ML20248G814
| ML20248G814 | |
| Person / Time | |
|---|---|
| Site: | 07000927 |
| Issue date: | 05/26/1998 |
| From: | Lodhi S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20013J968 | List: |
| References | |
| 565206, NUDOCS 9806050349 | |
| Download: ML20248G814 (50) | |
Text
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u.s. NUCLEAR Recut.AToRY CoMMISstoN Amendme t No. 05 MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code cf Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee in accordance with the Application dated April 27,1994,
- 1. Southwestern Oklahoma State University
- 3. License number SNM-873 is amended in Chemistry Department its er(tirety to read as follows:
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2.100 Campus Drive
- 4. ExpiratioE dife 1%ay 31,2008 Weatherford, Oklahoma 73096 h
- 5. Docket No. 070-00927
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Bypoduct, source, and/or sp,ecial J Chemicaland/or ysical form f ' i 8.
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\\SealedS urce"(Nucle ~ara A. 32. grams (One sealed source ylaterfais and Equipment Q/
not to exceed 2 curies)
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< CON,0(TIONS
- 10. Licensed material may be used only at the licensee's facilities located in Chemistry Pharmacy and Physics (CPP) Building of Southwestern Oklahoma State University, Weatherford, Oklahoma.
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- 11. Licensed material shall be used by, or under the supervision of Dr. Blake 1. Sonobe, Dr. Charles Rogers, Dr. Ray C. Jones, Dr. Garabad Armoudian, or Dr. Karen McGurk.
- 12. The Radiation Safety Officer for this license is Dr. Blake 1. Sonobe.
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- 13. Licensed material shall not be used in or on human beings.
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- 14. Sealed sources or detector cells containing licensed material shall not be opened or source from source holders by the licensee.
- 15. The licensee shall conduct a physical inventory every six months, or at other interval approved by NRC, to account for all sealed sources and/or devices received and possessed under the license.
9806050349 980526 PDR ADOCK 07000927 C
PDR OFFICIAL RECORD COPY ML40
s NRc FORM 374A u.s.
LEAR REGULATORY Commission PAGE 2 of 3 PAGEs Ucense Number SNM-873 MATERIALS LICENSE ordet or Reference Number SUPPLEMENTARY SHEET 0B00927 Amendment No. 05 l
- 16. A.
Sealed sources and detector cells containing licensed material shall be tested for leakage end/or contamination at intervals not to exceed six months or at such other inten,als as are specified by the certificate of registration referred to in 10 CFR 32.210, not to exceed three years.
B.
Notwithstanding Paragraph A of this Condition, sealed sources designed to emit alpha particles shall be tested for leakage and/or contamination at intervals not to exceed three monthc.
months prior to the transfer, assal;ed s[anbroknk ig ttjat a leak test has been made within six C.
In the absence of a certiScate from a t f
ource or detector bell feceived from another person shall not be put into use untiltested J"
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Each sealed source fatibted by the licensee shall be inspected ab tested for construction defects, D.
leakage, and contam,fnation prior to any use er transfer as a sealed s(urce.
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Sealed sources a ketectb.eill eed not beleak testedi (I) they containT$$ly hydrog r1 M Q(orIN 5
(ii) they contain ryly a radios ve
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(iii) the half-life ofjhe iso p
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D) they contain n$(more t8an igrocurjec4ty[ta$nd/or gam (pa emitting material or not (iv) o than 10 microcuries,pf al%
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gr (v) they are not designedh emit alpha parti es, are in storayehand are not being used. However, when they are removed from. storage for use or transfer to another person, and have not been tested within the required ledi?tesDpterva' l; th[i)Tshhifbe tested befere use or transfer. No sealed source or detector cell shall be s'to'ted for a period of more than 10 years without being tested for leakage and/or contamination.
F.
The test shall be capable of detecting the p esence of 0.005 microcurie of radioactive raterial on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, a report shall be filed with the U.S. Nuclear Regulatory Commission and the source or detector cell shall be removed immediately from service and decontaminated, repaired, or disposed of in accordance with Commission regulations. The report shall be filed within five days of the date the leak test result is known with the U.S. Nuclear Regulatory Commission, Region IV, ATTN: Director, O! vision of Nuclear Materials Safety,611 Ryan Plaza Drive, Arlington, Texas 76011. The report shall specify the source or detector cell involved, the test results, and corrective action taken.
G.
The licensee is authorized to collect leak test samples for analysis by Atomic Energy Industria! Labs, Houston, Texas. Attematively, tests for leakage and/or contamination may be performed ta/ persons specifically licensed by the Commission or an Agreement State to perform such services.
i NRc FORM 374A.
u.s. IRLEAR REGULATORY Cnnanasemanna PAGE 3 ' of 3 PAGES Woonee Number SNM-873 MATERIALS LICENSE Dociet or Relorence Number SUPPLEMENTARY SHEET 070-00927 Amendment No. 05
- 17. The licensee is authorized to hold radioactive material with a physical half-life of less than or equal to 120 days for docay-in-storage before disposal in ordinary trash, provided' A.
Waste to be disposed of in this manner shall be he'd for decay a minimum of ten half-lives.
B.
Before disposal as ' ordinary trash, the waste shall be surveyed at the container surface with the appropriate survey instrument set on its rpqst we scale and with no interposed shielding to
!o determine thatits radioactivity
% Wati lbi background. All radiation labels shall be removed or obliterated.
f C.
A record of each such d al permitted under this License Cw u ' i shall be retained for three years. The record musi ude the date of disposal, the date on byproduct materialwas -
placed in storage, th(, radionuclides disposed, the survey instrument
, the background dose rate, the dose rate measured a surface of each waste contaim;Tnd hefname of the individual who performed the dis %s61.
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- 18. Except as' specifically vided islicon shall et its program in accordance with the s on ocedured contained.jhe documents, including any enclosures, listed p. T
%',s rpgulati6ns shall govem unless the statements, representations, a
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- reWication and' correspondence are more i
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Applic'ation dated Ah 7,1 f' '
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Letter dated May 18, -
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Original signed by Sattar Lodhi, Ph.D.
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Nuclear Materials Safety Branch 2 Division of Nuclear Materials Safety Region i King of Prussia, Pennsylvania 19406 1
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May 26,1998 Docket No. 070-00927 License No.
