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INSTITUTIONREPORT NOPUB DATENOTE
AVAILABLE FROM
DOCUMENT RESUME
SE 018 840
Radiological Monitoring for Instructors. StudentWorkbook. Revised.Office of Civil Defense (DOD), Washington, D.C.SM-11.22.1Apr 6864p.; Occasional Small Print Used in SampleExercisesThe Fallout Plotting Template described in Chapter 3is available from ERIC/SMEAC, The Ohio StateUniversity, 1200 Chambers Road, 3rd Floor, Columbus,Ohio 43212 (on loan)
EDRS PRICE MF-$0.76 HC-$3.32 Plus PostageDESCRIPTORS *Educational Programs; *Emergency Programs;
*Instructional Materials; *National Defense;Radiation; *Radiation Effects; Safety; ScienceEducation; Workbooks
IDENTIFIERS Department of Defense; DOD
ABSTRACTThis student workbook includes the necessary
materials and some of the references needed by each student duringthe conduct of the Radiological Monitoring for Instructors (RMI)course. The contents include a radiation exposure record, instrumentexercise materials, fallout forecasting problems, dose and dose rateproblems, source handling techniques, quizzes and answer sheets, anda RMI course examination answer sheet. (LS)
***********************************************************************Documents acquired by ERIC include many informal unpublished
* materials not available from other sources. ERIC makes every effort ** to obtain the best copy available. Nevertheless, items of marginal *
* reproducibility are often encountered and this affects the quality *
* of the microfiche and hardcopy reproductions ERIC makes available *
* via the ERIC Document Reproduction Service (EDRS). EDRS is not* responsible for the quality of the original document. Peproductions ** supplied by EDRS are the best that can be made from the original. *
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-
4
THE PERSON OR ORGANLZAT,ON ORIGINA FING IT POINTS OF VIEW OR OPINIONSSTATED DO NUT NECESSARILY REPRESENT OF FICIAL Nal IONAL INSTITUTE OFEDUCATION POSITION OR POLICY
SCOPE OF INTEREST NOTICE
The ERIC Facility has assignedthis documentto: e-In uur judgement, this documentis also of interest to the clearing -houses noted to the right. Index-ing should reflect their specialpoints of view,
to'
RADIOLOGICAL MONITORING
FOR INSTRUCTORS
Student Workbook
(Supers-Aes SM-11.22-1 dated June 1964which may not be used)
DEPARTMENT OF DEFENSE
OFFICE OF CIVIL DEFENSE
CONTENTS
Note to the Instructor
This Student Workbook includes the necessary materials and some of the references neededby each student during the conduct of the Radiological Monitoring for Instructors course. Allpages are perforated for easy removal.
Page
Radiation Exposure Record 1
Instrument Exercise Materials:Worksheet for Operation Prospect Exercise 3
Worksheet for Instrument Familiarization Exercise 5
Table of Decay Correction Factor for Cobalt 60 7
Sample Worksheet for Instrument Radiation Response Exercise 8Sample Radiation Respones Curves for the CD .V-700 9
Worksheet for Instrument Radiation Response Exercise 10
Radiation Response Curves for the CD V-700 11
Sample Worksheet for Area Monitoring Exercise 13
Worksheet for Area Monitoring ExerciseWorksheet for Radiation Protection Exercise 15
Worksheet for Student Proficiency Exercise 17
Fallout Forecasting Problems 19
Fallout Plotting Template (inside back cover)Dose and Dose Rate Problems 21
Dose Rate Nomogram 25
Entry TimeStay TimeTotal Dose Nomogram 26
Source Handling TechniquesHomewon: Assignment 27
USAEC Compliance Offices by Regions 28
Sample Form AEC-374, Byproduct Material License 29
Sample Byproduct Material User's Certificate 31
10CFR-20, Standards for Protection Against Radiation 33
10CFR-30, Rules of General Applicability to Licensing of ByproductMaterial 41
10CFR-31, General Licenses 47Procedures and Regulations for the Care and Use of the OCD CD V-778
Radiation Training Source Set 51
ACE Licensing of OCD Source Sets for Radiological Monitor Training 67
Answer SheetsQuizFallout Forecasting Answer Sheet 71
QuizUse of Radiological Instruments Answer Sheet 73
QuizDose and Dose Rate Calculations .Answer Sheet 75
Quiz--Source Handling Techniques Answer Sheet 77
RMI: Course Examination Answer Sheet 79
4
iii
RADIATION EXPOSURE RECORD
\ NAME
AGE DATE. OF BIRTH
SOCIAL SECURITY NUMBER
DOSIMETER SERIAL NUMBER
DATEINITIAL FINALREADING READING
DOSE
DATE TOTAL EXPOSURE
SIGNATURE
5
WORK SHEET FOROPERATION PROSPECT EXERCISE
SOURCE LOCATION OF SOURCE
0 (BASE OF FIRE HYDRANT)
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
NAME
3
WORK SHEET FOR INSTRUMENTFAMILIARIZATION EXERCISE
CD V-700
DISTANCE(FEET)
RANGE METER MEASUREDRATEDOSE
c goy.)
1
2
3
4
5
6
8
10
12
14
16
18
20
CD V -715 (r/hr)
1 x
1.5 x
2 x
2.5 x
NAME
I
TABLE OF DECAY CORRECTION FACTORS FOR COBALT 60
X factor (1 month)
MONTHS 0 1
= 0.01
2 3 4
half life =
5 6
5.3 years
7 8 9
0 1.00 .99 .98 .97 .96 .95 .94 .93 .92 .91
10 .90* .89 -.88 .87 .86 .85 .84 .83 .82 .81
20 .80 .79 .79 .78 .77 .76 .75 .74 .74 .73
30 .72 .71 .70 .70 .69 .68 .67 .67- .66 .65
40 ,65 .64 .63 .62 .62 .61 .60 .60 .59 .58
50 .58 .57 .57 .56 .55 .55 .54 .54 .53 .52
60 .52 .51 .51 .50 .50 .49 .49 .48 .48 .47
70 .46 .46 .45 .45 .44 .44 .43 .43 .42 .42
80 .41 .41 .41 .40 .40 .39 .39 .38 .38 .38
90 .37 .37 .36 :36 .35 .35 .35 .34 .34 .34
100 .33 .33 .33 .32 .32 .31 .31 .31 .30 .30
110 .30 .29 .29 .29 .28 .28 .28 .28 .27 .27
120 .27 .26 .26 .26 .26 .25 .25 .25 .24 .24
130 .24 .24 .23 .23 .23 .23 .22 .22 .22 .22
140 .21 .21 .21 .21 .20 .20 .20 .20 .20 .19
SAMPLE PROBLEM: If the activity of a source was 8-millicuries in June
1961, what was the activity in April 1962?
ELAPSED TIME
DECAY CORRECTION FACTOR
SOURCE ACTIVITY IN APRIL 1962 8 X .90 = 7.2 me
10 Months
.90*
7
SAMPLEWORK SHEET FOR
INSTRUMENT RADIATION RESPONSE EXERCISESOURCE ACTIVITY 27C SERIAL No /23'2/FORMULA Used to determine calculated (ACTUAL) dose rates.
Dose rate in mr/hr = (13.21 (Number of millicuries Co6° )
(distance in teet 2
DISTANCE RANGE METERREADING =
MEASUREDDOSE RATE
(mr/hr)
CALCULATEDDOSE RATE
(ifirjhr)
1 00 x OFF = SCALE 96-2 /00 x .26 = 26 2/3 /00 x .74/ = /2/ /14 /00; x .07 = 7'0 6.05 lo x .39 = 3.67 3.r6 /0
/0 x
.26
. /l=
=
2.6**i 6
2..6 .X
1.58
lo /0 .1/ /./ / 012 10 x .07 = .70 0.714 /0 x . oc = .50 eq'16 1 x .33 = -33 .3718 / x .26 = .2 2q20 / x .22 = .2Z. .2.4z22 / x ./8 = ./ff .2024
x =
* Obtain reading near mid-scale on X10 range**, Before readings are taken, adjust calibration screw so measured
dose rate equals calculated (ACTUAL) dose rate at dose rate pointnearest to 2.5 mr/hr *
NAME8 C/
9
SAMPLE
RADIATION RESPONSE CURVES FOR THE CD V-700
SOURCE ACTIVITY WIZ SERIAL No. /234
50 5 .5
40 4 .4
30 3 .3
20 2 .2
10 1 .1
L 34T,
Calculated (Actual) Dose Rate (mr/hr)moe i emuim uo mmommissommimmommmoommormimummismisommemmommumanimmmissamplimmasmommommimmilmMOOSOOMOOM MOMOIMMOO IIIMOOMSSOMOMMOOOMMOMOOMOMMOSOMMMOMMUMMOME OMMUNOMMISMOMMOMMMEMEMOSMOMEEMMOMMEmmmOMUMEMOM M E SN O MOIN S M M OmossminimOMOMMOOMMUMMOMMIMIMMEMSOMEMMEMEOMMEMMOMOMMOMmmmmmmmsmmmmmmmummmmmmmmmmmmmmmmmOmmsmsmmmmmmmopmmO SOOMOMOMMISSIMMOMOMOOMMOSIMMOOMMOMMOMOMOOMMOMMOMMORMIIMIM M O M M OMSI MS M OMMOMOOMEMMSMM OMMM OMOMMOMMIIMMEMMUMMOMOMMIEMMUOMMMUMNOMMOMMOMOMOSOMmenMMIMMOMMOmmommingimmmampimpeommisimmilmmesmommummumgmapommMMEMMOOMMOMMUMEOMEMMEMOMOMMUOMMOMMLADMEMOIMMOMMEM O M OB SMIN MIA M MUO MOMMOMMOUOMOUOMMUSSOMMOOMMOMOXID OdOMMMOOMMOMMUMOMUEMO OMMOMMOMMODSMOMMIMMOMMOOMMMOM AOMMOMMOOMMIIMMSOMUMOmmommommingiallSommlimm eilmmulrnummilimemsmi mmmmmmsmmmmmmmmmmummmmmmmmmmsmmmmmmmmspMOO M BAIOMM MUS UMmAisOOWEAOOOU MSOMErnmeaMMUMOMEMOOMMEMMOssOmPAIMOMEMEMEMSEMOSOMMEm sm O mnwA m mmMMS OOMM RPA O OMMEMOMMEMMEOMMOMOMMOOMME mmommonsimplimmmommanmmmemplummummsommommon moommimmummimmilm.o u mer empmomommommemmommommommemprAmmil mmilimmismommammumnimmo
IMMOSOWOMM 2:1001MOWAIRIMMMOMMOMMEMOMMOOMMOOMMOWIOMMOAMIVAISMMMOMMOMOMEMO PAIMMEMOMEMOSOMMOMMOSMOMMEMOOMSOOMMOMirAmm sMOOMMOMOMMINIMMOIAVAUrAMOMOMUMMUMMOMMOMMOSMEMMOMOMOMMUMOE MMOMMIIIIMMOMSWAPIWAMOMOMMMUOMMEMOMMEMOMMOMMOMMEMMOmmMOMOMMOMMOOMWACIWASMOMOSSOUSSOMMIIMMOMTMOMOOMOMMEMMOamOMMOOMMOMMKAMMVANSOMOMMOMMMOMMOOMOMMOMOOSOMMOUMMA4MOPAMEOSOMUMMOUMOOMMOMMOME MMIlmilmma MommomOOMEOMorginmendminlmilmumilimmOMMIOmmemommis momOPAAMOMMMOMO RI E MOMOOOMMOOMVIWA M OM Mu nsrA mo i o l uwarA s mUM AIrd O S OMOMME.WrFAMOMOMMOMMOOMMIIMOSOMMOMMOMMMOMMOMMOMMMOMMOMMOmA:MOMMOOMOOO OSOM I OIIMOMMOSIIMMOMSOMMOMOMMOMMMOMOOMMOMMMOMMOOMMOMMOOMMOMM K,YAMM MEM M OMV OirlA me ou111P/IMOMOUSOOMMWIRMOOMMOMOMUMMOMMOOMBOOMMOMOOMMOMMOMMEMA SMOMMMO OBSS MOMrAM OV M O O
xl--------4x10
x100 10
DATE a /%3NAME
.2 .3 .4 .5
2 3 4 5
20 30 40 50
Calculated (Actual) Dose Rate (mr/hr)
_I 0
*Operational Check Source
9
WORK SHEET FORINSTRUMENT RADIATION RESPONSE EXERCISE
SOURCE ACTIVITY SERIAL No.
FORMULA: Used to determine calculated (ACTUAL) dose rates.
Dose rate in mr/hr = (13.2) (Ntimber of millicuries Co 6°
(distance in feeti 2
DISTANCE RANGE x METERREADING
MEASUREDDOSE RATE
(mr/hr)
CALCULATEDDOSE RATE
(mr/hr)
1 x =
2 x =
3 x
4 x =
5 x =
6 x _
8 x =
10 x
12 x =
14 x =
16 x =
18 x =
20 x =22 X
24 x =
x =
x
x =
NAME
10
zt7
1>
1>
1X tr
lM
6 0 0 0
0
04.
A.
0
0
Mea
sure
d D
ose
Rat
e m
r/hr
0 N
00
0 (.17
illisSMUOROMMOOOmmmemoilmomumemmolimmem
mom
seommomommemmumasumumumansMOMMEmmemmismamilminsons
OmmilesoMOMMEmosommisomOnsa mOMMOOsSOMOIWOMOSOUS
nsminipmesiMmellemmoemmmessommmemmilinOmmemmerm
mamilinimmemmipMOMOssommommilimmommamilliesilmomMOSMOMMon
milmOMMEMMOMOMMOOSMOUMOMOOMMOSEMOOKOMOMOOMMOMMOmmoss
w assmilimmosummesullimemismonsmemislimassamMillimMUSEMIESMOmm
immommommomilmommummummommemmowessommismemmummimmumme
milimmilimmimmOmOmOSIMMnimmummomminomplimmemmossim
mmommossmommaimmommommommommesmilipmMOMMOMMOOOMOMM
mmwmsasmmmmmmwmrmmgwmpmmwpmwmwmmmmwmmsmmmmwmmm
U MOSSIMMOSSOOMMEM mummummommesummemommumemsgmmulsom
munionommummile Tmmmmmmomssmmmmswimmmmmosggmissm
simmessmomm mem smiummommommensmomm
POMOMMISOMOMMOOM
MOOMOMMOOMOMO MOO OMSONISOOMMOOOMMOOMMWMOOSSOMMOOMOSOM
immommissommommtmemmommemommommismosimumsommoss
malmommmommemmommewsmossammommammommemmermamumm
MOOMMOMMOOMMOSOOSOSOODMOSSIMMISSOMOMMUOMMOOMMOSMOS2
MOMOOMEIMMUMMOOMEMOOmmilminiMOSEUSImiSameMOMMOsussa
smommummemwommummusimmemslinsimMOMMOODOWOMMMO
nnnnn nommommammemummotimmmilmommum nnnnnoweimmo nnnnn amonms
OOMMOMOOSOONOOSSOESOMOMMMOOMSSOMMOOMMOO OSOMOOMMO
marnammummegiminimonsemilmilimmallOOMMOMMOOMMMOOSOIMUME
ilimmumaummingsmemleamosompOOSOOOmommilmOMMOOmmommo
VISOSOMOUSMOMOQOMMOMOOMOMMOOMOOMOOSUOMMOOMMOOMMUOM
mansmumminimmissimminimmammismosommOSIMMOSIMMOUO
w immemmemmommumummommoommimmummossammummommomm
MUMMOMMWOMMOMOMMOMMOMMMOROMOMMEMOMMOMOMMUMMOMOMOMOMMOOM
moommingemmosommommommanmememisommummassmimmums
W OMMINIMMONMOMORMOOMMOMORMOMOMBONSMOOMOORMOOMODUSOSOOM
Immilommumwmommemmommimmimmumummensmilmsommummegm
smommommummmemeamommosamommornmosemmillommilommlummIlms
mummummessummommummumarmommilimMOMMOOOMMIlismsemil
memillmmilmOSIODOMMIOMO
smiummummommillisOmMOrnsomem
mommossommummummumm millaseimommisOlmsommimummoss
immsmommeminimmommemommummussmimmonesegossommomm
mumminimmommilimmommommimmommemismimmimmemmem
O MMOWOMMOMOMMMOWOOMMOMMOSMOMOOMMOMMOOMOMBellOOMMOSNOMOO
U MMOUOMOMSMOMODMOMOMMOSOMOOMMOOOMMOOMMOOMOMMOOMOSOMMOMO
wommummessomm mm msommommammismismimmummummams
mosmosommommummommommumminumammommimplimmommompossman
S OMOMOSSMOSIMMOOMMOsimmipsOMMOINIOMMonanOMOMOOMMO
OnSiallommOMOOMilmminlimuSiummummumnsummgemmomilmemmummi
mummommelimmu mimmlumemmillesSOOMMOMMMOMOSMOOMMIMOOMOO
MMOVOUMMOOMMOO
OSOMOMMISSMOMOMOMOSSOMOOMOOMOOMMOOOMMOO
imeiNimmesflurilisMINutigegspirgmemeggireptagmusimi
mosomemmOommws
EMMOOMmolimO
immummemommom
sgsammommess mommimmemommiummummummommilimme
smommusommussammemmommammammommimmmemmossmiss
MUMSMOMOMOMMUMBOMMMUMMOOMMOOMMEMOOMOOMOSMOMMOMOOMMUMMOM
w wwommummemimossmumwspwommoggsmosimmpmmemomimppismommeme
ssmsmsmmmmmmmgmmmgmgmwmmnummmmMmmmmgpmmmmmmmmmmmsm
w mmmmsmmsmmmmmmsmmmmmmmmosmmmmmmmOmmemmmmssmmm
MOOSOOMMOMMOMMISMEMOMOMMMOOMMOMMOSOOMOMSSEMOUSMOOSSOR
MOSSORMSOUSOMOOMOSEMMUMOMOMOOMMOOMMOSOOMMOMMUOMMOSOMOOM
1
SAMPLE
WORK SHEET FORAREA MONITORING EXERCISE
A
5 6 7 5
6 r/hr
F
5 4
5 8
6 7
37
8 3
20 r/hr
4 (1:
3 4
19
15
1
2
4
6
WORK SHEET FORAREA MONITORING EXERCISE
A
7
8
NAME
14
C D
1 1
WORK SHEET FORRADIATION PROTECTION EXERCISE
DISTANCE
TIME I DOSIMETER READINGSAVERAGE CALCULATEDREADING READING
DISTANCE
TIME DOSIMETER READINGSAVERAGEREADING
CALCULATEDREADING
-r
DISTANCETIME
SHIELDINGMATERIAL
DOSIMETER READINGS AVERAGEREADING
% REDUCTION
NAME
1 5
15
WORK SHEET FORSTUDENT PROFICIENCY EXERCISE
STATION I, LEAK TESTING
The results of the leak test were
STATION II, PROTECTION FACTOR
A. Outside dose rate =
Inside dose rate =
Shelter protection factor = outside dose rateinside dose rate
B. Using the protection factor found in A above, calculate the following dose rates:
1. Inside dose rate = 5 r/hr
Protection factor =
Outside dose rate =
2. Inside dose rate =
Protection factor =
Outside dose rate = 500 r/hr
NAME
17
10
STATION III, PERSONNEL MONITORING
Place an X on the diagram corresponding to exactlocations contamination is found on the person beingmonitored.
18
FALLOUT FORECASTING PROBLEMS
Problem 1Strike: 5-megaton detonation on Detroit, Mich.
Closest Rawin Station: Flint, Mich,
Latest OF Data: 11408 21310 41112 60920 80818
Plot the probable area to be affected by fallout from this weaponduring the first 3 hours after detonation.
0 40 80 120 160 200 Miles
MI MN MI MS
Stem
Scale 1" =. 40 Miles
20 mile diameter10,000 and 20,000 ft. vectors
Cloud 40 mile diameter40,000 60,000, and 80,000 ft. vectors
Ground Zero 40 mile diameter
19
18
Problem 2
Strike: 8-megaton detonation on Miami, Fla.
Closest Rawin Station: Miami, Fla.Latest OF Data: MIA 11409 21409 41912 62116 82418
Plot the probable area to be affected by fallout from this weapondufing the first 6 hours after detonation. Include the hourly
isochrones of fallout arrival.
80 160 240
MIAMI
320 400 Miles
EM I= MN I= MI I=Scale = 80 miles
Stem 20 mile diameter10,000 and 20,000 ft. vectors
Cloud 40 mile diameter40,000, 60,000 and 80,000 ft. vectors
Ground Zero 40 mile diameter
20
DOSE AND DOSE RATE PROBLEMS
Dose Rate Problems
1. If the dose rate at 1 hour after burst is 40r/hr, what will be the dose rate at 2, 4, 6, 8,and 10 hours?
2. If the dose rate at 11+1 is 100 r/hr, whatwill be the dose rate at 2, 4, and 10 hours?
3. If the dose rate at H+1 is 350 r/hr, whatwill be the dose rate at 5, 8, and 12 hours?
4. If the dose rate at 11+6 was 45 r/hr, whatwould be the dose rate at 1, 9, 12, and 15hours?
5. If the dose rate at.11+12 was 80 r/hr, whatwould be the dose rate at 1, 16, and 24hours?
6. If the dose rate at 11+20 was 10 r/hr, whatwill be the dose rate at 1, 20, 25, and 32hours?
7. If the dose rate at 11+30 is 10 r/hr, whenwould the dose rate be 7 r/hr?
8. At 11+20 days the dose rate in an area is 3r/hr. What will be the dose rate at 11+25days?
9. In a sheltered area with a protection factorof 100, the dose rate is 10 r/hr at 11+10.What will be the unsheltered dose rate at11+18?
10. In a shelter with a protection factor of1,000, the dose rate at 11+24 is 15 r/hr.What will be the dose rate in the shelter at11+40?
