ML19275B719
| ML19275B719 | |
| Person / Time | |
|---|---|
| Site: | 07001207 |
| Issue date: | 10/04/1979 |
| From: | NAVY, DEPT. OF |
| To: | |
| Shared Package | |
| ML19275B715 | List: |
| References | |
| P5100.5A, NUDOCS 8002280028 | |
| Download: ML19275B719 (47) | |
Text
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NOL INSTRUCTION P5100.5A g
SAFETY MANUAL y
Addendum No.1 RADIOLOGICAL 2
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PART 1:
lONIZING RADIATION aji
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36 N AVAL ORDN ANCE LABOR ATORY "TiE WHITE O AX, SILVER SPRING, MARYLAND
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PART I:
IONIZING RADIATION 5
INTRGOUCT1,0N
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PURPOSE These procedures are intended to serve as a guide for Laboratory personnel engaged in operations involving the use
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of radioactive materials and other radiation producing devices.
It also provides information on the activities and responsi-bilities cf the Health Physics Division, the Medical Officer, g
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and the Radiation Safety Committsee, as they relate to the Laboratory Radiological Safety Program.
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2.
POLICY
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The NCL Radiological Safety Committee is responsible for reviewing and approving radiation safety policies of the Laboratory.
Prinary responsibil~ity for radiation safety control at
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NOL is 6ssigned to the Chief, Health Physics Division.
Health 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
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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 CONTENTS
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Page 2
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I.
INTRODUCTION.......................................
1
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A.
Radiological Safety............................
1 B.
External Guides................................-
1
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~T II.
RADIOLOGICAL SAF.UI'Y ORGANIZATIONS AND RESTONSIBILITIES.......j...........................
1 A.
Health Physics Division.t......................
1 i
B.
Medical Officer................................
2 i
C.
Radiological Safety Committee..................
3
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III.
RADIATION SKP ETY PRACTICES.........................
4 5
A..
Accountability and Control.....................
4 B.
Collection and Disp sal of Radioactive Wastes..
4
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1.
Solid Wastes.............
5 c
5 5
2.
Liquid Wastes..............................
3.
Ultimate Disposal..........................
5
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C.
Contamination Limits...........................
5 3
1.
Internal...................................
5 3
2.
Surface....................................
S 3.
Air and Water Contamination................
6 E
D.
Criticality Precautions........................
6 I.
1.
Unsealed Quantities of Special Nuclear Material...................................
6 2.
Sealed Sources.............................
6 E.
Decontamination................................
7 1.
Area Decontamination.......................
7 2.
Equipment Decontamination..................
7 E
3.
Personnel Decontamination..................
7 F.
Emergency Procedures...........................
8 G.
Environmental Monitoring.......................
8 e.
1.
Routine Monitoring.........................
8 G
2.
Special Monitoring.........................
9 H.
Le ak Te sting Procedure s........................
9 1.
Techniques Employed........................
~9 j.
2.
Counting Methods...........................
10 I.
Maximum Permissible Exposure Limits............
10 J.
Medical Examinations............................
11 2
1.
Radiological He alth Examin ations........... 11 5
2.
Radiological Accidents.....................
12 3.
Routine Urinalyses.........................
12 4.
Special Examinations.......................
12 7
0 5.
Visitors in Work Status....................
12 L
K.
Monitoring Instruments.........................
13 1.
Dosimetric Devices.........................
13 n
2.
Film Badges................................
13
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3.
Pocket Ionization Chambers.................
13 17 c
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CONTENTS
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Page E
L.
Personnel Monitoring...........................
14 1-1.
Radiation Received at NOL..................
14 a.
Film Badges............................
14 j
b.
Pocket. Dosimeters......................
14-
/..
Individual Responsibility..................
15 3.
Visitors.......<....,.....................
15 a
4 '.
Radiation Received Away from NOL...........
15
~5 S.
Internal Contamination.....................
15 6.
Personnel Contamination....................
15
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7.
Notification of Exposure...................
16
_5 M.
I'ersonal Protection............................
16
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N.
Protective Clothing............................
16 O.
Plutonium Safety Requireme'nts..................
17 5'
l.
Criticality................................
17 5
2.
Pyrophoricity..............................
17 3.
Toxicity...................................
17 4.
Plutonium Storage and Fire Protection......
18 i
P.
Posting and Labeling...........................
18
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Q.
Pro cure me nt Con trol............................
19 R.
Radiation Survey Procedures....................
20
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S.
Relative Degrees of Radiation Hazards..........
21 T.
Remote Handling Equipment......................
23 U.
Special Warning Requirements...................
23 1.
Radiating Machines.........................
23
' 2. - Se al e d S our ce s..............................
23 3.
Contaminated Areas and Equipment...........
23 V.
Storing and Handling Radioactive Materials.....
24 W.
Transfer of Materia1...........................
25 X.
Tritium safeguards.............................
25 3.
Precautions................................
25 2.
Monitoring.................................
26 Y.
Work Performed After Regular Working Hours.....
26 Z.
Zone Precautionary Measures....................
27 l.
Zone Designations..........................
27
_1 a.
Zone 1 - Radiation-Free Areas..........
27
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b.
Zone 2 - Possible Contamination Areas..................................-
27 g
c.
Zone 3 - Radiation Area................
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d.
Zone 4 - High Radiation Area...........
27 GLOSSARY................................................
28
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REFERENCES
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(a)
AEC Code of Federal Regulations, Title 10, Part 20,
" Standards for Protection Against Radiation."
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NAVMED P-5055, Radiological Health Protection Manual.
(b) f (c)
PORACC, Vols I, II, III, Principles of Radiation and i
Contamination Control.
(d)
TID--7016, Rev I, Nuclear $afety Guide, 1961.
(e)
Hazardous Materials Regulations of the Department of
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Transportation, Tarif f No. 23,.1969.
(f)
NOLIUSTR P5100.5A, Safety Manual
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RADIATICI, SAFETY I.
INTRODUCTION E'2.,
A.
Radiolocical Safety 1.
The serious nature of radiation hazards requires that we observe most scrupulous precautions when working with radioactive materials.
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..3 2.
No amount of radiation exposure should be incurred unless it is necessary and warranted.
Therefore, every indi-vidual case of the use of ionizinq. radiation should be care-fully evaluated and used only if its use is considered more s.,
advisable than any other methods of investigation.
e 3.
Radiation will be confined at the source.
Pre-ji cautions will be taken to ensure that utilization of radiation and radioactive sources do not jecpardize other experiments, operations or activities.
a 5
2 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.
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E.
2xternal Guides 1.
The Laboratory obtains and uses radioactive materials under licenses granted by the U. S.
Atomic Energy Commission (AEC).
Under these licenses, the Laboratory is subject to
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inspection and control requirements as outlined in the AEC 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) ),
and other cognizant Naval activities.
II. RADIOLOGICE SAFETY ORGANIZATIONS AND RESPONSIBILITIES A.
Health Physics Division i
The Health Physics Division is responsible for the overall implementation and supervision of the Laboratory's
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Radiological Safety Program.
Operating as a part of the l
Safety Department, the Division serves the entire Laboratory.
Specifically, the functions of the Division are La:
~ i 1.
Interpret or modify existing radiological safety regulations.
In addition, the Division will formulate new 3
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r radiological safety regulations for the safe handling, utili-zation and. exposure to radiation, which will be. submitted to i
the Radiological Safety Committee for approval.
2.
Provide consultative services to project leaders, 7
scientists, investigators, technicians, and others, with i
regard to safety in the care and use of radioactive material and radiation producing deviets.
j 3
Provide film dosimetry for all Laboratory per--
3 sonnel and visitors who work with or near radiation sources.
Interpret and report results obtained from these devices and L_g forward them to the Medical Department for permanent filing.
4.
Review all requests for radioisotopes and irradiation services to assure that the proposals conform to r.
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licensing requirements.
5.
Maintain a central inventory of all radioactive 3
and radiation producing equipment utilized in the Laboratory.
.s 6.
Advise in the procurement of special nuclear 7
Inaterials.
2 7.
Provide advice in the planning for safe and leqel d4.=pnen1 of radioactive waste and monitor actual operation T.
8.
Measure and record the radiation levels and con-centrations of liquid and airborne radioactive materials being 3
b discharged within the Laboratory.
Periodic surveys in the form of air and water samples are also performed to detcrmine
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and control any release of rad.ioactivity outside the confir.es 7
of the Laboratory.
i.
9.
