ML20204G566
| ML20204G566 | |
| Person / Time | |
|---|---|
| Site: | 07000262 |
| Issue date: | 10/15/1987 |
| From: | Johnson H OKLAHOMA STATE UNIV., STILLWATER, OK |
| To: | |
| Shared Package | |
| ML20204G538 | List: |
| References | |
| 461711, NUDOCS 8810240154 | |
| Download: ML20204G566 (14) | |
Text
'
< PQav 313 W & kVCLE As 80W4' Yoav Coenadassioes
)
APraov80 0V Case t8 C 8 O M. 33,33. 34, 8164 4130 n ~ **
APPLICATION FOR MATERIAL LICENSE 6.
sur INST _UCTIONS: 588 TML APPAOPmIAf t LtCEN$4 APPUCATION GviDE FOR DETAILLO IN$TRUCTIONS FOR COMPLtTING APPUCATION. SEND TWO COPit$
08 TML ENTimt COUPLETf D APPUCATION TO THE NRC OphCE $PECIFit0 StLOW ptOgaAL Astiscits p Ls APPuCAttoaus entse is you Aas LoCatto tes tLussort empiania, sona wiCt.i4 Ale, wits %Ilota,letSGoyal.oM40,04 U S NUCLla.n alSutatoav Cowwits@s e
Di'titio% 0 9484 CYCLI A%Q waYgnial Saf ttv, hw$$
at9Coassias,4040 APPUCattosul To tha$wi4GTQsg, pg pqqgg U S ervCLlaa atov,tatoav Coww;ss@%, at3sO4 tit wattaia6s uCg%s %g gictione (LL OtMIe Psalokt Pitt APPUCatto%$ A4 00tLowl.ip v09 Ang LoCat t o I4 199 a ooll u t ti *0 AD C48% SMv4.4 4Ge37 Co%%ICTICVT DELAe Amt. DistasCT os COLuwg,a espwg aA Aay(AhD AaaahiSAS Co,toaao0,10Awo, maar$As Lovessaka. esoa takA.htsnassa, u
wass ACMV$ttfl ht A M&w#$Nial htW Jt a84 7 htw Vong, Pt%%8vgy&pria.
aoen we nic.o. e oates D Aa0T A. oa Lamoeda, toVTm 0Aa0f A.Ts aAS, WT AM, aMUO4 setANO,04 vanwo%f. 6E*@ APPUCATIONS 70 On avotate 0,84's0 APPUCAf toest 10 U S WVCLlan a80vtatom? Con. egg @%, a43*oN I hvCLgan asatgaiak StCtio's 9 U S hvCttaa 40VLatear CowedissiO4 agSl0% IV tal Paan at 84vt nsat t a tal a ADiatsoen Pactact@as stCT@%
ai40OpPa stia,P4 16 30 til a* A's PLa#4 Daivt 6satt 1000 w
anu%otoes, Ya 90011 PLatawa, ptomepa escaela att?UCa v Wit &48i.*t.aeonta Camouesa.
Pwe nto aiCO. lowin canopeia tensit&64 8, viagimia, via0ies iska408. 0R ALassa. Amito44. CALIPoswia. Manata. htv&D A, Ontoose.n&Swi40 tom att? via018ela. Stie0 APPucatiO46 70 4%0 y a f t smit 04sts A40 Potetessomt 14 Twg Pacific,4the ar*LICatso%$
70 y g hvCLEan at3ytatomy Cowed SB'o% 0 83'C4 65 ada tt asal n acia tiOnePactgCtio%ggCTQ *e y 3 hvC6 3an aeovLaton, consterss@N. at0@% v get waaitTia Statt?,Svitt 3900 w ATImid.L 40:4?6o4 peoTECYion 44C710%
e
&TLa%f a,04 M333 tage WaalA L ANI Sv878 310 wapewt Calga.CA 94084 l
e l
Pt Sott Loc.atIO i,t agal.It.tti St att$ St=0 APPUCattohe 70 twe.U.C, kvCLE Aa a40VLatoav Coesuisspos chty is i:=4 y ntSM to Poestte an.0 vet UClausto Mattal AL t
s u rain.v aci 0 w s vCuan atov6 10av C0w iniom mai.
o*
j i
. m i. *, a nuCu o. ea,C
. aa.,,,...i,
i haw s A%. w alv.so aoc at u e, *,,ucae r.
..a, C,
l Oklahoma State University
. u.uu%u c/o Assistant Vice President for Research 1
. Awt%out *,,0 vCiut.,vou s SNM-241 Oklahoma State University I
7" c nu. L o. vCtsn n=
Stillwater. OK 74078 l
~
8 ADQatta,tt. e= tat UCt%8tD waf tatak Win tt bl40 ca Po64ttstD l
Oklahoma State University Campus 8810240154 880601 l
Stillwater, OK 74078 REQ 4 LIC70 SNM-0241 PNV l
. uuto.. ai m o u Cocacnaa.ut w ia..uCar.o%
gua.ou wn.
Dr. H. M. Johnson 405/624-5716
.wir inwe i t.now. n Co... w.a.ia v.i t,.4 a% no.8 c. ieonwatio~ $0 n emovieso is enca ei0 4 t 6 uu%n anuCario% uset l
3 R D cactiv e.W.at t a iak....l h-.. ~1..-.- i
.8-~
~
e Pva.3ee a
.-,e A_.Ct%no vanni 6.,u n vuo i si eo
~ ~ -. -. - ~ ~
ee attac men ttac ment
,,%oiv,omavi, an.ou...ea mao..tio% :4.ltv.aocaaw a%o t-sia
. ta.,l.%s.o. ihoav ohats.oamma i= e= enwiu+0 ama CnD Anas t a +% a a c on a "
See attachment ee attac ment
. aciuties. o lov..wto i maoiatio.i antv Panoaa.
See attachment see attachment
\\
a vu%nt nn,s ua con oom s.<>
aws n C-Ast e wa%.o'"'"
n/a
.u Causeaf n/a l'"CYEl80s n/a 13 C t a t i..Ca.t ca.e.%Ci%4 s 0% Tot a.e s.me
., a.a,% t.t a..uca%t wg;t ast angs t =at au et at twe %ts %D me.a t 64%f at so%8 wact 1% Y a 8 a* uC41@% an t
< es..
uca%f t=3.a*.ucaint a%.c ag e 0. sic a6 g e g Cvvisit to.8.Ct at,.eCaf C% 0% SI=a.k.8 0. Tal a..uCa%t s aweg i% ritu 3 Clati.T Tuat twg a ucatiog is e
P.a,g aa g n on CO%a % D C on a n,..Y
- wi?.=n?,Te.,i D.s a 4 %:.6 t al.6 s t.a wga.' C%8 att ac 33 33 34. 34. 4%3 as a%@ t=47 abb 5s.DawaT.0am $0sita.eit D ata g t%.
caw 64 COCs c tCtaa e
a.
..t t i.
i t* a n gi% g tQ at v C4.is y 3 C stCt@410cs ac.t C. w%t 71 stes 53 stat tag wasIt it a Ca wigak C. 8.%s0 70 want a men.buv sal 58 Stattut%t 04 at.atstgtAvigg aatwigt on AGl%Cv o Tag w% tag $taf gg ag tg 4%, wattia mites is its Am 5.Ctiog i
l p,.t _ %,8
.w.
w t.u n, s... u..ic t.
,,,a
,a n e
pfp M $.
p Howard M. Johnson Licensing Representative 10-15-87
.m
.. m..
. %. v. 8.a C. I w..;. u.m.
. m, w.C.
s.. m ~,0.a%,.C,a,i,. Caw., m. ~,...._
.m.-,.
.e %. 8.
.a. C w.aC,T e. e.s.a a,i%. v$a.C.ai m,,~At o...on a%. o..ai
<,.,,a
,,,,.,,w w
-.%aCato...., _.,.. a.
tC..,-
C mo
.a a
n,,a.,,,a
,,,w.,,,
~
.,,,a
. %. na :. na t.6pa-tw
> t t ew
'i'
'*O poahaCUSEOniLY n,8 C.. i t
. n 40.
.n C.uxa.
wwul e.
a ~,to.,
[w
&( V !g &/k
'X g,, __
V 1
awx u aln et.
C nt%
.la eut l') c. itM4 )
NN
,a, aC v a C,,,4, wI e.,,.4 a 4,. a n g,p
g 5.
Radioactive Materials Element and Chemical and/or Manufacturer Maximum Activity Mass Number Physical Form
& Model No.
Per Source Which Will be Possessed at any one Time.
Plutonium-239 Plutonium:
Monsanto Research 1 sealed source of Beryllium Corporation 16 grams.
Serial # M-424 Plutonium-239 Plutonium:
Monsanto Research 1 sealed source of Beryliium Corporation 46.6 grams.
I Serial f M.107 Plutonium-238 Plutonium:
Monsanto Research Total not to exceed Beryllium Corporation 150 milligrams.
]
Serial # AJC-N-W.
PuBBe 1
4 a
6.
Use of Licensed Material i
Material will be used for "research and development" es defined in the 1
Code of Federal Regulations. Title 10. Section 30.4(q). Sesled sources l
will be used in instruments and gauges and for instrument calibration.
- 1
]
7.
Individuals Responsible for Radiation Safety Program j
a.
The President of the Oklahoma State University has appointed a Radiological Safety Comittee with the responsibility for advising appropriate administrators on the use of radiation devices and/or radioisotopes to the end that no hazard to the health or safety or the research work of others occurs. The organization, purpose, and J
function of this committee are spelled out in detail in the 1
attached "HANDBOOK of Responsibilities Procedures, and Regulations i
Governing the Safe Use of Ionizing Radidtions on the Campus of Oklahoma State University (March 1987) pp. 2 4."
For simplicity in future reference, this document will hereafter be simply referred j
to as the HANDBOOK.
b.
The below named individuals are now serving as member of the i
Radiological Safety Committee:
4.
Dr. R. J. Bahr D.V.M.
Dr. Eddie Basler Dr. Donald L. Cooper, M.D.
Dr. E.M. Hodnett, Emeritus l
Dr. H.M. Johnson, Radiological Safety Officer
]
Dr. W.A. Sibley, Chairman 1
}
~
\\
2 A Vita of each of the above members, giving his background and training as it applies to the handling of radiations and radioisotopes, is attached.
c.
Dr. H.M. Johnson was appointed Radiological Safety Of ficer (R.S.0.)
in 1986 and the duties of Radioisotope Procurement Agent (R.P.A.).
As R.S.O., he is responsible for monitoring adherence to the regulations of the committee which fall within the framework of NRC regulations and additional appropriate guidelines. As R.P.A., he is responsible for insuring that the procurement of radioisotopes complies with the University License and such other regulations as have been set up by the Comittee. A more complete statement of his responsibilities, authority, and operations is provided in the attached HANDBOOK, Sections I and II, pp. 4-10.
Dr. Johnson's Vita is presented below, along with appropriate references to his responsibilities and duties.
d.
Radiological Safety Committee members have already been listed above.
