows:
1.
Unsealed Guantities of Special Nuclear Material One "unita is defined as 250 grams of any unsealed special nuclear material.
No more than one unit may l
be used in a room at any time.
No quantities of unsealed special nuclear material greater than one gram may be used in rooms adjacent to a room '.(nere one unit is being used.
The Health Physics Division must be notified in advance before l
. gram quantities of unsealed special nuclear material may be y{i moved from any room.
Cuentities of special nuclear material greater than one gram not in use should be stored under the care of the Health Physics Division.
cr l
2.
Sealed Sources
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The " sealed source" configuration must meet pi l
the criteria established in TID-7016, " Nuclear Safety Guide,a
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(ref (d)), for subcriticality by virtue of quantity, size,
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e volume or dimension before procurement or use in the labora-l tory.
In addition, the basic configuration of the sealed source shall not be altered in any way during use.
Additional e
quantities of special nuclear materials shall not be used or h
stored in the sare or in adjacent rooms.
gje E
E.
De contamination g
v 1.
Aree Decontamination E
Decontamination of a work area shall be done by k
i personnel normally using the space or by the Public Works Department personnel, depending upon the type of effort required.
Health Physics personnel will perform all necessary monitoring surveys, make recommendations for decontamination procedures and arrange for participation of other personnel, as necessary.
2.
Ecuiement Decontamination Equipment used in the laboratory or on field
$I operations may become contaminated to the extent that radio-logical controls are required prior to further use or storage.
For uncontrolled use, it is mandatory that all equipment be decontaminated to final or standard clearance levels given in section C.
Arrangements for equipment decontamination shall i
be made in accordance with controlled maintenance work as described above.
3.
Personnel Decontamination There is no completely standardized system for skin decontamination.
However, certain general methods have been f airly successful and these are incorporated in the pro _.
cedure which is posted in each skin decontamination kit.
These kits are available from the Health Physics Division.
[
They should.be obtained by non-contaminated personnel or I
before operations start as spelled out in the appropriate Standard Operating Procedure (SOP).
The Health Physics 7
Division must be contacted whenever personal contamination l
has not been completely removed by washing with soap and F
l water.
h
~
N Personal clothing that has become contaminated W
must be removed and then decontaminated.
In no case will Ej contaminated clothing be worn away from the Laboratory.
The b
Eealth Physics Division will be advised of all instances of personal contamination and will recommend corrective action.
l l
I 1
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F.
Emercency Procedures A radiation incident could occur in spite of our f__
best ef forts to safeguard the use of radioactive materials.
Er-The incident may be in the form of a spilled radioactive g
liquid sample, a crushed radioactive solid source or a leak-ts ing radioactive sealed source.
There could also be a fire or explosive incident involving radioactive sources.
In the event of any of the above, there is a strong possibility that this interaction would create airborne material, In the g
event of such an occurrence the following procedures are to be followed:
1.
Withdraw to a safe distance from the affected area and restrict the area as much as possible.
[
2.
If possible, turn off air conditioning, hoods, j
fans, close windows and lock doors.
]
3.
Notify the Health Physics Division of your location and conditions.
Telephone 495-7780.
4.
If a radiation survey instrument is immediately available monitor self for personal contamination.
In any case, do not leave the immediate area until determined free of contamination.
1 5.
Summarize the situation as briefly as possible to the health physicist upon his arrival.
The Health Physics Division should be contacted immediately in the event of a lost or misplaced source of radiation.
G.
Environmental Monitorinc l
1.
Routine Monitorinq A periodic monitoring program will be conducted l
of alb potentially hazardous radioactive areas by the Health fj{
F t
)
Physics Division.
This will include ceasurement of radiation Eg Division will evaluate the situation and recommend corrective (e) l levels, and samplings of effluents being discharged to the public sewer system and to the air.
The Health Physics 2
action commensurate with the degree of hazard.
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2.
Soecial Monitorinc
~
Special monitoring surveys will be made by the p
Health Physics Division when it is deemed advisable, such as r
for the following-y a.
When radiological clearance of equipment or E
areas is desired.
b.
To determine contamination levels after S
decontamination operations.
I c.
To determine radiation and contamination levels in connection with specific experiments or operations.
(
d.
For issue of Special Work Permits.
~
e.
When new equipment or building alterations I.
might change existing radiation dose contours.
Results of these surveys shall be recorded and permanent records made of all significant findings.
The Health Physics Division will evaluate the situation and recommend corrective action.
H.
Leak Testina Procedures All sealed sources will be leak tested at approxi-mate intervals (i.e., six months for sealed byproduct materials sources; three months for sealed special nuclear (neutron) sources by the Health Physics Division.
1.
Te.ai @es E:noloved Filter paper wetted with alcohol (or other suit-able solvent) or dry, will be rubbed over the source or the appropriately accessible surf ace of the storage container.
Cotton tipped wooden applicator swabs, either l
wet or dry, will be rubbed over the source or the appropri-
[F
.] l l
ately accessible surface of the storage container.
l G!
The actual manipulation of the test media will JP be with suitable equipment (tongs, etc.) and any necessary d
portable shielding as required to keep personnel exposure D
within the limits prescribed in Title 10, Code of Federal 3
Regulations.
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2.