SNM-873 Control No. 565206 Joe Anna Hibler, Ph.D.
President Southwectem Oklahoma State University 100 Campus Drive Weatherford,OK 73096 Dear Dr. Hibler-This refers to your request for renewal of your NRC license. Enclosed with this letter is the renewed license. Please review the enclosed document carefully and be sure that you understand ai! conditions. If there are any errors or questions, please notiiy the U.S. Nuclear Regulatory Commission, Region i Office, Licensing Assistanco Team, (610) 337-5093 or 5239, so that we can provide appropriate corrections and answers.
The NRC is required to have your Taxpayer Identification Number in order to make payments (refunds). The self-addressed, stamped NRC Form 531, " Request for Taxpayer identification Number,"is enclosed.
Please be advised that your license expires at the end cf the day, in the month, and year stated in the license. Until your license is terminated, you must conJuct your program involving byproduct materials in accordance with the conditions of your NRC license, representations made in your license application, and NRC regulations. In particular, note that you must 1.
Operate in accordance with NRC regulations 10 CFR Par 119, " Notices, instructions and Reports to Werkers; Inspections," 10 CFR Part 20, " Standards for Protection Against Radiation," and c'her applicable regulations.
2.
Notify the NRC no later than 30 days after the mailing address on the license changes (no fee is required if the location of byproduct material remains the same).
3.
In accordance with 10 CFR 30.56(d), notify the NRC, promptly, in writing, and request termination of the license when you decide to terminate a?! sctivities involving materials authorized under the license.
4.
Request and obtain a license amendment before you:
a.
order byproduct material in excess of the amount, or radionuclides, or form different than authorized on the license; or b.
add or change the areas of use, or address or addresses of use identified in the license application or on the license.
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'2 SaA;z::: n Oklahoma State University
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- Receive wntion approval from the NRC prior to any change in ownership of your.
5.
p organization, in accordance with 10 CFR 30 34(b).
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' 6.
- Submit a complete renewal applice+ inn with proper lee or terminabon request at least 30 :
l; days before the expirabon date of your license. You will receive a reminder nobce L
approximately 90 days before the expiration date. Possession of byproduct material L
after your license expireo is a violation of NRC reguls', ions. A liconee will not normally-U1 be trxewed, except on a case-by-case basis, in instances where licensed material has
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never been possessed or need,
~ In addition, please nole that NRC Form 313 requires the applicant, by his/her signature; to venfy that the applicant understands that all statements contained in the application are true and h
correct to the best of the applicant's knowledge The signatory for tho' apphcahon should be the '
L licensae or a certifying official of the licensee rather than the Radiation Safety Officer or a -
consultant <
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..You will be periodically inspected by the NRC. Failure to conduct your program in'accordance.
with NRC regulabons, license conditions, and representations made in your license application
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and supplemental correspondence with NRC will result in enforcement action against you. This -
ll could include issuance of a notice of violation, or imposition of a civil penalty, or an order q
Y suspending, modifying or license as specified in the " General Policy and Procedure for NRC l-Enforcement Actions" (Enforcement Policy), NUREG 1600.
Since serious consequences to employees and the public can result from failure to comply with.
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NRC requirements, prompt and vigorous enforcement actions will be taken when dealing with licensees who do not achieve the necessary meticulous attention to detail and the high standard l
. of compliance which NRC expects of its licensees..
Thank you for your cooperation.
d Sincerely, l.
.i Original signed by Sattar Lochi, Ph.D.
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Sattar Lodhi, Ph.D.
Health Physicist Nuclear Materialc Safety Branch 2 Division of Nuclear Materials Safety i
Enclosures:
=1..
Amendment No. 5.
2.-
10 CFR Parts 19,20,21,30,70,170, and171 l
3.
NRC Forms 3,313, and 531 -
4.
Section 206 of the Energy Reorganization Act of 1974
' 5.
NUREG.1600, General Policy and Procedure for NRC Enforcement Actions (Enforcement Policy)
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Southwester Oklahoma State University cc:
. Blake 1. Sonobe, Ph.D., Radia6on Safety Officer i
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,c DOCUMENT NAME: G:ONMSDOCWORKLICLTRESNM873 16196584-To esosive a espy of thle sleeument, iruheets bi the bes: 'C' = Copy w/o ottschlenel
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OFFICE DNMS/RI lN DNMS/RI l
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NAME SLodhi k? /
DATE 05/26/98 "~
05/ /98 05/ /98 05/ /98 OFFICIAL RECORD COPY l
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[ Oklahoma State University Department of Chemistry May 18,1998 Dr. Sattar Lodhi Division of Nuclear Materials Safety Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA' 19406-1415
Dear Dr. Lodhi:
The following information is provided in response to your requests applicable to renewal of Nuclear Regulatory Commission License No. SNM-873.
- 1. The authorized users of the neutron source (neutron howitzer) are:
Dr. Blake 1. Sonobe, Radiation Safety Officer, Chairman of the Radiation Safety a,
Committee, Associate Professor and Chemistry Chairman.
Education: B.S. (Chemistry), US F Academy,1970; M.S. '(Nuclear Chemistry), Texas A&M University 1978; Ph.D' (Physical Organic Chemistry), University of California, Davis,1985. Thesis work included two years of research using the cyclotron at Texas A&M studying inner-shell ionization processes.
Experience: Radiation Protection Officer (Chemistry Department, USAF Academy) 1978-1981; member of the Base Radiation Safety Committee (USAF Academy) 1978-1981; taught Nuclear Chemistry (USAF Academy) 1978-1981 and 1984-1990.
Menber of the j
Southwestern faculty since 1990.
Experience with neutron sources: Neutron activation experiments in physical chemistry at the USAF Academy from 1984-1990, and in general chemistry at SWOSU from 1990 to present.
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- b. Dr. Charles Rogers, Professor of Physics.
Education:
B.A. (Physics), University of Utah, 1965; M.S. (1968) and Ph.D.
(Experimental Nuclear Physics), Oregon State University,1968. Dissertation work included four years of research using the 17 MeV cyclotron, production of isotopes, and monitoring radiation.