Revie.y and make recommendations on the red-safe aspects of all new f acilities involving radiation machines or radioactive materials.
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10.
Assist in training and indoctrination of personnel in radiological safety.
11.
Perform evaluation and project development in 5
the field of health physics for a sponsor.
This work should be related to laboratory problems.
B.
Medical Officer
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The Medical Officer is responsible for the industrial health of Laboratory personnel, specifically, he performs the following functions related to radiological safety.
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7 2
4 1.
Reviews all instances of radiological exposu[e in excess of the permissible limits (see Pago 10) and pre-pares reperts of such exposures for submission to the Bureau of Medicine and Surgery (BUMED).
52 2.
Investigates medical aspects of the radiological safety program of the Laboratory.
b 3.
Conducts pre-empLpyment and terminal physical examinations of all personnel who kill be or have been a
exposed to. radiation in their normal work function.
=a 4.
Performs radiological health examinations, as
. required by NAVMED P-5055.
3 5".
5.
Assists in the radiobiological assay program to determine possible internal exposure.
5 6.
naintains records of personnel exposures and interpreta tions.
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7.
Compiles and interprets data from radioclinical laboratory analyses performed by the Health Physics Division.
p He also recommends appropriate action as indicated.
5 C.
Radiolacical Safety Committee
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,1.
This Committee is responsible for performance of the following functions:
g a.
Approve radiological safety policies and procedures for the Laboratory.
b.
Review proposed procedures for operations, r,
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expe 1ments,,or tests involving radiation and/or radioactive materials.
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c.
Assist the Health Physics Division in the enforcement of radiation safety practices as set out in the z.
NOL Radiological Safety Procedures.
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d.
Develop a criterion of evaluation for qualification of users of radioisotopes and other sources j
of ionizing radiation.
e.
Approve or disapprove applications for senior users of radioactive materials.
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i f.
Consider and pass judgement on major equip-ment and facility needs of the various users of radioactive materials at NOL.
3
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L g.
Keep current on present and amended parts of the Federal Regulations pertinent to the conduct of the radiation safety program.
I h.
Maintain records of Committee action.
1.
Review plans for all new buildings and r
modification of existing structures where radioactive materials
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are to be used.
S j.
Serve as a reviewing committee for investi'-
9 gations of radiological incidents and make appropriate r
recommendations to management to include the Directorate, the i
Technical Director and/or Commanding Officer.
2 l
2.
Membershio
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5 The membership of this Committee sha.' ' be as follows:
i a.
At least one member (or alternate) from 3
cach Department utilizing sources of radiation.
The Committee Chairman is selected from this group.
E b.
The Radiological Safety Officer (represent-ing Health Physics).
Ex Officio Member and Recorder.
2 c.
The Medical Officer.
d.
Assistant for Nuclear Energy, i
III.
RADIATION SAFETY PRACTICES 7
A.
Accountability and Control 5.
The Health Physics Division maintains inventories.
of all radioactive materials within NOL.
Inventories are inclusive of byproduct, special nuclear, and source materials.
These materials are governed by the following regulations issued by the AEC:
Title 10 CFR - Parts 20, 30 - 36, 40, and 70.
Health Physics is also responsible for accountability control over certain unlicensed materials.
These materials 4
include both ionizing and non-ionizing sources of radiation.
It is mandatory that all authorized users inform the Health Physics Division with regard to the location and uses of such materials and equipment.
B.
Collection and Discosal of Radioactive Wastes 4
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Solid Wastes Special waste containers with disposable liners o
are provided by the Health Physics Division to the various Departments utilizing radioactive materials for the collect-ion and temporary storage of low-level radioactive wastes.
g These recepticles are yellow in color and contain the magenta radiation symbol and the wording " Caution - Radioactive Materials."
The Health Physics Division is responsible for collecting the contents of these containers on a routine basis.
Collected wastes are then placed in storage under the 4.a direct supervision of Health Physics prior to ultimate dis--
posal to a commercial waste disposal company.
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2.
Liauid Mastes f
Carboys will be provided to laboratories b
employing ligt id radioisotopes for the collection and conta.'.n-ment of medium-level wastes.
These radioactive wastes will 5
consist primarily of first-wash solutions.
Further washings k
of glassware will be restricted to certain designated sinks located in each of the laboratories usina radioisotopes.
A p
1,000 gallon capacity holding tank will be situated approxi-
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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 sampj eu for radioactivity by Health Physics personnel.
3.
Ultimate Discosal Rg Solid radioactive wastes and carboys contain-ing liquid wastes will ultimately be disposed of to a e-commercial firm.through an Interservice Agreement between
[j the Army, Edgewood Arsenal and the Naval Ordnance Laboratory.
Records will be maintained by the Health E._
Physics Division, of the kinds, quantities and dates of L
neasurement of all radioactive collections and disposals.
E C.
Contamination Limits p
1.
Internal
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The Radioactivity Concentration Guides (RCG8s) as recommended by the International Commission on Radiological Protection will serve as the laboratory guide with respect to contamination internal to the body.
2.
Surface The RCG's for surface contamination in radiation areas (see Section Y) are listed as tollows:
5 h
b Isotooe Averace Maximum Removah e Alpha Emitters 500 d/ min -
1,000 d/ min -
20 d/ min..
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100 cm2 100 cm2 b~
100 cm2 Deta-Gamma 0.2 mrad /hr 1.0 mrad /hr 200 d/ min -
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at 1 cm at 1 cm 100 cm2 E
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(For tritium, the removable limit is 10,000 d/ min - 100 cm.)'
2
{i If any of the above maximum or removable values are exceededs L
immediate action will be taken to isolate, contain and/or de-contaminate the area or personnel involved, hj 3.
Air and Water Contaminat. ion The Laboratory will comply with the requirements k_
of 10 CFR 20, Appendix B, of the U. S. Atomic Energy Commission
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with respect to air and water contamination limits, fs -
D.
_ Criticality Precautions E
Special precautions are required to assure that' b
the inadvertent accumulation of a sufficient quantity 2
of special nuclear materials (U233, u235 Pu239, or oth'er fission-able material) necessary to create a critical mass with an attendant nuclear chain reaction w.i't happen.
Requirements
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are as tellows:
1.
Unsealed Ouantities of Special Nuclee.- Material s
one " unit" is defined as 250 grams of at:y unsealed special nuclear 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.
The Health Physics Division must be notitied in advance before gram quantities of unsealed special nuclear material may be moved frcm any room.
Quantities of special nuclear material greater than one gram not in use should be stored under the care of the Health Physics Division.
2.
Sealed Sources The " sealed source" configuration must meet the criteria established in TID-7016, " Nuclear Safety Guide,"
6 i
(ref (d)), for subcriticality by virtue of quantity, size, volume 7t dimension bef ore procurement or use in the labora-tory.
In addition, the basic configuration of the sealed source e'aall not be altered in any way during use.
Additional quantitica of special nuclear materials shall not be used or
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stored in the same or in adj acent rooms.
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E.
Tecontamination 4
1.
Area Decontamination
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Decontamination of a work area shall be done by r
personnct normally using the space or by the Public Works -
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Depa rtme nt personnel, depending upon the typa of effort required.
Health Physics persont.el will perform all necessary monitoring surveys, make recommendations for decontamination procedures and arrange for participation of other personnel, w
as necescary.
2.
Equipment Decontamination
^-
p.
Equipnent used in the laboratory or on field 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 equipaent be decontem nated to final or standard clearance levels giver. in section,C.
Arrangements tur cylipment decontamination shall be made in accordance with controlled maintenance work as described above.
P 3.
Personnel Decontamination There is no completely standardized system for skin decontamination.
However, certain general methods have been f airly successful and those are incorporated in the pro-cedure which is posted in each skin decontamination kit.
The se hits are available f rom the He alth Physics ~ Division.
They should be obtained by non-contaminated personnel or hef ore operations start as spelled out in the appropriate i.
Standard Operating Procedure (SOP).
The Health Physics i.
Division must be contacted whenever personal contamination has not been completely removed by washing with soap and water.
n E
Personal clothing that has become contaminated must be removed and then decontaminated.
In no case will contaminated clothing be worn away f rom the Laboratory.
The Health Physics Division will be advised of all instances of personal contamination and will recommend corrective action.
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Emeroency Procedures A radiation incident could occur in spite of our
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best ef forts to safeguard the use of radioactive materials.
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The incident may be in the form of a spilled radioactive liquid sample, a crushed radioactive solid source or a leak-c.