Their Technical Vitas are included at this point.
TECHNICAL VITA 0F DR. R.J. BAHR, ASSOCIATE PROFESSOR OF VETERINARY MEDICINE AND SURGERY (RADIOLOGIST)
Academic Training D.V.M., Oklahoma State University,1970 B.S. Oklahoma State University, 1968 Specialty Radiology i
Experience and Training i
1970 - 19,1 Private Practice St. Petersburg, Florida 1971 - 1973 U. S. Air Force - Assistant Base Veterinarian, Sheppard A.F.B.
(7 months)
C.C.K. Air Force Base Taiwan Republic of China, Base Veterinarian (17 months) 1973 - D74 Radiology Internship Kansas State University 1974 - 1976 Radiology Re=,idency Department of Radiological Sciences University of California - Davis 1975 - 1976 Clinical Radiologist, Radiobiology Laboratory University of California Davis 1976 - 1980 Assistant Professor of Veterinary Radiology, University of Missouri - Columbia
3 i
l 1980 - 1982 Staff Radiologist, Grand Avenue Pet Hospital l
(private practice) Santa Ana, CA r
1982 - 1984 Independent private practice as a Veterinary.
l Radiologist 1984 - Present Associate Professor of Veterinary t
Radiology, Oklahoma State University t
i a
TECHNICAL VITA 0F DR. EDDIE BASLER, PROFESSOR OF BOTANY l
Academic Training:
I i
1952-1954 - Ph.D. from Washington University; Major - Botany 1950-1952 - M.S. from University of Oklahoma; Major - Botany j
1946-1950 - B.S. from University of Oklahoma; Major - Botany Field of Specialization:
Plant Physiology; Transport of plant homones, growth regulators f
and herbicides Professional Experience:
l 1954-1955 - Research Associate; Washington University, St. Louis, MO 1955-1957 - Assistant Professor; Washington University, St. Lcuis, l
MO 1957-present - Assistant Professor; Associate Professor, and Professor, Oklahoma State University, Stillwater, OK 1968
- Visiting Professor; University of Illinois, Urbana, IL
(
(
Exterience Using Radioisotopes:
1950-1952
- C-14 labeled plant hormone transport in plants.
University of Oklahoma 1952-1957
- C-14 labeled nucleic acid bases for studies on RNA synthesis. Washington University St. Louis, M0 i
i 1957-Present - C-14. H-3, 5-35 P-32, Rb-86 used in studies of plant homone transport and mode of action of herbicides
(
TECHNICAL VITA 0F DR. DONALD L. COOPER, M.D., DIRECTOR, OKLAHOMA STATE UNIVERSITY HO5PITAL AND CLINIC Academic Training:
M.D., University of Kansas, School of Medicine A.B., Kansas State College, Pittsburg, Kansas W
4 1
Field of Specialization:
General Practice l
Experience and Training:
I 1960-Present - Director, Oklahoma State University Hospital and Clinic, Stillwater, OK l
1958-1960
- Kansas State University Health Service, Manhattan, l
KS 1956-1958
- Private Practice 1954-1956
- U.S. Air Force--Research and Development Command, Albuquerque, NM 1953-1954
- Intern, St. Mary's and Children's Mercy Hospitals, Karsas City, M0 l
TECHNICAL VITA 0F DR. E.M. H0DNETT, EMERITUS PROFESSOR OF CHEMISTRY Academic Training:
r l
Ph.D., Purdue University Specialty:
Medicinal Chemistry Radiochemical Experience:
1954-1965
- Project leader, Oklahoma State University, direction of student in the study of mecha-l nisms or organic reactions by means of carbon-14 and hydrogen-3 on projects soon-sored by the U.S. Atomic Energy Commission.
Texaco. Dow Chemical Company, and the Oklahoma Agricultural Experiment Station, l
resulting in eight Ph.D. dissertations and l
twelve M.S. theses 1957
- U.S. Public Health Service, Mercury, Nevada.
Nuclear Test Series Of f-Site, Monitoring l
Program 1954
- Research participant, Oak Ridge National Laboratory, Use of radioactive compounds to study reaction mechanisms using C-14 mostly 1952-1953
- Associate Chemist. Argonne National Laboratory, Synthesis of radioactive or organic com-pounds in the study of the mechanisms of organic reactions, Used H-3 a great deal for labeling purposes 1952
- Synthesis of radioactive Systox with 5-35 1
1 l
5 o
TECHNICAL VITA 0F DR. H. M. JOHNSON, ASSOCIATE PROFESSOR, OF ENGINEERING TECHNOLOGY AND RADIOLOGICAL SAFETY OFFICER Academic Training:
1972
- Ph.D., Biochemistry and cell Physiology, Uni-versity of Texas at Austin 1968
- M.S., Radiation Health Physics, Colorado State University 1961
- B.S., Biological Science, Southeastern State University l
Teaching Experience:
1982-Present - Associate Professor of Engineering Technology 1975-1982
- Associate Professor, Radiation Safety and Health 1973-1975
- Associate Professor, Radiation and Nuclear Tech-l nology. Oklahoma State University 1
1972-1973
- Instructor. Oklahoma State University r
i
_P_r,ofessional Activities:
j Consultant to various Corporations involving:
Writing and reviewing operational precedures for maintaining radiation safety 4
Training Radiation Safety Officers l
Training technicians to hahdle radioisotopes Supervising technicians in performance of radiation surveys and swipe tests Member of the Radiation Safety Committee Teaches radiological safety on campus and as extension courses Organizational Activities:
Health Physics Society. Oklahoma Technical Society Central Oklahoma Society of Nuclear Medicine (ECHNICAL VITA 0F DR. WILLIAM A. SIBLEY, PROFESSOR OF PHYSICS AND CHAIRMAN, RADIOLOGICAL 5AFETY COMMITTEE Academic Training:
1960
- Ph.D., University of Oklahoma 1958
- M.S., University of Oklahoma 1056
- B.S., University of Oklahoma 1
Field of Specialization:
l l
Solid State Physics l
O/7//
6 1
Professional Experience:
1978-Present - Assistant Vice President for Research, Oklahoma l
State University l
1976-1978
- Director, School of Physical and Earth Sciences (Departrents of Chemistry, Geology, and Physics). Oklahoma State University 1970-1976
- Head, Department of Physics Oklahoma State l
University, Director of Research and Graduate Studies, College of Arts and Sciences (1974) 1961-1970
- Head, Non-Metals Section Solid State Division, Oak Ridge National Laboratory, Radiation Damage and Optical Properties in Insulation Crystals 1960-1961
- Radiation Damage in Metals, Kernforschunganlage, Julich and Institute for Metal Physics, Tech-nical University of Aachen, German Experience Using Radioisotopes:
1960-1979
- Co-60 gamma cell e.
The organization and purpose of the Radiological Safety Committee and its general functions with respect to personnel, procurement of isotopes, and supervision of isotope usage and disposal and de-scribed in the HANDBOOK, pp. 1-4.
More specific details of itt responsibility in these latter matters are provided on pages 5, 6, i
9 and 10.
i f.
The Radiological Safety Officer. Dr.
H.M.
Johnson is an appointee of the University President and a member of the i
Radiological Safety Comittee.
As such, his Technical Vita i
appears above with those of the other members. A general l
statement of his responsibility as R.S.O.
(and as R.P.A.) is r
given in the HANDBOOK, pp. 4-S.
Further specific details of his responsibilities and authority appear on pages 6, 7, 9, 15, 16 and 21.
i 8.
Training of Users The operational responsibility for PuBe sealed sources iM-424 and
- M-107 containing 16.00 and 46.66 grams Plutonium respectively has been vested in Dr. Howard M. Johnson, Associate Professor of Engineering Technology. Dr. Johnson is also the OSU Radiological Safety Of ficer and his vita is included with those of other members of that group in Item 7(d).
He uses the source for instrument calibration i
purposes.
Information on Dr. John Stone, responsible for source (MRC-N-SS-U-l Pu8Be, is given below.
l 1
l
y TECHNICAL VITA 0F DR. JOHN L STONE, PROFESSOR OF AGRONOMY Academic Training:
B.S.
- University of Nebraska N.S.
- Iowa State University Ph.D. - lowa State University Field of Specialization:
i Soil Physics Experience and Training:
'i 1969 - present - Professor of Agronomy, Oklahoma State University 1060 - 1959
- Associate Professor 1957 - 1960
- Assistant Professor i
Stone had formal course work in radioactivity and radioisotope handling at towa State University. He has been active in the invention and i
development of neutron probes for soil moisture measurements since l
1953, using RaBe neutron sources since that time. He has also worked with millicurie amounts of Strontium 80, 85, 89, and 90 and Cesium 137 for several years. He has had experience in handling PuBe neutron l
sources in the laboratory and field since 1970. For the past 7 years he has worked with Am(241)Be neutron sources which are widely used in soil I
moisture meters.
)
9.
Facilities and Equipment a)
Sealed Sources #M-424 and fM-107 t
I 1
When not is use for the purpose indicated in item 6, each source will be stored in their original shipping container in a posted, limited access area (Industrial Building) on the Oklahoma State i
University Campus with provisions made for appropriate monitoring l
and safety procedures. Should need arise limited access storage may be provided is a specially-designed "hot room" (Physical Sciences j
B-49) which is directly supervised by the Radiological Safety l
Officer.
l b) Sealed Source MRC-N-SS-PuBe-100 I
Although authorizatie,n for 150 milligrams of Pu-238, encapsulated as PuBe sources, continues to be requested, we presently have only one source containing 17 milligrams Pu-238 and do not anticipate TiTrther purchases.
This is a neutron source and is mounted in a I
modified Nuclear Chicago P-19 Moisture Gage designed to measure moisture and study water loss from vegetated areas.
j
'When not in use, equipment including the source will be stored i.1 posted, limited-access areas at Agriculture Experiment Stations or at the Agricultural Hall or the Agronomy Farm on the Oklahoma i
l l.
6/7//
i
8 t
L State University Campus at Stillwater. While in storage, the probes will under the control of the Stat'.on Superintendent or Dr.
i Stone.
The Agriculture Experiment Stations are:
Irrigation Research Station. Altus. OK l
Randy Bomar, Superintendent l
Cotton Research Station, Chickasha, OK Don Hooper, Superintendent j
Caddo County Research Station, Ft. Cobb, OK i
Willy Stokes, Superintendent Panhandle Research Station, Goodwell, OK J. P. Alexander. Superintendent j
L Sandy Land Research Station, Mangum, OK t
Randy Boman, Superintendent i
The station Superintendents have been trained in the hazards of r3dioactive materials and know emergency procedures to be taken.
- 10. Radiation Safety Program f
a) Special Procedures
[
I Storage, use and surveillance of the several Plutoniun sources have
[
already been covered in Item 9 above. However, since small soun.es mounted in moisture probes (17 millicurie Pu-238 source) may l
require transportation between use stations, some special procedures have been set up.
j The neutron sources are mounted integrally as part of soil moisture l
probes. Operators will not handle the source except as they handle l
the probes.