Experience: Post-doctoral research in low energy physics at Louisiana State University (1971-1972) included preparation of sources for irradiation, handling radioactive sources in 100 campus Drive Teatherford. okichoma Dm63098 (580) nm66. rax (580) nm95 886AO[0 0FFICIALRECORDCOPY MLto MAY 2 3 BG8
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source preparation and performing p-and y-ray spectroscopy. Member of the Southwestern Faculty since 1972 and teaches general and nuclear physics.
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Experience with neutron sources: Neutron activation experiments in physics at SWCSU from 1972 to present.
- c. Dr. Ray C. Jones, Professor of Physics.
Educatior;: B.S., Ph.D. (Physics), Louisiana State University (1967). Research included use of neutrons produced by D + T reactions. Has handled neutron sources up to 1 Ci.
Experience: Post-doctoral research at the University of California, Riverside (1967-1969).
Member of the Southwestern faculty since 1969 and teaches general physics.
I Experience with neutron soumes: Used neutron sources in graduate and post-doctortl work and in neutron activation experiments in physics at SWOSU from 1969 to present.
- d. Dr. Garabed Armoudian, Professor and Chairman of the Physics Department.
Education:
B.S. American University of Beirut; Ph.D. (Physics), Louisiana State University,1966.
Experience: Post-doctoral research at Columbia University (1966-1968) in high energy theoredcal physics. Member of the Southwestern faculty since 1968 and teaches general physics.
Experience with neutron sources:
Neutron activation experiments in. phyr.ics at Southwestern since 1968.
e.' Dr. Karen McGurk, Associate Professor of Chemistry Edecation:
B.S. (Chemistry), Southwestern Oklahoma State University,1972; Ph.D.
. (Chemistry and Biochemistry), Oklahoma State University,1976.
Experience: Isotope labeling experiments during graduate studies (1972-76). Memberof the Southwestern faculty since 1977.
l Experience with neutron sources: Neutron activation experiments in general chemistry at SWOSU since 1977.
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l At the beginning of the academic year, each user is required to review a summary of applicable
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l regulatory requirements and approved procedures for handling radioactive samples.
- 2. Licensed materials will only be used by or under the supervision of the individuals listed above.
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- 3. Use of the neutron source is very limited and access is controlled by the Radiation Safety
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Officer (howitzer is housed in a specially keyed lab). The neutron howitzer was used a total of i
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(d seven times during the last academic year. Prior to each use, the RSO will review the procedures l
for using the howitzer and precautions in handling activated samples with the user.
- 4. All personnel handling radioactive materials will be provided initial radiation safety tr:dning prior to handling radioactive materials and periodic refmsher training themafter.
- 5. The duties and responsibilities of the Radiation Safety Officer shall include:
- a. To annually review and update local guidelines and procedures for mceipt, use, and dispocal of radioactive materials.
- b. To ensure compliance with all applicable guidelines and regulations.
c.
To assess radiological hazards and prescribe and ensure implementation of appropriate radiation safety precautions.
- d. To ensure the use of licensed materials is by or under the dimet supervision of individuals specifically listed on the license.
- e. To ensure that all users (where appropriate) wear personnel monitoring equipment when using licensed materials.
- f. To ensure that licensed materials am properly secured against unauthorized removal at all times.
- g. To perfonn routine inspections of all laboratories using or storing licensed materials.
h.
To ensure the terms and conditions of the license are met and all required records maintained.
- i. To report to the Radiation Safety Committee annually all activities and results of surveys of the preceeding year.
6.
The personnel monitoring program will be in accordance with 10 CFR 20.1502.
Our monitoring records show that continuous exposure in very close proximity to the neutron source does not exceed 700 mrem per year.
7.
Personnel monitoring devices will be exchanged at the frequency mcommended by the processor. Our processor, Atomic Energy Industrial Laboratories of the Southwest, Inc., in Houston, TX, is a NVLAP-accredited processor.
8.
We will have available for use a properly operating neutron survey meter and all survey instruments will be calibrated by a vendor who is currently licensed by the NRC or an Agreement State to perfonn these calibrations.
9.
Our work is currently limited to non-volatile solids. However, should liquid samples be exposed to irradiation we follow the guidelines listed below.
Procedures for llandling Irradiated Liquid Samples
- a. All irradiated liquid samples will be handled in the fume hood in CPP-222.
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- b. Samples should be kept confined in c.n air-tight container when not in use.
- c. Users must wear approved gloves ar.d protective clothing when handling liquid samples.
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- d. Activity of the samples should be determined immediately following irradiation. Accurate records of use and disposition ofirradiated materials must be maintained.
- e. Any spills must be cleaned up and reponed immediately to the Radiation Safety Officer. 'Ihe Radiation Safety Officer will survey the ama to determine the level of reridual radiation and l
take appropriate actions to limit exposure to other personnel.
- f. All cleanup materials shall be properly disposed in an approved container for radioactive wastes.
- g. Upon completion of work with irradiated materials, all samples shall be stored in appropriate locations or properly disposed. No radioactive materials will be left in the hood when not in use.
- 10. After use of radioactive samples, the Radiation Safety Office will survey the work area to determine contamination. Surveys will include swipe tests of the area. Our background level in the lab and the hood is typically 0.1 to 0.2 mrem /hr. We consider any madings twice the background excessive and the area will be again decontaminated. The work ama will not be used until the radiation level is less than twice the background.
I1. We do not perform any work nor have plans to perform work which generates mdioactive waste. However, should radioactive wastes be generated, we will follow the guidelines below:
Procedures for Storage and Disposal of Radioactive Wastes
- a. All radioactive wastes will be properly labeled with identity of waste material, date material was declared waste, activity of waste, and estimated mass of waste.
- b. Radioactive waste will be kept in protected storage for a minimum of at least ten half-lives of the longest lived radioisotope. Appropriate shielding will be in place around the waste. The waste will be maintained in a low traffic area.
- c. After ten half-lives, the waste will be surveyed in a low background environment with a low-level survey meter with all shielding removed.
- d. If the radiation of the waste is at background, the materials will be discarded as normal trash.
If the radiation of the waste is above background, the waste will continued to be stored until the radiation is at backgmund levels or be disposed of as radioactive waste according to 10 CFR 20.1001 to 20.2401.
- e. When disposing as normal wastes, all radioactive material labels will be removed or the waste clearly labeled as no longer radioactive.