H ing radioactive sealed source.
There could also be a fire or k
explosive incident involving cadioactive sources.
In the event of any of the above, there id a strong possibility that f5 this interaction would create airborne material.
In the Fi event of such an occurrence the following procedures are to be followed:
a 5
1.
Withdraw to a safe distance from the affected area and restrict the area as much as possible.
p:
g 2.
If possible, turn off air conditioning, hoods, fans, close windows and lock doors.
9[
3.
Notify the Health Physics Division of your LE location and conditions.
Telephone 495-7780.
4.
If a radiation survey instrument is immediately
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available monitor self for personal contamination.
In any case, do not leave the immediate area until determined free of contamination.
g f
5.
Summarize the situation as briefly as possible to the health physicist upon his arrival.
(5 G
The Health Physics Division should be contacted immediately in the event of a lost or misplaced source of radiation.
G.
Environmental Monitoring 55 1.
Routine Monitorina E
A periodic monitoring program will be conducted E
of all potentially hazardous radioactive areas by the Health b
Physics Division.
This will include measurement of radiation IcVels, and samplings of effluents being discharged to the public sewer system and to the air.
The Health Physics i
e Division will evaluate the situation and recommend corrective action commensurate with the degree of hazard.
e 8
1.
r:
2.
Special Monitorinc Special monitoring surveys will be made by the i
Health Physics Division when it is deemed advisable, such as i,
for the following:
m.
a.
When radiological clearance of equipment or 3
areas is desired.
b.
To determine contam'ination levels after 3
decontamination operations.
C c.
To determine radiation and contamination
]
levels in connection with specific experiments or operations.
5.
d.
For issue of Special Work Permits.
il c.
When new equipment or building alterations might change existing radiation dose contours.
-.5 Results of these surveys shall be recorded and permanent i
records made of all significant findings.
The Health Physics Division will evaluate the situation and recommend corrective q
action.
E
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H.
Leak Testina Procedures n
411 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) l sources by the Health Physics Division.
a 1.
Technioues Emploved
[
Filter paper wetted with alcohol (or other suit-able solvent) or dry, will be rubbed over the source or the.
~
approprictcly accessible surface of the storage container.
~'
Cotton tipped wooden applicator swabs, either wet or dry, will be rubbed over the source or the appropri-ately accessible surface of the storage container.
The actual manipulation of the test media will be with suitable equipment (tongs, etc.) and any necessary portable shielding as required to keep personnel exposure within the limits prescribed in Title 10, Code of Federal Regulations.
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2.
Counting Methods Each wipe or specimen will be counted for alpha and beta-gamma in equipment of sufficient sensitivity to perform the test.
If any leak test reveals the presence of removable
-adioactivity in excess of 10% of the limit of.005 microcuries L
(i.e., 5 x 10-4 xCi) the source shall be immediately withdrawn from use and will be decontaminate 6 or disposed of according g
to regulations.
The AEC will be notified within five days of g
any leakage in excess of.005 xCi. -
I.
Maximum Permissible Exposure Limits g
na Title 10 CFR 20 sets forth the maximum permissible levels of radiation that an individual may receive per calendar i
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 genads - 1 1/4 rems.
2.
Hands and forearms, feet and ankles - 18 3/4 rems.
,3.
Skin of whole body - 7 1/2 rems.
Generally, for practical purposes, we are mainly concerned with radiation exposure which an individual may receive f rom a " bole body exposure.
It should be voted that a person may receive 15 times as mur:h radiation at she 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 4 hole body.
For our purposes at the Laboratory we shall base all our readings on whole body exposure and therefore, limit our exposures to the absolute minimum.
Individuals may receive 1250 mrem exposure to the whole body per calendar quarter.
If the individual has a reserve bank of radiation he may receive up to 3000 mrem in a calendar quarter as long es at no time does the individual 7
exceed the maximum permissible limit as determined by the equation (5 (N (age) -18) rems.
For example, if an individual is 19 years of age and has had no previous radiation history he or she would have a reserve bank of radiation.
In this case the reserve bank determined by the equation would 10 7
be as follows:
5(19 -18) 5 rems.
It should be apparent from this equation that individuals 18 years of age and under have no reserve bank of radiation.
~'
Also, Section 20.101 limits the exposure of minors (10 years of noe and under) to 1/10 the amount of radiation which an edult may receive.
The basic reacons for limiting the exposure of minors to rad'Ation,are threefold.
~
1.
Youth is still in the formative stages of physical development and therefore radiation damage must be avoided.
2.
Radiation muct be controlled at an early age in consideration of the maximum cumulative lifetime exposure.
limitations.
3.
The possibilit1 of raciation mutation effects on the population as a whole muo' be controlled, particularly
]
during the formative period.
J.
Medical Examinations The Medical Department shall maintain a record of radiation F. osages received by all individuals working with radioact:ve materials (Record of Esposure to Ionizing Radi-ation, NAVMED 143 2, (ref (b', ).
The records will be revieved at regular intervals by the Medical Officer to ensure that examinations and analyses are perf ormed as indicated below.
1.
Radiolacical Health Examinations Special examinations are given by the Medical Officer to employees who may be exposed to radiation:
a.
Upon entering employment and on termination of employment.
b.
In field operations involving the use of.
radioactive materials.
c.
Employees involved in radiation incidents, and in other situations deemed appropriate.
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2.
Radiolacical Accidenti A radiological accident is a spillage of radio-7 active material or any contaminating event in which there is a possibility of assimilation of radioactive material into the body.
Each person, whether enployed by NOL or not, who is involved in a radiological accident on NOL premises or at
~
an NOL administered field operation shall submit to a radio-i logical health examination.
E 3.
Routine Urinalyses l
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.
Special sampling shall be done at frequent intervals for personnel using unsealed quantities of tritium or plutonium.
.m 5.
4.
Special Examinations
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The Medical Officer will perfonn special exam-inations, as indicated below:
a.
Any employee possibly exposed to radiation Who develops an acute, unexplained illness of more than three days durs. tion.
b.
Any person Who has received an acute radi-ation expcsure (from eny source) in excess of 25 rem, or a chronic radiation exposure (from any scarce) of 75 rem if 7
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.
S.
Visitors in Work Status Medical examinations may be required for vis Ltors subject to occupational e;5posure to radiation while with in NOL jurisdiction.
Work status visitors may include milit.ary personnel from other installations, contractor personnel, students, or others.
Furthermore, any individual working four successive weeks or more in laboratory creas Where exposure to ionizing radiation is possible shall undergo radiological health examinations.
12
~.
I
.1 K.
Monitorino Instruments Monitoring instruments are essential tools in the radiological safety program.
It is necessary to maintain a
+
variety of types of monitoring equipment in order to measure tha different en"rgiea and levels of radiation involved.
The Health Physics Division is responsible f or the calibration of all portable instruments.
Tlfere are a number of fixed instal-lation instruments in the laboratory (such as continuous air monitors, laboratory-type counters, etc.) as well as a supply of portable instruments.
3 Authorized users of radioactive producing materials may obta.n instruments from the Coordinator of RADIAC Equip-ment, Code'916, NOL.
Representatives from the Health Physics Division will aid and advise in the use of radiation instre-ments as required.
p 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 indivic'aal.
The doses are recorded
~
ar.1 ccmstitute 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 cha:nbers.
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 radiation areas.
2.
Film Badoes The badge employed at NOL is a stainless steel 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.
3.
Pocket Ionization Chambers Pocket chambers are used to supplement film badges in certain designated radiation areas, since they provide an
/
13
~
immediate indication of the accumulated dose received.
While the chamber is used for dose contrel during a specific part of an operation or experiment, the film badge reading is accepted to be the actual amount of radiation recaived and will be retained na a permanent record mf exposure.
Sulf-reading dosimeters must be worn by all person.el presene f.n high radi-
~
atton areas (Zone ?).
L.
Personnel Monitorinq
=
~
The NOL Dosimetry Program is conducted in accordance with regulations established by the Radiological Health Pro-tection Manual (NAVMED P-5055), reference (b), and the AEC for the protection of persons c:: posed to ionizing radiation.
A i
complete recora of exposures received at the Laboratory or elsewhere shall be maintained by tha Medical Department for each person.
The completeness and validity of such a record
~ '
is dependent upon the cooperation >f 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
~
procedures to be followed by the individual whc may be expo' sed to radiation at NOL.
1.