Countina Methods 3
Each wipe or specimen will be counted for alpha f_.
and beta-gamma in equipment of sufficient sensitivity to ny 5
perform the test.
h If any leak test reveals the presence of removable E
radioactivity in excess of 10% of the limit of.005 microcuries US (i.e.,
5 x 10-4 xCi) the source shall be immediately withdrawn g
from use and will be decontaminated or disposed of according E
to regulations.
The AEC will be notified within five days of
~
any leakage in excess of.005 xC1.
I.
Maximum Permissible Excosure Limits i
Title 10 CFR 20 sets forth the maximum permissible E
levels of radiation that an individual may receive per calendar quarter.
This section of the regulations also limits the amount of cumulative radiation which an individual may re-ceive.
The amount of radiation per calendar quarter Which an individual may receive is as follows:
1.
Whole body, head and trunk, active blood-forming organs, lens of eyes, or gonads - 1 1/4 rems.
2.
Hands and forearms, feet and ankles - 18 3/4 rems.
3.
Skin of whole body - 7 1/2 rems.
1 Generally, for practical purposes, we are mainly l
concernod with radiation exposure Which an individual may receive from a hole body exposure.
It should be noted that a person may receive 15 times as much radiation at the extremities of the body due to the fact that there are no essential body organs in these areas.
It should also be noted that the skin of the Whole body may receive six times as much radiation as the Whole body.
For our purposes at l
the Laboratory we shall base all our readings on Whole body 4[
exposure and therefore, lunit our exposures to the absolute minimum.
gi Individuals may receive 1250 mrem exposure to the 6
whole body per calendar quarter.
If the individual has a p) reserve bank of radiation he may receive up to 3000 mrem in a p(.
calendar quarter as long as at no time does the individual exceed the maximum permissible limit as determined by the E
equation (5 (N(age) -18) rems.
For example, if an individual
{
is 19 years of age and has had no previous radiation history eI he or she would have a reserve bank of radiation.
In this case the reserve bank determined by the equation would 10 o
t
~
I be as follows:
5(19 -18) 5 rems.
It should be apparent from this equation that individuals 18 years of age and under L
have no reserve bank of radiation.
(,
w k(G Also, Section 20.101 limits the exposure of minors (18 years,of age and under) to 1/10 the amount of radiation which an adult may receive.
The basic reasons for limiting the exposure of minors to radiation are threefold.
fr 9
1.
Youth is still in the formative stages of i
physical development and therefore radiation damage must be avoided.
D.
1m_
Radiation must be controlled at an early age in consideration of the maximum cumulative lifetime exposure limita'. ions.
3.
The possibility of radiation mutation effects on the population as a whole must be controlled, particularly d'.tring the formative period.
h J.
Medical Examinations The Medical Department shall maintain a record of radiation dosages received by all individuals working with radioactive materials (Record of Exposure to Ionizing Radi-ation, NAVMED 143 2, (ref (b) ).
The records will be reviewed at regular intervals by the Medical Officer to ensure that examinations and analyses are performed as indicated below.
i l
1.
Radiolacical Health Examinations Special examinations are given by the Medical l
Officer to employees who may be exposed to radiation:
Upon entering employment and on termination l
a.
of employment.
b.
In 'fi' eld operations involving the use of y
radioactive materials.
55 Employees involved in radiation incidents,
- ?
and in other situations deemed appropriate.
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l 2.
Radiological Accidents h
A radiological accident is a spillage of radio-active material or any contaminating event in which there is F
a possibility of assimilation of radioactive material into the body.
Each person, whether employed by NOL or not, who F
is involved in a radiological accident on NOL premises or at an NOL administered field operation shall submit to a radio-logical health examination.
3.
Routine Urinalyses Routine urine samples, as ordered by the Medical officer, will be taken annually from personnel using radio-active materials in their normal duties, and from personnel working in areas where such materials are used routinely.
h Special sampling shall be done at frequent intervals for personnel using unsealed quantities of tritium or plutonium.
4.
Scecial Examinations
[
The Medical Officer will perform.special exam-inations, as indicated below:
Any employee possibly exposed to radiation a.
who develops an acute, unexplained illness of more than three days duration.
b.
Any person who has received an acute radi-ation exposure (from any source) in excess of 25 rem, or a chronic radiation exposure (from any source) of 75 rem if accumulated within a period of less than five years.
c.
Where a person is expected to be exposed to significant neutron, or high energy electron radiation, a special eye examination shall be conducted prior to assign-ment of such duty, semiannually, and upon termination of employment.
5.
Visitors in Work Status
{
Medical examinations may be required for visitors Kt.
subject to occupational exposure to radiation while within
$Y NOL jurisdiction.
Work status visitors may include military hj personnel from other installations, contractor personnel, gj students, or others.
Furthermore, any individual working th four successive weeks or more in laboratory areas where
{3 exposure to ionizing radiation is possible shall undergo gt, radiological health examinations.
12 e
1,
'e K.
Monitorinc Instruments Monitoring instruments are essential tools in the radiological safety program.
It is necessary to maintain a Ar-variety of types of monitoring equipment 'in order to measure the different energies and levels of radiation involved.
The Health Physics Division is responsible for the calibration of all portable instruments.
There are a number of fixed instal-
[
lation instruments in the laboratory (such as continuous air r
I monitors, laboratory-type counters, etc.) as well as a supply of portable instruments.