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- f. Should radioactive wastes be disposed prior to ten half-lives, these wastes will be transferred only to an authorized recipient.
- 12. 'Ourleak test service provider, Atomic Energy Industrial Laboratories of the Southwest, Inc.,
confirms (by telephone) they currently hold license from the State of Texas to provide this service.
If you have other questions concerning this license, please call me at (580) 774-3264. We are l
curnstly on break which permits me more time to attend to these matters.
Sincerely,.
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k Blake I. Sonobe Radiation Safety Ofr er 565266 j
OFFICIALRECORDCOPY mL 10 l
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t April 23,1998 Docket No.
070-00927 License No.
SNM4/3 i-Control No.-
565206 r
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' Joe Anna Hibler, Ph.D.
~ President South vestern Oklahoma State University
' 100 Campus Dnve Weatherford,OK 73096
Dear Dr. Hibler:
This concerns the application for renewal of your material license and our letter dated March 9, 1998, in which we nctified you that the application was deficient and that certain additional l
Information was rnquired.- To date, we have not received a response to our letter.
if we do not receive a reply within 30 days, it may be necessary to deny your application and terminate your license. Such action would require that you divest yourself of all recensed.
material.
l Sincerely, Original signed by Sattar Lodtsi, Ph.D.
Sattar Lodhi, Ph.D.
Health Physicist Nuclear Materials Safety Branch 2 Division of Nuclear Materials Safety cc:
Blake Sonobe, Ph.D., Radiation Safety Officer I
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DOCUMENT NAME: G:\\DNMS\\DOCWORKtlCLTRESNM873 13899028 To rnoelve e copy of this document, inacoes in the bos: *C" = Copy w/o attach /enct
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GATE 04/23/98 04/-/98 04/ /98 04/ 198 OFFICIAL RECORD COPY -
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March 9,1998 Docket No.
070-00927 License No.
SNM-873 Control No. 56520S Joe Anna Hibler, Ph.D.
President Southwester Oklahoma State University 100 Campus Drive Weatherford, OK '73096
Dear Dr. Hibler:
This is in reference to your Application dated April 27,1994 requesting to renew Nuclear Regulatory Commission License No. SNM-873. In cider to continue our review, we need the following additionalinformation:
1.
The documentation of training and experience of your proposed authorized users does not include their training and experien,ce of using a neutron source. Please provide documentation that demonstrates that each of your authorized users listed in item 8 of your application has had the experience of using a neutron source, handling of activated samples, and is familiar with the current applicable regulatory requirements, including those of 10 CFR Pad 20 (enclosed). Please specify the locations where this experience was acqu; ed by each of these individuals.
2.
You indicated that the Radiation Safety Committee may approve other faculty members to use the neutron source. Please note that the NRC must review qualifications and experience of all users before they are approved as authorized users on a specific license of limited scope. Please confirm that licensed material will only be used by, or under the supervision of the individuals listed on your NRC license. Another faculty member may use licensed material under the supervision of any one of the authorized users listed on your NPC license.
3.
Your application die not include training program for individuals who will use the neutron source or handle the activated samples. Please submit your training program that should include provisions for initial and periodic refresher training of these individuals.
The training should also include methods to minimize exposure to radiation and a review of current regulatory requirements.
4.
Please confirm that all personnel who will handle radioactive material will be provided initial radiation safety training prior to handling the radioactive material, and periodic refresher training thereafter.
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J. Hibler 2
- Southwester Oklahoma State University l
5.
Submit a description of the duties and responsibilities of your Radiation Safety Officer.
j The typical duties of a Radiation Safety Officer would be:
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To assess radiological hazards and prescribe, and ensure the implementation of, l
a.
appropriate radiation safety precautions.
b.
To ensure that the use of licensed material is by or under the direct supervision of individuals specifically listed on your license.
i To ensure that all users (where appropriate) wear personnel monitoring c.
equipment when using licensed materials.
d.
To ensure that licensed materials are properly secured against unauthorized removal at all times when notin use.
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To perform routine inspections of alllaboratories using or storing licensed e.
materials.
f.
To ensure that the terms and conditions of your license are met, and that all required records are maMained..
6.
Requirements for personnel monitoring are stated in 10 CFR 20.1502. Please confirm l
that your personnel monitoring program will be in accordance with tha requirements i
stated in 10 CFR 20.1502 7.
Please confirm t:1at personnel monitoring devices will be exchanged at the frequency recommended by the processor and will be processed and evaluated by a NVLAP-accredited processor as required by 10 CFR 20.1501(c).
8.
Please confirm that you will also have available for use; a properly operating neutron survey meter and all survey instruments will be calibrated by a vendor who is currently licensed by the NRC or any Agmement State to perform these calibrations.
9.
Please describe your procedures for handling irradiated liquid samples, and all volatile radioactive material. These procedures must include steps to minimize airborne radioactivity in the work place as well as releases into the environment. Please confirm that protective clothing will be used while handling liquid samples.
10.
Please confirm that appropriate surveys (!ncluding wipes after the use of liquids) to determine contamination of work areas will be conducted after each use of radioactive samples, and the affected areas will be decontaminated before these areas are allowed to be used for other work. Please specify your trigger levels.
t i_E_________.________._.______._.__
a J. Hibler -
. 3
- Southwestern Oklahoma State University '
11.
You stated that currently you do not generate any radioactive waste. However, your
- plans include possible use of liquid samples and other material. Please describe your procedures for handling radioactive waste that may be generated as a result of such activities. NRC regulations authorize holding of short lived radioactive waste for decay in storage if you wish to hold radioactive waste for decay,' please describe your
' procedures for holding radioactive _ waste for doct,y and its eventual disposal after decay -
Tne NRC requires that such waste be held for decay for at least 10 half-lives of the longest lived radioisotope in the waste, and the decayed waste be surveyed prior to
! disposal to ensure that it has decayed to background level. Please confirm that radioactive waste will only be transferred to an authorized recipient.
.12.
Please confirm that your leak test service provider (Atomic Energy Industrial Labs of the Southwest, hc.) currently holds license from State of Texas to provide this service.