Radiation Received at NOL
~
All persons who work with radioactive mutu2*:1 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
-badges to individual users is the responsibility of the Health Physics Divi ~sion.
All significant exposures will be investi-gated, whether or not the recommended limits have been exceeded.
b.
Pocket Dosimeters Personne~ working in Zone 4 areas (High Radi-ation Area) and/or any otner 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.
Users must check dosimeters frequently, and if a significant reading is indicated, the film badge will be processed immediately to substantiate the chamber reading.
/
14 m
7
2 2.
_ Individual Resconsi'ollity Each individual who is involved with ionizing radiation shall wear his film beige on the chest or collar at all times while in the radiation area.
If a badge is inadvertently left in a radiation field, the individual shall nobity the Health Physics Division of the circumstances related to the exposure.
Film badged shogld not be carried away from MOL.
Employees are specifically cautioned not to wear them when receiving medical x-cuy or radioisotope diegnostic exami-nation and/or treatment.
~
7 3.
Visitors
=
=.
All visitors to facilities utilizing radiation sources, including contractors anc' their employees, must wear i
film badges.
Personnel should r.ci. wear film badges for more than one activity except by prior arrangement with the Health
=
Physics Division.
4.
Radiation Received Away from NOL
=
f Occupational radiation doses received from outside the Laboratory shall also be included on each individual's record.
Each Division' Head shall notify Health Physics when work ir. ilving radiation is to be done at other activities.
If dosimetry service is not available at the other activJ.ty, special film badges shall be furnished by Health Physics and processed locally after return.
.5 5.
Internal contamination In cases of possible internal contamination, the Medical Officer will initiate requests for whole body counting, scanning and bioassays such as radiochemical urinalyses.
He will also interpret results, recommend corrective action, and maintain personnel exposure records.
The Health Physics Division will investigate and eid in evaluation of the findings.
In all such cases the total urinary output over a 24-hour period or periodo designated shall be collected and an analysis made for radioactivity.
6.
P,ersonnel Contamination The Health Physics Division should be contacted immediately in the event of contamination in excess of the lowest levels specified in Appendix A, Part II of Principles 15 J
~
~
of Radiation and Contemination Control (PORACC).
A complete 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 decontamination achieved and the final results of the decantam-ination process will be recorded on special monitoring reports.
~
Form NOL-5100/10 shall be completed by the supervisor resconsi-ble for the operation involved.
2 7.
Notification of Excosure a
Immediate notification of exposure in excess of s
prescribed limits will be made to the individual and to his
[
supervisor by the Health Physics Division.
M.
Personal Protection 5
1.
Eating, smoking, and drinking are prohibited in specified areas where possible radioactive contamination may 5
exist.
Nothing whatsoever shall be put into the mouth, such 5
as pipettes and stems of wash bottles.
2.
All open cuts must be covered before working with radioactive materials.
3.
Gloves are required +.o be worn when handling objecte,that may be contaminatcd.
4.
Protective clothing or equipment should not be worn or taken into any area where food is stored, prepared or eaten.
5.
Food containers or eating utensils shall not be used for storing or handling radioactive materials.
6.
A careful self-monitoring survey must be made by all personnel working with radioactive materials, before
=
departing to a radiation free area.
7.
Protective clothing, as recommended by the Health 2
Physics Division, shall be worn in all operations involving exposure to radioactive material.
Contaminated clothing shall be removed at point of departure from a contaminated area.
N.
Protective Clothina Protective clothing is required to effectively control the possibility of personal contamination to the individual.
16
?'
q All contaminated items should be removed to prevent the sp'ttad r.
of contamination to clean areas.
The type of protective apparel to be worn will depend upon the conditions and circum-stances involved.
For some types of exposure the following 7
5, items are recommended:
1.
Fine weave coveralls or laboratory coats for most Q
laboratory operations.
t, 2.
Gloves (surgeon's ' rubber, cotton, leather, or Fi heavy rubber, depending on the job) to prevent hand contam 5
ination.
i.h 3.
Shoe covering (plastic booties, rubber boots, or.
jj rubber overshoes as required) where potential floor or ground contamination exists.
j5F 4.
Respiratory protection (such as Army Assault Mask M-17 or Navy Mark V Mask) where there is danger of air-.
'=
borne contamination.
E~
EE 5.
Hoods (made of plastic or fine weave canvas) under appropriate conditions.
Protective clothing requirements for all operations in Zones 3 or 4 areas must be specified by the supervisor.
The Health Physics Division will advise on such matters.
gr O.
hivto'niumSafety Recuirements L
There are three main hazards involved in the use of plutonium:
criticality, pyrophoricity, and high toxicity.
1.
Criticality Criticality is the condition when fissionable 239Pu, etc.) is capable of sus-material (i.e.,
235U, 233U,
.m taining a chain reaction.
2.
Pvronhoricity Plutonium metal, hydrides and metallic alloys especially in a finely divided state, are capable of spon-teneous ignition.
This property of plutonium requires the
[][
installation of an automatic fire smothering system.
3.
Toxicitv Plutonium is one of the most dangerously toxic radioactive elements known today.
The long effective half-life E
L 17 lii U
p
and its alpha emissions have been known to produce neoplastic growth in the bone tissue of lower animals.
In man, the recommended permissible body burden for the bone is 0.04 pc, which is 2.5 times more restrictiva than radium.
The easiest method of entry into the human body
~.
Ju via coateminated air.
I ro:.c design of experimental apparatus and good housekeepisg are the first steps toward aerosol control.
Af ter a project has been initiated, air
~
and surf ace monitoring should be performed regularly.
All solutions of plutonium must he covered when not.in use.
3 Another method of entry is via contaminated wounds or breaks in the skin.
Once the material is present in the subcutaneous tissue, plutonium will slowly but continuously be released into the blood streem, liver, a".d bone.
Therefore, 1
all open wounds should be covered before starting work.
Any contact with plutonium should be f ellowed by alpha monitoring and decontamination, as necessary.
5 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
?
possible the glove box should be a completely closed system.
It is imperative that no leakage of plutonium from the glove box be tolerated since an escape into the laboratory may ontaminate the entire building and the building ventilation system.
In the event of such contamination the building must be evacuatcd and will remain unoccupied until satisfactory
_{
decontamination can be completed.
4.
Plutonium Storace and F ire Protection 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 cctivated fire smothering systems.
Large quantities (i.e.,
in excess of 100 millicuries) shall be used or stored only in areas which are further protected with automatic sprinklers.
. Automatic fire smothering systems and sprinkler systems should be of the fully supervised type connected to the central fire station.
P.
Postina and Labelinc All locations in which radioactive materials are used and stored must be posted with a standard radiation caution 18
sign.
The sign must contain the conventional three-bladed radiation cymbol in magenta (or purple) on a yellow background with the wording, " Caution - Radiation Area."
Radiation areas in which ca individual can receive 100 nrom/hr will be posted with a lik: sign stating " Caution - High Radiation Area."
"High Radiation Areas" are provided with audible and/or visible alarms which are energized during source exposure.
Storage
~
locations r.ust be labeled or ppsted with a sign stating
" Caution - Radioactive Materials" in magenta on yellow with 3
the conventional radiation symbol.
Laboratory beakers and flasks containing stock solutions of radioactive materials must be labeled with the standard caution sign as above and additional labeling to denote the kind, quantity, and date of measurement of the material contained.
Fo m 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 Pr ocedures to be followed in procuring radioactive sources and devices containinu medioactive material are as follows:
l.
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 via Health Physics Division, Bldg. T-9.
Requests.will also be routed to the Healta Physics Divisicn through normal channels.
2.
The Health Physics Division will:
a.
Review the request to determine conformity with safe ty and licensing requirements.
h.
Record data necessary to maintain a central record of all radioactive materials at the Laboratory.
c.
Forward the request for processing through regular supply channels.
The Health Physics Division should be notified immediately upon receipt of a radioactive shipment.
The
+
/
19
~.
T'
u f:
H Materials Division of the Supply Department receives shipmeats of radioactive materials and delivers them unopened to the Health Physics Division, Bldg. T-9.
Shipments of radioactive material received by the Mail, Correspondence & Files Division shall elso be delivered unopened to the Health Physics p.f Division, Uldg.
T-9.
u d.
On receipt of'the radioactive material, a
2 Health Physics representative will survey the shipping con-a tainer to determine that both the external radiation reading and smearable contamination are within acceptable radiation limits.
Acceptable limits are less than 200 beta-gamma disin-5
. tegrations per minute and less than 20 alpha disintegrations per minuta.