Dose Problems
11. If the dose rate at 11+1 was 200 r/hr, whatwould be the dose of a monitor if he enteredthe area at H+12 and stayed 4 hours?
12. If the dose rate at 11+1 was 50 r/hr, whatwould be the dose of a monitor if he stayedin this area from H+5 to 11+8?
13. If the dose rate at 11+1 was 500 r/hr, whatwould be the total dose of a monitor whoremained in this area for a 1.5 hour periodbeginning at 11+12?
14. What would be a monitor's dose if heentered an area at H+6 and left at H+8?At the time of entry, the dose rate was15 r/hr.
15. Firemen must put out a fire in an areawhere the dose rate was 50 r/hr at H+7.What will be their mission dose if it takes6 hours to fight the fire and they start theirmission at 11+12?
16. Vital medical supplies must be moved to ashelter area. The task will require 30minutes. If the worker enters the area at11+6 when the dose rate is 200 r/hr, whatdose will he receive?
17. An individual left a shelter at H+6 on amission to a nearby shelter but neverarrived at the other shelter. At 11+30 arescue team found him unconscious in thecontaminated area outside the originalshelter. At that time the dose rate was14 r/hr. What dose was received by theunconscious indiiridual?
18. A rescue team entered a contaminated areaat H+12 and accomplished a task in 4hours. What was their dose if the doserate at time of exit was 12 r/hr?
19. No water is- available in a 3helter. Thereis a safe supply nearby. It is a 45 minutewalk to the water and the mission will beginat H+10. If the dose rate at 11+7 was30 r/hr, what dose will be received inobtaining the water for the shelter?
20. What is the dose received in a shelter from11+18 to 11+24, if the unsheltered doserate at 11+16 was 120 r/hr and the shelterprotection factor is 200?
Entry Time Problems
21. If the dose rate in an area was 300 r/hr at11+1, when can a monitor enter the areafor a 3-hour stay and receive less than 50 r?
22. A monitor must stay in an area for 1 hour.The dose rate in this area at 11+1 was 150r/hr. He must limit his dose to 15 r.When can he enter?
20
21
23. In order to keep a monitor's dose below 20r for a stay time of 2 hours, what is theearliest possible entry time intoin areawhere the dose rate was 120 r/hr at 11+1?
24. If the dose rate in an area is 5 r/hr at11+20 and an individual must stay there3 hours, what is the earliest, time he canenter and not exceed a dose of 10 r?
25. A mission dose is set at 35 r. The dose ratein an area was 18 r/hr at 11+15. Whencan workers enter this area for a 3-hourperiod?
26. The task of removing equipment whichis located in a contaminated area willrequire 3 hours. The mission dose is setat 50 r and the dose rate at 11+9 was50 r/hr. When can the salvage crew enterthe area?
27. A monitor must make a survey of an areawhich will require 2 hours. The missiondose is set at 35 r and the dose rate in thearea was 18 r/hr at 11+1 day. When willthe monitor be able to enter the area?
28. People want to move from an improvisedshelter to a community shelter. At 11+6the route to be traveled had an average doserate of 85 r/hr. The trip will take 2 hoursand the mission dose is 50 r. When canthey leave?
29. A supply of drugs must be delivered as soonas possible to a shelter. The drive takes3 hours. The average dose rate along theroute to be followed was 125 r/hr at 11+4.The mission dose is 75 r. What is theearliest time that the drugs can arrive at theshelter?
30. A shelter with a protection factor of 500is running low on food. The nearestsupply would require 1-hour round-tripto obtain it. The average dose rate overthe route to be traveled was 60 r /hr at 11+7.The mission dose is set at 50 r. When canthe mission be started to obtain the food?
Stay Time Problems
31. A mission dose is set at 25 r and the missionwill begin at 11+12. What stay time ispermitted, if the dose rate at H+1 was500 r/hr?
22
32. At 11+1 the dose rate was 200 r/hr. Ifentry into the area is made at 11+6 andthe mission dose is set at 50 r, what is theallowable stay time?
33. A family entered a contaminated area atH+5. Their dose should not exceed 35 r.How long can they stay in this area if thedose rate at time of entry was 20 r/hr?
34. At 11+12 a monitor must start an emer-gency mission outside his assigned shelter.At 11+6 the outside dose rate was 75 r/hr.If his mission dose is not to exceed 20 r,how long can he take for the task?
35. At 11+3 the dose rate in an area was 40 r /hr.A rescue squad entered the area at 11+5.How long can they stay in the area if theirdose is not to exceed 25 r?
36. Personnel working in a warehouse in a con-taminated area received a dose of- 150 r.At 11+4 the dose rate was 1,300 r/hr andthey entered the working area at 11+8.How long were they in the area?
37. A message must be hand carried to anothershelter. What is the maximum time forthe mission if the average dose rate betweenthe shelters was 90 r/hr at H+2? Themission dose is set at 35 r and the messengeris to leave shelter at 11+6.
38. At 11+15 a Radef Officer must move toanother control center 75 miles away. Theaverage dose rate over the area of travelwas 75 r/hr at 11+6. How fast will . hehave to travel in order not to exceed a doseof 50 r?
39. An individual travels at a speed of 35 m.p.h.through a contaminated area where theaverage dose rate was 100 r/hr at 11+5.How far will he be able to travel beforeseeking shelter if he entered the area atH+13 and must limit his dose to 80 r?
40. Due to crowded shelter conditions somepeople will be moved at 11+9 to anothershelter. The outside dose rate was 250 r/hrat 11+3. Their exposure is not to exceed35 r. How long do they have to transfershelters?
21
ANSWERS
1. 18, 7.6, 4.7, 3.4, 2.6 11. 35 r 21. H+11 31. 1 hourr/hr 12. 15 r 22. H+6 32. 2.7 hrs.
2. 44, 19, 6.5 r /hr 13. 36 r 23. 11+7 33. 2.2 hrs.a. 51, 30, 18 r/hr 14. 25 r 24. 11+27 34. .6 hour4. 380, 28, 20, 15 r /hr 15. 120 r 25. H+21 35. 1.5 hrs.5. 1600, 58, 35 r /hr 16. 90 r 26. H+22 36. 1.6 hrs.6. 370,10, 8, 6 r/hr 17. 800 r 27. 11+23 37. 1.8 hrs.7. H+40. 18. 60 r 28. 11+17 38. 38 m.p.h.8. 2.5 r/hr 19. 27 r 29. H+18 39. 95 miles9. 500 r/hr 20. 2.7 r 30. H+8 40. .5
10. 8 r/hr
23
22
5000 -
30004
2000
Dose Rate
at 11+t
(R,)
moo _ DOSE RATEsoo 1
soo
NOMOGRAM400_300
200
100r60-$0-
40-30-
20-
to
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Time After Burst-2
34 -60C2 a-"
20-3040-
260
380=;100L-4
-6-e-107-12
L-20- 28-36
23
Dose Rateat H+1
01) a
3
4
6
10
20
30
40
SO
SO
100
200
-1-300
400
600
SOO
1000
2000
5000
25
EN
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300
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,--
800
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3 4 6 /
8 4
20 30 40 -
-60 80
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100
200
300
4004
600
800
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2000
--
3000
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.9 .8 .7 At
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ime
9
SOURCE HANDLING TECHNIQUESHOMEWORK ASSIGNMENT
A SHORT QUIZ WILL BE GIVEN OVER THIS MATERIAL DURINGTHE COURSE. SEE THE COURSE SCHEDULE FOR THE EXACT TIME.
1. Study the sample Byproduct MaterialLicense.
2. Study the following sections of 10CFR-20,Standards for Protection Against Radiation.20.3 Definitions.20.4 Units of radiation dose.20.101 Exposure of individuals in restricted
areas.20.104 Exposure of minors.20.201 Surveys.20.202 Personnel monitoring.20.203 Caution signs, labels, and signals.20.206 Instruction of personnel; posting of
notices to employees.20.207 Storage of licensed material.20.401 Records of surveys, radiation moni-
toring, and disposal.20.402 Reports of theft or loss of licensed
material.20.601 Violations.
3. Study the following sections of 10CFR-30,Licensing of Byproduct Material.
30.4 Definitions.30.31 Types of Licenses.
25
30.32 Applications for specific licenses.30.33 General requirements for issuance
of specific licenses.30.34 Terms and conditions of licenses.30.36 Expiration of licenses.30.37 Application for renewal of license.30.38 Amendment of licenses at request of
licensee.30.39 Commission action on applications
to renew, or amend.30.51 Records.30.52 Inspection.30.53 Tests.30.61 Modification and revocation of li-
censes.30.62 Right to withhold or recall By-
product Material.Violations.30:63
4. Study the following sections of 10CFR-31,General Licenses.31.2 Terms and conditions.31.4 Certain quantities of
Material.31.100 Schedule AGenerally
quantities.
Byproduct
licensed
27
U.S. ATOMIC ENERGY COMMISSION
Compliance Offices
Region Address
TelephoneNights and
Daytime holidaysI Region I, Division of Compliance 212-989-1000 212-989-1000
USAEC376 Hudson StreetNew York, N.Y. 10014
II Region II, Division of Compliance 404-526-5791 404-526-5791USAEC50 Seventh Street NE.Atlanta, Ga. 30323
III Region III, Division of Compliance 312-654-1680 312-739-7711USAECSuite 410, Oakbrook Professional BuildingOak Brook, Ill. 60523
IV Region IV, Division of Compliance 303-297-4211 303-237-5095USAEC10395 West Colfax AvenueDenver, Colo. 80215
V Region V, Division of Compliance 415-841-5620 415-841-5620USAEC2111 Bancroft WayBerkeley, Calif. 94704
28
20'
FORM AEC-374(1-60)
10 CFR 30
U.S. ATOMIC ENERGY COMMISSIONBYPRODUCT MATERIAL LICENSE
License Number 14-12501-01Page 1 of 2 pages
Amendment No. 01
Pursuant to the Atomic Energy Act of 1954 and Title 10, Cede of Federal'Regulations, Chapter 1, Parts 30,32, 33, 34, and 35, and in reliance on statements and representations heretofore made by the licensee, a licenseis hereby issued authorizing the licensee to receive, acquire, own, possess, transfer and import byproduct mate-rial listed below; and to use such byproduct material for the purpose(s) and at the place(s) designated below.This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954,and is subject to all applicable rules, regulations, and orders of the Atomic Energy Commission now or hereafterin effect and to any conditions specified below.
Licensee
1. Iowa Civil Defense Division
2. State Office Building, Room B-33Des Moines, Iowa 50319
In accordance with applicationdated January 8, 19".8
3.License No.14-12501-U1 is amendedin its entirety to read as follows:
4.Expiration dateOctober 31, 1972
5. Reference No.
6. Byproduct material 7. Cherriical and/or physical form 8. Maximumlicensee m(element and mass number)
A. Cobalt 60
9, Authorized use
A. Office of CivilDefenseCD V-CD V- aled
oUrce is
t of radioactivity whichat any one`time
40 sets1[00 millicuriestotal
A. For use fR rainin ns rument operators and for instrument
calibrat
10Soduct material may be used anywhere in the State of Iowa.
CONDITIONS
The licensee shall comply with the provisions of Title 10,Part 20, Code of Fesitral Regulations, Chapter 1, "Standardsfor Protection Against Radiation."
12. Byproduct material shall be used by, or under the supervision andin the physical presence of, individuals issued user certificatesby the Iowa Civil Defense Division in accordance with criteriaspecified in Iowa Civil Defense Division Radiological Defense OCDTraining Source Set Procedures Manual.
13. Sealed sources containing byproduct material shall not be opened.
14. Each sealed source of licensed material used outside of a shieldedexposure device shall have a durable, legible, and visible tagpermanently attached by a durable ring. The tag shall be at least
one (1) inch square, shall bear a conventional radiation symbol
307-892 0 - 68 - 3
2
29
U. S. ATOMIC ENERGY COMMISSIONBYPRODUCT MATERIAL LICENSE
Supplementary Sheet
Page 2 of_? Pages
License Number14-12501-01
Continued from Page 1 Amendment No. 01
prescribed in Section 20.203(a) of Part 20, and a minimum of the
following instructions: DANGER - RADIOACTIVE MATERIAL - DO NOT
HANDLE - NOTIFY CIVIL AUTHORITIES IF FOUND.
Replacement of tags and rings shall be carried out by the licenseein accordance with instructions contained in Iowa Civil DefenseDivision Radiological Defense OCD Training Source Set Procedures
Manual.
15. A. Sealed sources containing byproduct material with a half-lifegreater than thirty (30) days and in any form other than gasshall be tested for external leakage and/or contamination uponreceipt from another person, except when tile licensee- receivescertification from the person that the sources had b -en testedwithin six (6) months prior to transfer and foun e of
surface contamination. Thereafter, sources sha tested for
leakage and/or contamination at intervals not to six (6)
months. Records of leak test results Mall be ma ned by
the licensee.
B. The test for leakage and/ordetecting the presence if 0.0material on the test
,1001crocurie of radioactive.
atio hall be capable of
C. If the test revea r.sioa.-i:ive material, the licensee shall
take imme' to act . prevent spread of contamination and within
thirty (3 s after completion of the test shall notify the
. opes Division of Materials Licensing, U. S. Atomic
::-Co v.ssion, Washington, D. C., 20545. A copy of the
.o shall be sent to the Director, Region III, Division of2
lance, USAEC, 799 Roosevelt Road, Glen Ellyn, Illinois, 60137.
D. Leak test of sealed sources in OCD Sealed Source Sets shall beperformed by the licensee in accordance with instructionscontained in Iowa Civil Defense Division Radiological DefenseOCD Training Source Set Procedures Manual.
16_ Byproduct material shall be stored at locations specified inIowa Civil Defense Division Radiological Defense OCD TrainingSource Set Procedures Manual, except for temporary storage atlocations where training courses are conducted.
17. Except as specifically provided otherwise by this license,the licensee shall possess and use byproduct material describedin Items 6, 7, and 8 of this license in accordance withstatements, representations, and procedures contained in
application dated January 9, 1968.
DateFEB 7 FM
30
the U. S,Ato
-by inntopes Branch
Divielon of Meterials LicensingWashington. D. C. 2175.43
nergy Commission
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STORAGE
Byproduct material in amounts not to exceed two (2) source sets (60 millicuries total) shall bestored in loOked storerooms and/or vaults, except for temporary storage at locations where train-ing courses and/or instrument calibration exercises are conducted.
City
CheyenneLocation
a. Maintenance and Calibration Facilityb. Maintenance and Calibration Facility
Evanston Basement, Uinta County Memorial HospitalRock Springs 935 Adams (concrete vault)Cody Basement, Cody AuditoriumCasper Casper College (Physics Lab. Vault)Lovell School (Shoshoni Ave.) (safe)Afton % County Agent Veterans Building, Afton, Wyo.Cheyenne Vault No. 2, State Office Building (Department of Health)
32
3U
Sec.20.120.220.320.4en.s20.620.7
UNITED STATES ATOMIC ENERGY COMMISSION
RULES and REGULATIONS TITLE 10 - ATOMIC ENERGY
PART20
OLNISAL PROVISIONS
Purpose.Scope.Definitions.Units of radiation doss.Units of radioactivity.Interpretations.Communications.
PERMISSIBLE DOSES, LEVELS, ANDCONCENTRATION'
20.101 Exposure of individuals to radiationin restricted areas.
20.102 Determination of accumulated dose.20.103 Exposure of individuals to concentra-
tions of radloacti ie material In re-stricted areas.
20.104 Exposure of minors.20.105 Permissible levels of radiation in un-
restricted areas.20.106 Concentrations in effluents to un-
restricted areas.20.107 Medical diagnosis and therapy.20.106 Orders requiring furnishing of bio-
assay services.
PRECAUTIONARY PROCEDURES
20.201 Surveys.20.202 Personnel monitoring.20.2011 Caution signs, labels, and signals.20.204 Leceptions from pasting require-
ments
20.206 Instruction of personnel; posting ofnotices to employees.
20.207 Storage of licensed materials.WAITS DISPOSAL
20.301 General requirement.20.302 Method for obtaining approval of
prop9ssd disposal procedures.20.303 Disposal by release Into sanitary sew-
erage systems.20304 Disposal by burial in soil.20.305 Treatment or disposal by incinera-
tion.RECORDS, REPORTS, AND NOTIFICATION
20.401 Records of surveys, radiation motif.Coring, and disposal.
20.402 Reports of theft or loss of licensedmaterial.
20.403 Notifications of Incidents.20.404 Report to former employees of ex-
posure to radiation.20.405 Reports of overexposures and exces-
sive levels and concentrations,20.406 Notice to employees of exposure to
radiation.EXCITTIONS AND ADDITIONAL REQUIREMENTS
20.301 Applications for exemptions.20.302 Additional requirements.
ENFORCEMENT
20.601 Violations.Appendix Ai Reserved 1Appendix IIPermissible Concentrations in
air and water above natural background.Appendix C.Appendix DUnited States Atomic Energy
Commission Operations offices.
STANDARDS FOR PROTECTION AGAINST RADIATION
GENERAL PROVISIONS
§ 20.1 Purpose.(a) The regulations in this part estab-
lish standards for protection againstradiation hazards arising out of activitiesunder licenses issued by the AtomicEnergy ,Commission and,are issued pur-suant to the Atomic Energy Act of 1954(68 Stat. 919).
(b) The use of radioactive material orother sources of radiation not licensedby the Commission is not subject to theregulations in this part. However, it isthe purpose of the regulations in thispart to control the possession, use, andtransfer of licensed material by any li-censee in such a manner that exposureto such material and to radiation fromsuch material, when added to exposuresto unliceiized radioactive material andto other unlicensed sources of radiationin the possession of the licensee, and toradiation therefrom, does not exceed the
;'4 standards of radiation protection pre-0 scribed in the regulations in this part.ce § 20.2 Scope.u.el The regulations in this part apply to" all persons who receive, possess, use or
transfer byproduct material, source ma-terial, or special nuclear material undera general or specific license issued by theCommission pursuant to the regulationsin Part 30, 40, or '70 of this chapter.§ 20.3 Definitions. .
(a) As used in this part:(1) "Act" means the Atomic Energy
Act of 1954 (68 Stat. 919) including anyamendments thereto;
(2) "Airborne radioactive material"means any radioactive material dispersedin the air in the form of dusts, fumes,mists, vapors, or gases;
(3) "Byproduct material" means anyradioactive material (except special nu-clear material) yielded In or made ra-dioactive by exposure to the radiationincident to the process of producing orutilizing special nuclear material;
(4) "Calendar quarter" means anyperiod determined according to eitherof the following subdivisions:
Added 25 FR 11952
31
Pi
N
(i) The first period of any year maybegin on any date in January; providedthat the second, third and.fourth periodsaccordingly begin on the same date inApril, July, and October, respectively,and that the fourth period extend intoJanuary of the succeeding year, if nec-essary to complete a three-month quar-ter. During the first year of use of thismethod of determination by a licensee,the first period for that year shall alsoinclude any additional days in Januarypreceding the starting date for the firstperiod.
_(ii) The first period in a calendar yearof 13 complete, consecutive calendarweeks; the second period in a calendaryear of 13 complete, consecutive calen-dar weeks; the third period in a calendaryear of 13 complete, consecutive calendarweeks; the fourth period in a calen-dar year of 13 complete, consecutivecalendar weeks.*Alternatively, the four periods may con-sist of the first 14 complete, consecutivecalendar weeks; the next 12 complete.consecutive calendar weeks; the next 14complete, consecutive calendar weeks;and the last 12 complete, consecutivecalendar weeks. If at the end of a calen-dar year there are any days not fallingwithin a complete calendar week of thatyear, such days shall be included (forpurposes of this part) within the lastcomplete calendar week of that year.If at the beginning of any calendar yearthere are days not falling within a com-plete calendar week of that year, suchdays shall be included (for purposes ofthis part) within the last complete cal-endar week of the previous year.No licensee shall change the method ob-served by him of determining calendarquarters for purposes of this part exceptat the beginning of a calendar year.