We will continue our review upon receipt of this information. Please reply in duplicate to my
. attention at the Region i Office and refer to Mail Control No.- 565206. If you have any technical questions regarding this deficiency letter, please call me at (610) 337-5364.
In order to continue prompt review of your application, we request that you submit your
. response to this letter within 30 calendar days from the date of this letter. - - -
Sincerely,
. Ohginal signed by Sattar Lodhi, Ph.D.
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Sattar Lodhi, Ph.D.
Health Physicist Nuclear Materials Safety Branch 2
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Division of Nuclear Materials Safety
Enclosure:
10 CFR Parts 19,20, and 30 cc:
. Blake Sonobe, Ph.D., Professor 1
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- O J. Hibler 4
Southwester Oklahoma State University l
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DOCUMENT NAME: G:DNMSDOCWORKDEFLTROKLAHOMA.DEF 10880278 To rooelve e espy of thie document. Indeste in the boa: *C" = Copy w/o attach /enci "E" = Copy w/ ettschlenci
- N* = No copy OFFICE -
DNMS/Rk lN DNMS/RI l
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' i NAME SLodN W DATE 03/09/98 03/ /98 03/ /98 03/ /98 OFFICIAL RECORD COPY ML 10 l
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.________._______._________.._.______._._________________.___a
/g pstriuk UNITED STATES
%f CLEAR REGULATORY COMMISSi REGION IV I
611 RYAN PLAZA DRIVE, SUITE 400 l
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[
ARLtNGTON, TEXAS 760118064 MAY 9 1994 i
' Southwestern Oklahoma State University Docket No. 070-00927 ATTN: Joe Anna Hibler, President License No. SNM-873
.100' Campus Drive Control No. X65206 Weatherford, Oklahoma 73096 5
Gentlemen-This is to acknowledge receipt of.your application for renewal of the special nuclear material license identified above. Your application is deemed timely filed and, accordingly, the license will not expire until final action has been taken by this office.
Any correspondence regarding the renewal application should reference the control number specified and your license number.
Sincerely, -
originalSigned By sinie crusaynski Billie Gruszynski (Ms.)
Nuclear Materials Licensing Branch l
l-l OfflCIALRECORD00PY Mt. fd
]
MAY 9 1994 p.-
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I RIV:NMLB BG uszynski J
3/Q/94 L---------_
s, o)Se southwestern
~
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~ Oklahoma State University i
l OfIlce of the President April 28, 1994
-- @R0WRm Material Radiation Protection Section
,4 a
U.S. Nuclear Regulatory Commission, Region IV 20 @
hi 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 L
Gentlemen i
RE: License Renewal Application License No. SNM-873 Program Code 22120 The referenced Nuclear Materials License has an expiration date of May 31, 1994. We do wish to renew the license.
Since we did not file a complete application at the time of our last renewal application, we are filing a complete application this time. Since many of the things we do have not changed, much of this application will be similar to tha last complete application.
- Also, we have recently filed a renewal application for our license number 35-11189-01. As a part of these renewal applications, we are computerizing both our recordkeeping system and the system by which we are alerted to take care of the time dependent items in our license, (e.g. area surveys). We are also naming a new Radiation Protection Officer to take effect with the renewal of these licenses. Since the NRC has agreed to hear a petition to restore the generic exemption for nonprofit educational institutions, we have not included the renewal ree pending the outcome of that petition.
If you have questions about our program or suggestions about how we may carry out the program with greater safety, please let us know. If you need additional information you may call me or contact our current Radiation Protection Officer, Dr. Bobby Gunter at (405) 774-3121 or the new Radiation Safety Officer, Dr. Blake Sonobe at (405) 774-3264.
Thank you for your past assistance and for your attention to this application for renewal.
- erely, Joe Anna Hihler President est IICCU30 F00 M0" Enclosures ca.Hed PB2C 100 Campus Drive
- Weatherford. Oklahoma 73096-3098 * (405) 774 3766
- rax (405) 774-3795 5
0FFICIALRECORD00PY M t. #
- 6520e L
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' NRC FORM 213 U.S. NUCLEAR REGULATORY COMMISSION APPROvEDBYOMs NO 3150 0120 f0$R 30, 32. 33 E2RES 6 30#
34, 36 and 40 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THl5 WFOR-MATON COLLECTION REQUEST. 3 25 HOURS FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH IMNSB 7714). U.S. NUCLEAR APPLICATION FOR MATERIAL UCENSE Ma'*W3"K Ri? EON'*" O'C'T M "E *0F E 'w" C AG!
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MENT AND BUDGET, WASHINGTON DC 20103
. INSTR 9CTIONS: SEE THE APPROPRIATE LICENSE APPLICATION GUIDE FOR DETAILED INSTRUCTIONS FOR COMPLETING APPUCATION. SEND TWO COPIES OF YE ENTIRE COMPLETED APPLICATION TO 1NE NRC nFFICE SPECIFIED BELOW.
APP 62,ATION FOR DISTRIBUTION OF EXEMPT PRODUCTS FILE APPUCATIOe S WITH:
IF YOU ARE LOCATEDIN:
DIVtS;ON OF INDUSTRIAL AND MEDICAL NUCLEAR SAFETY ILUNOIS. INDIANA. IOWA. MICH.GAN. MINNESOTA, MISSOURI. OHIO. OR OFF;CE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS WISCONSlN. SEld) APPUCATIONS TO:
U $ NUCLEAR REGULATORY COMMISSION i
I WASHWGTON, DC 20b56 MATElllALS LICENSING SECTION I
U S NUCLEAR REGULATORY COMMIS$10N REGION lli l
ALL OTHER PERSONS FILE APPUCATIONS AS FOLLOWS 739 ROOSEVELT ROAD f
GLEN ELLYN. IL 00137 if VOUR ARE LOCATED IN:
)
r.RKANSAS, COLORADO. IDAMO. KANSAS. LOulSIANA MONTANA. NEBRASKA.
4 CONNECTICUT. DELAWARE DISTRICT OF C01UMSIA. MAINE. MARYLDAND.
NEW MEXICO. alORTH DAKOTA. OKLAMOMA. SOUTH DAKOT A. TEXAS, UTAH, MASSACHUSETTS. NEW MAMPSMIRE. NEW JsRSEY. NEstl VORK, PENNSYLVANIA.