Authorized users of radioactive producing materials may obtain instruments from the Coordinator of RADIAC 3;uip-me nt, Code 916, NOL.
Representatives from the Health Physics Division will aid and advise in the use of radiation instru-ments as required.
1.
Dosimetric Devices Dosimetric devices include all types of instru-mentation used to measure the accumulated radiation dose received by the individual.
These devices are worn for stated intervals and then processed to determine accumulated radi-ation dose received by the individual.
The doses are recorded and constitute the individual's official dose record.
The amount of allowable exposure is based on dose records.
Two types of personnel dosimeters are used at NOL:
film badges and pocket ionization chambers.
Film badges are provided to all radiation workers by the Health Physics Division.
Pocket chambers are also available through Health Physics for use in high radiacion areas.
2.
Film Bedces f
The badge employed at NOL is a stainless steel l
and cadmium multifiltered film holder which contains a two-film packet (10 mrem to 10 Rem and 1 Rem to 1,000 Rem).
A separate film, also inserted into the holder must be worn by
' ~ ~
all those personnel who work with neutron sources.
F 3.
Pocket Ionization Chambers l
Pocket chambers are used to supplement film badges 1
in certain designated radiation areas, since they provide an 13
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While immediate indication of the accumulated dose received.
the chamber is used for dose control during a specific part 5
of an operation or experiment,.the film badge reading is 4
accepted to be the actual amount of radiation received and will cy Self-reading be retained as a permanent record of exposure.
3 dosimeters must be worn by all personnel present in high radi-ation areas (Zone 4).
~
L.
Personnel Monitorinq The NOL Losimetry Program is conducted in accordanca with regulations established by the Radiological Health Pro-A.
tection Manual (NAVMID P-5055), reference (b), and the AEC for the protection of persons exposed to ionizing radiation.
A complete record of exposures received at the Laboratory or elsewhere shall be main:ained by the Medical Departrent for
.L each person.
The completeness and validity of such a record is dependent upon the cooperation of each individual in wearing his badge properly during the work day and in reporting any unusual circumstances or doses received outside of his regular employment.
Paragraphs (1) through (7) inclusive outline the p
procedures to be followed by the individual who may be exposed
~
to radiation at NOL.
l.
Radiation Received at NOL All persons who work with radioactive material or radiating sources shall be monitored with one or more of the following types of dosimeters:
a.
Film Badces The issue and collection of radiation dosimetry i
badges to individual users is the responsibility of the Health Physics Division.
All significant exposures will be investi-gated, whether or not the recommended limits have been exceeded.
b.
Pocket Dosimeters Personnel working in Zone 4 areas (High Radi-T ation Area) and/or any other place that a person could receive k
a whole body exposure of 100 mr/hr are required to wear two pocket dosimeters in addition to film badges.
Users must Eg check dosimeters frequently, and if a significant reading
)b:
is indicated, the film badge will be processed immediately to substantiate the chamber reading.
p N
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l 14 m.
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2.
Individual Resconsibility 3
sach individual who is involved with ionizing jL.
radiation shall wear his film badge on the chest or collar d-at all times while in the radiation area.
If a badge is-Q inadvertently left in a radiation field, the individual shall k
notify the Health Physics Division of the circumstances related to the exposure.
Film badges should not be carried away from E.1 NOL.
Employees are specifically cautioned not to wear them Q
when receiving r..adical x-ray or radioisotope diagnostic exami-
{
nation and/or treatment.
- ~
3.
Visitors All visitors to facilities utilizing radiation sources, including contractors and their employees, must wear film badges.
Personnel should not wear film badges for more than one activity except by prior arrangement with the Health Physics Division.
4.
Radiation Received Away from NOL o
Occupational radiation doses received from outside the Laboratory shall also be included on each individual's a
record.
Each Division Head shall notify Health Physics when work involving radiation is to be done at other activities.
j If dosimetry service is not available at the other activity, j
special film badges shall be furnished by Health Physics and j
processed locally after return.
5.
Internal contamina-ion I
In cases of possible internal contamination, the Medical Officer will initiate requests for whole body counting, scanning and bicassays such as radiochemical urinalyses.
He will also interpret results, recommend corrective action, and maintain personnel exposure records.
The Health Physics Division will investigate and aid in evaluation of the findings.
In all such cases the total urinary output over a 24-hour g"
period or periods designated shall be collected and an analysis made for radioactivity.
w 6.
Personnel Centamination a
U The Health Physics Division should be contacted UI immediately in the event of contamination in excess of the
[}
lowest levels specified in Appendix A, Part II f Principles
(;
L 15 i
of Radiation and Contamination Control (PORACC).
A complete j
iO monitoring survey will be made to evaluate the extent of the contamination.
Health Physics will provide the necessary
[
assistance to effect complete decontamination.
The degree of 37 -
decontamination achieved and the final results of the decontam-p ination process will be recorded on special monitoring reports.
r.:
Form NOL-5100/10 shall be completed by the supervisor responsi-ble for the operation involved.
~
ps 7.
Notification of Excosure h
Immediate notification of exposure in excess of A
prescribed li;aits will be made to the individual and to his supervisor by the Health Physics Division.
M.
Personal Protection 1.
Eating, smoking, and drinking are prohibited in specified areas where possible radioactive contami..ation may exist.