The probe instrument will be mounted when the sources j
are first received and the radiation fields around the probe ma pped. Operators will wear neutron film badges at all times when using probes.
L Use of the probe falls in three classes:
storage, transportation, l
and field measurement. Use will be normally for four hours a day at the most. The greatest radiation hazard to the operator is during the time of carrying the device from one measuring site to another. This usually takes about I minute per carry.
The source L
is near the ankles during this process. At other times the operator remains 10 feet away from the radioactive source, during j
which the source is in an access tube in the ground. The operator remains near the pulse counting unit of the device. Measurements are normally made three days a week at most.
Estimated whole body dose for 8 hr/ day, 5 day /wk use would be 30 mrem.
The expected
[
dose, then, is much under this amount because of lesser use.
l l
I i
g Sources will be transported from the Stillwater Campus and Experiment Stations storage location in the trunk of University-owned automobiles. Vehicles will be labeled by signs posted in the windows of the vehicles when radioactive materials (sources) are in the vehicles.
Curing transportation to and from the field, 15 cm of paraffin shielding will be provided, since the d* stance between the source and the operator may be the distance between the driver's seat and trunk of an automobile. Persons may be riding in the rear seat of the automobile, also.
Permanent storage will place the soJrce behind 25 cm of pareffin and will be constructed such that persons can not come within 1 meter of the source location.
In case of an accident involving the vehicle transporting sources of this nature, the following plan regarding emcrgency procedures to be followed is to be instituted:
The warning sign posted on the vehicle will contain information to get the procedure initiated in the event the responsible person in the vehicle is completely incapacitated.
Information on signs:
- 1) Carries the radioactive label (or will likely be printed on a large radioactive label -- 8" x 10").
- 2) Identifies: material, radioisotope, emission, quantity, radius of hazard, location in vehicle, brief description of container.
- 3) Tells who to notify: State Health Department, OSU Radiological Safety Officer, agronomy project leader, and gives phone numbers.
- 4) Tells not to move the source from the scene until it is checked by responsible persons.
The responsible person in the vehicle will be instructed as to the following procedures and requirements to be met in the event of an accident.
- 1) Render any aid needed to injured persons.
2)
If he is physically able, ascertain whether dar. age to the source is likely.
- 3) Notify all concerned of the presence of radioactive material.
- 4) See that the public is completely protected from radioactive hazard and solicit help as needed in this regard:
a) No cars er persons pass through smoke from burning vehicle.
i i
i i
n 10 b) No persons or vehicles allowed downwind, c) No persons are to handle the probe or container.
- 5) See that instructions on card are carried out, notifications made, ect.
The responsible person is always someone who is familiar with
(
the University regulations as well as Federal. We do not anticipate nor plan to effect interstate transfer of the source I
I so that portion of interstate commerce requirements is not involved.
Since the source is sealed amd mounted inside a probe which is inside a paraffin shield, the rupture of the source is not likely, except in a most devastating accident. What is more likely is that the shield material would be removed through shattering or burning.
The responsible person would use the neutron survey meter to ascertain the degree of hazard resulting from any damage to the thield.
The probe can be imersed in a large container of water or wet sand for reduction of such hazard, b) Radiation Detection Instruments All departments of the University using Byproduct and/or Special Nuclear Material maintain appropriate instrumentation.
The following specific instruments are routinely available to the individuals directly responsible for the Plutonium sources and exemplify the types of instrumentation used for surveying and smear contamination testing:
Type of Number Radiation Sensitivity Window Use Instrument Available Detected Range Thickness a) Available for Use by H. M. Johnson with Sources #M-424 & #M-107.
Eberline 1
o, 8. Y 0-500 mR/hr 1.7 mg/
survey Model R0-1 0-500 R/hr sqr. cm "Cutie Pie" Eberline 1
n 0-5000 CFM BF3 tube survey PNC-4 (logscale) w/ cadmium Fast / Slow shield &
Neutron Meter moderator W. B. Johnson 2
- 8. Y 0-20 mR/hr 1.5 mg/
survey GNS-5 Survey sqr.cm 9'W7H
11 l
Heter w/GP-200 probe W. B. Johnson 1
a 0-50000 CPM survey GSM-5 Survey Heter w/ ASP-2A alpha probe Baird Atomic 1
a, 8 0 CPM none Smear Con-Nuclear Spect-a Bkg.
tamination i
rometer 980530 60 CPN Tests w/912080 flow sBkg.
counter i
i b) Available for Use by J. Stone with Source #MRC-N-SS-W-PuSe-100.
r Nuclear Chicago 1 8, y 0-20 mR/hr 1.25 mg/
Survey Geiger Survey sqr. cm Meter t
t Eber11ne 1
n 0-5000 CPM BF3 tube survey PNC-4 (logscale) w/ cadmium Fast / Slow shield &
Neutron tiete*
moderator Nuclear Chicago 1 a
a Bkg.
0.9 mg/
Smear Alpha Detector 0 CPM w/055 Scintil.
sqr. cm Contam-ination lation Probe.
Model 305 Tests Shield and Model 186 Scaler l
c) Calibration of Instruments Neutron survey meters are calibrated on all scales using the Pu(239)Be source #M-107 as a calibrated point source. Batteries are also changed at the time of calibration.
Local regulations on instrument calibration for persons responsible for Byproduct and/or Special Nuclear Material use are given in the HANDBOOK, page 21.
Local calibration sservice is furnish ; by personnel of the Engineering Technology Laboratory.
Dr. H. M. Johnson, who is the RSO is in charge of the calibration.
Smear test instruments are calibrated at each operation using coenercially obtained calibration sourr+
i l
o 12 l
1 d) Although anticipated exposures and those actually observed over the previous fifteen years of experience with these sources are minimal, film badges are worn by responsible faculty members, i
supervisors, probe handlers and students.
The badges are furnished by commercial supplier R. S. Landauer, Jr. & CO., Glenwood Science Park, Glenwood, Illinois, 60425, and are of the type which will l
monitor n, x, beta, gamma.
These badges are evaluated by the suppliers on a monthly basis and, as mentioned above, no significant problems have been encountered.
l e) Leak Testing Leak testing of thr. Plutonium sources will be carried out by the responsible individuals indicated in item 8.
The tests will be I
i done in conformity with local regulations for general seipw testing of sealed radioisotopes, as detailed on pages 8 and 9 of the attached OSU HANDBOOK.
Specifically:
Each Plutonium source will be tested for leakage at intervals not i
to exceed six (6) months.
In the absence of a certificate from a
(
transferor indicating that a test has been made within (6) months l
prior to the transfer, the sealed source will not be put into use i
until tested.
l The test will be capable of detecting the presence of 0.005 microcuries of alpha contamination on the test sample.
The test sample will be taken from the source or from appropriate accessible surfar.es of the device in which the sealed source is permanently or t
semipermanently mounted or stored.
Records of leak test results will be kept in units of microcuries and maintained for inspection i
by the Commission.
[
If the test reveals the presence of 0.005 microcuries or more of
(
removable alpha contamination, we will innediately withdraw the sealed source from use and will cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in accordance with the Commission regulations.
Within five (5) days after determining that any source has leaked.
L we will file a report with the Material Licensing Branch, Division L
of Fuel Cycle and Material Safety. Office of Nuclear Material r
Safety and Safeguards U. S. Nuclear Regulatory Comission.
Washington, D. C., 20555, describing the source, the test results, the extent of contamination, the apparent or suspected c,ause of source failure, and the corrective action taken. A copy of the report will also be sent to the Director, U. S. Nuclear Requlatory Comission, Region IV, Office of Inspection and Inforcement 611 Ryan Plaza Drive, Suite 1000, Arlington, TX, 76012.
t f) A complete description of the Oklahoma State sniversity Radiation t
Protection and Control program is provided in the attached HANDBOOK.
This docu' rent was revhed in 1976 to meet the l
1
13 requirements of 10CFR33.13. As tsch, it has been accepted as Admendment #15 to our Type A specific license of broad scope for byproduct material (#35-00237-03) since January 12, 1977.
The HANDBOOK is distributed to Authorized Use s and concerned administrators in loose-leaf form allowing for modification as required. The right to make minor changes in response to local operating situations is reserved but major modifications arising from additional regulatory requirements will be reported to the Connission.
- 11. Waste Disposal l
There is at present no intention to discontinue use or dispose of the Special Nuclear Material on hand. At such time as it becomes necessary i
l to do 50 proper notification will be made to the Comnission.
l l
l l
i l
l l
- -- --------------------- - A & D H a
o r
(w HANOB00K OF RESPONSIBILITIE
S. PROCEDURE
S, AND REGULATIONS GOVERNING THE SAFE USE OF ION! ZING RA0!ATION l
ON THE CAMPUS OF l
OKLAHOMA STATE UNIVERSITY l
l O 1
l l
l I
Revised January 1937 llO
(,p,, q, j<y:p!:'
3-18-87 c
'/c 2 g
5Y ;'f
l l
i i
O l
RADIOLOGICAL SAFETY COMMITTEE W. A. Sibley. Assistant Vice President for Research. Chaiman H. M. Johnson. Department of Electronic / Computer Technology - Secretary l
E. Basler. College of Arts and Sciences f
E.M.Hodnett.CollegeofArtsandSciences(Emeritus) 1 R. J. Bahr. College of Veterinary Medicine i
F. R. Leach College of Agriculture D. L. Cooper M.D., Director. Student Health l
l t
H. M. Johnson, Radiological Safety Officer. Radioisotope Procurement i
Agent.LicensingOfficer(Extension 5716) i O
In the event of an EMERGENCY. if the Radiological Safety Officer is i
not imediately available, call the Safety Department (Extension 7241) l for alternate assistance.
I l
f 1
f i
I l
O 11 3-18-87 j
u o
m TABLE OF CONTENTS SECTION 1.
RADIOLOGICAL SAFETY ComlTTEE Page A.
Organization and Purpose......................................
2 8.
Funct i ons of Rad io log ica l Sa f e ty Commi ttee.................... 4 1
i 1.
Personnel.................................................
4 I
2.
Procurement...............................................
4 3.
Supervision of Usage and 0lsposal.........................
4 1
C.
Ra d l o l og i c a l S a f e ty O f f i ce r (R. S. 0. )..........................
4 0.
Radioisotope Procurement Agent (R.P.A.).......................
5 i
SECTION 11.
REGULATIONS CONCERNING THE PROCUREMENT I
ANO USAGE OF RADIOlSOTOPES, EQUlPMENT AND SERYlCES A.
Unsealed Radloisotopes........................................
5 l
1.
Application...............................................
5 2.
Approval..................................................
5 l
l 3.
Re s pon s t b I I i ty o f Com i tt ee............................... 6 l
l 4
ResponsibliIty of the R.S.0...............................
6 i
I 5.
Responsibility of the User................................
7 I
6.
Responsibility o' the School Director or Department Head..
7 B.
S e a l e d Ra d i o i s otop e s..........................................
8 1.
Appilcation...............................................