(5) "Commission" means the AtomicEnergy Commission or its duly author-ized representatives;
(6) "Government agency" means anyexecutive department, commission, inde-p e n d e n t establishment, corporation,wholly or partly owned by the UnitedStates of America which is an instru-mentality of the United States, or anyboard, bureau, division, service, office,officer, authority, administration, orother establishment in the executivebranch of the Government;
August 9, 1966
33
PART 20 - STANDARDS FOR PROTECTION AGAINST RADIATIONII(7) "Individual" means any human
being;(8) "Licensed material" means source
material, special nuclear material, or by-product material received, possessed.used, or transferred under a general orspecific license issued by the Commissionpursuant to the regulations in thischapter;
(3) "License" means a license issuedunder the regulations in Part 30, 40, or70 of this chapter. "Licensee" meansthe holder of such license;
(10) "Occupational dose" includes ex-posure of an individual to radiation (i)in a restricted area; or ( ii) in the courseof employment in which the individual'sduties involve exposure to radiation;
. provided, that "occupational dose" shall7... not be deemed to include any exposure2- of an individual to radiation for the pur-cc pose of medical diagnosis or medical
therapy of such individual."' ( 1 1) "Person" means (i) any individ-
Iual, corporation, partnetalIWItrm; ssso-elation. trust, estate, public or privateinstitution, group, Government agencyother than the Commission, any state,any foreign government or nation or anyPolitical subdivision "of' env such gov-ernment or nations, or other entity; and(ii) any legal successor, representative,agent, or agency of the foregoing;
(12) "Radiation" means any or all ofthe following: alpha rays. beta rays,gamma rays, X-rays, neutrons, high-speed electrons, high-speed protons, andother atomic particles; but not soundor radio waves, or visible, infrared, orultraviolet light;
(13) "Radioactive material" includesany such material whether or not subjectto licensing control by the Commission;
ra-(14 Restricted area" means anyrea access to which is controlled by the
t..4 licensee for purposes of protection of`,r,..' individuals from exposure to radiation
and radioactive materials. "Restricted. area" shall not include any areas usedh ss residential quarters, although a sepa-c4 rate room or rooms in a residential
building may be set apart as a restrictedrea;
, (15) "Source material" means (I)-...I uranium or thorium, or any combina-
tion thereof, in any physical or chemicalN form; or (ii) ores which contain by, weight one-twentieth of one percenta. (0.05%) or more of a uranium, b. tho-r- rium or c. any combination thereof.(4 [...Source material does not include special
nuclear material.F(16) "Special nuclear material" meansi) plutonium, uranium 233, uranium
enriched 'n the isotope 233 or in the iso-: tope 235, and any other material which: the Commission, pursuant to the provi-
atone of section 51 of the act, determinesu. to be special nuclear material, but does.-, not include source material; or (ii) any" material artificially enriched by any of
the foregoing but does not include sourcematerial;
&I (17) "Unrestricted area" means anyarea access to which is not controlled by
^ the licensee for purposes of protection ofindividuals from exposure to radiation
,A and radioactive materials, and any areaL" used for residential quarters..--- (b) Definitions of certain other words
and phrases as used in this part are setforth in other sections, including:
(1) "Airborne radioactivity area" de-fined in 4 20.203;
(2) "Radiation area" and "high radi-ation area" defined in 20.202;
(3) 'Personnel monitoring equipment"defined in § 20.202;
(4) "Survey" defined in 20.201;(5) Unita of measurement of dose (rad,
rem) defined in 20.4;(6) Unita of measurement of radio-
activity defined In f 20.5,
§ 20,4 Units of radiation dose.(a) "Dose," as used in this part, is the
quantity of radiation absorbed, per unitamass, by the body or by Any portion of..the body. When the regMations in thispart specify a dose during a period oftime, the dose means tba total quantityof radiation absorbed, per unit of mass,by the body or by any portion of thebody during such peridd of time. Severaldifferent units of dose are in current use.Definitions of units as used in this partare set forth in paragraphs (b) and (c)of this section.
(b) The rad, as used in this part, is ameasure of the dose of any ionizing radi-ation to body tissues in terms of theenergy absorbed per unit mass of the
7-' tissue. One rad is the dose correspond-: ing to the absorption of 100 ergs per gram
of tissue. (One mlllirad (mrad) =0.001u- rad.)
(c) The rem, as used in this part, isa measure of the dose of any ionizingradiation to body tissue in terms of itsestimated biological effect relative to adose of one roentgen (r) of X-rays. (Onomillirem (mrem) =0.001 rem.) The rela-tion of the rem to other dose units de-pends upon the biological effect underconsideration and upon the conditions ofirradiation. Per the purpose of the reg-ulations in this part, any of the follow-ing is considered to be equivalent to adose of one rem:
(1) II dose of 1 r due to X- or gammaradiation;
(2) A dose of 1 rad due to X-, gamma,or beta radiation;
(3) A dose of 0.1 rad duo to neutronsor hip% energy protons;
(4) A dose of 0.05 rad due to particlesheavier than protons and wi,h sufficientenergy to reach the lens of the eye;If it is more convenient to ,,./l,Asute theneutron flux, or equivalent, 0A-q to de-terinine the neutron dose .41 roads, uProvided in subparagraph C.:, of thisparagraph, one rem of neutrere:txdiationmay, for purposes of the retv.ilArriona inthis part, be assumed to be elV.11valentto 14 million neutrons per square cents-
` meter incident upon the body; or, ifthere exists s-ufficient information to esti-mate with reasonable accuracy the ap-proximate distribution in energy of the
32
neutrnns, the incident number of neu-t au, per square centimeter equivalentto one rem may be estimated from thefollowing table:
ICIVTION FLUX Doss EQUITALINTS
Neutron energy (Mee)
Number of Avertsneutrons per flux tosquare cep- deliver 100
Winter millirem Inequivalent 40 hours
to doss oil (neutrons!rem (lieu. em' per sec.)trails/mil)
0.0001Thermal
0.0060.020.10.51.02.56.07.51010 to 30
970X101720X10'1120X101400X101120X10143X10'26X10120X10'26X10624X IP24X10014X101
670500570210103011201117IT
(d) For determining exposures to X or'gamma 2/15,-.;W tGAL-fdev,lhe dose limitsspecified in H 20.101 to 20.104, inclusive,may be assumed to be equivalent to the"air dose", For the purpose of this part"air dose" means that the dose is meas-ured by a properly calibratANI appropriateinstrument in air at or near the body sur-face in the region of highest dosage rate.§ 20.5 Units of radioactivity.
(a r Radioactivity is commonly. and forPurposes of the regulations in this partshall be, measured in terms of disintegra-tions per unit time or in curies. One curie(c) =3.7 X10" disintegrations per sec-ond (dps) =2.2 X10" disintegrations perminute (dpm). A commonly used sub-multiple of the curie is the microcurie(ac). One pc-=0.000001 c=3.7 X 10' dps=2.2 x 10' dpm.
(b) For purposes of the regulations inthis part, it may be assumed that thedaughter activity concentrations in thefollowing table are equivalent to an airconcentration of 10-' microcuries ofRadon 222 per milliliter of air in equilib-rium with the daughters RaA, RaB, RaC,and RaC':
Maximum timebetween collection andmeasurement (hours)'
0,5_
3
Alpha-emitting daughteractivity collected per
milliliter of air
Micro -curies /cc
Total alphadisintegra-tions per
minute percc.
7.2X10-s 0. 184.5X10-s 0. 101.3X10-s 0.0280.3X10-3 0.0072
I The duration of sample collection and the durationof measurement should be sufficientb short comparedto the time between collection and measurement, as notto have a statistically significant effect upon the results.
PART 20 - STANDARDS FOR(C) Natural uranium and natural;
thorium, (1) For purposes of the regu-lations in this part, one curie of naturaluranium (U-natural in Appendix B orC) means the sum of 3.7 X le disintegra-tions per second from U-238 plus3.7 x 10" dis/sec from U-234 plus 9X10'dis/sec from U-235. Also, a curie ofnatural thorium (thorium-natural in'Appendix B or C) means the sum of3.7 X10' dis/sec from Th "' plus 3.7x lirdis/sec from Thy'.
(2) For the purpose of the regulations,.. in this part, one curie of natural uraniumc7. (U-natural in Appendix B or C) is equiv-2 alent to 3.000 kilograms, or 6,615 poundsea of natural uranium; and one curie ofa. natural thorium (thorium-natural invl44 Appendix B or C) is Anuivalent to 9,000
kilograms or 19,850 pounds of naturalthorium.§ 20.6 Interpretations.
Except as specifically authorized bythe Commission in writing, no interpreta-Mull ol'tlie meaning of the regulations inthis part by any officer or employee ofthe Commission other than a written in-terpretation by the General Counsel willbe recognized to be binding upon the
Commission,§ 20.7 Communications.
1
Except where otherwise specified inthis part, all communications and re-ports concerning the regulations in this
lo part, and applications filed under them,ishould be addressed to the Director ofRegulation, U.S Atomic Energy Com-=a. mission, Washington, D.C., 20545. Com-
7,,,- munications, reports and applications[may be delivered in person at the Com-mission's offices at 1717 H Street NW.,Washington, D.C.; at 4915 St. Elmo Ave-nue, Bethesda, Md.; or at Germantown,Md.;
§ 20.101 Exposure of individuals to ra-diation in restricted areas.
(a) Except as provided in paragraph(b) of this section, no licensee shallpossess, use, or transfer licensed mate-rial in such a manner as to cause any.individual in a restricted area to receivein any period of one calendar quarterfrom radioactive material and othersources of radiation in the licensee's pos-session a dose in excess of the limitsspecified in the following table:
Rents per calendar quarter...".1E I. Whole body; head and trunk; active::. blood-forming organs; lens ofeg eyes; or gonads 1%1s- 2. Hands and forearms: feet andr4wi ankles 18%
3. Skin of whole body 7IA
(b) A licensee may permit an indi-vidual in a restricted area to receive adose to the whole body greater than thatpermitted under paragraph (a) of thissection, provided:*
(1) During any calendar quarter thedose to the whole body from radioactivematerial and other sources of radiationin the licensee's possession shall not ex-ceed 3 rems; and
(2) The dose to the whole body, whenadded to the accumulated occupationaldose to the whole body, shall not exceed5 (N-18) rems where "N" equals the in-
PROTECTION AGAINST RADIATION
dividual's age in years at his last birth-day: and
(3) The licensee has determined theindividual's accumulated occupationaldose to the whole body on Form AEC-4,or on a clear and legible record contain-ing all the information required in thatform; and has otherwise complied withthe requirements of § 20.102. As used inparagraph (b), "Dose to the whole body"shall be deemed to include any dose tothe whole body, gonads, active blood-forming organs, head and trunk, or lensof eye.§ 20.102 Determination of accumulated
dose.(a) This section contains require-
ments which must be satisfied bylicensees who propose, pursuant to para-graph (b) of § 20.101, to permit individ-uals in a restricted area to receive ex-posure to radiation in excess of the limits.specified in paragraph (a) of § 20,101.
(b) Before permitting any individualin a restricted area to receive exposureto radiation in excess of the limits spec-ified in paragraph (a) of § 20.101, eachlicensee shall:
(1) Obtain a certificate on FormAEC-4, or on a clear and legible recordcontaining all the information requiredin that form, signed by the individualshowing each period of time after. theindividual attained the age of 18 in whichthe individual received an occupationaldose of radiation; and
(2) Calculate on Form AEC-4 in ac-cordance with the instructions appear-ing therein, or on a clear and legiblerecord containing all the informationrequired in that form, the previously ac-cumulated occupational dose received bythe individual and the additional doseallowed for that individual under§ 20.101 ( b ) .
(c) (1) In the preparation of FormAEC-4, or a clear and legible record con-taining all the information required inthat form, the licensee shall make a rea-sonable effort to obtain reports of theindividual's previously accumulated oc-cupational dose. For each period forwhich the licensee obtains such reports,the licensee' shall use the dose shown inthe report in preparing the form. Inany case where a licensee is unable toobtain reports of the individual's occu-pational dose for a previous completecalendar quarter, it shall be assumedthat the individual has received the oc-cupational dose specified in whicheverof the following columns apply;
Part of body
Column I Column 2
Assumed Assumedexposure exposure
In rems for In rems forcalendar calendarquarters quartersprior to beginning on
Jan. I, 1961 or afterJan. 1, 1961
Whole body, gonads,active bloodformingorgans, head and trunk.lens of eye.
331
33
(2) The licensee shall retain and pre-serve records used in preparing FormAEC-4.If calculation of the individual's ac-cumulated occupational dose for allperiods prior to January 1, 1961 yieldsa result higher than the applicable ac-cumulated dose value for the individualas of that date, as specified in paragraph(b) of § 20.101, the excess may be disre-garded.§ 20.103 Exposure of individuals to
concentrations of radioactive ma-terial in restricted areas.
(a) No licensee shall possess, use ortransfer licensed material in such a man-ner as to cause any individual in arestricted area to be exposed to airborneradioactive material possessed by thelicensee in an average concentration inexcess of the limits specified in AppendixB, Table I, of this part. "Expose" asused in this section means that the in-dividual is present in an 'airborne con-centration. No allowance shall be madefor the use of protective clothing orequipment, or particle size, except asauthorized by the Commission pursuantto paragraph (c) of this section.
(b) The limits given in Appendix B,Table I, of this part are based uponexposure to the concentrations specifiedfor forty hours in any period of sevenconsecutive days, In any such periodwhere the number of hours of exposureis less than forty, the limits specific:::in the table may be increased propor-tionately. In any such period wherethe number of hours of exposure isgreater than forty, the limits specifiedin the table shall be decreasedproportionately.
(c) (1) Except as authorized by theCommission pursuant to this paragraph,no allowance shall be made for particlesize or the use of protectiie clothingor equipment in determining whether anindividual is exposed to an airborne con-centration in excess of the limits speci-fied in Appendix B, Table I.
(2) The Commission may authorize alicensee to expose an individual in a re-stricted area to airborne concentrationsin excess of the limits specified in Ap-pendix B, Table I, upon receipt of anapplication demonstrating that the con-centration is composed in whole or inpart of particles of such size that suchparticles are not respirable; and thatthe individual will not inhale the con-centrations in excess of the limits estab-lished in Appendix B, Table I. Eachapplication under this subparagraphshall include an analysis of particle sizesin the concentrations; and a descriptionof the methods uscd in determining theparticle sizes.
(3) The Commission may authorizea licensee to expose an individual in arestricted area to airborne concentra-tions in excess of the limits specified inAppendix B, Table I, upon' receipt ofan application demonstrating that theindividual will wear appropriate pro-tective equipment and that the individualwill not inhale, ingest or absorb quanti-
April 5, 1966
35
PART 20 STANDARDS FOR PROTECTION AGAINST RADIATION
ties of radioactive material in excess ofthose which might otherwise be permit-ted under this part for employees inrestricted areas during a 40-hour week.Each application under this subpara-graph shall contain the followinginfui rnation :
(i) A description of the protectiveequipment to be employed, including theefficiency of the equipment for the ma-terial involved;
(ii) Procedures for the fitting, main-tenance and cleaning of the protectiveequipment; and
(iii) Procedures governing the use ofthe protective equipment, including su-pervisdry procedures and length of timethe equipment will be used by the indi-viduals in each work week. The pro-posed periods for use of the equipmentby any individual should not be of suchduration as would discourage observanceby the individual of the proposed pro-cedures; and
(iv) The average concentrations pres-ent in the areas occupied by employees.§ 20.104 Exposure of minors.
(a) No licensee shall possess, use ortrazzfor licensed material in such amanner as to cause any individual withina restricted area who is under 18 yearsof age, to receive in any period of onecalendar quarter from radioactive ma-terial and other sources of radiation inthe licensee's possession a dose in excessof 10 percent of the limits specified in
° the table in paragraph (a) of § 20.101.(b) No licensee shall possess, use or
u- transfer licensed material in such ar, manner as to cause any individual
within a restricted area, who is under 18years of age to be exposed to airborneradioactive material possessed by tlicensee in an average concentrationexcess of the limits specified in AppendiB, Table II of this part. ;rag purposeof this paragraph, con tra .ns mabe averaged over peri, I eaterthan a week.
(c) The provisions of ,F.tT ph (c)of S 20.103, shall apply to exposures sub-ject to paragraph (b) of this section.§ Permissible levels of radiation
in unrestricted areas.(a) There may be included in any ap-
plication for a license or for amendmentof a license proposed limits upon levelsof radiation in unrestricted areas result-ing from the applicant's possession oruse of radioactive material and othersources of radiation. Such applicationsshould include information as to antici-.pated average radiation levels and an-ticipated occupancy times for eachunrestricted area involved. The Com-mission will approve the proposed limitsif the applicant demonstrates that theproposed limits are not likely to causeany individual to receive a dose to thewhole body in any period of onc calendaryear in excess of 0.5 rem.
(b) Except as authorized by the Com-mission pursuant to paragraph (a) ofthis section, no licensee shall possess, useor transfer licensed material in such amanneras to create in any unrestricted
area from radioactive material and othersources of radiation in his possession:
(1) Radiation levels which, if an indi-vidual were continuously present in thearea, could result in his receiving a dosein excess of two millirems in any onehour, or
(2) Radiation levels which, if an indi-vidual were continuously present in thearea, could result in his receiving a dosein excess of 100 millirems in any sevenconsecutive days.§ 20.106 Concentrations in effluents to
unrestricted areas.
(a) A licensee shall, not possess, use,or transfer licensed material so as to re-lease to an unrestricted area radioactivematerial in concentrations which exceedthe limits specified in Appendix "B",Table II of this part, except as authorizedpursuant to § 20.302 or paragraph (b) ofthis section. Fox purposes-r,! "-sic sec-tion concentrations may be averaged overa period not greater than one year.
(b) An application for a license oramendment may include proposed limitshigher than those specified in para-graph (a) of this section. The Commis-sion will approve the proposed limitsif the applicant demonstrates:
(1) That the applicant has madereasonable effort to minimize the radiactivity contained in eM to un-restricted areas; and
(2) That it is not li radio-active material" ischarg e effluentwould result e expos of an indi-vidual co ations adioactivemate water exceeding thelimits pendix "B", TableII of t
(c) A pp'a ation for higher limitsursuftnt paragraph (b) of this sec-
shall include information demon-st ng that the applicant has made areasonable effort to minimize the radio-activity discharged in effluents to unre-stricted areas, and shall include, aspertinent:
(1) Information as to flow rates, totalvolume of effluent, peak concentration ofeach radionuclide in the effluent, and con-centration of each radionuclide in theeffluent averaged over a period of oneyear at the point where the effluent leavesa stack, tube, pipe, or similar conduit;
(2) A description of the properties athe effluents, including:
(i) chemical composition;(ii) physical characteristics, including
suspended solids content in liquid efflu-ents, and nature of gas or aerosol for aireffluents;
(iii) the hydrogen ion concentrations(p11) of liquid effluents; and(iv) the size range of particulates in
effluents released into air.(3) A description of the anticipated
human occupancy in the unrestrictedarea where the highest concentration ofradioactive material from the effluent isexpected, and, in the case of a river orstream, a description of water uses down-stream from the point of release of theeffluent.
(4) Information as to the highest con-centration of each radionuclide in anunrestricted area, including anticipatedconcentrations averaged over a period ofone year:
(i) In air at any point of human oc-cupancy; or
(ii) In water at points of use down-stream from the point of release of theeffluent..
(5) The background concentration ofradionuclides in the receiving river orstream prior to the release of liquideffluent.
(6) A description of the environmentalmonitoring equipment, including sensi-tivity of the system, and procedures andcalculations to determine concentrationsof radionuclides in the unrestricted areaand possible reconcentrations of radio-nuclides.
(7) A description of thd waste treat-ment facilities and procedures used toreduce the concentration of radionuclidesin effluents prior to their release.
(d) For the purposes of this sectionthe concentration limits in Appendix "B",Table II ofboundconcendischarilar con
36
3 II
Paryihall apply at thethe restricted area. The
of radioactive materialrou a stack, pipe or sim-
be determined withrespect to point where the materialleaves the conduit. If the conduit dis-
s within the restricted area, thecentration at the boundary may be
determined by applying appropriatefactors for dilution, dispersion, or decaybetween the point of discharge and theboundary.
(e) In addition to limiting concen-trations in effluent streams, the Com-mission may limit quantities of radio-active materials released in air or waterduring a specified period of time if itappears that the daily intake of radio-active material from air, water, or foodby a suitable sample of an exposed pop-ulation group, averaged over a periodnot exceeding one year, would otherwiseexceed the daily intake resulting fromcontinuous exposure to air or water con-taining one-third the concentration ofradioactive materials specified in Ap-pendix "B", Table II of this part.
(f) The provisions of this section donot apply to disposal of radioactive ma-terial into sanitary sewerage systems,which is governed by § 20.303
20.107 Medical diagnosis and therapy.Nothing in the regulations in this part
shall be interpreted as limiting the in-t entional exposure of patients to radia-tion for the purpose of medical diagnosisor medical therapy.
PART 20 STANDARDS FOR PROTECTION AGAINST RADIATION
§ 2:1108 Orders requiring furnishing ofbia-_e say services.
Where necessary or desirable in orderto aid in determining the extent of anindividual's exposUre to concentrationsof radioactive material, the Commissionmay incorporate appropriate provisionsin any license, directing the licensee tomake available to the individual appro-priate bio-assay services and to furnisha copy of the reports of such services tothe Commission.
PRECAUTIONARY PROCEDURES
§ 20.201 Surveys.(a) As used M the regulations in this
part, "survey" means an evaluation ofthe radiation hazards incident to the pro-duction, use, release, disposal, or pres-ence of radioactive materials or othersources of radiation under a specific setof conditions. When appropriate, suchevaluation includes a physical survey ofthe location of materials and equipment,and measurements oflevels of radiationor concentrations of radioactive materialpresent.
(b) Each licensee shall make or causeto be made such surveys as may be neces-sary for him to comply with the regula-tions in this part.§ 20.202 '-lersonnel monitoring.
(a) Each licensee shall supply appro-priate personnel monitoring equipmentto, and shall require the use of such
6: equipment by:2 (1) Each individual who enters a re-
stricted area under such circumstances"- that he receives, or is likely to receive,ts, a dose in any calendar quarter in excess
of 25 percent of the applicable valuespecified in paragraph (a) of § 20.101.
(2) Each individual under 18 years ofage who enters a restricted area undersuch circumstances that he receives, oris likely to receive, a dose in any calen-dar quarter in excess of 5 percent ofthe applicable value specified in para-graph (a) of § 20.101.
(3) Each individual who enters a highradiation area.
(b) As used in this part,(1) "Personnel monitoring equipment"
means devices designed to be worn orcarried by an indivie,,:al for the purposeof measuring the or..se received (e. g..film badges, pocket chambers, pocketdosimeters, film rings, etc.) ;
(2) "Radiation area" means any area,accessible to personnel, in which thereexists radiation, originating in whole orin part within licensed material, at suchlevels that a major portion of the bodycould receive in any one hour a d6se inexcess of 5 millirem, or- in any 5 con-secutive days a dose in excess of 100millirems;
(3) "High radiation area" means anyarea, accessible to personnel, in whichthere exists radiation originating inwhole or in part within licensed mate-rial at such levels that a major portionof the body could receive in any one houra dose in excess of 100 millirem.
Or "Danger "
§ 20.203 Caution signs, labels, and sig-nals.
(a) General. (1) Except as otherwiseauthorized by the Commission, sym-bols prescribed by this section shall usethe conventional radiation caution colors(magenta or purple on yellow back-ground) . The symbol prescribed by thissection is the conventional three-bladeddesign:
RADIATION SYMBOL
1. Cross- hatched area is to be magenta orpurple.
2. Background is to be yellow.
60°
4 I
4-, a AA
."5A ,>1
(2) In addition to the contents of signsand labels prescribed in this section, li-censees may provide on or near suchsigns and labels any additional informa-tion which may be appropriate in aidingindividuals to minimize exposure to radi-ation or to radioactive material.