Nothing whatsoever shall be put into the mouth, such as pipettes.and stems of wash bottles.
L 5
2.
All open cuts must be covered before working with radioactive materials.
3.
Gloves are required to be worn when handling objects that may be contaminated.
t 4.
Protective clothing or equipment should not be worn or taken into any area where food is stored, prepared or eaten.
I" 5.
Food containers or eating utensils shall not be
.used for storing or handling radioactive materials.
I 6.
A careful self-monitoring survey must be made by all personnel working with radioactive materials, before departing to a radiation free area.
f 7.
Protective clothing, as recommended by the Health C
Physics Division, shall be worn in all operations involving
[?$
l exposure to radioactive material.
Contaminated clothing shall W
T be removed at point of departure from a contaminated area.
~
td N.
Protective Clothinc Protective clothing is required to effectively control j
the possibility of personal contamination to the individual.
l l
16 4
l
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s,_
L All contaminated items should be removed to prevent the spread of contamination to clean areas.
The type of protective
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apparel to be worn will depend upon the conditions and circum-b stances involved.
For some types of exposure the following 7'
items are recommended:
L 1.
Fine weave coveralls or laboratory coats for most e
laboratory operations.
ta 2.
Gloves (surgeon's rubber, cotton, leather, or L'J heavy rubber, depending on the job) to prevent hand contam-f; Q
ination.
- m.
3.
Shoe covering (plastic booties, rubber boots, or rubber overshoes as required) where potential floor or ground contamination exists.
4.
Respiratory protection (such as Army Assault Mask M-17 or Navy Mark V Mask) where there is danger of air-borne contamination.
5.
Hoods (made of plastic or fine weave canvas) under j
appropriate conditions.
Protective clothing requirements for all operations in Zones i
3 or 4 areas must be specified by the supervisor.
The Health Physics Division will advise on such matters.
O.
Plutonium Safety Recuirements There are three main hazards involved in the use of plutonium:
criticality, pyrophoricity, and high toxicity.
1.
Criticality l
23Jg,the condition when fissionable Criticality is 239Pu, etc.) is capable of' sus-material (i.e.,
- 235g, taining a chain reaction.
2.
Pvrochoricity v
- C t's, Plutonium metal, hydrides and metallic alloys C
taneous ignition.
This property of plutonium requires the
{Lj especially in a finely divided state, are capable of spon-b installation of an automatic fire smothering system.
hi 3.
Toxicitv Plutonium is one of the most dangerously toxic radioactive elements known today.
The long effective half-life l
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e and its alpha emissions have been known to produce neoplastic growth in the bone tissue of lower animals.
In man, the 8
recommended permissible body burden for the bone is 0.04 uc, f_
which is 2.5 times more restrictive than radium.
gp The easiest method of entry into the human body y
is via contaminated air.
Proper design of experimental F
apparatus and good housekeeping are the first steps toward f
aerosol control.
After a project has been initiated, air h
and surface monitoring should be performed regularly.
All O
solutions of plutonium must be covered when not in use.
[
h Another method of entry is via contaminated wounds f
or breaks in the skin.
Once the material is present in the subcutaneous tissue, plutonium will slowly but continuously l
be released into the. blood stre am, liver, and bone.
Therefore, i
all open wounds should be covered before starting work.
Any H
contact with plutonium should be followed by alpha monitoring l
and decontamination, as necessary.
Operations involving plutonium solutions should' be performed in a glove box (unless specifically exempted in an SOP approved by the Health Physics Division).
Insofar as l
possible the glove box should be a completely closed system.
4 It is imperative that no leakage of plutonium from the glove box be tolerated since an escape into the laboratory may contaminate the entire building and the building ventilation system.
In the event of such contamination the building must 4
be evacuated and will remain unoccupied until satisf actory decontamination can be completed.
4.
Plutonium Storace and Fire Protection i
All quantities of plutonium, in excess of one microcurie, shall be stored in DOT approved shipping containers.
Unsealed quantities of metallic plutonium, hydrides and alloys, shall be stored and used only in areas which are provided with automatically activated fire smothering systems.
Large quancities (i.e., in excess of 100 millicuries) shall be used or stored only in areas which are further protected with RF automatic sprinklers.
{
Automatic fire smothering systems and sprinkler F3 systems should be of the fully supervised type connected to
[$j the central fire station.
[.
P.
Postina and Labelinq El gj
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All locations in which radioactive materials are used and stored must be posted with a standard radiation caution I
i 18 i
l l
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I
- a.
sign.
The sign must contain the conventional three-bladed h -
radiation symbol in magenta (or purple) on a yellow background with the wording, " Caution - Radiation Area."
Radiation areas in which an individual can receive 100 mrem /hr will be posted g
with a like sign stating " Caution - High Radiation Area."
L "High Radiation Areas" are provided with audible and/or visible alants which are energized during source exposure.
Storage "i
locations must be labeled or posted with a sign stating
.j
" Caution - Radioactive Materials" in magenta on yellow with I
[
the conventional radiation symbol.
.,T s
Laboratory beakers and flasks containing stock Q*
solutions of radioactive materials must be labeled with the standard caution sign as above and additional labeling to fm denote the. kind, quantity, and date of measurement of the material contained.
?