S i
i 1
0 111 10/1/76 V(c/7#
t l
i L
t
()
TABLE OF CONTENTS (Continued)
Page l
2.
Approval..................................................
8 t
3.
Responslbility of the Committee...........................
8 I
4 Responsibility of the R.S.0...............................
8 l
l 5.
Responsibility of the Person in Charge....................
8 I
6.
Responsibility of the School Director or Department Head.. 9 C.
Sources of lentzing Radiation Produced by Olf ference in l
Potential.................................................
9 j
i 1.
Application and Approval..................................
9 f
i 2.
Re s pon s i b i l i ty o f t he Coen i tt ee........................... 9 l
i 3.
Re s p on s i b i l i ty o f t he R. S. 0............................... 9 l
i 4.
Re sponsi bi l i ty of the Person i n Cha rge.................... 9 6
()
O.
Irradiation 3ervice..........................................
10 l
t SECTION til. SPECIFIC RADIOLOGICAL SAFETY i
STANDARDS A.
References...................................................
10 B.
Maximum Permissible Levels f rom External Sources in Re s t r i c t ed A re a s........................................... I l f
i C.
R a d i a t i on A r e a s..............................................
12 i
i 0.
P ro t ec t i v e C l o t h i n g..........................................
12 f
l l
E.
Con t am i n a t i on Con t ro l........................................
12 1.
Pe r s on n e l................................................
12 l
i 2,
Area.....................................................
13 3.
Rou t i ne La bora tory Su rvey s by Use r s......................
13 i
i gy 10/1/76 1
O TABLE OF CONTENTS (Continued)
Fuge j
F.
E s t i n g a n d Sec k i n g..........................................
14 G.
Pac ka g e Rec e i p t Proc edu re s..................................
14 i
f 1.
All Packages............................................
14 l
1 2.
Non - Ex emp t P a c ka g e s.....................................
15 i
H.
Storage, Transporting, and Handling of Radioactive t
Materials...............................................
16 l
1.
Wasto Olsposal (10CFR 20.30I)................................
17 t
1.
General..................................................
17 g
2.
Gaseou s Wa stes and Ai r Contami nants.....................
17 3.
Solid Wastss............................................
18 i
()
4.
L i q u i d Wa s t e s...........................................
18 J.
Pe r sonne l Mon i tor i ng........................................
19 l.
Responsibility for the Enforcement of Personnel Monitoring Procedures.................................
20 i
i 2.
VIsttors................................................20 f
3.
Teltium Bleassays.......................................
20
)
4.
todine Blosssays........................................
20 I
K.
Survey i nst ruments-- Acces s and Ca l i brat 'on................... ? !
L.
Responsibility f or Training in Health Physics............... 2l APPEN0lx A.
Selected Bibliography on Radiological Control i
P r oc e d u r e s.................................................. 2 2
(
i APPEN0lX B.
Quantitles of Radioisotope Packages Exempt f rom j
Specia l Hand l ing anc Moni toring ( 10CFR20.205)............... 24 i
- i. Packages Containing Radistsotopes in Ltquid Form........ 24 i
2.
Radioactive Material in Other Than Liculd Form.......... 25 l
i i
I v
10/l/76 l
m
l TABLE OF CCt4 TENTS (Continued) i i
Page 3.
Short Half-Life Material................................
25 l
APPENOlX C.
Radiation Accident Procedures...........,..........
26 i
1.
Mhor Spills involving No Rad'ation Hazard to Personnel., 26 i
2.
Major Spills involving Radiation Hazard to Personnel.... 27 i
I 3.
Accidents involving Radfoactive Dusts, Mists, Fumes, Organi c Vapors and Ga sas.............................. 27 1
I 4.
Injuries to Personnel involving Radiation Hazard........
28 1
i i
1 i O
}
i I
I l
9 4
[
. i i
i i
i l
O 4
t i
l 10/1/76 vi
- y ;,r e y
,- n 1L 4
f[ l,' -
p$ n G
- 4: 4<
v a
! /c : ) ~
c+.
N'
+
f e
^
HAN0000K GF RESPONSIBILITIES, PROCEDURES ANO
- REGULATIONS GOVERNING THE SAFE USE OF IONIZING RAOIATIONS ON THE CAMPUS.
0F OKLAn0MA STATE UNIVERSITY j
r 1
l l
Due to the Increased utilization of lor.lzing radiations on the j;
campus, It was deemed appropriate and necessary that a committee be i
apoolnted to help a'sure radiological safety. This committee was e,pp ointed on April ad,' 1957, and at the same time a Radiologica:
I Safety Of ficer was designated by the President of Oklahoma State University.
According to terms 'of the Energy Reorganization Act of 1974, l
amending the Atomic Energy Act of 1954, the U.
S.~ Nuclear Regulatory l
Commission (NRC) has authority over all operations involving by-
.j product material whether produced in their facilities or not. The Commission has entered into a working arrangement with the University i
under which It has grantsd a license to possess and handle certain j
radioactive materials. A license is subject to the recognition by the University and its staf f of certain rules and prccedures, and del-egates administrative responsibility to the University for possession, use, storage, and disposal of radioactive materials. The Ccmission i
reserves to itself cerialn rights to revoke or cancel arrangements, l
to repossess or recall active materials, to. Inspect facilities, and I
to review procedures. The continued existence and renewal of the t
license depends on the acceptance and observance of recognized pro-cedures by all members of the staf f of this University concerned in any way with the handling of radioactive material.
The purpose of such procedures is to insure insof ar as is humanly possible that radioactive materials are handled with the least possible hazard to the Individual worker, his associates, the University facilities, and the general public.
i h
I I
O i
l.
10/1/76 l
i d,
_--.,,..f_.__,
SECTION 1.
.JDl0 LOGICAL' SAFETY COMMITTEE S
A.
Oraanization end Purpose.
3 The Radiological Safety Ccanittee Is composed of representatives of the colleges and departments predominantly Involved in the handling of radioactive materials and the operation of machines producing lonizing radiations or particles. Mernbers are appointed for Indefinite forms by the President of the University upon recommendation by the appropriate Dean or other cJrcinistrator and the concurrence of the Com-mittee Chairman. This Committee is responsible to the President of the University and is charged with the responsibility for establishing safety measures to ensure the protection of all personnel, both of the University and of the public.
It is the responsibility of appropriate admir.Istrators and onerating personnel in each area to conduct proce-dures safely.
In setting up rules and procedures to minimize radiation exposure, j
the Oommittee calls attention to recognized necessary precautions which, when carried out in the proper spirit, will minimize the probability of an accident occurring.
If an accident should occur, the nossibility of harmful consequences is expected to be greatly reduced by adherence to these practices.
The Ccanittee hopes that it will not be viewed as a police force j
or a hurdle which must be circumvented before progress is made, but rather that it wlll be looked upon as a needed and desirable source of help and guidance to better assure that a p.*oject will be conducted safely and efficiently.
1 The Committee, in cooperation with Interested faculty and staff,
)
encourages and fosters new and worthwhlle programs involving lonizing radiations.
It works toward the Institution of educational programs so that all persons on the esmpus who are subject to radiation expo-sure will not only develop a healthy regard for the hazards of radla-tion but will also understand and respect the many benefits of its j
proper utilization.
i The Ccanlitee encourages and prunctes the use Ir research of radioisotopes and other radiation sources.
The Ccanittee desires to protect the 11terest of tr e, University with respect to public reactien and good wiii n matters involving O
2.
10/1/76 VW7//
i O
o.
radiation and use of radioactive materials. 'in this connection, the Cor.rnittee recognizes the Importance of an informed public and attempts to anticipate public reaction at all times. -indeed, this factor, along with others, is considered in the approval of every project.
To ensure that adequate safety measures are ernployed in the hand-Ilng, utilization, and disposal of all. radioactive materials, the Ccamittee must tiave availabic to It knowledge of their location, it must approve, from the standpoint of safety and health, the proposed users, procedures, and facilities associated with the employment of radiological meterials and equipment in research and Instructions To fulfill these purposes and the responsibilities set forth later, the Committee shall meet once each calendar quarter and upon additic,nal call when deemed necessary by the Chairman or the Radio-logical Safety Officer.
Approval of any proposed usage of radioactive material or radt-ation equipenent will be based on the adequacy of the safety measures to be exercised. Three principal f actors are considered by the Com-mittee in evaluating the adequacy of the safety risks In a proposed usage:
(1) the training, experience, and ability of ths applicant i
to cope with the hazards involved in the particular application, (2)
O the adequacy of the facilities and equipment for the proposed usage, and (3) the thoroughness of the attenf'lon given to safety precautions in the proposed experimental manipulations and disposal procedures.
The Committee establishes 1 basic safety regulations, maximum permissible radiation levels, and precautionary measures to serve as the guide to safe operations in.bsndling radioactive materials.
It requires adherence to these general stendards, in addition, the Committee may specify further regulations to.be observed for certain types of operations and for partictdar projects. These actions are taken within the f ramewerk of NRC regulations and additional appro-priate guidelines.
If the Committee at any time is not satisfled with the adequacy of safety practices employed in a project, it may require cessation of the project until satisfactory procedures have been adopted. Such corrective action is to be accomplished through established admints-trative channels.
]
Although It makes itself available for consultation and advice to the Student Health Centnr, the Committee normally delegates operational responsibility for the human medical uses of radiation by
]
that organization to its licensed meilcal staff; i
u O
3 10/l/76
b B.
Functions of Radioloqical Saf_aty Committee.
The Committee's responsibil.yles encompass the radiological aspects involved in the safe use and disposition of radioactive isotopes in-cluding fissionable materials, in the control and use of materials of equipment that emit high energy lonizing radiations or particles that are capable of causing lonization of chemical elements, and in the super-vision of irradiation services. Hereaf ter these are referred to as "Radioisotopes", "Equipment" and "Services". Definitions and regula-tions that pertain to each classification are presentud in Sectio.1 11.
l.
Personnel. The Ocmmittee determines the adequacy of the training of personnel responsible for the use of radioactive materials and/or other sources of lonizing radiations.
2.
Procurement. The procurement of all radioisotopes, equipment, and services must be approved by the Committee. The criteria for approval are the radiation and contamination risks involved. Applica-tion forms for the approval to procure radioactive isotopes directly or through Irradiation service are issued by the Committee.
Subsequently, individual orders for radioisotope procurement are routed through the Radiolsotope Procurement Agent to insure compilance with the Conmittee's approval. Requests for authorization to purchise or receive radiation equipment must be presented to tha Committee by letter, s
b 3.
Supervision of Usaae and Disposal, it is the responsibility of the Committee to ensure that the usage and disposal of all radio-Isotopes end equipment are in accordance with such safety standards as are recomconded by the National Bureau of Standards, the Oklahoma State Department of Health, and the Nuclear Regulatory Commission or its agencies, or as are established by the Committee.
However, actual operations are the responsibility of the appropriate adminisirator.
The Comml+ter
.us the authority to require that the user of any radioactive ma:.c is, equipment, and services as covered in this document, submit 's such examinations and inspections as the Committee may deem necessarr to assure safe operation.