(b) Radiation areas. Each radiationarea shall be conspicuously posted witha sign or signs bearing the radiation cau-tion symbol and the words:
CAuTIONIRADIATION AREA
(c) High radiation areas. (1) Eachhigh radiation area shall be conspicu-ously posted with a sign or signs bearingthe radiation caution symbol and thewords:
CAUTION,HIGH RADIATION AREA
(2) Each high radiation area shall beequipped with a control device whichshall either cause the level of radiationto be reduced below that at which anindividual might receive a dose of 100millirem in one hour upon entry intothe area or shall energize a conspicuousvisible or audible alarm signal in sucha manner that the individual enteringand the licensee or a supervisor of theactivity are made aware of the entry.In the case of a high. radiation area es-tablished for a period of 30 days or less,such control device is not required.
(d) Airborne radioactivity areas. (1)As used in the regulations in this part,"airborne radioactivity area" means (1)any room, enclosure, or operating area
in which airborne radioactive materials,composed wholly or partly of licensedmaterial, exist in concentrations in ex-cess of the amounts specified in Appen-dix B, Table I, Column 1 of this part; or(ii) any room, enclosure, or operatingarea in which airborne radioactive mate-rial composed wholly or partly of licensedmaterial exists in concentrations which,averaged over the number of hours inany week during which individuals arein the area, exceed 25 percent of theamounts specified in Appendix B, Table I,Column 1 of this part.
(2) Each airborne radioactivity areashall be conspicuously posted with a signor signs bearing the radiation cautionsymbol and the words:
cAITTIoN iAIRBORNE RADIOACTIVITY AREA
(e) Additional requirements. (1) Eacharea or room in which licensed materialis used or stored and which contains anyradioactive material (other than naturaluranium or thorium) in an amount ex-ceeding 10 times the quantity a alaimaterial specified in Appendix C of thispart shall be conspicuously posted witha sign or signs bearing the radiationcaution symbol and the words:
CAUTION'RADIOACTIVE MATEHIAL(8)
(2) Each area or room in which nat-ural uranium or thorium is used oistored in an amount exceeding one-hundred times the quantity specified itAppendix C of this pert shall be con-spicuously posted with a sign or signs
bearing the radiation caution symboland the words:
CAUTIONRADIOACTIVE MATERIAL(8)
(f) Containers. (1) Except as pro-vided in subparagraph (3) of this para-graph, each container of licensed mate-rial shall bear a durable, clearly visiblelabel identifying the radioactive con-tents.
(2) A label required pursuant to sub-paragraph (1) of this paragraph shallbear the radiation caution symbol andthe words "CAUTION, RADIOACTIVEMATERIAL" or "DANGER, RADIOAC-TIVE MATERIAL". It shall also providesufficient information 1 to permit in-
,r dividuals handling or using the con-.7 tattlers, or working in the vicinity there-2 of, to take precautions to avoid or mini-m mize exposures.U. (3) Notwithstanding the provisions of^-_, subparagraph (1) of this paragraph,
labeling is not required:(1) For containers that do not con-
tain licensed materials in quantitiesgreater than the applicable quantitieslisted in Appendix C of this part.
(ii) For containers containing onlynatural uranium or thorium in quantitiesno greater than 10 times the applicablequantities listed in Appendix C of thispart.
(iii) For containers that do not con-tain licensed materials in concentrations
lAs appropriate, the information will in-clude radiation levels, kinds of material, es-timate of activity, date for which activity isestimated, mass enrichment, etc.
August 9, 196637
PART 20 STANDARDS FOR PROTECTION AGAINSTgreater than the applicable concentra-tions listed in Column 2, Table I, Ap-pendix B of this part.
(iv) For containers when they are at-tended by an individual who takes theprecautions necessary to prevent theexposure of any individual to radiation orradioactive materials in excess of thelimits established by the regulations in
:7) this part.c.- (v) For containers when they are inir transport and packaged and labeled inl'- accordance with regulations of the In-(7, terstate Commerce Commission, Federal
Aviation Agency, or Coast Guard.(vi) For containers which are acces-
sible' only to individuals authorized tohandle or use them, or to work In thevicinity thereof, provided that the con-tents axe identified to such individualsby a readily available written record.
(vii) For manufacturing or processequipment, such as nuclear reactors, re-
...actor components, piping, and tanks.,...§ 20.204 Exceptions from posting re-
quirements.Notwithstanding the ,provisions of
i 20.203,(a) A room or area is not required to
be posted with a caution sign because ofthe presence of a sealed source providedthe radiation level twelve inches fromthe surface of the source container orhousing does not exceed five milliremPer hour.
(b) Rooms or other areas in hospitalsare not required to be posted with cautionsigns because of the presence of patients
2; containing byproduct material providedthat there are personnel in attendance
u. who shall take the precautions necessaryn to prevent the exposure of any individual
4,4
to radiation or radioactive material inexcess of the limits established in theregulations in this part.
(c) Caution signs are not required tobe posted at areas or rooms containingradioactive materials for periods of lessthan eight hours provided that (1) theMaterials are constantly attended duringsuch periods by an individual who shalltake the precautions necessary to pre-vent the exposure of any individual toradiation or radioactive materials in ex-cess of the limits established in the regu-lations in this part and; (2) such area or
room is subject to the licensee's control.(d) A room or other area is not re-
quired to be posted with a caution signo because of the presence of radioactive
materials packaged and labeled in ac-cordance with regulations of the Inter-
- state Commerce Commission, FederalAviation Agency, or Coast Guard.
§ 20.206 Instruction of personnel; post-ing of notices to employees.
(a) All individuals working in or fre-quenting any portion of a restricted areashall be informed of the occurrence ofradioactive materials or of radiation insurli portions of the restricted area;shall be instructed in the safety prob.
associated with exposure to suchmaterials or radiation and in precau-tions or procedures to minimize expo-
r
'For example. containers in locations suchas water-filled canals, storage vaults, or hotcells.
August 9, 19663 8
sure; shall be instructed in the applicableprovisions of Commission regulations_and licenses for the protection of per-sonnel from exposures to radiation orradioactive materials; and shall be ad-vised of reports of radiation exposurewhich employees may request pursuantto these regulations.
(b) Each licensee shall post a currentcopy of the regulations in this part, acopy of the license, and a copy of oper-ating procedures applicable to workunder the license conspicuously in a suf-ficient number of places in every estab-lishment where employees are employedin activities licensed by the Commissionto permit them to observe such docu-ments on the way to or from their placeof employment or shall keep such docu-ments available for employees' examina-tion upon reouest.
(c) ForM AEC-3, "Notice to Evi-1 ployees" shall be conspicuously postedfAl in a sufficient number of places In every(-) establishment where, employees are Cm-, Ployed in activities licensed by the Coin-s- mission to permit employees working in
or frequenting any portion of a restricted
fromto observe a copy on the way to or
from their place of employment.sr Nan: Copies of Form AEC-9, "Notice to
Employees," may be obtained by writing tothe Director of the appropriate U.S. AtomicEnergy Commission Regional ComplianceOffice listed in Appendix "D" or the Director,
;.; Division of Materials Licensing. U.S. AtomicEnergy Commission, Washington, D.C., 20545.
.720.207 Storage of licensed materials.Licensed materials stored in an unre-
stricted area shall be secured against un-authorized removal from the place ofstorage.
WASTE DISPOSAL
§ 20.3111' 'General requirement.No licensee shall dispose of licensed
material except:(a) By transfer to an authorized re-
cipient as provided in the regulations inPart 30, 40, or 70 of this chapter, which-ever may be applicable; or
(b) As authorized pursuant to§ 20.302; or
(c) As provided in 420.303 or20.304, applicable respectively to the
2; disposal of licensed material by release^ into sanitary sewerage systems or burialu.tr in soil, or in § 20.106 (Concentrations in,,, Effluents to Unrestricted Areas).
§ 20.302 Method for obtaining approvalof proposed disposal procedures.
Any licensee or applicant for a licensemay apply to the Commission for ap-proval of proposed procedures to disposeof licensed material in a manner nototherwise authorized in the regulationsin this chapter. Each application shouldinclude a description of thelicensed material and any other radio-active material involved, including thequantities and kinds of such materialand the levels of radioactivity involved,and the proposed manner and condi-tions of disposal. The application shouldalso include an analysis and evaluationof pertinent information as to the nature
RADIATION
of the environment, including topo-graphical, geological, meteorological,and hydrological characteristics; usageof ground and surface waters in the gen-eral area; the nature and location ofother potentially affected facilities; andprocedures to be observed to minimizethe risk of unexpected or hazardous
pcosures.The Commission will not approve any
application for a license to receive II-censed material from other persons for
u. disposal pn land not owned by the:.0 Federal government or by a Stet:!government.
.190.303. Disposal by release into sani-tary sewerage systems.
No licensee shall discharge licensedmaterial into a sanitary sewerage systemunless:
(a) It is readily soluble or dispersiblein water; and
(b) The quantity of any licensed orother radioactive material released intothe system by the licensee in any one,day does not exceed the larger of sub-paragraphs (1) or (2) of this paragraph:
(1) The quantity which, if diluted bythe average daily quantity of sewage re-leased into the sewer by the licensee,will result in an average concentrationequal to the limits specified in AppendixB, Table I, Column 2 of this part; or
(2) Ten times the quantity of suchmaterial specified in Appendix C of thispart; and
(c) The quantity of any licensed orother radioactive material released inany one month, if diluted by the averagemonthly quantity of water released by
. the licensee, will not result in an averager, concentration exceeding the limits spec-^ iced in Appendix B, Table I, Column 2u. of this part; andn (d) The gross quantity of licensed and4,4 Cher radivaaive material released into
the sewerage system by the licensee doesnot exceed one curie per year.Excreta from individuals undergoingmedical diagnosis or therapy with radio-active material shall be exempt fromany limitations contained in thissection.§ 20.304 Disposal by burial in soil.
No licensee shall dispose of licensedmaterial by burial in soil unless:
(a) The total quantity of licensed andother radioactive materials buried at anyone location and time does not exceed, atthe time of burial, 1,000 times the amoUntspecified in Appendix C of this part; and
(b) Burial is at a minimum depth offour feet; and
(c) Successive burials are separated bydistances of at least six feet and not morethan 12 burials are made in any year.
PART 20 - STANDARDS FOR PROTECTION AGAINST RADIATION
§ 20.305 Treatment or disposal by incin-eration.
No licensee shall treat or dispose of ^licensed material by incineration exceptas specifically approved Dy the Commis-sion pursuant to §§ 20.106(b) and 20.302
RECORDS, REPORTS; AND NOTYPICATION
§ 20.401 Records of surveys, radiationmonitoring, and disposal.
(a) Each licensee shall maintain rec-ords showing the radiation exposures ofall individuals for whom personnel mon-itoring is required under § 20.202 of theregulations in this part. Such recordsshall be kept on Form AEC-5, in accord-ance with the instructions contained inthat form or on clear and legible rec-
t ords containing all the information re-- quired by Form AEC-5. The dtfSes en-ccu. tered on the forms or records shall be forin periods of time not exceeding one calen-
dar qiiafter.(b) Each licensee shall maintain rec-
ords in the same units used inthis part, showing the results
or surveys required by § 20.201 (b), anddisposals made under §§ 20.302, 20.303,
end 20.304,(c) Records of individual radiation
exposure which must be maintained pur-suant to the provisions of paragraph (a)
; of this section shall be preServed until,o December 31, 1070, or until a date 5 years-, after termination of the individual's em-= ployment, whichever is later. RecordsLL which must be maintained purSuant tocl this part may be maintained in the form
of microfilms.NOTE: Prior to December 31, 1970, the Com-
mission may amend this paragraph to assurehe further preservation of records which it
determines should not be destroyed..§ 20.102 Reports of Owl' t or lo-s of
ik,I,Sell material.Each licensee shall report by telephone
and telegraph to the Director of theappropriate Atomic Energy CommissionRegional Compliance Office listed in Ap-pendix D. Immediately after its occur-rence becomes known to the licensee, anyloss or theft of licensed material in suchquantities and under such circumstancesthat it appears to the licensee that asubstantial hazard may result to personsin unrestricted areas.
o § 20.103 Notifications of incidents.(a) Immediate notification. Each 11-
censee shall immediately notify the Di-P. rector of the appropriate Atomic Energy" Commission Regional compliance Office
shown in Appendix D by telephone andtelegraph of any incident involving by-product, source or special nuclear mate-rial possessed by him and which mayhave caused or threatens to cause:
(1) Exposure of the whole body of anyIndividual to 25 rems or more of radia-tion; exposure of the skin of the wholebody of any Individual of 150 reins ormord of radiation; or exposure of thefeet. ankles, hands or forearms of anyindividual to 375 rims or more of radia-tion: or
ig40cc
(2) The release of radioactive mate-rial in concentrations which, if averagedover a period of 24 hours, would exceed5,000 times the limits specified for suchmaterials In Appendix B, Table II; or
(3) A loss of one working week ormore of the operation of any facilitiesaffected: or
(4) Damage to property In excess of$100,000.
(b) 7'wen ty-lour hour notifiention.Each licensee shall within 24 hoursnotify the Director of the appropriateAtomic Energy Commission RegionalCompliance Office listed in Appendix Dby telephone and telegraph of any inci-dent involving licensed material pos-sessed by him and which may havecaused or threatens to cause:
(1) Exposure of the whole body of anyindividual to 5 rems or more of radia-tion; exposure of the skin of-the wholebody of any individual to 30 rear ormore of radiation; or exposure of thefeet, ankles, hands, or forearms to '15rems or, more, of radiation; or
(2) The release of radioactive material in concentrations which, if aver-aged over a period of 24 hours, wouldexceed 500 times the limits specified forsuch materials in Appendix B, Table II;Or
(3) A loss of one day or more of theoperation of any facilities affected; or
(4) Damage to property in excess of$1,000.
(c) Any report filed with the Corn-misgion pursuant to this section shall beprepared so that names of individualswho have received exposure to radiationwill be stated in a sepaiste part of the
Eeport.§ 20.404 Report to former employees of
exposure to radiation.
.sr
At the request of a former employeeeach licensee shall furnish to the formeremployee a report of the former em-ployee's exposure to radiation as shownin records maintained by the licenseePursuant to § 20.401(a). Such reportshall be furnished within 30 days fromthe time the request is made; shall covereach calendar quarter of the individual'semployment involving exposure to radi-ation, or such lesser period as may berequested by the employee, The reportshall also include the results of any cal-culations and analyses of radioactive
LLmaterial deposited in the body of theemployee and made pursuant to the pro-visions of § 20.108. The report shall bein writing and contain the followingstatement:
This report is furnished to you under theprovisions of the Atomic Energy Commissionregulations entitled "Standards for Protec-tion Against Radiation" (10 CFR Part 20).You should preserve this report for futurereference.
(b) The former employee's requestshould include appropriate identifyingdata, such as social security numberand dates and locations of employment.
Revlsold 31 FR 4668
-**Revised 32 eR 10432
3 ?
§ 20.405 Reports of overexposures andexcessive levels and concentrations.
(a) In addition tc any notificationrequired by 1 20.403, each licensee shallmake a report in writing within 30 daysto the Director, Divi-sion of ' Compliance, U.S.Atomic Energy Commission, Washington,D.C., 20545 , witha copy to the Director of the appropriateAtomic Energy Commission RegionalCompliance Office listed in Appendix D,of (1) each exposure of an individual toradiation or concentrations of radioac-
"' tive material in excess of any applicable9", limit in this part or in the licensee's, license; (2) any incident for which noti-LT. fication is required by I 20.403; and (3)1,z. levels of radiation or concentrations of
radioactive material (not involving ex-cessive exposure of any individual) inan unrestricted area in excess of tentimes any applicable limit set forth inthis part or in the licensee's license.Each report required under this para-graph shall describe the extent of ex-posure of persona to radiation or toradioactive Material: levels 'cut fatiltlonand concentrations of radioactive mate-rial involved; the cause of the exposure,levels or concentrations; and correctivesteps taken or planned to assure against
__Lrecurrence.(b) In any case where a licensee is
required pursuant to the provisions ofthis section to report to the Commissionany exposure of an individual to radia-tion or to concentrations of radioactivematerial, the licensee shall also notify
'S such individual of the nature and extentof exposure. Such notice shall be in
fg, writing and shall contain the following, statement:" This report is furnished to you under the
provisions of the Atomic Energy Commissionregulations entitled "Standards for Protec-tion Against Radiation" (10 CFR Part 20).You should preserve this report for futurereference.
(c) Any report flied with the Coin-mission pursuant to this section shall be
'a prepared so that names of Individuals'" who have received exposure to radiationu. will be stated in a separate part of thedeport.§ 20.406 Notice to employees of ex-
posure to radintson.At the request of any employee, each
licensee shall advise such employee an-nually of the employee's exposure toradiation as shown in records main-tained by the licensee pursuant to§ 20.401(a).
EXCEPTIONS AND ADDITIONALREQUIREMENTS
§ 20.501 Applications for exemptions.cg The Commission may, upon applicationLL by any licensee or upon its own initiative,(4 grant such exemptions from the require-
ments of the regulations in this part asit determines are authorized by law andwill not result in undue hazard to lifeor property.§ 20.502 Additional requirements.
The Commission may, by rule, regula-tion, or order, impose upon any licenseesuch requirements, in addition to those
September 2, 1967
39
PART 20 - STANDARDS FOR PROTECTION AGAINST RADIATION
established in the regulations in thispart, as it deems appropriate or necessaryto protect health or to minimize dangerto life or property.
ENFORCEMENT
§ 20.601 Violationm.An injunction or other court order may
be obtained prohibiting any violation ofany provision of the act or any regulationor order issued thereunder. Any personwho willfully violates any provision ofthe act or any regulation or order issuedthereunder may be guilty of a crime, andupon conviction, may be punished by fineor imprisonment or both, as provided bylaw.
40
38
UNITED STATES ATOMIC ENERGY COMMISSION
--'''',RULES and REGULATIONS TITLE 10 -. ATOMIC ENERGY
Sec.30.130.230.330.430.530.6
PART30
GENERAL RROVLSIONS
Purpose and scope.Resolution of conflict.Activities requiring license.Definitions.Interpretations.Communications.
RIERIPTIONS
30.11 Exemptions from licensing.30.12 Persons using byproduct material un-
der certain Atomic Energy Commis-sion contracts.
30.13 Carriers.30.14 Sligtpt concentrations.30.16 Certain Items containing tritium
or promethium 14730.16 Resins containing scandium 441
and designed fur sand-con-solidation In of t yetis.
Limnos=30.31 Types of licenses.30.32 Applications for specific licenses.30.33 general requirements for issuance of
specific, licenses.30.34 Terms and conditions of licensee.30.35 Reference. in licenses outstanding on
effective date of recodificatlon ofthis part.
30 36 Expiration of licenses.30.37 Applications for renewal of licenses.30.38 Applications for amendment of li-
censes.30.39 Commission action on applications to
renew or amend.RECORDS, INSPECTIONS AND TESTS
30.51 Records.30.52 Inspections.30.53 Tests.
Er(roscracercr30.61 Modification and revocation of li-
censes.30.62 Right to withhold or recall byproduct
material.30.63 Violations.
SCHEDULES
30.70 Schedule A-Exempt concentrations.
GENEsst, PROVISIONS
§ 30.1 Purpose and scope.This part prescribes rules governing
licensing of byproduct material underthe Atomic Energy Act of 1954, asamended (68 Stat. 919), and exemptionsfrom the licensing requirements per-
o mitted by section 81 of the Act, applicable:3 to all persons in the United Stestes.ce § 30.2 Resolution of conflict.
The requirements of this part are inaddition to, and not in substitution for,other requirements of this chapter. Inany conflict between the requirements inthis part and a specific requirement inanother part of the regulations in thischapter, the specific requirement gov-erns.
RULES OF GENERAL APPLICABILITY TOLICENSING OF BYPRODUCT MATERIAL
§ 30.3 Activities requiring license.-Except for persons exempt as providedin this part and Part 150 of this chapter,no person shall manufacture, produce,transfer, receive, acquire, own, possess,use, import or cxport byproduct materialexcept as authorized in a specific or gen-eral license issued pursuant to the regu-lations in this chapter.§ 30.4 Definitions.