Form AEC-3, " Notice to Employees" shall be conspic-uously posted in each area where radioactive materials are in use/or storage.
These forms designate the radiation safety responsibilities of both the employee and the employer and are available through the Health Physics Division.
Q.
Procurement Control u
lI
^
9 Procedures to be followed in prcicuring radioactive
-sources and devices containing radioactive material are as follows:
1.
The user organization should prepare the Stub Requisition (Requisition / Turn-In Document, NDW-NOL 4235/2),
and any special instructions or correspondence that are necessary and appropriate.
All stubs will specify delivery a
via Health Physics Division, Bldg. T-9.
Requests will also be routed to the Health Physics Division th ough normal cha nels.
2.
The Health Physics Division will=
r a.
Review the raquest to determine conformity y
with safety and licensing requirements.
L-lJ a
b.
Record data necessary to maintain a central
%h record of all radioactive materials at the Laboratory.
C.
c.
Forward the request for processing through
-s regular supply channels.
~
- }
The Health Physics Division should be not' lied b
i=.ediately upon receipt of a radioactive shipment.
The 19 30)R OR'G NL
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Materials Division of the Supply Department receives shipn..tts of radioactive materials and delivers them unopened to the Health Physics Division, Bldg. T-9.
Shipments of radioactive I
material received by the Mail, Correspondence & Files Division shall also be delivered unopened to the He lth Physics a
Division, Bldg. T-9.
p I
d.
On receipt of the radioactive material, a d
Health Physics representative will survey the shipping con-
~
k tainer to detccmine that both the external radiation reading i?
and smearable contamination are within acceptable radiation limits.
Acceptable limits are less than 200 heta-gamma disin-tegrations per minute and less than 20 alpha disintegrations w.
per minute.
Materials receiving special irradiation will e.
be handled directly by Health Physics Division personnel.
f.
All outgoing shipments of radioactive materials from the Laboratory must be made under the supervision of L
Health Physics.
Shipments will be performed in compliance with the Post Office, Department of Transportation Regulations 1
(ref (d ), and AEC Rules and Regulations (ref (a) ).
R.
Radiation Survev Procedures The Health Physics Division routinely surveys all areas within the Laboratory in which radioactive materials are used and stored.
The frequency of these surveys will range from one week to one month dependent upon the amount I
of use made of the materials, radiation levels involved, and previous laboratory radiation findings.
Special radiation j
surveys will be performed by Health Physics personnel at the l
request of the user.
The Health Physics Division will make a reasonable effort to contact the responsible user of the
[
radioactive material prior to the conduct of the radiation survey so that the responsible user will have knowledge of the survey and also to assure that the laboratory or room is not scheduled for use at that time.
The Health Physics D ivis ion, however, must of necessity, survey any room or 4-f7!
laboratory whern radioactive materials are used or stored at any time deemed necessary in the i'nterest of radiation hyy safety.
Radiation surveys consist of radiation instrument readings to determine background levels of radiation and gj Ea filter-disc swipes as a check on possible laboratory contam-M1 ination.
In addition, air samples are taken in certain Y- -
designed areas within and on the perimeters of NOL to determine l
any deviation from normal natural occurring radiation count.
Air samples are also taken in laboratories or rooms which have been determined contaminated during a routine radiation survey.
l 20
?0DR ORIGINAL i
i Filter discs are used to swipe work surfaces such as work benches, sinks, hoods, and floors of laboratories as a part I
of the radiation survey process.
These filters are then counted
{
for alpha, beta, and gamma radiation content.in the Health
((
Physics Laboratory and tha results recorded.
If contamination g
is detected as a result ci the survey, the supervisor in r
charge of the laboratory is immediately contacted and arrange-
{
ments are made for removal of the contamination.
The cleaned p
area is then resurveyed by Health rhysics to determine that p
the radiation contamination levels are within acceptable limits.*
g M
S.
Relative Decrees of Radiation Hazards
$y-If radiation safeguards are not followed, an individual may receive a significant exposure from either external or
[
internaI radiation.
Radiation that is external can be readily
[j measured and evaluated.
The exposure dose may be reduced to acceptable ** values by reducing the time of exposure, intro-1 ducing appropriate shielding, and/or increasing the distance h
from the source.
h The internal radiation hazard is much more subtle and, I
unfortunately, much more probable in terms of general use of J
liquid radionuclides.
When radionuclides become fixed in the body they are difficult to measure and little can be done to 1
improve the hazard situation.
" Good Housekeeping" practices are required to prevent
?
spillage and ultimate spread of radioactive contamination in laboratorie s.
Areas in which contamination is known to exist should be roped off immediately.
The following table represents the relative degree of hazard per given quantity of certain radionuclides.
l q
Acceptable Limits:
Less than 10 alpha counts per minute; I
I less than 50 beta-gamma counts per minute.
d 1250 mrem per quarter and/or 5,000 mrem per year.
fr (See also Sec. I, page 10. )
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HAZARD FROM ABSORPTION INTO THE BODY Group l Activity Scale l 1.