The Committee has estaellshed procedures for keeping areas In-volved in the usage and disposal of radioisotopes, equipment, and services under such surveillance as is needed to minimize the radio-logical risks and hazards to the safety and health of all involved.
C.
Radloloqlcal Saferv Officer (R. S. 0.).
A Radiological Saf ety Of ficer, who is also a member of the Com-mittee, is appointed by the President of Oklahoca State University.
The Radiological Safety Of ficer is responsible for monitoring the adherence to the regulations of the Committee concerning radiological (3
V 10/l/76 Q'A/7//
+.
7; t
(v safety and health on University property.
Where unsafe practices involving use of radioactivity and radi-attons, or where practices in violation of established regulations are observed, the Radlological Safety Of ficer has the authority to require cessation of the project until a review can be made by the Corrrnittee,.and an administrative decision has been mado, if necessary.
D.
Radioisotope Procurement Aaent (R. P. A.).
A Radioisotope Procurement Agent, who is also a member of the
- Corrrnittee, 'Is designated to be responsible for Ir.suring that the pro-curement of radioisotopes compiles with the University License and such other special regula^1ons as have been "et up by the Cnmmittee.
He is also responsible for handling all negorlations with the NRC concerning the University License and its requirements. At the dis-cretion of the Consnittee, the Radiological Safety Of ficer may be assigned the duties of the Radioisotope Procurement Agent as an additional responsibility.
An Alternate Radioisotope Procurement Agent is designated by the Conunittee to act in the absence of the regular Agent.
O sectio" ii-acou'^Tio"s cc e ca"i"o T"e eaocuae"c"r ^"o USAGE OF RAD 10lS0 TOPES, EQUIPMENT AND SERVICES i
A.
Unsealed Radloisotooe,s,.
4 i
j l.
Acolication. Application for permission to procure and
~
utill.te all unsealed radioisotopes, however to be obtained, is made on Icotope Form A-I provided by the Commlttee through the R.S.O.
On this fonn the applicant will set forth clearly the isotope desired, the quantity, the Intended use, and the final disposition. A copy of all applications is kept In the files of the R.S.O.
l 2.
Approval. The Cctnmittee has final judgment as to Thc approval of en application by any regular member of the University faculty re-j ques +1ng authorization to purchase and utillze a specific radiolsotope.
Once granted, the authorization remains in continuous force unless it 1
a is withdrawn by request of the applicant, by vote of the Conynittee upon rectxtrnendation of the R.S.O., or by termination of the applicant's employment with Oklahctna State University.
The maximum authorized single purchase amount of the isotope is j
that specified in the CorrnIttee's approval. A request for an increase v
s.
In the authorized amount of the isotope or for approval of a substan-tlat change in its planned use which will involve additional radio-l logical risks and hazards is to be directed to the Corrrnittee through O
1 3
10/1/76 i
O t
the R.S.O. for his consideration and recommendation. When deemed appropriate upon review of the Committee, such a request will be I
treated in the same manner as a new project.
Granting approval to an' application does not. affect the limita-tions which may be placed on the University by the NRC in present or f uture IIconses. The University does not.have authority to approve
- the use of radiolsotopes with human subjects or experiments involving 4
widespread distribution of radiolsotopes.- In these cases special approval must be obtained from the NRC.
3.
ResDo9sibi lItv of Conynlttee. The Committee. requires adher-l ence to the safe practices set forth In Section lil at all times.
Evidence of hazardous conditions and/or failure to comply with these safe practices may cause the Comittee to demand cessation of all operations and to withhold permission for continuance of the project i
until assured of the remedy of the hazardous conditions and compilance with the established safe procedures, it decides with the R.S.O. what Inspections, monitor!ngs, spot checking, and other Investigations of the use of radiolsotopes on the campus are to be made.-
{
The Committee requires that every radioactive source in posses-slon of the University be assigned to a specific Individual who shall O
be responsible for its use.
In certain circumstances-It may be con-venient for one person to be assigned responsibility for a departmen-tal Inventory consisting'of several teaching and/or Instrument check sources. The Committee approves the Individuals to whom these responsibilities are delegated.
4.
Responsibility of the R.S.O.
The R.S.O. will schedule i
routine inspections and surveys of areas of use of by-product material reflecting the hazards of use, experience of the user, and facilities available to the user. Quarterly written reports by Individual users and department heads will assist the R.S.O. In determining the desired frequency for surveys.
In general, quarterly inspections will be made of those areas continuously using radlotsotopes. The nature of the inspection will be determined by the R.S.O. giving consideration to the potential or existing hazards of each Individual use.-
He may Investigate the use and method of handling of any Isotope on the campus at any time. He will point out to the Individuals using the isotopes any unsafe conditions or practices that he observes.
In the event that the practices are not appropriately modlfled, he may demand cessation of the project pending subsequent action of the Ccan-mittee.
If cessation of a project is demanded, the R.S.O. must report i
the Incident to the chairmLn at once.
I
.O-l 6
10/l/76 j
1--
L.)
He must keep adequate records on observations, inspections, and Investigations of the use of radioisotopes on the campus.
He investi-gates any reported accident or spill of radioisotopes on University property.
5.
ResponsibilI+v of the User. As a prospective user, the applicant must furnish information requested by the Committee and by the R.S.O., at the time of original approval and/or at any subsequent time requested, regarding the proposed usage of isotopes and the pro-cedures expected to be used. The applicant may be required to demon-strate the anticipated procedures.
So long as his authorization for the utilization of any radiation source remains in force, the user must provide a quarterly survey of his operation for the R.S.O. on a form to be furnished by the Committee.
He must make note of planned changes in his operation which warrant increased inspection or a Committee reassessment of his specific isotope use authorization He must report to the R.S.O. as promptly as possible any accident involving radioactive isotopes or any spill or leakage of radioisotopes.
The loss or theft of any radioactive materials must be reported to the R.S.O. Inmediately upon discovery.
He is responsible for adherence to the safe practices and required laboratory recordkeeping procedures set forth in Section 111.
6.
Responsibility of the School Of rector or Department Head.
This administrator is ultimately responsible for the safe execution of all activities of his school or departmeat invo'"Ing the use of ioniz-Ing radiations and neutrons in ac' 1ar--
- lth
,e requirements of this Handbook. Each such administrative unit is resr unsible for estabilshing, where necessary, safety procedures and maintaining adequate records pertatning to uses of radioactive materials and radiation devices by members of its staff. Reference should be made to the following:
Part 20, "Standards for Protection Against Radiation,' U.S. Nuclear Regulatory Commission, Title 10, Chap. I, Code of Federal Regulations.
He will see that an inventory of all radloactive materials is provided annually on the standard form available from the Committee.
In addition, a copy of all orders for radioactive materials will be filed with the R.P. A. and R.S.O. at the time of requi,ltion.
He must inform the R.S.O. of all operations and manipulations where hazard f rom lonizing radiations or neutrons could be involved.
l He shall report immediately to the University R.S.O. any accidents involving exposures, spills, and/or leaks that result I., radlological risk or hazard.
I 10/1/76
l N) 8.
Sealed Radioisotopos.
All sources are considered to be unsealed sources unless the integrity of the seal has been established experimentally. Typical examples of sealed sources are: Co-60 and Cs-137 calibration sources for gamma survey meters, NI-63 detector cells for gas chromatographs, RaBe and PuBe neutron source moisture probes, Co-60 Irradiation devices and the like.
1.
Application.
See Section 11, A, l.
Certain exceptions are allowed to the usual application procedure for small sealed sources in Instrument check kits and demonstration sources containing exempt quantitles (10 CFR 30.718) of radioisotopes or Initially installed as calibration standards in radiation measuring devices manufactured under the general license provisions of 10 CFR Part 31. The R.S.O. should be consulted for details.
Note, however, that such sources must still be obtained through the regular procurement procedure (Section I, B, 2), assigned to a specific inoividual and carried on the departmental Inventory.
2.
Approval. See Section 11, A, 2.
3.
Responsibility of the Committee. See Section ll, A, 3.
4.
Responsibility of the R.S.O.
See Section ll, A, 4.
5.
Responslbility of the Person in Charqe. He must furnish Information requested by the Committee and/or the R.S.O. at any time.
When several Individuals in a given department, section, or work group have been approved by the Committee to handle sources, responsi-bility for sealed sources may be changed or transferred to these Individuals providing a record Is kept. The Committee may require that the person responsible keep a log of usage for these sources.
This log shall be available for inspection by the Committee or its delegate on request.
l No person shall transport a radioactive source of f-campus unless It has been expressly approved on the application, or express approval has been glven by the Co7mittee or its representative, or the sealed source has an activity of less than one (1) microcurie.
l He is responsible for seeing to it that the usage complies with the regulations on safe handling set forth in Section Ill.
Each sealed source ot5er than those exempt by size or speelfic l
regulation must be swipe-tested for leakage at not greater than l
8 10/l/76 I
L
s L
6-month Intervals and records maintained for each test. The tests will
-be carried out on or about April I and October I of each year.
If a newly-received sealed source does not have a certificate f rom a trans-feror Indicattr,g that a leak test has been made within six months prior to the transfer, IT shall not be placed into use until tested.
If the sample Indicates a contamination activity greater than 0.005 microcurles, the source is to be withdrawn from use and the R.S.O. notifled immediately.
6.
Resoonsibility of the School Ofrector or Oeoartment Head. See Section 11, A, 6.
C.
Sources of lonizino Radiation Produced by Offference in Potential, j
l.
Apolication and Acoroval..All app!! cations seeking perm!ssion to purchase such equipment should be made by letter to the Comittee through the R.S.O.
Typical examples aro x-ray equipment, particle accelerators and electron microscopes.
j 2.
Responsibility of the Comith, it is the responsibility of the Committee to inventory all such equipment in the possession of the University on University property and used Ly University personnel.
t The Committee must approve the person who is to be responsible for the supervision of the operation and manipulation of each item of equip-J ment. This person shall be considered responsible for all operations and manipulations unless the Comittee is notifled to the contrary In writing t
}
The Conynittee may require that a log of the operations and manipula-tions be kept and that this log be subject to the inspection of the Com-mittee or its agent.
It also requires that the person In charge use this equipment so as to conform to the safe practices set forth in Sectlen 111.
f in the event of any violation of these practices, the Committee may demand cessation of the operations.
1 3.
Resoonsibility of the R.S.O.
He Inspects and surveys each item in accordance with the stipulations of the Committee.
i He demands cessation of any manipulation if, in his judgment, unsafe practices are continued after being brought to the attention of the person in charge. He reports at once to the chairman of the Comittee eny unsafe conditions and practices known to persist. Resumption of manipulation by the user takes place only by the consent.of the Com-l mittee or its agent.
He keeps records of all surveys and Inspections that are madr, 4
4.
Resoonsibility of the Person in Charce. He must prov' Ja a l
quarterly survey of his operation for the R.S.O. on a form to *.o O
9 10/1/76 i
furnished by the Comittee.
He is to notify the Committee of any change in the equipment that increases the radiological risks or hazards in-volved.