E
[
e.
Materials receiving special irradiation wil.
be handled directly by Health Physics Division personnel.
f f.
All outgoing shipments of radioactive materials E
from the Laboratory must be made under the supervision of Health Physics.
Shipments will be performed in compliance
~
with the Post Office, Department of Transportation Regulations (ref (e) ), and AEC Rules and Regulations (ref (a) ).
2 R.
Radiation Survey Procedureg 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
=
of use made of.the materials, radiation levels involved, and previous laboratory radiation findings.
Special radiation surveys will be performed by Health Physics personnel at the request of the user.
The Health Physics Division will make a reasonable ef fort 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 Division, however, must of necessity, survey any room or laboratory where radioactive materials are used or stored at any time deemed necessery in the interest of radiation safety.
Radiation surveys consist of radiation instrument readings to determine background levels of radiation and filter-disc swipes as a check on possible laboratory contam-ination.
In addition, air samples are taken in certain designed areas within and on the perimeters of NOL to determine any deviation from normal natural occurring radiation count.
~
Air semples are also taken in laboratories or rooms which have been determined contaminated during a routine radiation survey.
20
Filter discs are used to avipe work surf aces such as work benches, sinks, hoods, end ficors of laboratories as a part of the radiation survey process.
' 'he se filters are then counted for alpha, beta, and gamma radiation content in the Health Physics Laboratory and the results recorded.
If contamination is detected as a result of the surtey, the supervisor in charge of the laboratory is immediately contacted and arrange _
ments are made for removal of the contamination.
The cicaned thea resurveyed by He;;lth Ihysics to determine that are a is the radiation contamination levels 'are within acceptable limits.*
S.
Relative Degrees of Radiati'on Hazards If radiation safeguards are not followed, an individual may receive a significant exposure from either external or
~.
internal radiation.
Radiation that is external can be reacily measured and evaluated.
The exposuce dose may be reduced to acceptable ** values by reducing the time of exposure, intro-ducing appropriate chielding, and/or increasing the distance from the source.
2:
The internal radiation hazard is much more subtle and, unfortunately, much more probable in terms of general use of
~
liquid radionuclides.
When radionuclides become fixed in the
~
body they are difficult to measure and little can be done to improve the hazard situation.
- 'uood Housekeeping" practices are required to pre ent spillage and ultimate spread of radioactive contamination in laboratories.
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.
3 Acceptable Limits:
Less than 10 alpha counts per minute; less than 50 bata_ gamma counts per minute.
1250 mrem per quarter and/or 5,000 mrem per year, (See also Sec. I, page 10. )
z e
G 21 e
g-s I
HAZARD FROM ABSORPTION INTO THE BODY
.h Group '
Activity Scale l g
1 SLIGHT HAZARD ^
1 e louc loouc 1mc lornc icome l euriy 2
"Na K
Cu" Mn 42 52 z4 INT EF.-
L' E
HIGH LEVF 73 i MW
'\\ N \\\\
~
?
- As76, As77, Kr
- Hg 85 1 97 a
i I
I I
I I
I l
I I
l I
I I
M 2
MODERATELY DANGEROUS 5
I I
l l
l 3
3 l4 3
22 35 H,C
,P Na S
I I
g g
l g
C1 Mn Fe",
Co l
1 1
I I
I I
![
136 54 60 i
i i
i i
l I
33 l6 I
I I
I I
I
- Sr89, Cb95 Ru Ru 6E I
I I
I I
I I
5 MX INTER-
\\\\\\ U \\
Y'
- Cs Te 127, Te 12 9, I 131 137 Low LEVEL HIGH LEVEL "1EO!AT 5
\\
\\\\\\\\\\\\
- Ba
- Lal4, Cc l
I l
I41 I
I I
l l4 1
I I
I l
l 1
l Pr!43
- Nd147, Aut9s l
g
=
l
- Au199, Hg "2 Hg l
l l
I 2
25 I
I I
i 1
I c.
3.
VERY DANGEROUS g
i g
g l
l t._
45 55 Ca Fe Sr90 93 8
I I
f I
I
,Y d[EVgl LOW INTER-DU \\ \\
r i?
- Zr atEDIAT HIGH LEVEL 95 Ce
, Pm'47 344 39,,Ra226 (in equi-210 1 e lope 100 e 1mc 10me loome 1 curie Bi Pu librium)
- Principal gamma emitters Activity to be handled in Laboratory NOTES:
1.
Effective radiotoxicity is obtained from consideration of the following factors: half-life, energy and character of radiations, selective localization in the body, rates of elimination, quantities involved, and modes of handling in typical experiment s.
c 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, t
3.
The above hazard grotipings cannot be taken as applying
[.-
to externa} irradiation.
L 22 L.
T.
Remoto Handlina m;im.ent Work uith radioactive material requires remote handling equipment for proper control and canfinement of loose activity.
It is the responsibility of the Departmental users to obtain such facilities as needed for these operations which may include the following-1.
Glove boxes.
+
2.
Enclosea work spaces or restricted rooms.
3.
Shielded areas constructed of lead bricks, concrete 5
pits, etc.
_(
4.
Tongs, and shielded manipulators for use with high levels of activity.
Health Physics will advisa on the procurement and use of the above items as necessary.
U.
Soecial Warnina Requirements
=
1.
Radiatinc Machines All x-ray units are nquipped with audible and/or visible, alarms which are automatically activated wh n '"e machines are turned on.
Additional door interlocks are provided et high energy fixed x-ray installations which cause 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 rr4iation.
2.
Sealed Sources Facilities utilizing sealed radioactive sources for radiographic and calibration purposes must be equipped 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 area).
Standard radiation warning signs are required to be posted and flashing light systems will operate when the source is exposed.
3.
Contaminated Areas and Ecuipment All contaminated equipment, including vehicles, will be tagged with radioactive material tags that clearly 23
/
T1 g
f
- ].
indicate the extent and location of the contamination.
This
~,
equipment will not be put to use until cleared by the Health Physics Division.
- e.,
V.
Etoring and Handling Radioactive Materials Redicactive materials will be stored in a shielded a
area such as a lead brick cavp, or shipping container.
The storage crea and container are required to be labeled with 5
radiation warning signs.
(See Part O, para.
4, Plutonium Storage and Fire Proc.ection, page 18.)
h An operation using radioactive solutions shall be conducted over a tray or basin of sufficient capacity to hold
=
all the solution if spilled.
5e 531utions shall be kept in containers strong enough to withstand breakage and leakage.
For high activity levels, the contciner shall have a secondary container or catchment I
under or around it.
Caution should be exercised in handling highly radior,ccive 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
.\\
secondary non-breakable containers.
There should be sufficient absorbent material to take up the entire sam.ple if spilled.
=
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.
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, J
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 cpproval of Health Physics,.
No contaminated materials shall be taken into machine shops or other service areas, unless these areas have been
.i specifically approved for work with contaminated materials.
Movements of radioactive materials external to NOL (e.g., over the state highways) must comply with the DOT regulations.
The Health Physics Division is responsible for assuring compliance with these regulations.
/
24
W.
Trancter of Materi al Transfers of radioactive materials must be approved
~
by the Radiation Safety Of ficer and/or the Radiation Saf ety 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 radioactive materials unaer a given responsible user.
How-
~
there'are situations in'which a quantity of radioactive
- ever, material may be useful on a special project by another indi-vidual.
This transfer may be completed under the following +
~
conditions:
}
1.
The transferee must be duly authorized by the Radiation Safety Committee to receive the radioactive material.
2.
The transferee must have available facilities and equipment necessary to safeguard the use of the radio-
=
active material.
I 3.
Records will be maintained to reflect locations and users of radioactive sources at all times.
E X.
Tritium Safeouards 1.
Precautions
=
Special precautions need to be taken when working
~
with tritium compounds, or tritium-contaminated materials in quantities in excess of one millicurie.
These include the wearing of rubber glo~.es and the use of glove boxes or hoods.
Rubber gloves should be changed frequently and destroyed, since tritiated water ~vepor has the ability to pass through rubber within a tew hours.
All equipment which has come into contact
, either gas or T 0 vapor, will retai~n some tritium with tritium-2
=
and should be considered contaminated.
Stopcock grease, vacuum pump oil, and plastics are readily contaminated.
Materials such as glass or stainless steel also retain small quantities of tritium.
At ordinary room temperatures, tritium will diffuse through glass or stainless steel or from tritiated 5
accelerator targets.