As used in this part and Parts 31-36of this chapter:
fa) "Act", means the Atomic EnCrgy,Act of 1954, inCluding any amendmentsthereto;
(b) Terms defined in section 11 of theAct shall have the same meaning whcnused in the regulations in this part andParts 31-36 to the extent such terms arenot specifically defined in this part;
(c) "Agreement State" means anyState with which the Commission hasentered into an effective agreement un-der subsection 274b. of the Act. '"Non-agreement State" means any other State;
(d) "Byproduct material" means anyradioactive material (except specialnuclear material) yielded in or maderadioactive by exposure to the radiationincident to the process of producing orutilizing special nuclear material;
(e) "Commission" means the AtomicEnergy Commission and its duly author-ized representatives;
(f) "Curie" means that amount ofradioactive material which disintegratesat the rate of 37 billion atoms persecond;
(g) "Government agency" means anyexecutive department, commission, inde-pendent establishment, corporation,wholly or partly owned by the UnitedStates of America which is an instrumen-tality of the United States, or any board,bureau, division, service, office, officer,authority, administration, or other estab-lishment in the executive branch of theGovernment ;
(h) "Human use" means the internalor external administration of byproductmaterial, or the radiation therefrorp, tohuman beings;
'(i) "License", except where otherwisespecified means a license for byproductmaterial issued pursuant to the regula-tions in this chapter;
(I) "Microcurle" means that amountof radioactive material which disinte-grates at the rate of 37 thousand atomsper second;
39
(k) "Person" means (1) any individ-ual, corporation, partnership, firm, as-sociation, trust, estate, public or privateinstitution, group, Government agencyother than the Commission, any State orany political subdivision of, or any Po-litical entity within a State, any foreigngovernment or nation or any politicalsubdivision of any such government ornation, or other entity; and (2) any legalsuccessor, representative, agent, or agen-cy of the foregoing;
(1) "Physician" means an individuallicensed by a State or territory of theUnited States;-the District of Columbiaor the Commonwealth of Puerto Rico todispense drugs in the practice of medi-cine;
(m) 'Production .facility" means pro-duction facility as defined in the regula-tions contained in Part 50 of this chapter;
(n) "Radiographer" means any indi-vidual who performs or who, in attend-ance at the site where the sealed sourceor sources are being, used, personallysupervises radiographic operations andwho is responsible to the licensee for as-suring compliance with the requirementsof the Commission's regulations and theconditions of the license;
(0) "Radiographer's assistant" meansany individual who, under the personalsupervision of a radiographer, uses radio-graphic exposure devices, sealed sourcesor related handling tools, or survey in-struments in radiography;
(p) "Radiography" means the exami-nation of the structure of materials by,nondestructive methods, utilizing sealedsources of byproduct materials;
(q) "Research and development"'means (1) theoretical analysis, explora-tion, or experimentation; or (2) the ex-tension of investigative findings andtheories of a scientific or technical na-ture into practical application for experi-mental and demonstration purposes, in-cluding the experimental production andtesting of models, devices, equipment,materials and processes. "Research anddevelopment" as used in this part andParts 31-36 does not include the internalor external administration of byproductmaterial, or the radiation therefrom, tohuman beings;
(r) "Sealed source" means any by-product material that is encased in acapsule designed to prevent leakage orescape of the byproduct material;
(5) "Source material" means sourcematerial as defined in the regulationscontained in Part 40 of this chapter;
(t) "Special nuclear material" meansspecial nuclear material as defined inthe regulations contained in Part 70 ofthis chapter;
April 29, 1967
41
PART 30 - RULES OF GENERAL APPLICABILITY TO LICENSING, ETC.
(u) "United States", when used in ageographical sense, includes all territo-ries and possessions of the United States,the Canal Zone and Puerto Rico;
(v) "Utilization facility" means a uti-lization facility as defined in the regulzi-tons contained in Part 50 of thischapter.§ 30.5. Interpretations.
Except as specifically authorized bythe Commission in writing, no interpre-tation of the meaning of the regulationsin this part and Parts 31-36 by any of-ficer or employee of the Commissionother than a written interpretation bythe General Counsel will be recognizedto be binding upon the Commission.§ 30.6 Communications.
Except where otherwise specified, allcommunications and reports concerningthe regulations in this part and Parts31-36 and applications filed under them,should be addressed to the Director ofRegulation, U.S. Atomic Energy Com-mission, Washington, D.C., 20545. Com-munications, reports and applicationsmay be delivered in person at the Com-mission's offices at 1717 H Street NW.,Washington, D.C.; at 4915 St. Elmo Ave-nue, Bethesda, Md.; or at Germantown,Md.
EXEMPTIONS§ 30.11 Exemptions from licensing.
The Commission may upon the appli-cation of any interested person, or uponits own initiative, exempt certain classesor quantities of byproduct material orkinds of uses or users from the require-ments for a license set forth in section 81of the Act and in the regulations in thispart and Parts 31-36 when it makes afinding that the exemption of suchclasses or quantities of such material'orsuch kinds of uses or users will notconstitute an unreasonable risk to thecommon defense and security and to thehealth and safety of the Dublic.""§ 30.12 Peisons using byproduct mate-
rial under certain Atomic EnergyCommission contracts.
Any prime contractor of the Commis-sion is exempt from the requirements fora license set forth in sections 81 and 82of the Act and from the regulations inthis part to the extent that such con-tractor, under his prime contract withthe Commission, manufactures, pro-duces, transfers, receives, acquires, owns,possesses, uses, imports, or exports by-product material for: (a) The perform-ance of work for the Commission at aUnited States Government-owned orcontrolled site, including the transpor-tation of byproduct material to or fromsuch site and the performance of con-tract services during temporary inter-ruptions of such transportation; (b) re-search in, or development, manufacture,storage, testing or transportation of,atomic weapons or components thereof;or (c) the use or operation of nuclearreactors or other nuclear devices in aUnited States Government-owned ve-hicle or vessel. In addition to the fore-going exemptions, any prime contractor
April 29, 1967
42
or subcontractor of the Commission isexempt from the requirements for a li-cense set forth in sections 81 and 82 ofthe Act and from the regulations in thispart to the extent that such prime con-tractor or subcontractor manufactures,produces, transfers, receives, acquires,owns, possesses, uses, imports or e::portsbyproduct material under his prime con-tract or subcontract when the Commis-sion determines that the exemption ofthe prime contractor or subcontractor isauthorized by law; and that, under theterms of the contract or subcontriact,there is adequate assurance that thework thereunder can be 'accomplishedwithout undue risk to the public healthand safety. Any person exempt fromlicensing under this part prior to theeffective date of this amendment whowould otherwise be required by virtue ofthis section to obtain a license shallcontinue to be so exempt on an interimbasis. Such interim exemption shall ex-pire 60 days from the effective date ofthis amendment, unless. within said 60-day period either an application for alicense covering the activity or an appli-cation for an appropriate exemptionunder this section is filed with the Com-mission. If either such application isfiled within such 60-day period, theInterim exemption shall remain in effectuntil final action in the matter is takenby the Commission.§ 30.13 Carriers.
Common and contract carriers and theUnited States Post Office Department areexempt from the regulations in this partand Parts 31-36 and the requirementsfor a license set forth in section 81 of theAct to the extent that they transport by-product material in the regular courseof their business as carriers.§ 30.14 Exempt concentrations.
(a) Except as provided in .paragraphs(c) and (d) of this section, any personis exempt from the requirements for alicense set forth in section 81 of the Actand from the regulations in this part andParts 31-36 of this chapter to the extentthat such parson receives, possesses, uses,transfers, owns or acquires products ormaterials containing byproduct materialin concentrations not in excess of thoselisted in § 30.70.
(b) This section shall not be deemedto authorize the import, of byproduct ma-terial or products containing byproductmaterial.
(c) A manufacturer, processor, or pro-ducer of a product or material in anagreement State is exempt from the re-quirements for a license set forth in sec-tion 81 of the Act and from the regula-tions in this part and Parts 31, 32, 33, 34and 36, to the extent that he transfersbyproduct material contained in a prod-uct or material in concentrations not Inexcess of those specified in 30.70 andintroduced into the product or materialby a licensee holding a specific licenseissued by an agreement State or the Com-mission expressly authorizing such intro-duction. This exemption does not apply
4t)
reU.
to the transfer of byproduct materialcontained in any food, beverage, cos-metic, drug, or other commodity or prod-uct designed for ingestion or inhalationby, or application to, a human being.
(d) No person may introduce byprod-uct material into a product or materialknowing or having reason to believe thatit will be transferred to persons exemptunder this section or equivalent regu-lations of an agreement State, except inaccordance with a license issued pur-suant to 32.11 of this chapter or thegeneral license provided in 150.20 ofPart 150.
30.15 Certain items containing tritiumor promethium 147.
(a) Except for persons who applytritium or promethium 147 to, or personswho incorporate tritium or promethium147 into, the following products, or per-sons who import for sale or distributionthe following products containing tritiumor promethium 147, any person is exemptfrom the requirements for a license setforth in section 81 of the Act and fromthe regulations in Parts 20 and 30-36 ofthis chapter to the extent that such per-son receives, possesses, uses, transfers,exports, owns, or acquires the followingproducts:
(1) Timepieces or hands or dials con-taining not more than (1) 25 millicuriesof tritium per timepiece, (ii) 5 millicuriesper hand, or (iii) 15 millicuries per dial(bezels when used shall be considered aspart of the dial).
(2) Lock illuminators containing notmore than 15 millicuries of tritium or notmore than 2 millicuries of promethium147 installed in automobile locks. Thelevels of radiation from each lock il-luminator containing promethium 147will not exceed 1 millirad per hour at 1centimeter from any surface when meas-ured through 50 milligrams per squarecentimeter of absorber.
(3) Balances of precision containingnot more than 1 millicurie of tritium perbalance or not more than 0.5 millicurieof tritium per balance part'
(4) Automobile shift quadrants con-taining not more than 25 millicuries oftritium.
* * (5) Marine compasses containing notmore than 750 mink-dries of tritium gasand .other marine navigational instru-ments containing not more -than 250._millicuries of tritium gas.--76) The'rmostat dials and pointerscontaining not more than 25 millicuriesof tritium per thermostat.° (7) Glow lamps containing not morethan 10 microcuries of tritium per lamp.
"Addd 31 FR 1434944, Amended 32 Fa 7115
Export shipment. of precision balances issubject to the licensing authority and regula-tions of the Department of Commerce. is-suance of an exemption by the Atomic EnergyCommission for export of tritium containedIn balances of precision or the parts thereofdoes not relieve any person from complyingwith the licensing requirements and regula-tions of the Department, of Commerce.
PART 30 - RULES
1
centimeter from any surface when meas-ured through 50 milligrams per squarecentimeter of absorber.
(3) Balances of precision containingnot more than 1 roillicurie of tritium perbalance or not more than 0.5 millicurieof tritium per balance part.'
(4) Automobile shift quadrants con-taining not more than 25 millicuries of
...tritium.4.--*4,45) Marine compasses Containing notmore than 750 millicuries of tritium gasand other marine navigational instru-ments containing not more -than 250millicuries of tritium gas.
(6) Thermostat dials and pointerscontaining not more than 25 millicuriesof tritium per thermostat.
[
..(7) Glow lamps containing not morethan 10 mierocuries of tritium per lamp.
.8) Spark gap tubes containing notmore than 30 microcuries of promethium147. The levels of radiation from eachspark gap tube containing promethium147 will not exceed 0.5 millirad per hourat 1 centimeter from any surface whenmeasured through 7 milligrams persquare centimeter of absorber.
(b) Any person who desires to applytritium or promethium 147 to, or to in-corporate tritium or promethium 147into, the products exempted in paragraph(a) of this section, or who desires to im-
7) Port for sale or distribution such productscs containing tritium or promethium 147,4. should apply for a specific license, pur--c, suant to 32.14 of this chapter, which
liCense states that the product may bedistributed by the licensee to personsexempt from the regulations pursuant toParagraph (a) of this gection.
'Export shipment of precision balances issubject to the licensing authority and regula-tions of tile Department of Commerce. Is-suance of an exemption by the Atomic EnergyCommission for export of tritium containedIn balances of precision or the parts thereofdoes not relieve any person from complyingwith the licensing requirements and regula-tions of the Department of Commerce.
*. Addled 31 FR 14349Amended 32 FR 755
Added 32 FR 6433
OF GENERAL APPLICABILITY
§ 30.16 Resins containing scandium 46and designed for sand-consolidationin oil welts.
Any person is exempt from the require-ments for a license set forth in section81 of the Act and from the regulationsin Parts 20 and 30-36 of this chapter tothe extent that such person receives,possesses, uses, transfers, exports, owns,or acquires synthetic plastic resins con-taining scandium 46 which are designedfor sand-consolidation in oil wells, andwhich have been manufactured or im-ported for sale or distribution, in accord-ance with a specific licdnse issued DUISU-ant to 1 32.17 of this chapter or equiva-lent regulations of an agreement State.The exemption in this section does notauthorize the manufacture or import ofany resins containing scandium 46.
* Added 32 FR 4241
41
TO LICENSING, ETC.
LICINSES
§ 30.31 Types of licenses.Licenses for byproduct material are of
two types: General and specific. Specificlicenses are issued to named personsupon applications filed pursuant to theregulations in this part and Parts 32-36.General licenses are effective without thefiling of applications with the Commis-sion or the issuance of licensing docu-ments to particular persons.§ 30.32 Applications for specific li-
censes.(a) Applications for specific licenses
should be filed on Form AEC-313, "Ap-plication for Byproduct Material Li-cense", with the Director, Division ofMaterials Licensing, U.S. Atomic En-ergy Commission, Washington, D.C.,20545. Applications may be filed in per-son at the Commission's offices at 1717H Street NW., Washington, D.C.; at 4915St. Elmo Avenue, Bethesda, Md.; or atGermantown, Md. Information con-tained in previous applications, state-ments or reports filed with the Commis-sion may be incorporated by reference,provided that such references are clearand specific.
(b) The Commission may at any timeafter the filing of the original applies-Akin, and before the expiration of the li-cense, require further statements in or-der to enable the Commission to deter-mine whether the application should begranted or denied or whether a licenseshoUld be modified or revoked.
(c) Each application shall be signedby the applicant or licensee or a personduly authorized to act for and on hisbehalf.
(d) An application for license filedpursuant to the regulations in this partand Parts 32-36 will be considered alsoas an application for licenses authorizingother activities for which licenses are re-quired by the Act, provided that the ap-plication specifies the additional activ-
December 12, 196743
1
PART 30 - RULESities for which licenses are requested andcomplies with regulations of the Commis-sion as to applications for such licenses.§ 30.33 General requiremeI for issu-
ance of specific licenses.(a) An application for a specific li-
cense will be approved if:(1) The application is for a purpose
authorized by the Act;(2) The applicant's proposed equip-
ment and facilities are adequate to pro-tect health and minimize danger to lifeor property;
(3) The applicant is qualified by train-ing and experience to use the materialfor the purpose requested in such man-ner as to protect health and minimizedanger to life or property; and
(4) The applicant satisfies any specialrequirements contained in parts 32-36.
(b) Upon a determination that an ap-plication meets the requirements of theAct, and the regulations of the Commis-sion, the Commission will issue a spe-cific license authorizing the possessionand use of byproduct material (FormAEC 374, "Byproduct Material License")..§ 30.34 Terms and conditions of li-
censes.(a) Each license issued pursuant to the
regulations in this part and the regu-lations in Parts 31-36 shall be subject toall the provisions of the Act, now or here-after in effect, and to all valid rules, reg-ulations and orders of the Commission.
(b) No license issued or granted pur-suant to the regulations in this part andParts 31-36, nor any right under a li-cense shall be transferred, assigned or inany manner disposed of, either volun-tarily or involuntarily, directly or in-directly, through transfer of control ofany license to any person, unless theCommission shall, after securing full in-formation, find that the transfer is inaccordance with the provisions of the Actand shall give its consent in writing.
(c) Esth person licensed by the Com-mission pursuant to the regulations inthis part and Parts 31-36 shall confinehis possession and use of the byproductmaterial to the locations and purposesauthorized in the license. Except asotherwise provided in the license, a li-cense issued pursuant to the regulationsin this part and Parts 31-36 shall carrywith it the right to receive, acquire, own,possess and import byproduct materialand to transfer such material to otherlicensees within the United States au-thorized to receive such material.
(d) Each license issued pursuant. tothe regulations in this part and Parts31-36 shall be deemed to contaii. theprovisions set forth in section 183b.-d.,inclusive, of the Act, whether or notthese provisions are expressly set forthin the license.
(e) The Commission may incorporate,in any license issued pursuant to the reg-ulations in this part and Parts 31-36, atthe time of issuance, or thereafter byappropriate rule, regulation or order,such 'additional requirements and con-ditions with respect to the licensee's re-ceipt, possession, use and transfer ofbyproduct material as it deems appro-priate or necessary in order to:
(1) Promote the common defense andsecurity ;
April 29, 1967
44
OF GENERAL APPLICABILITY TO(2) Protect health oitO minimize dan-
ger to life or property;(3) Protect restricted data;(4) Require such reports and the
keeping of such records, and to providefor such inspections of activities underthe license as MR/ be necessary or ap-propriate to effectuate the purposes ofthe Act and regulations thereunder.g -.0.35 References in licenses outstand-
ing on effective date of recodificationof this part.
References to sections of Parts 30 and31 and to Parts 30 and 31 in licenses out-standing on the effective date of thisrecodification shall be deemed to bereferences to the sections of Parts 30-36and to Parts 30-36 superseding thosedenoted in the outstanding licenses.§ 30.36 Expiration of licenses.
Except as provided In I 30.37(b), eachspecific license shall expire at the end ofthe day, in the month and year statedtherein.§ 30.37 Applications for renewal of li-
censes.(a) Applications for renewal of a spe.
cific license shall be filed in accordancewith I 30.32.
(b) In any case in which a licensee,not less than thirty (30) days prior tothe expiration of his existing license, hasfiled an application in proper form forrenewal or for a new license, such exist-ing license shall not expire until the ap-plication has been finally determined bythe Commission.§ 30.38 Applications for amendment of
licenses.Applications for amendment of a li-
cense shall be filed in accordance with30.32 and shall specify the respects in
which the licensee desires his license tobe amended and the grounds for suchamendment.§ 30.29 Commission action on applica-
tions to renew or amend.I1 considering an application by a li-
censee to renew or amend his license theCommission will apply the applicable cri-teria set forth in S 30.33 and Parts 32-36of this chapter.
RECORDS, INSPECTIONS AND TESTS
§ 30.51 Records.
Each person who receives byproductmaterial pursuant to a license issuedpursuant to the regulations in this partand Parts 31-36 shall keep records show-ing the receipt, transfer, export and dis-posal of such byproduct material.
o § 30.52 Inspections.;3- (a) Each licensee shall afford to thece Commission at all reasonable times op-u. Portunity to inspect byproduct material" and the premises and facilities wherein
byproduct material is used or stored.(b) Each licensee shall make available
to the Commission for inspection, uponreasonable notice, records kept by himpursuant to the regulations In thischapter.
4
LICENSING, ETC.§ 30.53 Tests.
Each licensee shall perform, or permitthe Commission to perform, such tests asthe Commission deems appropriate ornecessary for the administration of theregulations in this part and Parts 31-36,including tests of:
(a) Byproduct material;(b) Facilities wherein byproduct ma-
terial is utilized or stored;(c) Radiation detection and monitor-
ing instruments; and(d) Other equipment and devices used
in connection with the utilization orstorage of byproduct material.
ENFORCEMENT
§ 30.61 Modification and revocation oflicenses.
(a) The terms and conditions of eachlicense issued pursuant to the regula-tions in this part and Parts 31-36 shallbe subject to amendment, revision ormodification by reason of amendmentsto the Act, or by reason of rules, regu-lations and orders issued in accordancewith the terms of the Act.
(b) Any license may be revoked, sus-pended or modified, in whole or in part,for any material false statement in theapplication or any statement of fact re-quired under section 182 of the Act, orbecause of conditions revealed by suchapplication or statement of fact or anyreport, record or inspection or othermeans which would warrant the Com-mission to refuse to grant a lice:use onan original a. ication, or for violationof, or failure to observe any of the termsand provisions of the Act or of any rule,regulation or order of the Commission.
(c) Except in cases of willfulness orthose in which the public health, inter-est or safety requires otherwise, no li-cense shall be modified, suspended orrevoked unless, prior to the institutionof proceedings therefor, facts or con-duct which may warrant such actionshall have been called to the attentionof the licensee in writing and the licenseeshall have been accorded an oppor-tunity to demonstrate or achieve com-pliance with all lawful requirements.
§ 30.62 Right to withhold or recall by-product material.
The Commission may withhold, recallor order the withholding or recall of by-product material from any licensee whois nci; equipped to observe or fails toobserve such safety standards to pro-tect health as may be established by theCommission, or who uses such materialsin violation of law or regulation of theCommission, or in a manner other thanas disclosed in the application there-_.1:or approved by the Commission.
§ 30.63 Violations.
An injunction or other court order maybe obtained prohibiting any violationof any provision of the Act or any regu-lation or order issued theretinder. Anyperson who willfully violates any pro-vision of the Act or any regulation ororder issued thereunder may be guiltyof crime and, upon conviction, may bepunished by fine or Imprisonment orboth, as provided by law.
PART 30 - RULES OF GENERAL APPLICABILITY TO LICENSING, ETC.
SCHEDULES
§ 30.70 Schedule A-Exempt concentra-tions.