He keeps such records'as may be required by the Committee and makes these records available to the Committee or its Agent.
He notifies the C u lttee in writing of.any change in his responst-bility to the equipment.
He permits the R.S.O. to inspect and survey the equipment at any time.
He is responsible to the Committee for assuring that the equipment Is utilized in accordance with the established standards of safe practices.
4 O.
Irradiation Service.
Any exposure of material (s) to lonizing radiations and/or neutrons for experimental purposes is deemed an Irradiation service.
trradiation which Induces radioactivity in the material Irradla'cd O.
Is governed by the safety procedures established for the radiation facility. The Irradlated materials are within the jurisdiction of the Committee. Their procurement, use, and disposal are governed by the rules, regulations, policles, and procedures established (see Section 11, 1
Part A and Part B) for radioactive materials obtained from other sources.
Irradiation which does not Induce radioactivity In the materfal(s)
Irradiated is goverred by the safety procedures established for the radiation facility.
SECTION lit. SPECIFIC RADIOLOGICAL SAFETY STANDARDS A.
References.
The worker is referred to Part 20, "Standard 3 for Protection Against i
Radiation."
U. S. Nuclear Regulatory Commission, Title 10, Chapter I,
}
Code of Federal Regulations. This regulation establishes standards which must be followed in handling radiot tive materials.
It also prescribes limits which govern exposure of personnel t7 radiation and concentrations of radioactive material, concentrations of radioactive material which may i
be discharged into air and water, and disposal of radioactive wastes.
In add'tlon, it estabilshes certain precautionar/ procedures and administra-tive controls. Unless otherwise stated in this Handbook, the standards i
- O 10 10/1/76
- - - yu7H
O
~
and regulations provided ln 10CFR 20 are those with which workers.at Oklahoma State University are expected to comply. As future amendments or modlfIcations of regulations become offIclal, they wilI apply, unless alternative regulations that ~are applicable are provided by the Radio-logical Safety Committee.
A copy of the current U. S. Nuclear Regulatory commission, Title 10, Chapter I, Code of Federal Regulations is available for Inspection in the office of the R.S.O.
Another copy is available in the University Library as are a number of useful National Bureau of Standards Handbooks (see Section IV) on the safe handling of radioactive materials and radiation devices.
8.
Maximum Permissible levels from External Sources In Restricted Areas.
t The maximum permissible level for total body radiation exposure shall be 1.25 rem per calendar quarter. A calendar quarter shall refer to any of the following periods: January 1 - March 31, April 1 - June 30,-
July 1 - September 30, October 1 - December 31.
This~shalI not be acquired at a rate greater tnan 0.1 rem per week except when operating conditions require a highor rate for a special project. When such a higher rate is to be usted, a safety of ficer must be present during the operation.
. O The maximum permissible level for exposure to a limited portion of the body shall be the same as for whole-body exposure except that the hands, forearms, and feet may be exposed to a maximum of 18.75 rem per calendar quarter where necessary for operational reasons.
No Individual under 18 years of age may receive in any one calendar quarter f rom radioactive matorial and radiation producing devices a dose in excess of 10 percent of the limits specifIed above.
The lowest possible dally exposure should be striven for in every f
operation. The exposure limits listed above represent the total additive i
exposure from all components of radiation invo,ved.
i The maximum permissible accumulated dose to the whole body shall be 1
calculated according to the following formula l
MPO = 5 (N-18) rems MPO =
the maximum permissiblo dose in rams I
N =
Individual's age in full years 1
~
The relationship between R, rad, and rem is considered to be as given in the following table. Maximum values of average neutron flux for a 40-hour week exposure are also given.
4
- O Il 10/1/76 l
--m,
,r
.. -. ~, - - - -.
,,y-
.~
+
i O
Maximum-Neutron Type of Quality Flux for 40-hour Radiation Factor rem / week rad / week
~ Week Exposure X or gamma.
1 0.1
'0.1 Beta 1
0,1 O.I Protons 10 0.1 0.01-Alpha.
20 0.1 0.005 2
Fast neutrons
~15/n/cm /sec-Thennai neutrons 670/n/cm /sec C.
Radiation Areas.
An area shall be designated as a "Radiation Area" when a major portion of the body could receive in any one hour a dose in excess of 5 millirem,-or in any five consecutive days a dose In excess of 100 millirem.
An area shall be designated as a "High Radiation Area" when a major portion of the body could receive in any one hour a dose in excess of 100 millirem.
D.
Protective Clothina.
Sultable gloves are reccanended whenever hand contamination is probable.
Rubber gloves shall be worn when handling open vessels contalning alpha <
material or when handling any equipment of comparable hazard. Rubber gloves are to be preferred for cases where liquid contamination may be present or where radioactive dust might filter through a cloth glove. Rubber gloves are to te cleaned, if practical, before removal. All gloves are to be stored and handled so as to prevent contamination of the inside surfaces.
Laboratory coats and/or aprons are recommended as additional protection for personal clothing during handling of materlais where spillage Is possiblw.
E.
Contamination Control.
1.
Personnel. All persons inf le working with redloactive materials wherein hand and shoe contamination is possible, are to a.
Accomplish decoriamination before eating, smoking, appiv',ng make-up or leaving work, b.
Wash rubber gloves before removing f rom hands unless the radiation level requires innedtate removal.
O 12 10/l/76
s
'i t
O
!- Q l
c.
Refrain from wearing protective clothing outside of the laboratory area if there is any possibility that it has' been contaminated.
j d.
Utilize the available equipment to assure that decontamina-tion has been effected. Reference'Is made to National Bureau of Standards Handbook 48.
l No work with long-lived alpha and beta-gamma emitters, in any chemical or physical form, is to be perfonned by a person having a break in his skin below the wrist unless sultable gloves known to be clean on the inside are worn.
The pipetting by mouth of IIquids containing appreciable radioactivity.
Is forbidden. 1he term "appreciable" In this connection is taken to in-clude all radioactivity other than naturally occurring trace amounts present in water, potassium compounds, etc.
2.
frea. All areas in which there Is radiation in excess of 0.5 mrem /hr shall be physically isolated and appropriate signs posted to prevent persons from entering the area without being aware of radiological hazard.
l Signs having the radiation symbol will be standard for radiation hazards.
The symbol will also be used to distinguish radioactive source containers, contamination areas, hot sinks, barriers, etc.
All spills of radioactive material must be cleaned up promptly. Clean-Ing responsibility shall rest on the Individual (s) working in the area In-i volved and responsible for the' spill, and a survey shall be made af ter l
cleaning to verify that the cleaning aas removed the radloactive material (s).
I Cleaning tools shall be assigned to the room In which the work operations l
l are being performed and not removed or used elsewhere under any circumstances.
The Safety Of ficer shall be notified of all spills or Ireldents involving possible contamination.
k 3.
Routine I.aboratory Surveys by Users.
Individuals approved to procure and use radioisotopes are responsible for determining the levels of I
radiation and/or removable contamination present in f acilities under their use or supervision. The following minimum guidelines will be observed and will serve as a basis for procedures to be established as a part of the appil-l l-l cation for permission to procure and use radloisotopes.
l a.
Approved Individuals are responsible for determining the external radiation levels and/or removable surface contamination levels present in facilities under their supervision.
l b.
Maximum permissible removable surface contamination is 10 2
uct/cm as determined by dry swipe tests using filter paper on a surf ace area i
2 of 100 cm for low-energy beta emitting Isotopes and I mr/hr (measured in air 1
O 1
13 10/1/76 l
4'& /7//
~
at l-inch.from a 2 square Inch area of surface). Surfaces indicatl'ng activities In excess of the above shall'be decontaminated Immodlately using appropriate procedures.
c.
Areas In which radiolsotopes are used on a continuous or regular basis will be surveyed at Intervals not to exceed one month l
using methods appropriate to the isotope (s) In use.
i l
d.
Areas in which radioisotopes are used on an irregular or Intermittent basis shall be sutveyed on the above bM!s during periods of continuous use. Terminal surveys'shall be conducted upon cessation of an intervo! of activity.
e.
Authorized users are responslble for the maintenance of up-to-date permanent records of the results of area surveys. Records
[
will be made available to the R.S.O. upon request.
F.
Eatina and Smokina.
Eating, storing, or preparation of food and delnk in a laboratory or room where radioactive materials are handled Is not permitted.
Smoking In such laboraterles is also prohibited as is the applica-O
+io o+ co me+ic or v ether c+ivi+v hick isei<ic tiv i#cc Inhalation and Ingestion hazards.
These prohibitions may be relaxed in an office area of a labora-i tory that has been demonstrated to be free on contamination.
G.
Package Recelot Procedures.
I 1.
All Packaqes. All packages of radioactive materials will be delivered as received to the authorized user for Inspection and opening.
All packages shall be examined carefully to ascertain if the package i
has been open64, damaged, and/or contaminated in transit. Any suspected package shall not be opened until the Radiological Safety Of ficer has i
l been consulted and appropriate procedures estabilshed.
Each authorized user shall maintain a log of all radiolsotopes received, including a record of package condition and of any examina-tions, surveys or swipe tests performed on the package.
Due care shall be exercised when opening packages of radioactive materials, including the wearlag of gloves end other appropriate i
protective clothing and the use of hoods sad other equipment to protect personnel and minimize the possibility of contamination.
ilO 14 10/1/76
- x l.
l 2.
L' y,', '
el. i.
.t the i"et 91 Regulations require-
.' N e- '
r v'
.os ive - er ls.ie de -
' n.
s1 y th. 1 ensee.
monitored for radicactl, e
L..ng frecist arr i >Sonts t.,
Briefly, these,rs
'eNP na a
3
- 's t, * ) Mon ti rino for c...
pick up the pack a-at w.
tamination as svo.. Js r<
c
'en three (3)
., airer receipt if receipt !-
_t urs, on tro e or 1han
(,hteen (18) hours l' -
..orma l wot..Ing hc"rt.
Jnt='ning less tne.. me-Ifled l
Packages of radioact minimum quantity of spect 3.es are e.vem t from '...ese.iew i
r provisions. Accordingly,
.stope users on the Oklahoma State University Campus shall:
1 a.
Ascertain the q.,
.."y of each iodlolsotope which he or l
she uses that requires special,tandling procedures (See APPENDIX 8, this l
Handbook).
l b.
If the isotope requirements are in excess of exempt quantl-ties, the users shall prepare a written statement of the handling and monitoring procedures to be followed upon receipt of the package by:
1.
University Postal !tation O'
2.
University Receiving Station 3.
Other receiving point c.
One copy of the statement shall be filed with the Campus R.S.O. and one copy filed with the Campus R.P.A. unless the two are the same person.
On receipt of a purchase order the R.P.A. shall ascertain:
a.
If the user is authorized to procure the Isotope and the quantity ordered, b.
Whether or not the quantity ordered is exempt f rom special handilng and monitoring.
c.
Whether or not a written statement of handling and monitor-Ing procedures is on f'le, if a quantity in excess of the exempt quantity is ordered.