There are some tritium losses caused by 3
the heat created during accelerator operation.
There is also an exchange mechanism involved when the tritium is in contact with atmospheric hydrogen.
Accelerator targets must always be handled with forceps and rubber gloves since several curies of tritium per square centimeter may be absorbed on the surf ace of the target.
Deuterium tarcets should also be handled with forceps and gloves, since tritium contamination of several microcuries may also be present.
9
~
25
.w g
- x... *
~
Tritium contaminatio:. Is of ten associated wit 2
vacuum pumps.
Accordingly, specia'. precautions must be observed when disassembling or repeiring a pump that has i
been used on a system containing tritium.
Health Physics e,
should be notified in advance of this operation.
Oil and mercury associated with the pumpa should be assayed by Health Physics and if necessary, disposed of as contaminated 5
materials.
2.
Monitoring b
All personnel working t:ith tritium shall period-ically submit urine samples for body uptake evaluation.
The i
Health Physics Division will provide advice on the frequency 5,
of monitoring.
All areas in which tritium is used in quanti-ties in excess of one millicurie, especially in vacuum pumps n-for systems containing tritium, shculd be monitored by Health a
Physics personnel for absorbed surt. ace tritium.
Air monitor-ing instruments, capable of detecting tritium, are available and should be used when there is the possibility of release m
of tritium to the atmosphere.
=::.
Y.
Work Performed After Regular Workino Hours
~
W The Health Physics Division is to be notified of any work involring the use of high level radioactive materials rr.
after re; lar working hours.
In Zcne 4*
areas, at laert two
[
people will be present at all times (NOLINSTR P5100.5A, para.
20, (ref (f) ).
The Health Physics Division will be informed of any b
proposed work in radiation areas or in locations where radio-activo contamination may be present.
A representative of the g-Health Physics Division will evaluate the existing hazard b
and if approved, will forward the work request with his recommen-dations to the Maintenance Control Division.
hh Protective clothing or tools, if required will be provided by the maintenance supervisor.
Maintenance personnel will then follow instructions set forth in the Special Work Permit.
A representative of the Health Physics Division will E
monitor and establish working times for the operation.
Any operation which might result in the liberation of radioactivity E
into the air (aerosols, gases or vapors) must be performed in
[k a fume hood.
If the airborne concentration is likely to be above the recognized RCG, special precautions must be taken to assure personnel safety.
See page 27 f or zone definitions.
e 26 i
Requ,irements for respiratory protection in relation to the leve t of concentration of activity or a'.rborne con-tamination.o are contained in Section C of this manual.
Z.
Zone Precautionary Measures 1.
Zone De s icnat ions I
Laboratory areas are divided into four zones, as
- l follows
.i a.
Zone 1 - Radiation-Free Areas 5
Radioactive materi,1 not permitted.
Examples:
cafeteria, nuditorium, offices, passenger elevators, etc.
No dosimetry required.
b.
Zone 2 - Possible Contamination Areas
=
~
Background control required.
Examples:
freight elevators, radiation ccunting rooms, film storage and develop-e ing areas, laboratories for radiochemical urinalyses and tracer
!L studies.
Contamination control procedures are required and must be formally documented.
c.
Zone 3 - Radi =* i nn Area Work areas where radioactive material may be handled roucinely and radiation producing devices are used.
d.
Zone 4 - High 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.
m O
m e
0 27
~.
N
=
GLOSSAhY Absorbed Dose:
The energy imparted to matter by ionizing radiation per unit mass of irradim ed material at the place of interest.
The unit of absorbed dose is the rad.
One rad equals 100 ergs per gram.
Accelerator:
A device for imp'arting very high velocity to charged particles such as electrons or protons.
These fast
=
}
particles can penetrate matter and are known as radiation.
Alnha Particle:
A small electrically charged particle of very high velocity thrown off by many radioactive materials including uranium and radium.
It is identicel with the
~
nucleus of a helium atom and is made up of two neutrons and two protons.
Its electric charge lu positive and twice as great as that of an electron.
Attenuation:
The process by which a beam of radiation is m
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-E jected through matter.
Beta Particle:
A small electrical]y charged particle thrown off by muay radioactive materials.
It is identical wlG. 'he electron 'and possesses the smallest electrical charge founa in nature.
Body Burden:
That amount of radionuclides distributed through-out the body that will result in a maximum permissible RBE dose rate to the critical organ.
Tha critical organ is con-sidered to be that organ of the body where the greatest amount of damage is done.
Contamination, Radioactive:
Deposition of radioactive material in any place where it is not desired, particularly where its presence may be harmful.
The harm may be in vitiating an experiment or a procedure, or in actually being a source of
]
danger to personnel.
_ Counter:
A device for counting nuclear disintegration to measure radioactivity.
The signal which announces a disinte-gration is called a count.
Curie:
A measure of the rate at which a radioactive material throws off particles.
The radioactivity of one gram of radium is a curie.
One curie corresponds to 37 billion disintegrations per second.
28
i c
i D:rcay :
When a radioactive atom dia ntegrates it is said to decay.
An atom of polonium decayr ;o form lead, ejecting an 1,
alpha particle in the process.
Dosimeter An instrument used to Jetect and measure an accumulated dosage of radiation; a pencil-size ionization 4
chamber with built-in self-reading electrome ter used f or 5
personnel monitoring.
1 Film Badge:
A piece of masked photographic film worn like a badge by nuclear workers.
It is darkened by nuclear radi-
=
ation, and radiation exposure can be checked by inspecting the film.
=
Gamma Rays:
The most penetrating of all radiations.
Gamma rays are very high energy x-rays.
z.,
5 Health Physics:
Health Physics is a profession devoted tc the protection of man and his environment from unwarranted 3
radiation exposures 3
Laser:
Light amplification by stimulated emission of radi -
p ation.
The laser region is that portion of the spectrum
{
which includes ultra-violet, visible light, and infrared.
Leak Test:
A test performed to determine radiation source leakage.,
Monitoring:
Periodic or continuous determination of the i
amount of ionizing radiation or radioactive contamination M
present in an area.
Neutron:
One of the three basic atomic particles.
The neutron weighs about the same as the proton but has no electric charge.
~
Maximum Permiscible Dose:
That dose of ionizing radiation established by concetent authorities as an amount below which thure is no reasonable expectation of risk to human health, and which at the same time is somewhat below the lowest level I
at which a definite hazard is believed to exist.
An obso-lencent tenn.
Radiation:
The emission and propagation of energy through space or through a material medium in the form of waves; for instance, the emission and propagation of electromagnetic
?
waves, or of sound and clastic waves.
Such radiation commonly is classified, according to frequency such as infra-red, visible (light), ultra-violet, x-ray, and gamma ray; O
29 O
9 1
and by type of corpuscular emissions, such as alpha or beta radiation.
Radioactive Inntooe, or Nuclide:
A radioactive form of an element having identical chemical properties but dif f erent atomic mass.
i.
Radioactivity:
The spontaneous decay or disintegration of an unstable atomic nucleus uswally, accompanied by the emission p
of ionizing radiation.
Radiograghv:
The making of shadow images on photographic emulsion by the action of ionizing radiation.
The image is -
the result of the differential attenuation of the radiation
=
in its passage through the object being radiographed.
u Relative Biolacical Effectiveness (RBE) :
The RBE is a facter i
used to compare the biological effectivenesF of absorbed radiation doses (i.e., rads) due to different types of ion-izing radiation, more specifically, it is the experimentally c.,
w determined ratio of an absorbed dose of a radiation in question to the absorbed dose of a reference radiation required to produce an identical biological ef fect in a
=
particular organism or tissue.
REM:
(Acronym for roentgen equivalent man.)
The unit of dose of any ionizing radiation *fah produces the same bio-logical effect.as a unit of absorbed dose of ordinary X-rays.
The RBE dose (in rems) = RBE 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 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.
Survev, Radiolacical:
Evaluation of the radiation hazards incident to the production, use, or existence of radioactive materials or other sources of radiation under specific conditions.
Such evaluation customarily includes a physical survey of the disposition of materials and equipment, measure-ments or estimates of the levels of radiation that may be involved, and sufficient knowledge of processes using or af f ecting these materials to predict hazards resulting from expected or possible changes in materials or equipment.
30
X-Rav:
Highly penetrating radiation similar to gamma rays.
Unlike gam:aa rays, X-rays do not come from the nucleus of the atom but from the surrounding electrons.