Element (atomicnumber)
Antimony (31)_____
Argon (18)
Arsenic (33)
Barium (56)
Beryllium (4)
5BismuthBromine (38Cadmium ( )
Calerum (M)
Carbon (6)Cerium (58)
Cesium (55)
Chlorine (17)Chromium (24)
fo Cobalt (27)
Cg Copper (29)LL Dysprosium (65)-- _
" Erbium (68)
Europium (63)
Fluorine (9)__ ------Gadolinium (64)----
Gallium (31)Germanium (32)Geld (79)
Hafnium (72)Hydrogen (1)Indium (49)
Iodine (53)
Iridium (77)
Iron (26)
Krypton (36)
Lanthanum (57)Lead (82)Lutetium (71)Manganese (25)._
Mercury (50)
Molybdenum (42)__Neodymium (60)---
Nickel (28)Niobium (Colum-
bium) (41).Osmium (73)
Palladium (46)
Isotope
Column
Gee con-centrationuc/m1
ColumnlI
Liquidand
solidconcen-trationuchnl
Sb 122Sb 124Sb 12.5
3X10-42X10-41X101
A 37 1X10-11A 41 4X10-1As 73 5x10-1As 74 5X10-4As 76 2X10-4As 77 8X10-4B 131 2X10-1Ba 140 3X10-4Bel 2X10-1BI 206 4X10-4B r 82 4X10-7 3X10-1Cd 109 2X10-1Cd 115m 3X10-4Cd 115 3X10-4Ca 46 9X10-1Ca 47 5X10-4C 14 1X10-4Ce 141 9X10-4Ca 143 4X10-4Ca 144 1X10-4Cs 131 2X10-1Cs 134m 6X10-1Cs 134 9X10-1CI 38 9X10-7 4xicrsCr 51 2X10-1Co 57 5X10-1Co 58 1X10-1Co 60 5X10-4Cu 64 3X10-1Dy 165 4X10-1Dy 166 4X10-4Er 169 9X10-4Er 171 1X10-1Eu 162 6X10-'(T fl= 9.2 Sirs)Eu 156 2X10-1F 18 2X10-4 8X10-1Gd 153 2X10-4Gd 159 8X10-4Ga 72 4X10-4Ge 71 2X10-1Au 196 2X10-1Au 196 5X10-4Au 199 2X10-1HI 181 7X10-411 3 5X10-1 3X10-1In 113m 1X10-1In 114m 2X10-41 126 3X10-' 2X10-1I 131 3X10-' 2X10-11 132 8X10-1 6X10-4I 133 1X10-1 7X10-1I 134 2X10-1 1X10-4Ir 190 2X10-1Sr 152 4X10-4Ir 194 3X10-4Fe 65 8X10-1Fe 59 6X10-4Kr 85m 1X10-4Kr 85 3X10.4La 140 2X10-4Pb 203 4X10-1Lu 177 1X10-1Mn 52 3X10-4Mn 54 1x10-'Mn 66 1X10-111g 197m 2X10-1He 197 3X10-1Lig 203 2X10-4
19497Nd147
2X10-16X10-4
Nd 149 3X10-1Ni 65 1X10-1Nb 95 1x10-'Nb 97 9X10-1Os 185 7X10-4Os 191m 3X10-1Os 191 2X10-1Os 193 6X10-4Pd 103 3X10-1Pd 109 9X10-4
307-802 0 68 - 4
Element (atomicnumber) Isotope
ColumnI
Cu con-tration
notml 1
Column11
Liquidandsolid
00110113-tratIonWall 1
Phosphorus (15)---- P 32 2X10-4Platinum (7$)_ Pt 191 1X10-4____
Pt 193m 1X10-1Pt 197m 1X10-1Pt 197 1X101
Potassium (19) K 42 3X10-1Praseodymium Pr 142 3X10-4
(60) Pr 143 5X10-4Promethium (61) Pm 147 2X10-1
Pm 149 4X10-4Rhenium (75) Re 183 6X10-1
Re 186 9X101Re 188 6X10-4
Rhodium (46) Rh 103m 1X10-IRh 105 1X101
Rubidium (37) Rb 66 7X10-4Ruthenium (44)____ Ru 97 4X10-1
Ru 103 IIX101Ru 105 1X10-4Ru 106 1X10-4
Samarium (82) Gm 153 IIX10-4Scandium (21)_____ Sc 46 4X10-'
Sc 47 9X10-'Sc 48 3X10-4
Selenium (34)______ Se 75 3X101Silicon (14) 51 31 OX10-1Silver (47) Ag 106 1X10-4
Ag 110m 3X10-'Ag III 4X101
Sodium (11) Na 24 2X101Strontium (38) Sr 89
Sr 911X10-47X10-4
Sr 92 7X10-4Sulfur (16)Tantalum (73)
S 35Ts 182
9X10-1 6X1014X10-4
Technetium (43)____ To 96m 1X10-1Tc 96 1X101
Tellurium (52)______ Ts 126mTe 127m
2X10-13X10-'
Te 127 3XTe 129m 3X1Ts 131m 6X10-4Ts 132 3X10-'
Terbium (65) Tb 160 4X10-'Thallium (81) Ti 200
TI 2014X10-13X10-'
TI 202 1X10-1TI 204 1X10-1
Thulium (69) rism 170Tm 171
5X10-45X10-1
Tin (50) Sn 113 9X10-4Sn 125 2X10-'
Tungsten (Wolf- W 181 4X10-'ram) (74).
Vanadium (33)W 187V 48
7X10-43X10-4
Xenon (54) Xe 131m 4X104Xe 133 3X101Xe 1 35 1X1X101
Ytterbium (70) Yb 175 1X10-1Yttrium (39) ----- -- Y
Y9091m
2X10-43X10-1
Y 91 3X10-4192 6X10-4Y93 3X10-4
Zinc (30) Zn 65Zn 64m
1X10-17X10-4
Zn 69 2X10-1Zirconium (40) Zr 95
Zr 970(10-42X10-4
Bets and/or gammaemittingbyproductmaterial notlisted above withhalf-life less than
1X10-14 1X101
3 years.
NOTE 1: Many radioisotopes disintegrate into isotopeswhich are also radioactive. In expressing the concen-trations In Schedule A, the activity stated is that of theparent isotope and takes into account the daughters.
NOTE 2: For purposes of 130.14 where there is involveda combination of isotopes, the limit for the combinationshould be derived as follows:
Determine for each isotope in the product the ratiobetween the concentration present in the product andthe exempt concentration established in Schedule A forthe specific isotope when not in combination. The sumof such ratios may not exceed "I" (i.e., unity).Example: .
Concentration of Isotope A In Product+Exempt concentration of Isotope A
Concentration of Isotope B in Product $IExempt concentration of Isotope B
Values are given only for those materials normallyused as gases.
311O/EM for solids.
4
Caosa Ricrwanws TABLENew section
30.130.2
Old section30.1, 30.2
New30.3 30.330.4 30.430.5 30.530.6 New30.11 30.830.12 30.630.13 30.730.14 30.9, 30.32(f)30.15 30.1030.16 30.1230.17 30.1430.31 30.2030.32 30.2230.33 30.23, 30.31(a)30.34 30.32(4)-(d),30.31(b),30.3830.35 New30.36 30.3430.37 30.3530.38 30.3630.39 .30.3730.51 30.4130.52 30.4330.53 30.4430.61 30.5130.62 30.5230.63 30.6130.70 30.73
June 29, 1965
45
Sec.31.131.231331.4
31.5
31.6
31.7
31.0
31.9
31.10
UNITED STATES ATOMIC ENERGY COMMISSION
RULES and REGULATIONS TITLE 10 - ATOMIC ENERGY
PART31
Purpose and scope.Terms and conditions.Certain devices and equipment.Certain quantities of byproduct ma-
terial.Certain measuring, gauging or con-
trolling devices.General license to install devices gen-
erally licensed in 1 31.5.Luminous safety devices for use in
aircraft.Americium 241 in the form of cali-
bration or reference sources.General license to own byproduct
material.General license for Strontium-90
in ice detection devices
Scarnoras31.100 Schedule AGenerally licensed
quantities.
g 31.1 Purpose and scope.This part establishes general licenses
for certain quantities of byproduct mate-rial and byproduct material containedin certain items. Part 30 of this chapteralso contains provisions applicable to thesubject matter of this part.
31.2 Terms and conditions:(a) The general licenses provided in
this part are subject to the provisions of11 30.14(d), 30.34 (a) to (e), 30.51 to30.63 and Parts 20 and 36 of this chap-ter 1 unless indicated otherwise in thelanguage of the general license.
(b) Persons who transfer, receive, ac-quire. own, possess, use or import Items
'a and quantities of byproduct materialpursuant to the general licenses provided
ex in 11 31.3 and 31.4:11- (1) Shall not effect an increase in the(9) radioactivity of said items or quantities
by adding other radioactive materialthereto, by combining byproduct mate-rial from two or more such items or quan-tities, or by altering them in any othermanner so as to increase thereby therate of radiation therefrom;
(2) Shall' not administer externally orinternally, or direct the administrationof, said items or quantities or any partthereof to a human being for any pur-pose, including, but not limited to, diag-nostic, therapeutic, and research pur-POWS :
(3) Shall not add, or direct the addi-tion of, said items or quantities or anyPart thereof to any food, beverage, cos-metic, drug, or other product designedfor ingestion or inhalation by, or appli-cation to, a human being;
I Attention is directed particularly to theprovisions of the regulations in Part 20 ofthis chapter which relate to the labeling ofcontainers.
August 25, 1965
GENERAL LICENSES FOR CERTAIN QUANTITIES OFBYPRODUCT MATERIAL AND BYPRODUCT MATERIALCONTAINED IN CERTAIN ITEMS
(4) Shall not include said items orquantities or any part thereof in anydevice, instrument, apparatus (includingcomponent parts and accessories there-to) intended for use in diagnosis, treat-ment or prevention of disease in humanbeings or animals or otherwise intendedto affect the structure or any functionof the body of human beings or animals.§ 31.3 Certain devices and equipment.
A general license is hereby issued totransfer, receive, acqUire, own, possessand use byproduct material incorporatedin the following devices or equipmentwhich have been manufactured, testedand labeled by the manufacturer in ac-cordance with the specifications con-tained in a specific license Issued to himby the Commission.
(a) Static elimination device. Devicesdesigned for use as static eliminatorswhich contain, as a sealed source orsources, byproduct material consisting ofa total of not more than 500 microcuriesof polonium 210 per device.
(b) Spark gap and electronic tubes.Spark gap tubes and electronic tubeswhich contain byproduct material con-sisting of not more than 5 microcuriesper tube of cesium 137, or nickel 63, orkrypton 85 gas, or not more than onemicrocurie per tube of cobalt 60.
(c) Light meter. Devices designed foruse in measuring or determining lightintensity which contain, es a sealedsource or sources, byproduct materialconsisting of a total of not more than200 microcuries of strontium 90 perdevice.
(d) Ion generating tube. Devices de-signed for ionization of air which con-tain, as a sealed source or sources, by-product material consisting of a total ofnot more than 500 microcuries of po-lonium 210 per device or of a total of notmore than 50 millicuries of hydrogen 3(tritium) per device.
31.4 Certain quantities of byproductmaterial.
A general license is hereby issued totransfer, receive, acquire, own, possess,use and import the quantities of byprod-uct material listed in 1 31.100, ScheduleA, provided that no person shall at anyone time possess or use, pursuant to thegeneral licensing provisions of this sec-tion, more than a total of ten such sched-uled quantities.§ 31.5 Certain measuring, gauging or
controlling 'devices.(a) Subject to the provisions of this
section, a general license is hereby issuedto own, receive, acquire, possess and usebyproduct material when contained indevices designed and manufactured forthe purpose of detecting, measuring,
4 4
0
LL
0
CrLL
0
gauging or controlling thickness, density,level, interface location, radiation, leak-age, or qualitative or quantitative chem-ical composition, or for producing lightor an ionized atmosphere.
(b) The general license contained inthis section applies only to devices whichhave been:
(1) Manufactured in accordance withthe specifications contained in a specificlicense issued by the Commission to themanufacturer of the device pursuant to1 32.51 of this chapter, or In accordancewith the specifications contained in aspecific license issued-to the manufac-turer by an agreement State which au-thorizes the manufacture of the devicefor distribution to persons generally li-censed by the agreement State; and
(2) Installed on the premises of thegeneral licensee by a person authorizedto install such devices under a sPecifiC:license Issued to the installer by theCommission pursuant to Parts 30 and 32of this chapter or by an agreement State,if a label affixed to the devices at thetime of receipt states that installationby specific licensee is required. Therequirement of this subparagraph (2)does not apply while devices are held instorage in the original shipping con-tainer pending installation by specificlicensee.
(c) The general license contained inthis section applies only to devices which(1) are labeled in accordance with theprovisions of the specific license whichauthorizes the distribution of the deviceto general licensees, and (2) bear a labelcontaining the following or a substan-tially similar statement which containsthe information called for in the follow-ing statement: 1
The receipt, possession, use, and transferof this device, Model , Serial No.
, are subject to general license orthe equivalent and the regulations of theU.S. AEC or of a State with which the AEChas entered into an agreement for the exer-cise of regulatory authority. Removal ofthis label is prohibited.
Cstrrion-Raotoacrtve Maziam,
(Name of supplier)The model, serial number, and name of
supplier may be omitted from this labelprovided they are elsewhere specified inlabeling affixed to the device.
(d) Persons who own, receive, acquire,possess or use a device pursuant to thegeneral license contained in lig s motion:
(1) Shall not transfer, abandon ordispose of the device except by transferto a person authorized by a specific li-cense from the Commission or an agree-ment State to receive such device andshall furnish to the Director of the ap-propriate Atomic Energy CommissionRegional Compliance Office listed in Ap-pendix "D" of Part 20 of this chapter,"Standards for Protection Against Ra-diation", within 30 days after any trans-
., Devices generally licensed under this sec-tion acquired prior to July 1, 1960, may bearlabels authorized by the regulations in effecton Jan. 1, 1965.
47
PART 31 - GENERAL LICENSES FOR CERTAIN QUANTITIES, ETC.' fer, a report containing the name of the
manufacturer of the device, the type ofdevice, the manufacturer's serial num-ber of the device, and the name and ad-dress of. the person receiving the device;. (2) Shall assure that all labels affixed
to the device at the time of receipt andbearing a statement that removal of thelabel is prohibited are maintainedthereon and shall comply with all in-structions contained in such labels:
(3) Shall have the device tested forleakage of radioactive material andproper operation of the on-off mecha-nism and indicator, if any, at the timeof installation of the device or replace-ment of the byproduct material on thepremises of the general licensee andthereafter at no longer than six-monthintervals or at such longer intervals notto exceed three years as are specified inthe label required by I 31.5(c) ; providedthat devices containing only kryptonneed not be tested for leakage, and de-vices containing only, tritium need not betested for any purpose;
(4) Shall have the tests required bysubparagraph (3) of this paragraph andall other services involving the radioac-tive material, its shielding and contain-ment, performed by the supplier orother person holding a specific licensefrom the Commission or an agreementState to manufacture, install or servicesuch devices;
(5) Shall, within 30 days after the oc-currence of a failure of or damage to theshielding of the radioactive material or
4T, the on-off mechanism or indicator or47, upon the detection of. 0.005 microcuriere or more of removable radioactive mate-". rial, furnish to the Director of the ap-
propriate Atomic Energy CommissionRegional Compliance Office listed in Ap-pendix "D" of Part 20 of thil chapter,"Standards for Protection Against Ra-diation", a report containing the name ofthe manufacturer of the device, the typeof device, the ;manufacturer's serial num-ber of the device and a brief descriptionof the event and the remedial actiontaken; and shall maintain records of alltests performed on the devices as re-quired under this section, including thedates and results of the tests and thenames of the persons conducting thetests;
(6) Upon the occurrence of a failureof or damage to, or any indication of apossible failure of or damage to, theshielding or containment of the radio-active material or the on -off mechanismor indicator, shall immediately suspendoperation of the device until it has beenrepaired by the supplier or other per-son holding a specific license from theCommission or an agreement State tomanufacture, install or service such de-vices, or disposed of by transfer to a per-son authorized to receive the byproductmaterial contained in the device; and
(7) Shall be exempt from the require-ments of Part 20 of this chapter, exceptthat such persons shall comply with theprovisions of §§ 20.402 and 20.403 of thischapter,
(e) Persons who possess byproductmaterial pursuant to this general licenseshall not export such byproduct material
30 FR 10947
June 17 , 1967
48
without a specific license from the Com-mission authorizing such export.§ 31.6 General license to install devices
generall7 Heensed in § 31.5.Any person who holds a specific license
issued by an agreement State authoriz-ing the holder to manufacture, installor service a device described in § 31.5within such agreement State is herebygranted a general license to install andservice such device in any non-agree-ment State; Provided, That:
(a) Such person shall file a reportwith the Director, Division of MaterialsLicensing, U.S. Atomic Energy Commis-sion, Washington, D.C., 20545, within 30days after the end of each calendar quar-ter in which any device is transferredor installed. Each such report shallidentify each general licensee under§ 31.5 by name and address, the type ofdevice transferred, and the quantity andtype of byproduct material contained inthe device.
(b) The device has been manufac-tured, labeled, installed, and serviced inaccordance with applicable provisionsof the specific license issued to such per-son by the agreement State.
fc) Such person assures that anylabels required to be affixed to the deviceunder regulations of the agreement.State which licensed manufacture of thedevice bear a statement that removal ofthe label is prohibited.
(d) Such person shall furnish toeach general licensee to whom he trans-fers such device or on whose-premiseshe installs such device a copy of thegeneral license contained in § 31.5.§ 31.7 Luminous safety devices for use
in aircraft.(a) A general license is hereby issued
to own, receive, acquire, possess, anduse tritium or promethium 147 containedin luminous safety devices for use in air-craft, provided each device contains notmore than 10 curies of tritium or 100millicuries of promethium 147 and thateach device has been manufactured, as-sembled or imported,in accordance witha license issued under the provisions of§ 32.53 of this chapter or manufacturedor assembled in accordance with a spe-cific license issued by an agreementState which authorizes manufacture orassembly of the device for distribution topersons generally licensed by the agree-ment State.
(b) Persons who own, receive, acquire,possess or use luminous safety devicespursuant to the general license in thissection are exempt from the require-ments of Part 20 of this chapter, exceptthat they shall comply with the pro-visions of §§ 20.402 and 20.403 of thischapter.
(c) This general license does not au-thorize the manufacture, assembly, re-pair or import of luminous safety devicescontaining tritium or promethium 147.
(d) This general license does not au-thorize the export of luminous safety de-vices containing tritium or promethium147 except in accordance with the provi-sions of Part 36 of this chapter.
(e) This general license does not au-thorize the ownership, receipt, acquisi-
**Rev 1,ed 32 FR 7247
4
tion, possession or use of promethium 147contained in instrument dials.§ 31.8 Americium 241 in the form of
calibration or reference sources.(a) A general license is hereby issued
to those persons listed below to own, re-ceive, acquire, possess, use and transfer,in accordance with the provisions ofparagraphs (b) and (c) of this section,americium 241 in the form of calibrationor reference sources:
(1) Any person in a non-agreementState who holds a specific license issuedby the Commission which authorizes himto receive, possess, use and transfer by-product material, source material, or spe-cial nuclear material; and
(2) Any Government agency, as de-fined in § 30.4(g) of this chapter, whichholds. a specific license issued by theCommission which authorizes it to re-ceive, possess, use and transfer byproductmaterial, source material, or specialnuclear material.
(b) The general license in paragraph(a) of this section applies only to calibra-tion or reference sources which havebeen manufactured in accordance withthe specifications contained in a specificlicense issued by the Commission to themanufacturer or importer of the sourcesPursuant to 32.57 of this chapter or inaccordance with the specifications con-tained in a specific license issued to themanufacturer by an agreement Statewhich authorizes manufacture of thesources for distribution to persons gen-erally licensed by the agreement State.
(c) The general license in paragraph(a) of this section is subject to the pro-visions of §§ 30.14(d). 30.34 (a) to (e),and 30.51 to 30.63 of this chapter, andto the provisions of Part 20 of this chap-ter. In addition, persons who own, re-ceive, acquire, possess, use and transferone or more calibration or referencesources pursuant to this general license:
(1) Shall not possess at any one time,at any one location of storage or use,more than 5 microcuries of americium241 in such sources;
(2) Shall not receive, possess, use ortransfer such source unless the source,or the storage container, bear.: a labelwhich includes the following statementor a substantially similar statementwhich contains the information calledfor in the following statement:
The receipt, possession, use and transfer ofthis source, Model , Serial No.are subject to a general license and the reg-ulations of the United States Atomic EnergyCommission or of a State with which theCommission has entered into an agreementfor the exercise of regulatory authority. Donot remove this label.CAUTION RADIOACTIVE MATERIAL
THIS SOURCE CONTAINS AMERICIUM241. DO NOT TOUCH RADIOACTIVEPORTION OF THIS SOURCE.
(Name of manufacturer or importer)(3) Shall not transfer, abandon, or
dispose of such source except by transferto a person authorized by a license fromthe Commission or an agreement Stateto receive the source.
(4) Shall store such source, exceptwhen the source is being used, in a closedContainer adequately designed and eon-
asccv.
PART 31 - GENERAL LICENSES FOR CERTAIN QUANTITIES, ETC,
strutted to contain americium 241 whichmight otherwise escape during storage.
(5) Shall not use such source for anypurpose other than the calibration ofradiation detectors or the standardiza-tion of other sources.
(d) This general license does notauthorize the manufacture or import ofcalibration or reference sources contain-ing americium 241.
(e) This general license does notauthorize the export of calibration orreference sources containing americium241.
g $ 31.9 General license to own byproductmaterial.
[
A general license is hereby issued toown byproduct material without regardto quantity. Notwithstanding any otherProvision of this chapter, a general li-censee under this paragraph is not au-thorized to manufacture, produce, trans-fer, receive, possess, use, import or exportbyproduct material, except as authorizedin specific license.
..vti 31.10 General license for strontium 90M ice detection devices.
(a) A general license is hereby issuedto own. receive, acquire, possess, use, andtransfer strontium 90 contained in icedetection devices, provided each devicecontains not mom than fifty microcuriesof strontium 90 and each device has beenmanufactured or imported in accordancewith the specifications contained in alicense issued by the Commission pur-suant to I 32.61 of this chapter or in ac-cordance with the specifications con-tained in specific license issued to themanufacturer by an agreement Statewhich authorizes manufacture of the icedetection devices for distribution to per-sons generally licensed by the agreementState.
(b) Persons who own, receive, acquire,possess, use, or transfer strontium 90
xcontained in ice detection devices Pur-silent to the general license in paragraph
w (a) of this section:i (1) Shall, upon occurrence of visuallye observable damage, such as a bend orri
crack or discoloration from overheating,to the device, discontinue use of the de-vice until it has been inspected, testedfor leakage and repaired by a personholding a specific license from the Com-mission or an agreement State to manu-facture or service such devices; or shalldispose of the device pursuant to theprovisions of I 20.301 of this chapter;
(2) Shall assure that ill labels affixedto the device at the time of receipt, andwhich bear a statement which prohibitsremoval of the labels, are maintainedthereon;
(3) Are exempt from the require-ments of Part 20 of this chapter exceptthat such persons shall comply with theProviblyurs of 11 20.301. 20.402, and 20.403of this chapter.
(c) This general license does not au-thorize the manufacture, assembly, Wit-assembly, repair, or import of strontium90 in ice detection devices.