OR WYOMING, SEND APPUCATIONS TO:
RMODE ISLAND OR VERMONT, S&ND APPUCAYlONS TO:
MATERIAL RADIATION PROTECTION SECTION UCENSWG ASSfSTANT SECTION U.S NUCLEAR REGULATORY COMMIS$10N, RFGON IV NUCLEAR MATERIALS SAFE 1Y ORANCH
$11 RYAN PLAZA DRIVE. SUITE 400 U S. NUCLEAR REGULATORY COMMISSION, REGION 1 ARUNGTON, TX 190114D84 9
9 fl M
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b ph b N 87 475 ALLENOALE ROAD f*
t KING OF PRUS$iA, PA 1940lf1418 ALASKA. ARlIONA. CAUFORNIA. MA4 It E24MN.WAS
.) usO AND U.S. TERRITORIES AND POSSESb ihl THE PACIFlc, SEND A L A l' Al.ABAMA. FLORIDA. GEORQlA. KENYUCKY. MISSISSIPP1, NOltTH CAROUNA.
TO:
PUERTO RICO. SOUTM CAROUN A. TENNFSSEE, VIRGINIA, VIRGIN ISLANDS, OJL WEST VIRGfMIA, SEND APPuCATIOel8 70:
NUCLEAR MATERIALS SAFETY SECT 6hs Rr n
'EGIOlf%m Q U S. NUCLEAR REGULATORY COMMU 1,H
.I NUCLEAR MATERIALS SAFETY SECTION 1450 MARIA LANK U S NUCLEAR REGULATORY COMMISSON ftkGION ll WALNUT CREEK. CA 98501L6308 101 MARIETTA STREET, NW, SUITE 2500 ATLANT A. GA 30323 PERSONS LOCATED IN AGREEMENT STATES SEND APPUCATIONS TO THE U.S. NUCLEAR REGULATORY COMMISSION ONLY IF rHEY WlSH TO E UCENSED MATERIAL IN STATES SUSJECT TO U.S. NUCLEAR REOULATORY COMMISSION JURISDICTIONS.
} THl3 IS AN APPLICATION FOR (Check aswarme#e temJ
- 2. NAME AND MAluNG ADDRESS OF APPUCANT fincludse bp Cods; Southwestern Oklahoma state Univers ity 3
A. NEw uCENSE
- 8. AMENDMENT TO UCENSE NUMBE" l00 Campus Driye SNM-873 C. RENEwAt OF uCENSE NuMsER Chemistry Department Wentherford. Oklahoma 73096 l
l J. ADDRES$lESI WHERE LICENSED MATERIAL WILL BE USED OR POSSESSED.
I Southwestern Ok l a hom a State University 100 Campus Drive Weatherford, Oklahoma 73096 l TELEPHONE NUM/9R4-3121
- 4. NAME OF PERSON TO DE CONTACTED A80U" TMfS APPUCATION (405)
Bobby Gunter SUBMIT ITEMS E THROUGH 11 DN til a 11' PAPER, THE TYPE AND SCOPE OF INFORMATION TO BE PROVIDED l$ DESCRIGED IN THE LICENSE APPLICATON GUIDE.
S. MADCACYlVE MATERIAL s Element end mens numest, b. chsmsel anil/st physcal form, and c. mammum amount S. PURPOSEIS) FOR WHICH UCENSED MATEAIAL WILL BE USED.
when we lie
^ t env one time.
s
- IEN. TENS"[x'P "E N 8 TRAWWG FOR WDIVOUALS WORKING IN OR FREQUENTING RESTRICTRED AREAS.
9 FACluTIES AND EQUIPMENT.
- 10. RADIATION SAFETY PROGRAM.
- 12. UCENSEE FEES (See 10 CFR IM emf Secaon fMJr;
- 11. WASTE MANAGEMENT.
iagouwt FEE CATEGORY l ENCLOSED 8 13 CERTIFICATION iMar be conesersa by apsAcanr1 THE APPUCANT UNDERSTANDS THAT ALL STATEMENTS AND REPflESENTATONS MADE IN THIS APPUCATION ARE BfNDWG L*0N THE APPLICANT.
THE AePLICANT AND ANY OFFICIAL EXECUTING THl3 CERTIFICATION ON SEMALF OF THE APPUCANT. NAMED IN ITEM 2. CEllTIFY THAT THl3 APPLICATION IS PREPARED IN CONFORMITV WITH TITLE 10. CODE OF FEDERAL REGULATIONS, PARTS 30. 32,33,34. 36, AND 40 AND THAT ALL INFORMATION CONTAINED MEREIN, is TRUE AND CORRECT TO THE BEST OF THElft KNOWLEDGE AND SELIEF.
WARNING is U S C. SECTON 1001 ACT OF JUNE 25,1988. 82 STAT. 749 MAKES IT A CRIMINAL OFFICE TO MAKE A WILLFULLY FALSE STATEMENT OR REPRESENTATION TO % QEPARTMENT OR AGENCY OF THE UNITED STATES AS TO ANY MATTER WITHIN ITS JURISDICTION.
SIGN 'TURE CERTIFYWG OFFICER l TYPED / PRINTED NAME l TITLE l DATE Dr. JoAnna Hibler P r e s i de n t C-cR 7
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FOR NRC uSE ONLv
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~ FEE CATEGORY COMMENTS maa1 EK \\ \\)
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Item 5. Rsdioact1ve! Material l
I l
The radioactive material consists of thirty-two (32) grams of I
plutonium encapsulated as a single 2-Curie source. The slapjfit two Curie source was obtained from Nuclear Materiais and Equipment
~
Corporation and is their neutron source Model Numec B. The source
'i will be used in a Numec Neutron-Pac neutron howitzer fabricated by Nuclear Materials and Equipment Corporation. The isotopic content.
was given by them as follows Pu-239 (91.463 %), Pu-240 (7.755
%), Pu-241 (0.752%, and Pu-242 (0.030 %).
item 6. Use of Licensed Material 1
The neurton source -(Pu-Be) will be used in the radiochemistry, I
general chemistry, and physics laboratories of the Chemistry 1
Jepartment and Physics Department which are located in the Chemistry, Pharmacy, Physics building'(known as CPP) on the 1
campus of Southwestern Oklahoina State University. Tne material will also be used in closely supervised undergraduate research. All of the-j
. proposed uses are in the education and training of undergraduate i
students.