They are produced by electren bombardment.
When these rays pass through an object they give a shadow picture of the denser portions.
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31
LEAK TESTING PROCEDURES 1.
All sealed sources will be leak tested by the llealth Physics Section as described below:
s Alpha sources at three (3) month intervals; Gamma sources at six (6) month intervals a.
Techniques Employed (1) Filtcr paper wetted with alcohol (or other suitabic solvent), or ry, will be rubbed over the source or the appropriately accessible surface of the storage container.
(2) Cotton-tipped wooden applicator swabs, either wet or dry will be rubbed over the source or the appropriately accessible surface of the storage container.
b.
_ Counting Methods (1) Each wipe or specimen will be counted for alpha and beta-gamma in equipment of sufficient sensitivity to perform the test. A list of the detection instruments is part of this attachment.
(2) If any Icak test reveals the presence of removable radioactivity in excess of 10% 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. The following calculation is used in making these determinations:
cpn ( bserved) - background Efficiency =
dpm of standard 7 cpm
_10 cpm
.3969
=
Efficiency =
1.39 x 104 dpm
% Efficiency = Eff. x 100
.3969 x 100 = 39.69%
Net cpm (of sample) dp _
efficiency 50 - 10 dpm =
P*
.3969 f f0) r dpm (of sampic) x (4.51 x 10- )
microcuries =
d 100.78
-5
=
6 4.M x 10 pc1 or
- 2. 2.? x 10 100.78 x (4.51 x 10- ) = 4.54 x 10-pei The NRC will be notified within five days of any leakage in excess of 0.005 microcuries
T' s
s N
SPECIAL REQUIREMEMTS GOVERMING THE PURCHASING, RECEIVING, AND SHIPPIMG'0F RADIOACTIVE MATERIAL g
J PURCHASING
- 1. Authorized user determines the need for a particular radioactive source.
2.
User consults with Health Physics personnel with regard to radia-tion safety requirements and submits a Standard Operating Proce-dure (SOP) to Health Physics for approval.
3.
S0P is then submitted to Safety Division for docket' control num-ber and to the user's Division Head for approval.
- 4. Upon approval of the SOP, the user submits a purchase request through Health Physics.
The request must be initialed as approved by dealth Physics prior to procurement.
RECEIVING
- 1. Muclear Regulatory Commission and Department of Transportation Regulations require that radioactive shipments be provided with special labeling as prescribed in Title '32 S:172.403' (a), (b),
(c) and (d) yellow-I, yellow--II and yellow-III labels, to denote the kind and quantity of naterial contained.
The receiving in-voice should also contain information stating the quantity and kind of material received.
I%
2.
If the container is not labeled, the shipping papars would note 7
the fact that labeling is not required in accordance of specifica-U tion 173.391 (Limited quantities of radioactive materials and f
radioactive devices) or 173.392 (Low specific acti.vity radio-
.'j active material).
[,
t
- 3. L'han incom# ng shipmen't:, arrive, Receiving Branch personnel will i-notify the Health Phynien Section inmediately unenever it is j_s de ternined that a shipmn t containa or cay con t< tin radioac tive L.
material.
Posters entitled " PROCEDURES TO BE l'OLLOUED UPOL
}
RECCIPT OF PARCELS COMTAIMTHG RADIOACTIVE MATEiM/iL" are conscic-i nously posted within the receiving dock.
I 12a 1 of 6 l
SPECIAL REQtIIREMEllTS GOVERNIMG THE PURCHASII'G RECEIVING, 3
AND SHIPPING OF RADIOACTIVE MATERIAL (cont'd)
The Health Physics Branch is responsible for assuring that any handling of radioactive shi.pments will not presen t a radiation hazard to Shipping Branch personnel.
The assigned Health Physi-cist will monitor throughout the packaging and shipment processes -
to prevent exposure of any individual from exceeding acceptable radiation dosage limits.
Film badges. S TLDaare providc4 as needed.
Radioactive material shipments will be monitored by the Health Physics Branch for radiation emission prior to release from the laboratory, including possible radioactive contamination on the shipping container.
Shipping documents will be checked to assure that the appropriate information is given as required by HRC and DOT regulations.
Shipping papers will contain the following information:
1)
The name of the radionuclide and the form, or a description of the physical and chemical form if the material is not in special form.
2 )- The activity contained (in curies, millicuries or microcuries).
3)
The gross weight of the container, if over 110 lbs.
4)
The requirement for the transporting vehicle to be placarded.
5)
If the package is one which has been approved by the U.
S. Energy Research and Development Admin.
(ERDA) or the Nuclear Regulatory Commission (NRC),
a notation of the package identification as ERDA or URC prescribes.
6)
The type of packaging required by the Denartment of Transportation. for Type A Qty of. NRC nType B Qty.
7)
The category of the label to be applied:
RADI0 ACTIVE WHITE-I:
if measures 0.5 millirca or less per hour on external surface and in not a "large quantity'.'i RADIOACTIVE YELLOW-II:
if measures more than 0.5 but less than 50 millirem per hour on surface and no t exceeding 1.0 millirem per hour a t three ieet from any poin t on the external.urface of package.
RADIGACTTVE YELLOW-III:
if measures more than 50 millirem per hour on external surface or exceeds 3.0 millirem per haun at three feet from any surface of the package, and does no t exceed 200 nillirem per hour et the surface and 13 millirer per hour at three feet from the external surface of the package, or the package contains a "large quantity"- of radioactive material.
12a 2 of 6
SliIPPING 1.
Shipping Branch, Supply Department, is responsible for final packaging and shipment of radioactive material.
b'
- 2. When special packaging is recessary to ecmply with reaulations
.[
governing shipping of radioactive materials, IIealth Physics Sec-b tion will advice and assist as necessary to satisfy the require-h ments.
3$
3.
The radioactive material user will be responsible for transfer t
i, to the Shipping Branch of outgoing parcels containing radioactive d-materials.
The Health Physics Section will advise and assist in these matters and must approve final transfer of the material for shipping.
t 4.. All shipping paper, marking and labeling shall meet the the requirement as specified in DOT Reg. Title 49 parts: Type A Qtye M 172-200 thru. 172-204.; 172-300 thru 172-330.; 172-400 thru 172-446 and all packaging as specified in Reg. 173-391 thru 173.446.
t
- 5. All shipping of Type B Quantities shall meet the requirements of Title 10 CFR Part 71.
t i
l Type A Type B Transport Grp.
(Quantity in curies)
I 0.001 20 II 0.05 20 III 3
200 IV 20 200 V
20 5,000 VI S VII 1000 50,000 m__
Special form 20#
5,000 MT li except 252 Cf, limit is 2.
e.
M fr v
!D r.k-la.
[2a 3 of 6
4 General packaging and shipment requirements.
Unless otherwise specified, all shipments of radioactive materials must meet all requirenents of this section, and must be packaged as follows:
The outside of each package must incorporate a feature such as a.
cent, which is not readily breakable a nd which while intact, will be evidence a
has not 'cen illicitly opened.
t nn the package o
b.
The smallest outside dimension of any package must be 4 inches or greater.
c.
Each radioactive material must be packaged in a packaging which has been designed to maintain shielding efficiency and leak tightness, so that under conditions normally incident to transportation, there will be no release of radioactive material.
If necessary, additional suitabic inside packaging must be used. Each package must be capabic of meeting the standards according,
to specification 173-398 (b) and 173.24.
h A> w e. A'? MI, 4 x. W e H N
r a,u s g.
d.
Internal bracing or cushioning, where used must be adequate to assure that, under the conditions normally incident to transportation, the distance from the inner container or radioactive material to the outside wall of the package remains within the limits for which the package design was based, and the radiation dose rate external to the package does not exceed the transport index nwnber shown on the label.
Inner shield closures must be positively secured to prevent loss of the contents.
The packaging must be designed, constructed and loaded so that c.
during transport:
(1) The heat generated within the package because of the radioactive materials present will not, at any time during transportation, affect the efficiency of the package under the conditions normally incident to transportation, and (2) The temperature of the accessible external surfaces of the package will not exceed 1220F in the shade when fully loaded, assuming still air at ambient tenperature.
If the package is transported in a transport vehicle consigned for the sole use of the consignor, the maximum accessibic external surface temperature shall be 1800F.
12a 4 of 6
hhen packages containing " Fissile radioactive material" means the following materials:
Uranium-233, Uranium-235, Plutonium-23S or any material containing any of the foregoing materials. The following materials are not classified as fissile radioactive naterials are exempted from this section and must instead be packaged in accordance with the other provisions of this subpart, as appropriate:
a.