SLIGHT HAZARD 1pe loue locue 1m: lome loome 1 curie Z4 42 52 l
Na 'K Cu" Mn
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- Hg As76, As77, Kr 85 197
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MODERATELY DANGEROUS 3
l4 32 22 35 H,C
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, Na
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g 136 54 60 I
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- Fe59, Co 183 l6 I
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- Sra9, Cb95 Ru
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- Cs 131 WTER-Tel21, Tel29, 1 l37 low LEVEL HIGH LEVEL
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- Bal40, Lal4, Ce I
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- Pr343, Nd147, *Aut9a j
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- Au!99, Hg Hg "5 I
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VERY DANGEROUS g
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l 45 55 Ca Fe Sr90 Y91 I
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HIGH EVEL Zr95, Ce
,Pm dE L. AECIAT-l44 147 Pu23 9, Razz 6 (in equi.
Bi21 1 e lope loope 1.,e 10mc loome 1 curie librium)
Activity to be handled in Laboratory
- Principal gamma emitters-l NOTES:
1.
Effective radiotoxicity is obtained from consideration of the following factors: half-life, energy and character of l
radiations, selective localization in the body, rates of l
elimination, quantities involved, and modes of handling in typical experiments.
2 The slant boundaries between levels indicate borderline zones and emphasize that there is no sharp transition be-tween the levels and the protection techniques required.
3.
The above hazard groupings cannot be taken as applying to external irradiation.
22
I
.. u _
T.
Remote Handline Ecuirment Work with radioactive material requires remote handling a
equipment for proper contrcl and confinement of loose activity.
[p; It is the responsibility of the Departmental users to obtain such facilities as needed for these operaticns which may include the following:
1.
Glove boxes.
- 2.'
2.
Enclosed work spaces or restricted rooms.
3.
Shielded areas constructed of lead bricks, concrete pits, etc.
e J-and shielded manipulators for use with high 4.
- Tongs, levels of activity.
Health Physics will advise on the procurement and use of the above items as necessary.
U.
Soecial Warninc Recuirements 1.
Radiatine Machinen All x-ray units are equipped with audible and/or visible alarms which are automatically activated when the machines are turned on.
Additional door interlocks are provided at high energy fixed x-ray installations which cause l
the units to shut down in the event the doors are opened during exposures.
Operators are required to be in continuous attendance when portable x-ray machines are in use.
The area is also required to be posted with radiation caution signs and barricaded at the 2 mr/hr level of radiation.
2.
Sealed Sources Facilitiea utilizing sealed radioactive sources for radiographic and calibration purposes must be equipped "7
(iri with permanent shielding barricades of sufficient thickness to reduce radiation levels outside the barricades to accept-able limits (5 mr/hr - radiation area or 2 mr/hr unrestricted 6
area).
Standard radiation warning signs are required to be R
posted and flashing light systems will operate when the source
'd l
l is exposed.
A di 3.
Contaminated Areas and Bruiement 9
'~
All contaminated equipment, including vehicles, will be tagged with radioactive material tags that clearly l
23 i
P*
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~~
-. e
. - ww.es.
..-..+-e,
L.
1 indicate the extent and location of the contamination.
This
[
~
equipment will not be put to use until cleared by the Eealth j
Physics Division.
V.
Storinc and Eccdlinc Radioactive Materials f
[
Radioactive materials will be stored in a shielded area such as a lead brick cave, or shipping container.
The 1
storage area and container are required to be labeled with radiation warning signs.
(See Part O, para. 4, Plutonium Storage and Fire Protection, page 18.)
N An operation using radioactive solutions shall be conducted over a tray or basin of sufficient capacity to holel l
all the solution if spilled.
o Solutions shall be kept in containers strong enough to withstand breakage and leakage.
For high activity levels, the container shall have a secondary container or catchment under or around it.
Caution should be exercised in handling highly radioactive liquids in the laboratory.
Work areas (bench tops, hoods, etc.) must be covered with absorbent material.
Liquid samples carried between rooms must either be enclosed within non-breakable containers or surrounded by
["
h secondary non-breaNable containers.
There should be sufficient absorbent material to take up the entire sample if spillad.
j l
Samples shall not be carried to the counting room with bare hands.
They should be carried in trays or the like
[
to eliminate the possibility of spillage.
[f Glassware known to be contaminated will be rinsed in the laboratory where it is used.
A five gallon polyethylene liquid waste container provided by the Health Physics Division, I
will be used for the collection of the first rinse from contaminated glassware.
No radioactive material shall be removed from any building without the specific approval of Health Physics.
b No contamincted materials shall be taken into machine h
shops or other service creas, unless these areas have been hM i
specifically approved for work with contaminated materials.
lij Movemente of radioactive materials external to NOL k.1 (e.g., over the state highways) must comply with the DOT f(
{fd regulations.
The Health Physics Division is responsible for assuring compliance with these regulations.
24 e
t
l i
l l W.
Transfer of Material Transfers of radioactive materials must be approved by the Radiation Safety Officer and/or.the Radiation Safety
@61 Committee, dependent upon the level of radiation of the material and safeguards employed.
It is understood that several laboratories may be involved in the routine use of, f
radioactive materials under a given responsible user.
How-M ever, there are situations in which a quantity of radioactive h
material may be useful on a special project by another indi-f vidual.
This transfer may be completed under the following g
4 b
conditions:
A 1.
The transferee must be duly authorized by the Radiation Safety Committee to receive the radioactive material.
2.
The transferee must have available facilities j
and equipment n:cessary to safeguard the use of the radio-l L
active material.
3.