If the purchases have not complied with the above requirements, he i
will return the purchase order to the user, noting the deficiency for correction.
If the purchase is in order, he will process the order to the appropriate administrative officer, sending one copy of the isotope Order Form to the R.S.O. and retalning one copy for his files.
If special (3
\\J 15 10/l/76
e rm =
/~N he..Jling and monitoring is required, the R.P.A. shall notify the R.S.O.
that u non-exempt order has been processed.
The R.S.O. ascertains that (a) the procedures proposed by the user are appropriate and adequate, (b) that the procedures are implemented by the user.
The user is responsible for Implementing the required special handling and monitoring a.
procedures.
b.
Immediate notification of the R.S.O. If contamination is found.
c.
Maintaining written records of the receipt and monitoring results.
All incidents of non-compilance with these procedures shall be brought before the Radiological Safety Committee for action.
i Fallure to comply with these procedures could result in loss of radioisotope usage privileges by an Individual user.
O H.
Storace. Transoortino, and Handlino of Radioactive Materlaf s.
Quantitles of long-lived alpha eeltters or similar hazardous suba stances having an activity greater than I microcurie shall be securely covered during storsqe and kept in an adequately protected and venti-lated location.
Any transfer of materials must be done in such a manner as to avoid the possibility of spillage or breakage.
Double containers are recemendet I,n, such manipulations.
Any work with materials susceptible to atmospheric distribution (i.e., dusting, spillage, vaporizing, ef f ervoscence of solution, etc. )
shall be performed in adequate hoods, unless the safety of other pro-cedures has been established. Sultablo Instrumentation for each type of material to be used must be available and in operating condition in the area in use. "Sultable" In this case will mean that the Instrument will detect maximum permissible levels of contamination, radiation level, air hazard, etc., as are associated with the material (s) Involved. Ref-erence is made to National Bureau of Standards Handbooks 51 and 92.
It is recognized that in the course of some experiments there will be a need for the handling of "hot" equipment or the reworking of "hot" O
16 10/1/76
m 7
O
-equipment to conform to the requirements of the experiment..Such equipment should not be taken into non-radioactive areas until (a) all personnel within such areas are notifled of the Intent to bring li the material, (b) complete protective measures have been incorporated to assure minimum contamination to the area and to assure that any atmos-pheric distribution of the material resulting frcm the handling or re-working will be below the maximum permissible concentration value for the airborne material.
It is apparent that certain equipment will conform to the safe limits associated with fixed contamination (i.e.,
I radiation hazard), but the same material dispersed in the atmospnere would be above the safe concentration values for the material ingested.
All areas'where radiation materials and equipment are to be stored must be clearly marked with the radiation symbol and any other pertinent '
information. Such markings shall be placed in such a position that there will be no radiological risk or hazard to any personnel while l
i reading it, 1.
Weste Olsoosal (10CFR 20.301).
l.
Gene ra l. Most of the radioactive wastes that will be produced at Oklahoma State University must be stored on campus for radioactive f
decay or transported elsewhere for permanent disposal.
O It is necessary to I,eep the volume of such waste as small as practicable.
In order to make full use of concentrating techniques and of the natural decay characteristic of redloactive substances, it is important that waste be segregated and labeled as far as practical accord-Ing to type, it shall be the responsibility of all Individuals producing radloac-tive waste to be aware of disposal limits and to conform to all regul.e-ments pertinent to safe disposal.
In particular, efforts should be mad 6 l
to limit the volume of radioactive wastes and to furnish Informatlon concerning the nature of wastes being collected for subsequent disposal, i
t 1.e., (a) Isotope (s), (b) estimated activity in waste (MCI), and (c) date of estimation.
All radioactive waste materials or equipment are to be removed frcan the working area as rapidly as possible. During the time that these materials or equipment remain in the working area, shlelding should be utillzed to minimize the radiological risks and hazards.
2.
Gaseous Wastes and Air Contaminants, if the radloactive waste (s) to be disposed of is (are) in the gaseous state, the concentra-tions of of fluents at all locations to which people have access without time lim!tation shall not exceed the permissible 24-hoor Ingestion or O
17 10/1/76
O or inhalation limits for the isotope (s) as'given in 10CFR.
The discharge of particulate radioactive contamination is to be avoided by the use of filters or suitable experimental techniques. All operations with radioactive materials and equipment shall be carried out in such a manner as to minimize contamination of the air and keep the operation within the limits given in 10CFR. See Sec. 20.103 for applica-tion of this regulation.
3.
Solid Wastes.
If the radioactive waste (s) to be disposed of is (are) in the fonn of a solid, it (they) shall be placed in properly labeled containers to be stored in a radioactive waste storage area until natural. radioactive decay has reduced the contamination to background 1
level or until the waste may be sent to an appropriate waste disposal area.
It is desirable that short-lived materials be kept separate from those of long half-lives where feasible. Whenever possible the nature of
]
the material being disposed of should be fully described on a tag or 4
sticker attached to the container.
Waste cans for solid radioactive waste shall be removed when the maxi-mum safe radiation level or volume is reached. The safe radiation level is defined as the level such that no one can receive an exposure of more than 50 mrem per 8-hr day at the surface of the container.
3 All waste packages shall be carefully wrapped to preclude the possi-bility of external contamination.
For disposal by comercial contractors or decay, contact the R.S.O.
for proper approval forms and instructions.
4 4.
Liquid Wastes. Liquid waste materials are of such a nature that the responsibility for conforming to safe disposal practices rests on the individual user of radioactive materials. The feasibility of a safe liquid waste disposal program will be based upon the methods used by the individual user of radioactive isotcpes to get rid of his waste and a statement of these methods is a required part of the Isotope Authorization Form A-1.
In i
some instances, the holding of liquid waste for radioactive decay will be preferable to releasing the material into the sewage. Whenever the material is to be released into the sewage the individual must ascertain that the 1
radioactive concentration will comply with the limitations established by i
the Radiological Safety Comittee.10CFR 20.303, and the state and local l
j governments.
l Known dilution factors within the sewage system will be useful to the individual user, but it is apparent that the daytime dilution factor within the sewage network will not be the same as nighttime dilution factors. The i
i
- O 3 18-87
~
S pd appropriate dilution factor for the time of release should be utilized where practical. The possibility of several individuals using the l
sewage system dilution factor simultaneously exists.
To assure that this problem does not arise, the individual user shall notify the R.S.0. when-ever he will include the campus sewage system's dilution factor in his liquid waste disposal to conform to maximum concentration values.
If a conflict on time of disposal exists, the R.S.O. will arrange another time for the project involved.
In addition to using the sewage system's dilution factor, a dilution factor of at least 100 should always be used at the point of release.
This will minimize the possibility of a slug effect where a material might remain concentrated all the way through the sewage system.
Wastes that are liquid in form or that are to be reduced to a liquid for disposal shall be governed by the following procedures:
l The maximum concentration of radioactivity released from the Oklahoma State University sewage system shall conform with specifications in the Code of Federal Regulations.
The quantity of H-3 and C-14 which may be released into the l
sewer system may not exceed 5 Curies / year for H-3 and l
1 Curie / year for C-14. All other radioactive material, excluding H-3 and C-14, combined will not exceed 1 Curie / year.
Whenever the release of any liquid waste will exceed the maximum radioactive concentration limits for Oklahoma State University sewage, l
the waste shall be either (a) diluted below the maximum concentration f
l limits and then released. (b) held for radicactive decay to a point i
below the maximum concentration limits and then released, or (c) prepared i
l for shipment to a waste disposal area.
l l
A single disposal of liquid waste having a total radioactivity con-tent greater than 1 millicurie shall be reported in advance to the R.S.O.
Records must be kept of all liquid waste disposal and reported to the R.S.O. quarterly on the waste disposal forms provided by the Radio-l logical Safety Comittee.
J.
Personnel Monitoring.
l Personnel monitoring equipment as approved by the Radiological Safety Comittee shall be worn by all persons entering a radiation area under such circumstances that a daily whole-body exposure of 5 mrem or more is likely to be received. Signs will be posted designating the areas in which persons are required to wear personnel monitoring equip-ment.
O 19 3-18-87 l
l L
.s o
O
'l.
Responsibility for the Enforcement of Personnel Monitorinq Procedures, it shall be the respor.sibility of all individuals to wear personnel monitoring equipment within the radiation areas as' defined cbove. Supervisors are to assure compliance in the matter for the people for whom they are responsible.
2.
Visitors. The term "Visitors" is usec'. to designate all persons l
for whom personnel monitoring equipment is not provided on a routine basis, including employees of Oklahoma State University, as well as visitors from the outside. Visitors shall be given the same personnel l
monitoring coverage as regular personnel working in a radiation area.
Personnel monitoring records will be maintained in accordance with Sections 20.101, 20.102, and 20.401 of 10CFR 20.
3.
Tritium Bloassays. Personnel using activities In excess of 100 MCI and in the form of water or gas and personnel using activities in excess of 25 MCI in any other form, with the exception of tritlated foil detector devices, will be required to have a urinc assay performed within one week of single contact or weekly for repeated use (see below).
Personnel who make repoated use of activit!es in the range of 5 to l
25 MCI in any form other than water or gas will be monitored by quarterly urine assays.
In these and subsequent statements, "repeated use" Is taken to mean operational procedures involving separate contacts with the stated j
activity amounts which occur at times averaging less than a week apart.
[
Liquid scintillation counting of yrine specimens for teltlum activity is the accepted bloassay procedure.
If teltlum levels greater than 25 uCl/ liter are observed In an assay, the person involved will be j
l required to cease all use of tritium pending further Investigation.
i Levels greater than 2.5 uCI/Ilter will be considered "cause for concern" l
and imediate steps will be taken to review the mode of cperation.
l 4.
lodine Bleassays. Pe sonnel performing operations which involve only simple handling and/or dilution of lodine-125 or lodine-131 purchased In forms stabilized by the addition of a reducing agent will be required to undergo bicassays upon use of activltles in excess of 25 mCl. The essays will be performed within one week of single contact or weekly for repeated ase.
Personnel performing lodination operations using lodine-125 or lodine-131 activities in excess of 5 mCl will be required to undergo bio-assays within one week of $1ngle contact or weekly for repeated use.
Bloassays will consist of a garrna count of thyroid activity co rled O
20 10/1/76 l
l>
e-e t
o out at a hospital approved by the Radiological Safety Comittee. A detectable thyrold borden will be treated as "cause for concern".
The R.S.O. will be furnished a copy with8n 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the record of each bloassay showing levels above the limits stated above; a perma-nent record will be kept of all bloassays even though the results may be negative. Persons performing the bicassays and the method of pro-cedure will have the orlor approval of the R.S.O.
- eene*****enen**enene*******u********************************en****
r i
Note: These figures apply only to persons 18 years of age or above, J_n, this reaard of any other Involving radiation exposure of persons 4
n under 18 years of age, refer to 10CFR20. Background levels also will be ostablished, as stated above, for persons whose duties r6 quire theti to work In an area where they likely would Ingest material re-lersed in case of accident.