Scasamas31.100 Schedule AGenerally li-
censed quantities.The following quantities of byproduct
material are generally licensed pursuantto 31.4.
Byproduct material
Column ColumnNo. I No. II
Not as a Assealed sealedsource source
(micro-images) curies)
Antimony (8b 124)Arsenic 76 (Aa 76)Mingo 77 (As 77)Barium 140Lanthanum 140 (Ba-
TIA111140um) BsCad ( 100-87)ilner 109 (CdAg109)
CCIialecihrt11448(C(C1s4)46)
Cerium 144 Praseodymium(Corr 144)
CeedhlumBmium IV (Cella 187)_ _Corine 36 (Cl 36)Chromium 51 (Cr 51)Cobalt 60 (Co 60)Copper 64 (Cu 64)Europium 154 (Eu 154)Fluorine IA
alliu ( 72)Germanium m 71 (Ge 71)Gold 196 (An IN)Gold 109 (Au 199)Hydrogen 8 (Tritimn)(1( 3)ilnodidimum131114r 114)1311)
.1' Iridium 192 (Or 192)GO Iron 55 (Ft W)Z Iron 60 (Fe 59)..,. Lanthanum 140 (La 140)..'' ManManganeseganese
5652 ((Mn nM n.)
""_m Molybdenum 99 (Moo) 99)''' Nickel 69 (Ni 69)
Nickel 68 (NI 63)Niobium 95 (Nb 95)Palladium 109 (Pd 109)Palladium 101Rhodium 103 (Pd-phollistp1h0L3)
Polonium 210 (Po MO)Potandum 42 (H-42)Praseodymium 148 (Pr 141)Promethium 147 (Pm 147)Rhenium 116 (Re 196)Rhodium 165 (Rh 105)Rubidium 36 (Rb in)Ruthenium 106Rhodium 106
(RnRh 106)Samarium 153 (Sm 157)Scandium 46 (5c 46)Sliver 105 (Ag 1Silver 111 (ICI
HSodium ((Na 22Sodium 24 Na 24
-Strontium 119 (Sr 19)}Bresnan' 90Yttrium 90 (SrY)TBulfurantalum 132
15 (S 38)_1121
Technetium 96 c 96)Technetium 09 To 99Tellurium 127 1
Tellurium 129 (Ti 129Thallium 234 ( 204)Tin 113 (Sn 111)Tungsten 175 (W 115)Vanadium 42 (V 40
90)313.
Beta and/or Gamma emlttlillgiproduct material no:listed
1010 1010 10
1 1060 60
10 1010 10to to
1 101 101 10
to to1 10
to toI 10
ao to10 10co so10 to10 10
250 2501 10
10 1010 10es ao
I 1010 10
I 10to to10 10
1 101 10
10 1010 10
to to10 100.1 1
1010 1010 1010 1010 1010 10
1010 10
1 101 10
10 1010 1010 10
10
0.1 1
so so10 10
101 10
10 1010
so so10 1010 101 101 10
1010 10
1 10
C11088 RiTiltiNcil TABLIC
New section Old section31.1 New51.2 3021(b)31.3 3021(a) (1),30.7131.4 30.21(a) (2)31.5 30.21(e) (1)(6)31.6 30.21(c) (6)31.7 110.21(d)31.6 -, 30.21(s)31.9 30.21(1)31.100 30.72
46
August 17, 1 965
49
PROCEDURES AND REGULATIONS FOR THE CARE AND USE OFTHE OCD CD V-778 RADIATION TRAINING SOURCE SET*
A.1 Only those source handling and main-tenance techniques which are directly relatedto the specific handling of the Office of CivilDefense CD V-778 Radiation Training SourceSets will be discussed in this publication.These will include information on the equip-ment in the Sets; preparation and activityof the sealed sources; Atomic Energy Com-mission and Office of Civil Defense rules andregulations governing the receipt, use, storage,and transfer of the Sets; and instructions forthe replacement of rings and tags, and forleak testing the sealed sources. This publica-tion supersedes Procedures and Regulationsfor the Care and Use of OCD Training SourceSets, published October 1, 1961.
EQUIPMENT
A.2 The OCD CD V-778 Radiation Train-ing Source Set consists of the following items:
6 5.0 mc Cobalt 60 Sealed Sourcestotaling 30 mc (CD V-784)
Or
12 0.5-5.0 mc Cobalt 60 SealedSources totaling 30 mc (CD V-786)
1 Lead Container, small (CD V-791)1 Lead Container, medium (CD
V-792)2 Locks for Lead Container (CD
V-792)1 Long-Handled Tongs for Handling
Sources (CD V-788)8 Radiation Area Signs2 0-200 mr Dosimeters (CD V-138)1 Dosimeter Charger (CD V-750)1 Geiger Counter (CD V-700)
A.3 This Training Source Set has been de-signed specifically for use in training exercisesand is not intended as an accurate calibrationsource. You will note that two different train-ing source sets have been procured by OCDwhich differ only in the number and activityof the individual sealed sources. In this publi-cation, reference will be made to the CD V-784and CD V-786 to, distinguish between the twosets. ISSUANCE OF A PARTICULAR SETWILL BE AT THE DISCRETION OF OCD.
Available separately as TM-67-1.
PREPARATION OF THE SEALED SOURCES
A.4 Any radioactive material that is en-cased in, and is to be used in, a container in amanner intended to prevent leakage of theradioactive material, or any of its daughterproducts, is referred to as a sealed source. Thesources in the OCD Training Source Set are ofsuch a nature. The radioactive material isCobalt 60, which was prepared by the neutronirradiation of Cobalt 59 in a nuclear reactor.
4?
27Co5D -kont 27Co60
FRONTVIEW
DANGER RADIOACTIVEMATERIAL
DO NOT HANDLENOTIFY CIVIL
AUTHORITIES IF FOUND
An OCD Sealed Source
51
A.5 The Cobalt 60 decays with a 5.3-yeahalf-life by beta and gamma emission toNickel 60.
(5.3 -yrs.)22Co" _If3°(.32 Mev)+28Ni60
+2-y's(1.17 +1.33 Mev)A.6 The Cobalt 60 is gold or nickel plated
and is encapsulated in a standard Oak Ridgescrew-type capsule. The CD V-784 capsuleshave a nonmagnetic stainless steel base with amagnetic noncorrosive stainless-steel screw-typecap. The CD V-786 capsules are brass. As aminimum, the cap is sealed to the base of eachcapsule with silver solder having a. melting pointof 1,100° F or above. Each capsule has anapproximately .17i-tyh-square yellow warningtag attached to it.
ACTIVITY OF TRAINING SOURCE SETS
A.7 Each of the six CD V-784 sealed sourceswas 5 millicuries plus 20% or minus 10% on thedate of encapsulation. This date and activity--is marked on the tag attached to each source.As indicated in the following example, the tablebelow can be used to compute the total activity
of the set or the activity of an individual capsuleat any time after encapsulation.
Example:
What will be the activity of one of the 5millicurie sealed sources (CD V-784) and thetotal activity of the Set 19 months after thedate of encapsulation?
Source activity ondate of encapsula-tion =5 millicuries
Elapsed time =19 monthsDecay correction
factor from tablebelow =0.812
Source activity 19
months after en-capsulatiOn =0.812X5=4.06
=4.1 mc+20%-10%Total activity of the
CD V-784 Set =6 capsules X 4.1 me/capsule
=24.6 me + 20%10%
Table of Decay Correction Factors for Cobalt 60
Months 0 1 2 3 4 5 6 7 8 90 1. 000 0. 9891 0. 9783 0. 9676 0. 9571 0. 9467 0. 9363 0. 9262 0. 9160 0. 906110 . 8962 . 8864 . 8768 . 8673 . 8578 . 8484 . 8391 . 8300 . 8209 . 812020 . 8032 . 7944 . 7858 . 7772 . 7687 . 7603 . 7520 . 7439 . 7357 . 727730 . 7198 . 7120 . 7042 . 6965 . 6889 . 6814 . 6739 . 6666 . 6594 . 652140 . 6451 . 6380 . 6311 . 6242 . 6174 . 6107 6040 . 5974 . 5909 . 584450 . 5781 . 5718 . 5655 . 5594 . 5533 . 5473 . 5413 . 5354 . 5296 . 523860 5181 . 5124 . 5068 . 5013 . 4958 . 4905 . 4851 . 4798 . 4746 . 469470 . 4643 . 4592 .4540 . 4493 . 4444 . 4396 . 4347 . 4300 . 4253 . 420780 .4161 .4116 . 4071 , 4026 . 3982 . 3939 . 3896 . 3854 . 3812 . 3770
A.8 The CD V-786 sealed sources wereprocured in January 1956, and at that timeeach. Set was 30 millicuries ±25%. Presentactivity of a CD V-786 Set can be computedfrom the table above, as indicated in thefollowing example.
Example
What was the total activity of a CD V -7$6Training Source Set in January 1960?
Elapsed, time =48 months
52
48
Decay correction factor fromtable above =0.591
Activity in January 1960=30 mcX0.591 =17.7mc±25%
A.9 The individual sources in the CDV-786 Sets are not calibrated. However, theycan be calibrated using the CD V-138, 0-200m dosimeters. For the calibration range,select a point and lay out a circle with a radiusof 1 to 2 feet. This point should be in a largeopen area to minimize the contribution from
scattered radiation. Zero the two CD V-138dosimeters which are component parts of theSet, and several additional CD V -13S's if theyare available. Check all dosimeters for leakage.Locate the lead container with the sources atsuch a distance fromthe- calibration rangethat they will not affect the dosimeter readings.Place the dosimeters'in an upright position onthe .circle. Make certain the t nothing shieldsthe dosimeters from the source. Place onesource in position and expose the dosimetersfor as long as necessary to obtain at least a.50 mr exposure. The time will vary dependingon the size of the source. Compute the activityof the source as indicated in the followingexample. Remember to keep radiation ex-
posures of individuals to a minimum. All
calculations sliOuld be done before the sourcesare used in training, or after they have beenreturned to the storage area.
Example
Average reading of dosimeters placed at 1foot for 1.5 hours=96 mr
Dose rate ( mr/hr)Dosimeter reading (mr) 96 mr
Time (hr) l.o hr=64 mr/hr
Calibration formula
dose rate (inr/hr)---13.2XCo60 activity (inc)
distance' (ft)
64 mribs=__(13.2) (Co" t vi ty)
(1)2
Co" activity=(64) (1)
(13.2)
activity=4.9 me
A.10 Once a source is calibrated, it shouldbe marked to indicate its activity, and -thedate of calibration should be recorded': Agrease pencil or paint can be used to mark theactivity on the yellow warning tags attachedto the CD V-786 sources. Mark the sourcevery quickly to keep your exposure to a mini-mum. The activity of each source at a laterdate can be determined as outlined in para-graph A.7.
4'
PROCEDURES FOR INITIAL CHECK ONRECEIPT OF AN OCD TRAINING SOURCESET
A.11 The transportation of radioactive ma-terials moving in interstate commerce by rail,water, or by public. highway (except in U.S.mail), is regulated by the Interstate CommerceCommission, and some States extend the ICQregulations to intrastate transportation. Inaddition, local authorities may impose addi-tional limitations on the transportation ofradioactive materials, as in the case of theirmovement through tunnels or within portareas.. (See par. A.49 and A.50.)
A.12 The OCD Training Source Sets arenormally shipped to the licensed custodian bymotor freight or railway express, with theauxiliary equipment being packed separately'from the lead containers. The keys to theSets are sent to the licensee by registeredmail, return receipt requested. The step -by.:-step procedure listed below should be followedwhen a Training Source Set is received by alicensee from OCD or on permanent transferfrom another licensee. The licensee must weara CD V-138 dosimeter at all times when theTraining Source Set is being used, checked, orrepaired. Remember to keep radiation exposuresto a minimum.
a. Check to see that each of the lead con-tainers, CD V-791 and CD V-792, bears alabel including the following information:radioisotope, number of sealed sources, totalactivity of the sources, and the date ofencapsulation, or date of last calibration.
b. Count the number of sealed sources,and place them on disposable paper. TheCD V--784 Set should contain six sources.The CD V-786 Set should contain 12 sources.If the Set is issued directly from OCD, anydiscrepancy should be noted on Form DD1149-2, Requisition and Invoice/ShippingDocument (EAM). If the Set is perma-nently transferred from another licensee, thenew custodian should note any discrepancieson the letter of receipt furnished OCD.(See par. A.45.) In both cases, the custodianshould also advise the State of anydiscrepancy.
c. Leak test each sealed source in accord-ance with the instructions, beginning with
53
paragraph A.13. Record the results of theinitial leak test and keep them on file. Eachsealed source must be leak tested every 6months from the date of the initial test.
d. Replace rings or tags on any sealedsource which is not properly ringed ortagged, Replace rings and/or tags in accord-ance with the instructions beginning withparagraph A.21.
e. Return the sources to the lead con-tainers, and place the OCD Training SourceSet in the authorized storage area.
LEAK TESTING PROCEDURES FOR OCDTRAINING SOURCE SETS
A.13 Immediately upon receipt and there-after at intervals not to exceed every 6 months,each recipient of an OCD Training Source Set,in accordance with a condition on his byproductmaterial license, is responsible for performingthe following test for external leakage, and/orcontamination of individual sources. Recordsof leak tests must be maintained by thelicensee.
A.14 Remove the CD V-791 lead containerfrom the CD V;792 lead container. Moistena piece of paper which has a high wet strength,such as filter paper or a paper towel, and wipethe inside of the CD V-792 lead container.
A.15 Using a CD V-700 Geiger counter,with the shield open, the earphones attached,the range set to the most sensitive scale (X1),and the window as close as possible to, butnot in contact with, the filter paper or papertowel, thoroughly monitor the paper. Sincegamma radiation is of primary interest, thefilter paper can be measured while wet. Acareful check of the background radiationshould be made prior to monitoring the paper.Care should be taken that the monitoring isperformed at a-distance from the sealed sourceswhere they do not affect the CD V-700 naturalbackground readings during the monitoringoperation.
A.16 Any average reading of the CD V-700above normal background must be attributedto contamination. Do not be concerned withan apparent momentary slight increase in thecounting rate of the paper as the variation innormal background and meter deflections maycause this.
54
A.17 If the test reveals any removableradioactive material, the licensee must takeimmediate action to prevent the spread of con-tamination. The sources and the contaminatedfilter paper must be placed in the lead container,and the licensee must immediately notify theRadef officer in his OCD region. The entireSet must be kept secure and locked pendingdisposition instructions. In accordance withthe leak test condition on his license, thelicensee must also notify the AEC of the leakingcapsules within 30 days after the completionof the test.
A.18 If the CD V-792 shows no evidence ofradioactive contamination, remove one of thesealed sources from the CD V-791 container,using the 18-inch handling tongs (CD V-788).Using the tongs and/or pliers, so the licensee's
5 0
Leak Testing of Sealed Sources
hands will not come close to or In. contact withthe source, wrap and wipe each hidividualsource on a piece of -the high wet strengthpaper which has been moistened with water.Sufficient pressure to effect a thorough removalof any contamination should be applied. Aseparate paper should be used for each source.
A.19 Remove the sealed source from thepaper, and place it on disposable paper. Usingthe CD V-700, thoroughly monitor the paperto determine if the source is leaking or contam-inated. Any average reading of the CD V-700above normal background must be attributed toleakage and/or contamination. As the test foreach capsule is completed, place the capsule inthe CD V-792 lead container until all capsuleshave been tested. This will further reduceexposure doses.
A.20 Leak test each source and wipe testthe CD V-791 small lead container in the samemanner as the CD V-792. If the leak testresults are negative, return the sources to theCD V-791 small lead container, and place theSet in its normal storage location.
REPLACEMENT OF RINGS AND TAGS ONSEALED SOURCES
A.21 A second condition on byproductmaterial licenses issued to civil defense organiza-tions or personnel requires. the replacement ofthe one inch yellow warning tag and/or ringattached to each source, should they becomedetached through usage or accident. It is theresponsibility of the licensed custodian of theTraining Source Set to replace the rings andtags in accordance with the following instruc-tions. New tags and rings and new radiationarea signs may be obtained from
Defense General Supply CenterCivil Defense Supply DivisionRichmond, Va. 23212
A.22 The CD V-792 lead container housingthe CD V-784 sources is equipped with specialholes for the replacement of tags- and rings.See the following illustration.
A.23 The CD V-792 lead container housingthe CD V-786 sources does not provide similarholes. Therefore, the licensee must preparethem. Using an ordinary power drill, make a1-inch-deep ',3i;-inch hole in the top of the CDV-792. The hole should be placed about one-
5i,
RingReplacement
TagReplacement
Location of Tag and Ring Replacement Holes in theCD V-792
half inch from the inside rim. With a screw-driver, make a small slot on each side of the holeto accommodate the metal ring on the source.This hole is for the replacement of tags and willallow you to work on the ring in an uprightposition. (NoTE.-The slot should not be sodeep that it hinders the separation of the ringin replacing the tag.)
A.24 A second hole %-inch deep and 9i-inchin diameter should be drilled adjacent to the tagreplacement hole. This second hole will holdthe source in an upright position, yet willexpose the hole in the source which accom-modates the ring. The slots on the tag replace-ment hole will distinguish it from the ringreplacement hole.
A.25 Tags should be replaced in accordancewith the following step-by-step procedure:
a. Place the CD V-792 on a table strongenough to support it. In this position you-will be able to work on the sealed source andkeep your radiation exposure to a minimum:
b. Place the screwdriver, long-nosed pliers,and new tag on the table where they can beeasily and quickly reached when needed.
c. Place the untagged source in the properhole with the aid of the 18-inch handlingtongs. Make certain that the separationportion of the ring is at the top. Make noattempt to remove any portion of the old tagfrom the sealed source.
d. With the source and ring in position,insert the blade of the screwdriver into oneend of the separation portion of the ring.
c. Place the new tag on the ring with theaid of the long-nosed pliers.
55
Replacement of Tags
f. Remove the screwdriver and with thelong-nosed pliers carefully slide the tag alongthe separation portion until it is permanentlyattached to the ring.A.26 Rings should be replaced in accordance
with the following step-by-step procedure.a. Place the CD V-792 on a table strong
enough to support it.b. Place the screwdriver, long-nosed pliers,
tag, and ring on the table where they can beeasily and .quickly reached when they areneeded.
c. Place the 1 -inch yellow warning tag onthe new ring.
d. Using the 18 -inch handling tongs, placethe source without the ring into the properhole in the CD V-792.
56
e. Insert the blade of the screwdriver intoone end of the separation portion of the ring.
f. Insert the ring through the hole in thesource.
g. Remove the screwdriver and with thelong-nosed pliers 'carefully slick the ringthrough the hole until it is permanentlyattached to the source.A.27 The replacement of rings and tags
should be completed as quickly as possible tokeep radiation exposures to a minimum. Asmuch as possible, perform the operations atarm's length. Only the individuals whosenames appear on the byproduct materiallicense as individual users should replace eitherthe rings or tags on the sealed sources.
.1=1110111
Replacement of Rings
REGULATIONS GOVERNING THE USE ANDSTORAGE OF OCD TRAINING SOURCESETS
A.28 An Atomic Energy Commission By-product Material License requires the licenseeto be responsible to the AEC for the propercare, handling, and storage, of the OCD Train-ing Source Set in his custody as well as reportingto the AEC any loss, damage, or accidentresulting from violations of AEC standards.The acceptance of the license binds the licensee(not OCD) to the conditions set by the AECunder which. the Training Source Set is placedin his jurisdiction. These regulations areclearly outlined in Title 10, Chapter 1, Part 20,of the Code of Federal Regulations entitled,"Standards for Protection Against Radiation."
53
A copy of these regulations (10CFR-20) isissued to each licensee with his byproductmaterial license.
A.29 In addition to the AEC requirements,OCD requires each licensee possessing an OCDTraining Source Set loaned to him through theState civil defense office to comply with addi-tional regulations. This means the licensee isresponsible to the AEC for the proper care,use, and storage of the Training Source Set butis responsible to the State which, in turn, isresponsible to OCD for the property account-ability of the Set. Important'AEC regulationsand all OCD regulations are contained in theremaining paragraphs of this section. Thelicensee is referred to 10CFR-20 for theadditional AEC regulations.
57
A.30 StorageThe preferred location forthe storage of the Training Source Set is in alocked, unoccupied, and isolated area. Onlywork necessary to normal storage operationsshall be performed in the storage area. Onlyauthorized personnel shall be allowed to enterthestorage area and their duration of occupadcyshall be kept to a minimum. Determinationof the radiation levels in the immediate storagearea shall be made with a CD V-700 and thereadings recorded, dated, and filed. Normally,the Set shall be stored only at those locationsspecifically authorized on the license. Tem-porary storage is permitted at other locationswhen training activities make it impractical toreturn the Set to its normal storage site aftereach use.
A.31 Posting--Each area or room in whichan OCD Training Source Set is used or stored,regardless of whether it is the normal or atemporary storage area, will be considered arestricted area and shall be conspicuouslyposted with the radiation area signs issuedwith the Training Source Set. Restrictedarea means any area to which access is con-trolled by the licensee for purposes of protec-tion of individuals from exposure to radiationand radioactive materials. Restricted areashall not include any area used as residentialheadquarters, although a separate room orrooms in a residential building may be set apartas a restricted area.
The following information must be posted onall entrances to the storage area: (1) radio-isotopes stored, (2) number of Sets and numberof sources per Set, (3), total activity and date ofcalibration, and (4) whom to call in case of anemergency. In addition, the standard radia-tion area signs which are included with theOCD Training Source Set will be posted in con-spicuous places in areas where the Source Setis used or stored. Signs will be sufficient innumber and placed so as to be clearly visiblefrom any approach to the area.
A.32 Caution SignsStandard radiationarea signs shall include the conventional three-bladed symbol and the words, 'Caution (orDanger) Radiation Area," printed in magentaor La yellow-background. The signs included
58
with the Training Source Sets meet theserequirements.