Not :: ora than 15 grams of fissile material; b.
Thorium, or uranium containing not more than 0.72 percent by weight of fissile material; Uranium compounds or other than netal, and aqueous solutions of c.
uranium, in which the toal amount of uranium-233 and plutonium present does not exceed 1.0 percent by weight of the uranium-235 content, and the total uranium content; d.
Ilomogenous hydrogenous solutions or mixtures containing not more than; (1) 500 grams of any fissile material, provided the atomic ratio of hydrogen to fissile material is greatern than 7,600 or (2) 800 grams of uranium-235, if the atomic ratio of hydrogen to fissile material is greater than 5,200 and the content of other fissile material is not more than 1.0 percent by weight of the total uranium-235 content of (3) 500 grams of uranium-233 and uranium-235 if the atomic ratio of hydrogen to fissile material is greater than 5,200 and the content of plutonium is not more than 1.0 percent by weight of the total uranium-233 and uranium-235 content.
Fissile radioactive materials packages are classified according to the controls needed to provide nuclear criticality safety during transportation as follows:
Fissile Class I - Packages which may be transported in unlimited number a.
and in any arrangement, and which require no nuclear criticality safety control, a transport index is not assigned to Fissile Class I packages. Ilowever, the external radiation IcVels may require a transport index number.
h.
Fissile Class II - Packages which may be transported together in any arrangement but in nembers which do not exceed an aggregate transport index of 50.
For purposes of nuclear crit icality safety control, individual packages may have a transport index of not icss than 0.1 and no more than 10.
!!owever, the ex ternal radiation levels may re" ult e a higher transport index number but not to exceed 10.
Such shipments equire no nuclear criticality s tfety control by the shipper during transpor :ticn.
Fj:,sile Class III - Shipments of packq s dich do not meet the c.
requiremenWoTI tssile Class I or Il and which are. controlled to provide nuclear criticality safety in transportation by special arrangements between the shipper and the carrier.
J2a 5 of o
d
. Definitions.
(a)"Large quantity" means a quantity of radioactive material, the_ aggregate of which exceeds any one of-the following:
For transport groups as defined in paragraph (b) below:
Group I or II radionuclides:20 curies; Group III or IV radionuclides:200 curies; Group V radionuclides: 5000 ctiries ;
Group VI'or VII radionuclides: 50,000. curies;.
For special form' material as defined in para-graph (c) below: 5,000 curies.
(b).-Tran~ port group" means any'one of'seven grIups '. '
s into which radionuclides in normal form are classified, according to their toxicity and their relative potential hazard in transport.
.For further information as to classification, See Code of Federal Reg's Title 10, (CFR 10).
Par,t 71:4 E Appendix C.
(c)".Special form" means any of the following physical forms of licensed material of any transport group:
- 1) The ma terial is.in solid form having no dimension less than 0.5 millimeter or at least one dimencion greater than 5 millime.ters; sublime, or ignite in air at a temperature ofdoes not melt,
.J 1,0000F; will not shatter or crumble if. subjected.to l
the percussion test described in CFR 10 Part'.7.1, I
Appendix D; and is not dissolved or converted ~into I.
dispersible form to the extent of more than 0.005 %
i by weight by immersion for 1 week in water at_680F.
or in air at 860F.;or
~~
- 2) The material is securely contained in a capsule having no d.imesnion less than 0.5 millimete'r or at I
least one dimension greater than 5 millimeters, which i
uill retain,its contents if subjected to the tests prescribed in Appendix D (CFR 10~Part 71); an'd which is, constructed of materials which do not melt, 0
- sublime, or ignite in. air at 1,475 F., and do not dissolve or conv.ert in to dispen.ible form to the extent of more than 0.005 % by ve)/nt by immersion for 1 week in uater at GSOF. or in air at 860F.
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o
,1
't 12a 6 of 6 1
PROCEDURES FOR ISSUASCE AND PROCESEING OF FILM BADGES Film Badges 1.
New films will be furnishea en a routine monthly frequency by the Health Physics Division.
2.
Each film badge has the employee's name and identifying numbers.
Only the person indicated may wear that film badge.
3.
Each film badge is dated to show the period covered.
4.
Control badges, not to be worn, are maintained at each rack location.
These control badges are developed monthly.
5.
Film is purchased through DASA Contract, DASA 120-71-D-3594.
Processing of the film is provided by the Naval Medical Center in Bethesda, MD.
The results are reported to this activity, and are reviewed by the RSO to determine the necessary action required.
6.
The Radiological Safety Officer will review all reports and check for any high or unusual results.
The individual involved and ais supervisor will be informed of film badge findings.
7.
The Radiological Safety Officer will be responsible for maintaining a file on all film badge results received.
Duplicate records are maintained on a computer generated Form DD-ll41.
8.
Personnel working in Zone 4 areas (High Radiation Area) 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.
9.
Radiographic personnel shall be removed from exposure to radiation when necessary to keep their individual dosages frcm exceeding 100 mrem per week.
10 Lithium Fluoride Thernoluminescent Dosimetern should be used also for neutron monitoring. (see page 2 of Page 12b).
12b 1 of 3
LITHIUM FWORIDE 'mEP3!0 LUMINESCENT DOSIMETRY:
Each individual will be issued by Health Physics section a lithium fluoride thermoluminescent dosimeter (LIF TLD). These LIF TLD will be forwarded for reading and dose determination, every 2 months (not to exceed 90 days) to the Radiological Safety Service, National Naval Medical Center, Bethesda, Maryland 20014.
r Each LIF TOLD will bear the employee's.name and identifying numbers.
Only the person indicated may wear that LIF TLD.
Each LIF TLD will be numbered and logged on a separated sheet of paper to show the period covered.
Control LIF TLD (which are not to be worn) are maintained at each rack location.
These Control (LIF TLD) are also developed every two months.
LTD Program:
The LIF TLD is capable of detecting gan=a, X-ray and neutron radiation.
The LIF TLD will be issued to monitor personnel for gamma and/or neutron radiation. The LIF TLD contains two lithium fluoride chips; one has been enriched with lithium six which will respond to gamma radiation and thermal neutron radiation, while chip number two has been enriched with lithium seven which will only gespond to gamma radiation. The range of the gIF TLD is 00.005 to 1 x 10 Rea for gamma radiation and 00.030 to 1 x 10 Rem for neutron radiation.
Collection:
The LIF TLD's in their holders, shall be mailed to the Radiological Safety Service, National Naval Medical Center, Bethesda, Maryland 20014, within three working days following collection.
The dosimeters shall be arranged in the same order as they appear on the NAVMED 6470/3.
The dosimeters and NAW!ED 6470/3 shall be shipped in a mailing container,.such as box NSN 8115-00-782-3939,,(7 1/2" x 4 3/8")
or box NSN 8115-00-782-3940 (7 1/2" x 7 x 3 3/8") that will prevent damage to the dosimeters.
Because of the cost of the LIF TLD cards they shall be mailed using traceable means to prevent loss.
12b 3
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i
e The Model L-70 has the Gamma and X-Ray sensiti.vity supressed so the reading is 200 mrem full scale for thermal neutron only.
Diameter 1/2" Length 1 1/2".
Model L-S1 is an X and 1;anma ray chamber for 2r full scale range.
It is normally worn with an open adjustable finger ring to protect the hands of isotope workers.
Diameter 1/2" Length 1 1/2".
Model L-60 Charger._ reader for charging and reading above mters Tt m:.es the rugged type qmtrt: t'the r '. o l tmet ers lia tt eries are ea s ily replaced.
They consist of one 1 1/2 volt size D cell to provide light for the uieroscope field and six 22 1/2 volt No. 412 minimax batteries. % cir life is at least two years (shelf-life).
The scale is narked clearly so that all the afore menti.oned meters can be read without interpolation. (Ref Johnson 5 Associates Catalog).
Do:;in et er :
DT-518/PD Non self-indicating dosimeter capabic of detecting and recording fast neutron exposure from 10 to 50,000 rem and ganma ray doses from 1 to 10,000 rem.
This is done by means of sulfur tablets for neutron dose and thermo-luminescent powder for gamma and x-ray dose:
Size 1.1" x 5" x 5";.017 pounds.
Sulfur tablets are processed after exposure and counted. The thermo-luminescent powder is placed in a Victoreen 2800 model unit & read.
14363 12c