Records will be maintained to reflect locations and users of radioactive sources at all times.
i X.
Tritium Safecuards e
1.
Precautions Special precautions need to be taken when working i
with tritium compounds, or tritium-contaminated materials in quantities in excess of one millicurie.
These include the wearing of rubber gloves and the use of glove boxes or hoods.
Rubber gloves should be changed frequently and destroyed, since tritiated water vapor has the ability to pass through rubber within a few hours.
All equipment which has come into contact l
with tritium, either gas or T 0 vapor, will retain some tritium 2
and should be considered contaminated.
Stopcock grease, vacuum pumo oil, and plastics are readily contamincted.
Materials such as glass or stainless steel also retain small quantities of tritium.
Ac ordinary room temperatures, tritium J
will diffuse through glass or stainless steel or from tritiated Nr accelerator' targets.
There are some tritium losses caused by
{}
j the heat created during accelerator operation.
There is also e
an exchange mechanism involved when the tritium is in contact.
E{
with atmospheric hydrogen.
Accelerator targets must always 2
be handled with forceps and rubber gloves since several curies e
of tritium per square centimeter may be absorbed on the surf ace of the target.
Deuterium targets should also be handled with f@
forceps and gloves, since tritium contamination of several microcuries may also be present.
25 I
a s
4 n
w.
t_N rr Tritium contamination is of ten associated with f-vacuum pumps.
Accordingly, special precautions must be g
observed when disassembling or repairing a pump that has
(,
been used on a system containing tritium.
Health Physics fr a
should be notified in advance of this operation.
Oil and p
mercury associated with the pumps should be assayed by C
Health Physics and if necessary, disposed of as contaminated
(
materials.
3 si',
F 2.
Monitorinq h
All personnel working with tritium shall period-w ically submit urine samples for body uptake evaluation.
The I?"-
I Health Physics Division will provide advice on the frequency of monitoring.
All areas in which tritium is used in quanti-ties in excess of one millicurie, especially in vacuum pu=ps d
for systems containing tritium, should be monitored by Health I
Physics personnel for absorbed surface tritium.
Air monitor-ing instruments, capable of detecting tritium, are available e
and should be used when there is the possibility of release d
of tritium to the atmosphere.
(i Y.
Work Performed After Recular Workinc Hours The Health Physics Division is to be notified of any work involving the use of high level radioactive materials after regular working hours.
In Zone 4* areas, at least two people will be present at all times (NOLINSTR P5100.5A, para.
j.
20, (ref (f) ).
i
. The Health Physics Division will be informed of any l
proposed work in radiation areas or in locations where radio-I active contamination may be present.
A representative of the j
Health Physics Division will evaluate the existing hazard and if approved, will forward the work request with his reccmmen-dations to the Maintenance Control Division.
1 i
Protective clothing or tools, if required will be provided by the maintenance supervisor.
Maintenance personnel will then follow instruccions set forth in the Soecial Work
- r Pernit.
A representative of the Health Physics Division will h
monitor and establish working times for the operation.
Any p
operation which might result in the liberation of radioactivity E
into the air (aerosols, gases or vapors) must be performed in E
a fume hood.
If the airborne concentration is likely to be O
N(
above the recognized RCG, special precautions must be taken l
to assure personnel safety.
n
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~
l See page 27 for zone definitions.
(
l 26 t
1 l
L l
e
)-
Requirements for respiratory protection in relation I
to the level of concentration of activity or airborne con-taminations are contained in Section C of this manual.
W Z.
Zone Precautionary Measures
{
1.
Zone Desicnations
-Laboratory areas are divided into four zones, as
(
Zone 1 Radiation-Free Areas a.
A Radioactive material not permitted.
Examples:
cafeteria, auditorium, offices, passenger elevators, etc.
No dosir.etry required.
b.
Zone 2 - Possible Contamination Areas,
Background control required.
Ecamples :
freight elevators, radiation counting rooms, film storage and develop-laboratories for radiochemical urinalyses and tracer l.
Contamination control procedures are required and
'g ing areas, studies.
p must be formally documented.
Zone 3 - Radiation Area c.
I Work areas where radioactive material may be i
handled routinely and radiation producing devices are used.
i d.
Zone 4 Mich Radiation Area Examples:
work areas in which the radiation level is such that a major portion of the body could receive greater than 100 mrem /hr; work areas in which an aerosol greater than 10 times the RCG is generated.
im Q
L q
I-o s
l II..
27 i
f l
\\
S u
l i
GLOSSARY j*
o X3 sorbed Dose:
The energy imparted to matter by ionizing h
radiation per unit mass of irradiated material at the place p
of interest.
The unit of absorbed dose is the rad.
One rad d
equals 100 ergs per gram.
ge Accelerator:
A device for imparting very high velocity to charged particles such as electrons or protons.
These fast g
W particles can penetrate matter and are known as radiation.
(#
Aloha Particle:
A small electrically charged particle of f-very high velocity thrown off by many radioactive materials 1;
It is identical with the nucleus of a helium atom and is made up of two neutrons and c
two protons.
Its electric charge is positive and twice as great as that of an electron.
Attenuation-The process by which a beam of radiation is reduced in intensity when passing through some material.
It is the combination of absorption and scattering processes and leads to a decrease in flux density of the beam when pro-jected through matter.