.*ene.*********een***enene.....e** e*******=******e****ewenseene***e K.
Survey Instruments--Access and Calibration.
))
Applications for permission to use radioisotopes will include a list f
of equipment available for the detection of radioactivity and a statement of check and calibration procedures to be followed. Survey Instruments i
will be calibrated at least annually. The R.S.O. will ascertain through Inspections and by quarterly survey statements of the authorized users 4
that callbrations are maintained for the required survey Instruments.
A local calibration service has been established to assist those users who do not have adequate calibration sources and/or f acilities.
j i
L.
Responsibility for Tralnino In Health Physics.
1 L
j lt shall be the responsibility of department heads to ascertain that
)
3 personnel working in radiation areas are Indoctrinated in these procedures.
l j
Personnel without tralning in Health Physics or experience in safety pro-l 1
cedures In handling radloactive materials should receive this Indoctrina-i i
tion under the close supervision of an adequately experienced Individual.
[
l i
i I
i l
i!O
,1 21 10/1/76 I
t O
r APPENDIX A SELECTED BIBLIOGRAPHY ON RADIOLOGICAL CONTROL PPOCEDURES l
L Part 20, "Standards for Protection Against Radiation", U. S.
Nuclear Regulatory Connission, Title 10, Chapter 1, Code of Federal Regulations (10 CFR20 In text).
"Report of ICRP Committee 11 on' Permissible Dose for Internal Radiation (1959)", Health Physics 3_,
1-380 (June, 1 %0).
U.S.N.R.C. Regulatory Guides on Occupational Health (Olvision 8).
l a
-[
Radiological Health Handbook, U. S. Department of riealth, Educa-j tion, and Welfare (PHS) (Revised 1970).
The National Institutes of Health Radiation ' Safety Guide, U. S.
Departmenv of Health, Education, and Welf are (PHS), OHEW Publication No. (NIH) 73-18 (Revised 1972).
j O
A number of useful booklets are available as Reports of the i
National Council on Radiation Protection and Measurements (NCRP)
]
and/or National Bureau of Standards (NBS) Handbooks. Some examples are l
NBS-48 Control and Removal of Radioactive Contamination in Labora-i tories (1951).
5 NBS-49 Reccmmendations for Waste Disposals af Phosphorus-32 and 4
lodine-131 for Medical Users (1951).
i NBS-51 Radlological Monitoring Methods and Instruments (1959).
j NBS-53 Reccanendations for the Olsposal of Carbon-14 Wastes (1953).
NBS-56 Safe Handling of Cadavers Containing Radioactive isotopes j
(1953).
I NBS-57 Photographic Dosimetry of X-and Ganvna-Rays (1954).
1 NBS-59 Permissible Oose f rom External Sources of lonizing Radiation (1954).
NBS-63 Protection Against Neutron Radiation up to 30 Milllen j
Electron Volts (1957).
i O i
j 22 10/1/76 l
i 1
r 4.
l l
0 j
l 4 i NBS-66 Safe Design and Use of Industrial Beta-Ray Sources (1958).
NBS-69 Maximum Permissible Body Burden and Minimum Permissible Con-centrations of Radionucilces (1959).
j NBS-72 Measurenent of Neutron Flux and Spectra for Physical and Biological Applications (1960).
NBS-73 Protection Against Radiations f rom Soa' led Gema Sources (l960).
~
i 4
f NBS-75 Meaaurement of Absorbed Dose of Neutrons, and Mixtures of Neutrons and Gamma-Rays (1961).
NBS-78 Report of the international Commission of Radiological Units and Measurements (1961).
NBS-80 A Manual of Radloactivity Procedures (1961).
y NBS-92 Safe Handling of Radioactive Materials (1964).
I l
NBS-93 Safety Standard for Non-Medical X-ray' and Sealed Gamma-Ray i
Sources Part I, General (1964).
4 j '
NBS-97 Shielding for High-Energy Electron Accelerator. Installations (1964).
NCRP-32 Radiation Protection in Educational Institutions (1966).
i j
NCRP-39 Basic Radiation Protection Criteria (1971).
1 3
Many reference books and/or textbooks are available and in ecmon use. Several that may prove helpful are:
j Elemntary Radiation Physics. G. S. Hurst and J. E. Turner (John Wiley and Sons, Inc. 1970).
I l
l Introduction g Health Physics. Herman Comber (Pergamon Press,1969).
l 2
i i
Nuclear _ Radiation Physics (4th Edition), Ralph E. Lapp and Howard L.
l Andrews (Prentice-Hal1. Inc. 1972).
{
j Thermoluminescent Oostmetry. J. R. Cameron, N. Sunthara t ingam, and G. N. Kenney (University of Wisconsin Press, !968).
1 I
i I
i i
\\
O 1
(
)
23 10/1/76 I
i
i
/~'i
(,/ -
APPENDIX B QUANTITIES OF RADI0 ISOTOPE PACKAGES EXEMPT FROM SPECIAL HANDLINGANDMONITORING(10CF20.205) 1.
Packages Containing Radioisotopes in Liquid Form (a) Hydrogen-3 10 mci Carbon-14 10 mci Sulfur-35 10 mci r
lodine-125 10 mci (b)
Isotope Transport Group Exempt Quantity Limit Antimony-125 III 1 mci 4'
Barium-133 II 0.1 mci j
Bismuth-207 III 1 mci 1
Calcium-45 IV 1 mci
)
t.esium-137 III 1 mci
~
Chlorine-36 III 1 mci Chromium-51 IV 1 aCi Cobalt-60 III 1 mci O
Iodine-131 III 1 mci i
j Iron-59 IV 1 mCl i
Krypton-85*
!!!., VI 1 mci 1
Lead-210 0.1 mci 1
Manganese-54 IV 1 mci Nickle-63 IV 1 mci Phosphorous-32 IV 1 mci Polonium-210 1
0.01 mci i
Potassium-42 IV 1 mci Radium-226 I
0.01 mci i
Rubidium-86 IV 1 mC1 Selenium-75 IV 1 mci
]
Sodium-22 III 1 mci Strontium-90 0.1 mC1 4
I
]
Tantalum-182 1 mci Zirconium III 1 mci f
i I
1 i
- Kr-85 uncompressed, i.e., pressure not exceeding one atm is Transport Group VI.
l
)O 3-18-87 24 1
\\
\\
i n
1 e
t i
-2.
Radioactive Material in Other Than Liquid Form Transport Group I
0.001 Ci l
II 0.05 Ci III 3 Ci IV 20 Ci V
20 Ci i
VI 1000-Ci l
i t
3.
Short Half-Life Material j
Packages containing radio-nuclides with half-lives-f of less than 30 days and a total quantity of no more than j
i 1000 mci are exempt.
t I
i I
r i
1 l
i O 1
i l
s i
\\
4 r
i i
1 l
3 i
i l
1 i
i t
i 1
l 1
1 1
O i
25 a
i t
3-18-87
- l
\\
l 1
s l*
O o-i APPENDlX C RADIATION ACCIDENT PROCEDURES i
t i
1 Emergencies wllI generally be In the nature ~of spllIs, f f res, or explosions, as a result of which radioactive materials are spread around the Installation.
In the event of such OlSSEMINATION OF RA0lO-3 ACTIVE MATERIALS, the following general procedures are given as a-guide to be adapted to the speclfic. nature of the emergency.
l.- Minor Sollis involvino No Radiation Hazard to Personnel.
(a) Notify all.other persons in the room at once.
J (b) Permit only the minimum number of persons necessary i
to deal with the spill into the area.
(c) Confine the f, pill Innediately.
t 1.fould Sollist Don protective gloves Orop absorbent paper on spill O
l Ory Sollist l
f Don protective gloves Oampen thoroughly, taking care not to spread tha contamination l
i (d) Notify the faculty nember in charge of the labora-tory and the Radle N cal Safety Officer as soon i
as possible.
(e) Monitor all persons involved in the spill and cleaning.
1 (f) Decontaminate the area according to the directions of the Campus Radiological Safety Officer.
l (g) Permit no person to resume work in the area until l
a survey Is made, and approval of the Radiological l
Safety Of Heer Is secured.
l (h) Prepare a complete history of the accident and
[
subsequent activity related thereto for the records i
of the Radiological Safety Officer.
j l
l 1
O 26 10/1/76 i
?
i
.?
O Q
2.
Major Sollis involvino Radiation Hazard to Personnel (a) Notify all persons not Involved in the spill to j
vacate the room at once.
(b1 If the spill is liquid, and the hands are pro-tected, right the container.
(c)
If the spill is on the skin, flush thoroughly.
(d)
If the spill is on clothing, discard outer or protective clothing at once.
(e) Shut of f air conditionlej units serving the l a boratory.
(f) Vacate the roons.
(g) Notify the f aculty member In charge and the Radiological Safety Officer as soon as possible.
(h) Take immediate steps to decontaminate personnel involved, as necessary.
(I) Decontaminate the area por the recommendations of the Radiological Safety Officer.
(Personnel involved in decontamination must be adequately protected.)
(J) Monitor all persons Involved in the spill and cleaning to determine adequacy of decontanina-tion.
O' (k) Permit no person to resume work in the area until a survey is made and approval of the Radiological Safety Officer is secured.
(1) Prepare a complete history of the accident and subsequent activity related thereto for the records of the Radiological Safety Officer.
3.
Accidents involvinq Radioactive Dusts. Mists. Funes, Orqanic Vapors and Gases (a) Notify all other persona to vacate the room Immediately.
(b) Hold breath and vacate room.
(c) Shut of f air conditioning by master switch.
(d) Notify the f aculty member in charge and the Radiological Safety Of ficer at once.
(e) Ascertain that all doors giving access to the room are closed and post conspicuous warnings or guards to prevent accidental opening of doors.
(f) Report at once all known or suspected Inhalations of radioactive materials.
(g) The Radiological Oafety Officer shall evaluate the hazard and the necessary safety devices for safe 1
re-entry.
O 27 10/1/76 W.
m ge c
(h) Determine the cause of contamination and r ectif y the condition.
(I) Decontaminate the area.
(J) Perform air survey of the area before permit +5ng work to be resumed.
(k) Monitor all persons suspected of contamination.
(I) Prepare a canplete history of the accident and subsequent activity related thereto for the records of the Radiological Safety Officer.
4 Injuries to Personnel Involvinq Radiation Hazard (a) Wash minor wounds immediately, under running water, while spreading the edges of the gsC).
(b) Report all radiation accidents to personnel l
(wounds, overexposure, Ingestion, Inhalation) to the f aculty member in chargo and the Radio-logical Safety Of ficer as soon as possible.
(c) Call a physician.
(Stuaent Hospital and Clinic).
(d) Permit no person involved in a radiation injury to return to work without the approval of the Redlological Safety Officer tnd the attendant
(
)
p*ysician.
I
's /
(e) Prepare a complete history of the accident and subsequent activity related thereto for the records of the Radiological Safety Officer.
l l
1 l
l
\\
l 1
i
(~')
l 28 10/l/76 U(J7//