]
The following experiments have been performed and/or j
proposed.
- a. Neutron activation to produced radioactive nuclides with short half-lives [i.e. 52 V, 66Cu, 108Ag, SeMn, ' 116 min] for the determination of those half-lives.
- b. Studies of the element (s) present in in unknown samples by neutron activation analysis,
)
1
- c. Studies of the amounts ~of element (c) present in unknown
- samples by neutron activation.
- d. A systematic determination of the neutron flux in the neutron j
l howitzer by thin foil activation. Count rates (Geiger-Meuller i
detection) have been less.than 1,000 cpm.
j 1
- e. Studies of neutron activation and decay by the irradiation of l
l metal foils.
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item 7. Individuals Responsible for Radiation Safety-
)
Dr. Blake Sonobe will to be Radiation Protection Officer and Chairman of the Radiation Safety Committee for the University. Dr.
I Sonobe has a 8. S. form the U.S. Air Force Academy, an M.S.
1 (Nuciear Chemistry) from Texas A&M University [1978], and a Ph.D.
(Physical Organic Chemistry) from the Univers:ty of California, Davis, i
[1985]. He served as Radiation Protection Officer for the Chemistry Department at the U. S. Air Force Academy from 1978-1981.' He also served as a member of the Base Radiation Safety Committee at the U. S. Air Force Academy from 1978-1981. Dr. Sonobe has taught Nuclear Chemistry at the U. S. A.ir Force Academy frorn 1978-1981 and from 1985-1990.
In addition, Bol bv Guntqr, (M. S. in Physics, Vand6roilt l
University (1961); Ph.D., Chemistry, University of pirkansas (1968).
)
Atomic Energy Commission Health Physics fellow at Vanderbilt j
University (1957-58) and at Oak Ridge National Laboratory (1968-1 59); health Physicist and Senior Health Physicist, General as Radiation Protection (1959-1964)} who has served the University Dynamics / Fort Worth Officer from 1967 to the present will be 1
1 available to work with Dr. Sonobe, the new Radiation Protection 1
- Officer, to make the transBion to a new Radiation Protection Officer as smoothly and as safely as possible.
Item 8. Training / Experience of Direct Users.
All undergraduate laboratories at Southwestern Oklahoma i
State University are taught by full time faculty members rather than by j
student and/or graduate assistants. The faculty members who staif the various laboratories and research projects which use the Pu-Be i
source may change from year to year, so the Radiation Safety.
Committee [see item"10 below] has an approval clause in our j
procedures policy; certainly, students would never be approved as j
direct users in the context that they would be responsible for safety, i
Faculty members whc have routinely been involved in the use of the Pu-Be neutron source in our educational program are as follows.
- a. Riake SoDoha; will serve the University as Radiation Protection
' Officer and as Chairman of the Radiation Safety Committee (See Item 7); probably will teach the Radiochemistry course some during the term of this license, j
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b.' CharlesFogers, B. A., University of Utah (1965); M. S. (1968) u and Ph.D., Physics, Oregon State University (1968) in experimental nuclear physics; Ph.D. thesis research included 4 years experience with a 17 MeV cycloyton, production of isotopes, and mon!toring radiation; post-doctoral research in low energy physics at Louisiana State University (1971-72) included preparation of sources for irradiation, handling radioactive sources in source preparation, and performing beta and gamma spectroscopy. Faculty member Southwester Oklahoma State L niversity (1972 to present).
' c.$ Bobby Gprilqr, M. S. in Physics, Vanderbilt University (1901);
Ph.D., Cnemistry, University of Arkansas (1968). Atomic Energy Commisslor: Health Physics fellow at Vanderbilt University (1957-58 and at Oak Ridge Kationai Laboratory (1958-59). Health P
sicist and Senior Health Physicist, General Dynamics / Fort W rth (1959-1964). Duties included environmental monitoring, bioassay, special analysis, area monitoring, liguld waste disposal, counting room supervision, and shift supervision. Faculty member (1967 to present) Southwestern Oklahoma State University, Weatherford, Oklahoma. Currently teaches the Radiochem!stry course and has served the University as Radiation Protection Officer from 1967 to the present.
' d. Ray C. J.gjogs, B. S.; Ph.D., Physics, Louisiana State University (1967); experience at LSU included work with neutrons produced i
by D + T reaction; has handled neutron sources up to 1 Curie.
i Post-doctoral research at the University of California, Riverside (1987-69). Faculty member Southwestern Oklahoma State University (1969 to present).
- e. Garabed Armoudian, B. S., American University of Beirut; Ph.D., Physics, Louisianna State University.(1966-); Post-doctoral I
research Colutnbla University (1966-68); research in high energy theoretical physics. Faculty member Southwestern Ok'ahoma i
State University (1968 to present).
Item 9. Facilities and Equipment.
L All work with the requested Pu-Be neutron source materials will be cairied out on the campus of Southwester Oklahoma State University. A' map of the campus is attached as page 1 of Appendix 1. All of the work with radioactive materials requested s
- under this license renewal will be carried out in the " Chemistry, i
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Pharmacy, Physics!' buildin currently symbolized CPP'g which is building 7 on the map and is In university building and room dos!ginations although the older designations were only one letter [P for physics & the first floor, C for chemistry and the second floor, and P aga n for pharmacy and the third floor]. The CPP building has three floors, exclusive of the basement, and schematic diagrams of those floors are given on pages 2 (first floor),3 (second floor), and 4 (third floor) of Appendix 1. The first floor is primarily the De 3artment of Physics, the second flooris 3rimarily the Department of C1emistry, and the third floor is the Schoo of Pharmacy although there is some 3
overlap of room and laneratory assignments between iloors and among.the various academic units. While the schematic diagrams of the floors are essentially complete, details have been included only when such details are related to our educational use of radioactive materials. Rooms in the CPP bt.ilding have three digit numbers, and the first digit is the floor.
Room CPP-222A is used as the only storage area for Pu-Be neutron sourco and for the storage of foils and materials irradiated by the source. This room has a separate lock from other rooms in the building. The Radiation Protection Officer has a key to CPP-222A, and there is a key in the office of the Chairman of the Department of Chemist!y.