Beta Particle:
A small electrically charged particle' thrown off by many radioactive materials.
It is identical with the electron and possesses the smallest electrical charge found in nature.
Body Burden:
That amount of radionuclides distributed through-out the btdy that will result in a maximum permissible R33 dose rate to the critical organ.
The critical organ is con-sidered to be that organ of the body where the greatest amount of damage is done.
l Contamination, Radioactive:
Deposition of radioactive material t
in any place where it is not desired, particularly where its y
presence may be harmful.
The harm may be in vitiating an
{
experiment or a procedure, or in actually being a source of j
danger to personnel.
f l
p k!
Counter:
A device for counting nuclear disintegration to A
n measure radioactivity.
The signal which announces a disinte.-
I gration is called a count.
i gj l
Curie:
A measure of the rate at which a radioactive material d
C throws off particles.
The radioactivity of one gram of radium N
is a curie.
One curie corresponds to 37 billion disintegrations
~
per second.
29 I
l P00R ORM.
I
- s
'N**
- *"M * * * * * <
.s O'
Decav:
When a radioactive atom disintegrates it is said to decay.
An atom of polonium decays to form lead, ejecting an alpha particle in the process.
b kr Dosimeter:
An instrument used to detect and measure an accumulated dosage of radiation; a pencil-size ionization E
chanber with built-in self-reading electrometer used for C
F personnel monitoring.
E&L Film Badce:
A piece of masked photographic film worn like
~
h a badge by nuclear workers.
It is darkened by nuclear radi-ation, and radiation exposure can be checked by inspecting ha, the film.
Gamma Ravs:
The most penetrating of all radiations.
Gamma riys are very high energy x-rays.
3
_ Health Physics is a profession devoted to Health Physics:
the protection of man and his environment from unwarranted radiation exposure.
Light amplification by stimulated emission of radi-l Laser:
ation.
The laser region is that portion of the spectrum f
which includes ultra-violet, v,isible light, and infrared.
[L l
Leak Test:
A test performed to determine radiation source leakage.
Monitoring:
Periodic or continuous determination of the amount of ionizing radiation or radioactive contamination present.in an area.
Neutron:
One of the three basic atomic particles.
The o
neutron weighs about the same as the proton but has no electric charge.
Maximum Permissible Dose:
That dose of ionizing radiation established.by competent authorities as an amount below which j
there is no reasonable expectation of risk to human health, Q@
and which at the same time is somewhat below the lowest level l
at which a definite hazard is believed to exist.
An obso-l lescent term.
Radiation:
The emission and propagation of energy through A
I l
space or through a material medium in the form of waves; for l
instance, the emission and propagation of electromagnetic 4
E waves, or of sound and elastic waves.
Such radiation commonly is classified, according to frequency such as infra-bk red, visible (light), ultra-violet, x-ray, and gamma ray; i
29
T.
4 L.
o o
. U b
1 and by type of corpuscular emissions, such as alpha or beta
{ -
radiation.
J Radioactive Isotoce, or Nuclide:
A radioactive form of an j;-
element having identical chemical properties but different 6
M atomic mass.
b Radioactivitv:
The spontaneous decay or disintegration of i
an unstable atomic nucleus usually acccmpanied by the emission f
of ionizing radiation.
ps Radiocraohv:
The making of shadow images on photographic g
emulsion by the action of ionizing radiation.
The Unage is la _
~
the result of the differential attenuation of the radiation in its passage through the object being radiographed.
i Relative Biolacical Effectiveness (RBE) :
The RBE is a factor used to compare the biological effectiveness of absorbed radiation doses (i.e., rads) due to different types'of ion-i=ing radiation, more specifically, it is the ezperbnentally b
determined ratio of an absorbed dose of a radiation in f
question to the Wbsorbed dose of a reference radiation required to produce an identical biological effect in a particular organism or tissue.
REM:
(Acronym for roentgen equivalent man.)
The unit of dose of any ionizing radiation Which produces the same bio-logical effect as a unit of absorbed dose of ordinary X-rays.
The RBE dos" rems) = RSE X absorbed dose (in rads).
Roentcen (r);
An exposure dose of X or gamma radiation such that the associated corpuscular emission per 0.001293 g of air produces in air ions carrying one electrostatic unit of l
electricity of either sign.
Sealed source:
Any byproduct or special nuclear material that is encased in a capsule designed to prevent leakage or escape of the byproduct or special nuclear material.
Survey, Radiolocical:
Evaluation of the radiacion hazards incident to the production, use, or existence of radioactive E[
materials or other sources of radiation under specific kO conditions.
Such evaluation cuctcmarily includes a physical f
survey of the disposition of materials and equipment, measure-p ments or estimates of the levels of radiation that may be F1 involved, and sufficient knowledge of processes using or bi af fecting these materials to predict hazards resulting from 69 expected or possible changes in materials or equipment.
jJ m.
30 9
3 ~..
_. _.. _.1_
l 1.
,,u e
X-Ray:
Highly penetrating radiation similar to ga:ma rays.
Unlike gamma rays, X-rays do not come from the nucleus of the atom but from the surrounding electrons.
They are produced by electron bombardment.
When these rays pass through an Z
object they give a shadow picture of the der.ser portions.
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M 4
G p
G 9
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31 1SS2O f
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