A.33 Uses-7-The licensee shall use the Traid-ing Source Set for only those activities specifi-cally authorized under item 9 of his byproductmaterial license. An authorized use whichreads: "To be used in training of instrumentoperators, and for instrument calibration pur-poses" does NOT sllow the licensee to use theTraining Source Set for the training of radio-logical defense instructors.
A.34 SupervisioniThe OCD Cobalt 60Sealed Source Set may only be used for the pur-poses stated in the AEC Byproduct MaterialLicense. It must be used by, or under thesupervision and in the physical presence of, oneof the individual users designated in the license.
A.35 Instruction of PersonnelBefore enter-ing a restricted area, all individuals shall beinformed of the presence of radioactive ma-terials and shall be instructed in the hazards ofexcessive exposure to such materials and inprecautions or procedures to minimize exposure.
A.36 Exposure of IndividualsUnder no cir-cumstances shall the licensee use the TrainingSource Set in such a manner as to cause anyindividual in a restricted area to receive in anyperiod of 7 consecutive days from radioactivematerial and other sources of radiation in thelicensee's possession, a whole body gamma dosein excess of 100 mr, or a whole body gamma dosein excess of 5 r in any one year. No licenseeshall use the Training Source Set in trainingexercises or classes involving individuals under18 years of age.
A.37 Personnel Monitoring EquipmentEach licensee shall issue a CD V-138 dosimeteror an equivalent dose recording instrument toeach individual entering a restricted area.
A.38 RecordsEach licensee shall maintainrecords showing the radiation exposure of allindividuals exposed to radiation from radio-active materials in his possession. Theserecords shall show the name, age, date of birth,Social Security number, method of determiningthe close (i.e., film badge, CD V-138 dosimeter,etc.) and the total weekly whole body gammaradiation dose of each individual. Summariesof the total whole body gamma dose .for eachcalendar quarter, or 3-month period, and thetotal yearly whole body gamma close shall be
maintained for each individual who has anexposure history which extends for a time periodof 2 weeks or 14 consecutive clays or more.When the exposure history of an individualexceeds 1 year, totals of the yearly accumulatedwhole body gamma dose,and calculations of thepermissible accumulated gamma close shall alsobe maintained. The permissible accumulateddose to gamma radiation can he obtained fromthe formula,
PAD = 5 (N -18)
where PAD is the permissible accumulatedgamma, close in roentgens (r) and N is the age ofthe individual being considered in years and isgreater than 18. These radiation exposure rec-ords of each individual must be preserved bythe licensee until December 31, 1965, or until 5years after the date of the last exposure of theindividual to radioactive material in the custodyof the licensee. Each licensee shall. maintainrecords showing the results of surveys asrequired by paragraph A.30. Each licenseeshall keep records showing the use, receipt,and transfer of an OCD. Training Source Set.It is suggested that the licensee maintain alog of the activities involving the Set issued tohim.
A.39 InspectionEach licensee shall affordto the AEC and to OCD at all reasonable timesopportunity to inspect the Training SourceSet, the premises, and the facilities where theSet is used or stored, and shall make availablefor inspection, upon reasonable notice, required_records kept by him.
A.40 Inspection of Source CapsulesWhenthe sources are retismpfl to their lead containersafter being removed for any purpose, eachsource must be monitored with a CD V-700to insure that the Co" source 'material is con-tained inside each capsule. This monitoringshould be performed at a distance from theother sources where the gamma radiation levelsare not significantly above natural back-ground. Each source capsule must be in-spected each time the source set,is used.
A.41 Loss or Theft of Sealed .SourcesThelicensee is required to report Promptly to theAEC any loss or theft of radioactive material insuch quantities and under such circumstancesthat it appears to ',he licensee that a substantial
hazard may result to persons in unrestrictedareas. However, the licensee is requested tonotify the OCD Regional Radiological DefenseOfficer immediately in the event of a suspectedloss or theft of a sealed source or.sourees,nof anaccident resulting from a leaking source. Thiswill enable the Radiological Defense Officer toassist the licensee in determining whether or nota loss has occurred, in determining the serious-ness of an accident, and in .notification of theAEC, if required.
A.42 Loss of Cow Source Material from theCapsuleIn the event that an empty sourcecapsule is discovered during the inspection,required by paragraph A,40, the remainingsource capsules should be secured in the leadcontainers. After monitoring personnel in thearea for possible contamination and wipe testingthe outside of the CD V-792 to insure that it isnot contaminated, move the sources in the leadcontainers out of the general area wherethey were in use. Using a CD V-700, mon-itor the entire area until the Cow is locatedwithin a small area (less than 1 square foot).If the Cow material, which is a small needle, canbe seen with the naked eye, it should be pickedup and placed in the lead container along withthe other sources and the empty source capsule,using the CD V-788 handling tongs or a pair oflong-handled forceps or pliers. The Cow mate-rial should not be picked up with the fingers underany circumstances, nor should any attempt bemade to return the Cot.'" needle to the empty sourcecapsule. If the Uouu material is on an earth,sand, or gravel surface, it can be carefullyscooped up with a shovel and placed along withthe earth, etc., in the large CD V-792 container.No attempt should be made to separate the Cowneedle from the extraneous material. Once theCow material is inside the lead containers, theyshould be marked, sealed, and the sourcestreated as if they were leaking, as described inparagraph A.17.
A.43 After completing the operations de-scribed in paragraph A.42, the general area andndthe personnel and equipment used to pick upthe Co'r material should again be monitored toinsure that they are free of radioactive contam-ination. Until the Cow material iN round, thegeneral area should be restricted to all personnelexcept those involved in the monitoring opera-
59
tions. If monitoring of the area fails to indicatethe presence of contamination after the Co"material has been located and removed, thearea may be returned to unrestricted status ifnecessary. However, it is suggested that thearea be monitored by someone qualified in thefield of health physics, at the request of thelicensee, prior to returning it to unrestricted use.The licensee must report the incident to theOCD Regional Radiological Defense Officer assoon as possible to request disposition and re-placement of the Source Set. In accordancewith the conditions of his license, the licenseemust also report the incident to the AECwithin 30 days.
A.44 If the Co" source material cannot belocated, or the presence of radioactive contam-ination is detected as a result of the incident,the OCD Regional Radiological Defense Officernm/ be contacted immediately for assistance.
A.45 Transfer Temporary loan of OCDTraining Sonrce Sets to-other licensees withinthe United States authorized to receive suchmaterial is allowed. However, if a licensee pos-sessing an OCD Training Source Set antici-pates moving from his present location to an-other, and, if the new location will prohibithim from exercising the required control andsupervision of the Source Set, he must reportthis intention as soon as possible to the Statecivil defense office. The State office may per-manently transfer the Set to another licenseewith the approval of OCD or return the Set toOCD. if it is transferred to another licensee,the new custodian must furnish to the Statecivil defense office for transmittal to OCD: (1)a copy of his byproduct material license, and(2) a letter indicating receipt of the TrainingSource Set and acceptance of responsibility forit. If the Set is to be returned to OCD, theState must notify the OCD regional office andaction will be initiated for the return of the Setdirectly from the custodian.
60
5 b
A.46 Renewal of Byproduct Material Li-censesA Training Source Set custodian mustmake application for renewal of his license 60days prior to its expiration or he must notifyOCD, through the State civil defense office, ofhis intentions not to initiate license renewal andrequest disposition instructions for the Set.
A.47 ViolationsThe. licensee is responsibleto the AEC for the proper use and storage ofthe Training Source Set and for compliancewith 10-CFR-20, Standards for ProtectionAgainst Radiation, or 10-CFR-30, Licensing ofByproduct Material.
A.48 Return of Sets-All OCD TrainingSource Sets loaned to the States shall be returnedto OCD when the licensee and the State desireto be relieved of the responsibility for the Sets.Arrangements, for the disposition of the SourceSets should be made with the OCD RegionalOffice through the State civil defense office.
A.49 Transport of Training Source SetsThe OCD Training Source Sets may be trans-ported to the training site in a vehicle, pro-vided the source set is padlocked, the vehicle islocked, and the vehicle is posted on both sidesand the rear with radiation signs with thestatement "DangerousRadioactive Material"in 3-inch letters on a contrasting background.'Phis type of sign may be obtained from somelocal trucker's associations. The automobileshould be monitored to determine radiationlevels within it, and the occupants should wearCD V-138 dosimeters to measure their exposureduring transport of the Set.
A.50 State and City RegulationsIn addi-tion to AEC and OCD regulations, many Statesand cities have additional requirements whichgovern the use, storage, and particularly thetransportation of radioactive materials. It isthe licensee's responsibility to contact theappropriate State and city departments forinformation on such regulations.
AEC LICENSING OF OCD SOURCE SETS FOR RADIOLOGICALMONITOR TRAINING
The Division of Materials Licensing of theAtomic Energy Commission has the responsi-bility for the licensing of byproduct material(radioisotopes). This means, therefore, that theAEC has the responsibility and authority tolicense the possession and use of any radio-isotope which is produced in a nuclear reactor.The Cobalt 60 used in the sealed sources in theOCD Training Source Sets is a byproductmaterial and, therefore, is subject to AECregulations. The conduct of a RadiologicalMonitoring Course requires that the instructordo licensed to possess and use the OCD Cobalt60 Sealed Source Set (CD V-784).* Thislicensing authority has been delegated toseveral of the States, but their regulationshave to be consistent with the USAEC regula-tions. For further details, see Title 10AtomicEnergy, Code of Federal Regulations, Part 150,"Exemptions and Continued Regulatory Au--thority in Agreement States Under Section274."
In order to implement this licensing au-thority, the AEC has issued a specific regulationwhich sets forth the basic criteria for issuanceof byproduct material licenses (Form AEC 374).This regulation is Title 10Atomic Energy,Code of Federal Regulations, Part 30, "Rulesof General Applicabill y to Licensing of By-.product Material" (10 3FR 30). The USAECrules and regulations for the safe use of radio-active material are contained in Title 10Atomic Energy, Code of Federal Regulations,Part 20, "Standards for Protection AgainstRadiation" (10 CFR 20). This regulationestablishes standards under which all licensedradioactive materials must be used. One ofthe first provisions in 10 CFR 30 is a statementof who must have a license for possession anduse of byproduct material. The regulation statesthat no person in the United States shall
'The C D V-784 is a set of six sealed capsules, each containing nominally5 me of Cobalt 60. The CD V-784, and associated containers, handlingand monitoring equipment comprises the CD V-778 Training Source Set.
307-892 0 - 65 - 5
acquire, possess, use or transfer byproductmaterial except as authorized by a licenseissued by the AEC.
The possession and use of any OCD ModelCD V-784 Cobalt 60 Source Set requires aspecific license. Specific licenses are those forwhich an application must be submitted to theAEC. The minimum requirements for approvalof an application and issue of a license are thatthe applicant has (1) proposed a use authorizedby the Atomic Energy Act of 1954; (2) equip-ment and facilities adequate to protect healthand 'minimize danger to life or property; and(3) personnel qualified by training and experi-ence to use the material for the proposed usein such a manner as to protect health and mini-mized danger to life or property. These are broadrequirements and not specific for any particulartype of program. Each application for a specificlicense must, therefore, contain complete anddetailed information describing the applicant'squalifications and proposed procedures.
A problem that has been frequently encoun-tered in the licensing program is the determina-tion of who is responsible for the UCD TrainingSource Sei, and who should be the applicantand, subsequently, the licensee. The licenseeby definition must be a legally responsible"person." A "person" is defined in 10 CFR 30as an individual, corporation, partnership, firm,association, trust, estate, public or privateinstitution, group, government agency otherthan the AEC, any State or any politicalsubdivision thereof, or any political entitywithin a State. Therefore, when a legally con-stituted sponsoring organization exists, whethera. governmental agency at the State, cuz:lity,city, or Federal level or a corporate organiza-tion, n.nd the individual who will actually usethe Source Set acts as an agent of the sponsoringorganization, then the organization must bethe licensee. The Office of Civil Defense haslegal authority under section 201(h) of PublicLaw 920, gtst Congress, as amended, to dis-
61
tribute the Cobalt 60 Training Source Sets byloan for civil defense purposes only to theStates. Therefore, training source sets havebeen loaned to State Civil Defense organiza-tions, who in turn have made them availableto localities in support of their civil defenseprograms:
in past years many AEC licenses have beenissued to individuals who have satisfactorilycompleted the Radiological Monitoring for In-structors course. There have been numerousapplications for individual licenses where theindividual would more appropriately have beennamed as a "user" under a State or localCivil Defense organization license. OCD andthe AEC have completed a review of the li-censing of OCD Cobalt 60 Sealed Source Setsfor the training of radiological monitors. Sincethe applicant, and subsequently, the licenseeis legally responsible for the safe use and pos-session of the OCD Training Source Set, it isinappropriate that an individual be the licensee.It is most appropriate that each State CivilDefense agency have one license for the useof all training source sets for all radiologicalmonitor training within the State.
Effective immediately, it is the joint policyof OCD and AEC not to issue or renew a by-product material license to an individual formonitor training in a State subsequent to issu-ance of a license to the State Civil Defenseagency for the use, possession, and storage ofall OCD Cobalt 60 Sealed Source Sets.
Each person who will use the OCD sealedsources for radiological monitor training musthave an understanding of the basic principlesof nuclear radiation and radiation safety. Sec-tion 30.33(a)(3), Title 10 CFR, Part 30, re-quires only that an applicant be qualified bytraining and experience to use the byproductmaterial for the purpose requested in such amanner as to protect health and minimizedanger to life and property. A person who (1)has satisfactorily completed an OCD Radio-logical Monitoring for Instructors course givenby An authorized organization and instructorand (2) has a general background which wouldpermit him to comprehend the subject matterpresented in such a course, cr,ii e rally beauthorized as a user on an agency's specificlicense to use an OCD source set to train moni-tors. It is impossible to define the exact natureof the background which someone must have
62
because definite requirements would probablyrestrict and hamper the radiological monitortraining program. As a general guideline, aperson should have a scientific/technical back-ground that would enable him to understandthe basic principles of radiation to the extentthat he may be in a position to impart necessarytechnical information to others.
When adequate selection criteria have beenestablished by an applicant such as the StateCivil Defense agency and sufficient sourcehandling procedures have been developed andpublished, the AEC will issue a specific licenseto the State organization that will allow it toauthorize any individual that meets the'statedminimum formal training and experience cri-teria to use a training source set for the trainingof monitors. Individuals by name need not belisted on the license (or application). In thoseStates where this type of procedure is in effect,some type of "user permit" is normally issuedto each individual that has a need to use,possess or store a source set.
Since the civil defense training program in-volves both the training of monitors andmonitor instructors, OCD and the AEC differ-entiate between the minimal required formaltraining and experience for persons who willtrain only monitors and that required forpersons who will train monitor instructors.Persons who will train instructors must have abroad background in the radiation field. Sucha person must have a knowledge of radiationbeyond the scope of the principles presented inthe OCD Radiological Monitoring for Instruc-tors course. Additional information regardingthe minimal required formal training and ex-perience for persons who will train- monitorinstructors is contained in OCD memorandumdated September 14, 1964, Subject: "Guidelinesfor Byproduct Material Licensing in Connectionwith the Conduct of the Radiological Moni-toring for Instructors Course." The training ofmonitor instructors is conducted primarily atselected universities.
Each R\II instructor is familiar with thedetails of the licensing program for monitortraining in his State. Additional specific infor-mation about the current details of the licensingprogram for training monitors in each State isto be obtained from the State Civil Defenseoffice. Before a local Civil Defense organization
r 00
applies for a license, the State Civil Defenseoffice should be contacted to see if they do notalready have a license under which the pro-spective applicant is covered for any necessaryuse of an OCD Training Source Set. About one
DIST:OCD Regions, Staff College.
5
half of the States presently have in effect aState license and issue a user permit to qualifiedindividuals. The remainder of the, States areexpected to have a State license in effect beforethe end of September, 1968.
63
Quiz Fallout Forecasting
ANSWER SHEET
COURSE: Radiological Monitoring for Intructors
.Flint
N
!Detroit
0 80 160 240 320
Scale 1" = 80 miles
400
DATE SCORE
U()
NAME AND STUDENT NUMBER
65/00
QuizUse of Radiological Instruments
ANSWER SHEET
COURSE: Radiological Monitoring for Instructors
PART IA.
Answer
B.
Answer
PART IIA
B
C.
D
PART
2
3.
4.
DATE SCORE NAME AND STUDENT NUMBER
67%
61
QuizDose and Dose Rate Calculations
ANSWER SHEET
COURSE: Radiological Monitoring for Instructors
Problem 1
RI =
Rt =
D/R1 =
T, =
To
Problem 2
R1 =
Rt
=
rre =
DATE SCORE NAME AND STUDENT NUMBER
6/70
62
Quiz -Source Handling Techniques
ANSWER SHEET
COURSE: Radiological Monitoring for Instructors
T F T F T F
1. ( ) ( ) 17. ( ) ( ) 33. ( ) ( )
2. ) ) 18. ( ) ( ) 34. ( ) ( )
3. ( ) ( ) 19. ( ) ( ) 35. ( ) ( )
4. ( ) ( ) 20. ( ) ( ) 36. ( ) ( )
5. ( ) ( ) 21. ( ) ( ) 37. ( ) ( )
6. ( ) ( ) 22. ( ) ( ) 38. ( ) ( )
7. ( ) ( ) :23. ( ) ( ) 39. ( ) ( )
8. ( ) ( ) 24. ( ) ( ) 40. ( ) ( )
9. ( ) ( ) 25. ( ) ( ) 41. ( ) ( )
10. ) ( ) 26. ( ) ( ) 42. ( ( )
11. ) ( ) 27. ( ) ( ) 43. ( ) ( )
12. ) ( ) 28. ( ) ( ) 44. ( ) ( )
45. ( ) ( )
13. ) ( ) 29. ( ) ( ) 46. ( ) ( )
14. ) ( ) 30. ( ) ( ) 47. ( ) ( )
15. ) ( ) 31. ( ) ( ) 48. ( ) ( )
16. ) ( ) 32. ( ) ( ) 49. ( ) ( )
50. ( ) ( )
DATE SCORE NAME AND STUDENT NUMBER
63
RMI COURSE EXAMINATION ANSWER SHEET
1.
2.
3,
4,
a
(
(
(
(
)
)
)
)
b
(
(
(
(
)
)
)
)
c
(
(
(
(
)
)
)
)
d
(
(
(
(
)
)
)
)
26-
27.
28.
29.
(
(
(
(
a b
) (
) (
) (
) (
)
)
)
)
c
(
(
(
(
)
)
)
)
d
(
(
(
(
)
)
)
)
51-
52-
53.
54.
a
(
(
(
(
)
)
)
)
b
(
(
(
(
)
)
)
)
c
( )
( )
( )
( )
d
( )
( )
( )
( )
5. ( ) ( ) ( ) ( ) 30. ( ) ( ) ( ) ( ) 55- ( ) ( ) ( ) ( )
6. ( ) ( ) ( ) ( ) 31. ( ) ( ) ( ) ( ) 56. ( ) ( ) ( ) ( )
7. ( ) ( ) ( ) ( ) 32- ( ) ( ) ( ) ( ) 57. ( ) ( ) ( ) ( )
8. ( ) ( ) ( ) ( ) 33. ( ) ( ) ( ) ( ) 58- ( ) ( ) ( ) ( )
9. ( ) ( ) ( ) ( ) 34. ( ) ( ) ( ) ( ) 59. ( ) ( ) ( ) ( )
10. ( ) ( ) ( ) ( )* 35, ( ) ( ) ( ) ( ) 60. ( ) ( ) ( <) ( )
11. ( ) ( ) ( ) ( ) 36- ( ) ( ) ( ) ( ) 61- ( ) ( ) ( ) ( )
12. ( ) ( ) ( ) ( ) 37. ( ) ( ) ( ) ( ) 62- ( ) ( ) ( ) ( )
13. ( ) ( ) ( ) ( ) 38. ( ) ( ) ( ) ( ) 63- ( ) ( ) ( ) ( )
14. ( ) ( ) ( ) ( ) 39- ( ) ( ) ( ) ( ) 64- ( ) ( ) ( ) ( )
15. ( ) ( ) ( ) ( ) 40. ( ) ( ) ( ) ( ) 65. ( ) ( ) ( ) ( )
16. ( ) ( ) ( ) ( ) 41. ( ) ( ) ( ) ( ) 66. ( ) ( ) ( ) ( )
17. ( ) ( ) ( ) ( ) 42. ( ) ( ) ( ) ( ) 67. ( ) ( ) ( ) ( )
18. ( ) ( ) ( ) ( ) 43. ( ) ( ) ( ) ( ) 68. ( ) ( ) ( ) ( )
19. ( ) ( ) ( ) ( ) 44. ( ) ( ) ( ) ( ) 69- ( ) ( ) ( ) ( )
20. ( ) ( ) ( ) ( ) 45- ( ) ( ) ( ) ( ) 70- ( ) ( ) ( ) ( )
21. ( ) ( ) ( ) ( ) 46- ( ) ( ) ( ) ( ) 71- ( ) ( ) ( ) ( )
22., ( ) ( ) ( ) ( ) 47. ( ) ( ) ( ) ( ) 72- ( ) ( ) ( ) ( )
23. ( ) ( ) ( ) ( ) 48. ( ) ( ) ( ) ( ) 73. ( ) ( ) ( ) ( )
24. ( ) ( ) ( ) ( ) 49. ( ) ( ( ) ( ) 74- ( ) ( ) ( ) ( )
25. ( ) ( ) ( ) ( ) 50. ( ) ( ) ( ) ( ) 75. ( ) ( ) ( ) ( )
QUIZ SCORES COURSE EXAM SCORE FINAL SCORE
DATE NAME AND STUDENT NUMBER
6 4
U, S, GOVERNMENT PRINTING OFFICE 1968 0 - 307-892
73
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