Although only solid materials have been irradiated in the neutron howitzer in the past, facilities are available to handle liquids.
Room CPP-222A has a glove box hood with a separate exhaust system and a special sink with a controlled drain. Room CPP-222 is the Radiochemistry preparation laboratory for student use. CPP-222 has a stainless steel top with ' lipped' edges on the lab bench top to help contain spills and control possible contamination. In addition, experimental stations on top of the bench are in cafeteria trays lined with absorbent paper to further reduce the possible spread of contamination from work with aqueous samples. Also, CPP-222 has a filed floor rather than the usual concrete floor to make to clean-up of potential spills easier and more complete. Finally, room CPP-222 has a regular fume hood. The counting area for chemistry courses is in CPP-219, directly across the hall from the storage and preparation areas, and the counting area for physics courses is in CPP-105. The tensfer of sources from the neutron howitzer in CPP-222A to and from the counting areas is done by full time faculty members.
Areas adjacent to CPP-222A are shown on the schernatic l
diagrams in Appendix 1. These are all classrooms and laboratories.
o a
There are no office areas and routine work areas adjacent to the use and storage locations. In addition, the Department of Physics has a storage area in CPP-106 where sorne foils and materials are kept.
Those sources are under the supervision of approved members of the Department of Physics.
Radioactive nuclides are used primarily in CPP-222, CPP-219, CPP-105, CPP-106, and CPP-109. Sometimes, however, those sources are used in other laboratories, where radioactivity measurements are a once a semester experiment (e.g. the chemistry course for nurses, pre-pharmacy physics and general chemistry ll) and in some classrooms for demonstrations.
'We do not routinely use either protective clothing or respiratory equipment because most of our sources are sealed sources. We do have several clasp!_ng_.jt Ije remo_te handling devises which are about 2_{aetjoiii.~Sance the maximum activity in our sources is not high, we believe the additional two feet of distance will be sufficient for safe handling of our sources.
Item 10.
Radiation Safety Program The Radiation Safety Committee at Southwestern Oklahoma State University is responsible to the university administration for all work with radioactive materials. This committee currently consists of one member each from the School of Allied Health, School of Pharmacy, Department of Biology, Department of Chemistry, and Department of Physics. The Radiation Protection Officer for the university serves as Chairman of the Radiation Safety Committee.
The Radiation Safety Committe reports directly to Dr. William Kermis, j
Associate Vice President for Academic Affairs, who is also an ex i
officio, non-voting member of the committee. The Radiation Safety j
Program is outlined below with equipment, procedures, and methods.
I A. Detection instruments to measure and monitor our L.,
radioactive materials are given in the following table.
1 L-Type =
Manufacturer's Use Number Radiation Range Name/Model #
&aiiable Detected Survey
. Vicoreen/6A surveying several p,7 0-50 j
meter mr/hr i
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Survey 1 Atomic Acc/
surveying.
1 n
0-300 SN87B mrem /hr Scaler 2 the Nucleus /
assaying several p,y 0-105.
500 counts Dos-Bendix/
measuting several p,y 0-200 imeter3 CD V-138 mr Dos-Bendix/
measuring several n
0-120
.imeter3 609 mram.
Crystal Nuclear Data /
assaying 1
y 0-106 Scint.
2200 counts
- 1. The neutron survey meter was recently returned by the vendor who has done past calibrations with a note they could no longer find parts. We are currently looking for a new vendor to repair and calibrate this instrument.
L
- 2. The detectors on these scalers are end window GM tubes with a window thickness of 1.4L-2.0 mg/cm2,
- 3. We do have dosimeter chargers for both types of dosimeters.
One beta-gamrna survey instrument and the neutron survey meter are calibrated twice a year (see note 1 above) by NDS Products 111 Anderson Pasadena, Texas 77506 Telephone: (713) 475-2986.
NDS products has Texas License LOO 991. Since Texas is an
> Agreement State, we believe the possession of the Texas license by
.L NDS Products fulfills the requirements conceming calibration procedures for these instromonts.
L We do possess e standard 137Cs source (Tracerlab Model R-
- 34) for the calDration of our scintillation crystals. We do not routinely
. calibrate instruments used primarily in teaching situations although we may use the calibrated instruments in those situations.
l.
p Li L) 1 Since our leak tests are done by a commercial firm, we do not routinely calibrate quantitative measuring instruments although we could do so for 0.662 MeV gammas. We do not currently have an air l
airbom problem nor an effluent problem from the use of the Pu-Be source. We do no bioassay work. The only known spill in the past ten years was when a studen; dropped a planchet with about 1,000 dpm l
of 32P in about two mL of solution on the stainless steel bench top in j
CPP-222. That spill was on absorbent paper and was easily cleaned.
i No activity was detected on the stainless steel bench top after the l
absorbent paper was removed. The wastes were stored for d' cay.
B. Personnel monitoring devices will be permanent film badges beta-gamma film and neutron film in each badge) worn by those most closely involved in our nuclear program. Currently, that is Dr. Gunter in tne Department of Chemistry and Dr. Rogers in the Department of Physics. A permanent film badge will be assigned to Dr. Sonobe as Radiation Protection Officer when his term begins.
These badges contain a beta / gamma film and a neutron film, and they are changed monthly. They are supplied by and evaluated by Atomic Energy Industrial Labs of the Southwest,Inc.
6410 Fannin Street, Suite 107 Houston, Texas 77030-3098.
Atomic Energy Industrial Labs has Agreement State license number Tx11-1067. We do note that in almost 26 years of work at Southwestern Oklahoma State University Dr. Gunter's accumulated exposure on film badge records is 325 mrem, and Dr. Rogers' accumulated exposure on film badge records is 109 mrem in a shorter period of time, in addition, the storage room film badge inside the door to CPP-222A (see page three of Appendix 1 for the film badge location) has an accumulated exposure 9,883 mrnn for continous exposure over the 24 years since the building opened in late 1969; that is a little over 1 mrem per hour inside the storage room door. These accumulated film badge exposures reinforen our other indications (e.g. area surveys] that the radiation fields here are small.
We do not routinelyperform bioassays, since most of our work l
with radioactive materials is with sealed sources. None of our
}
radioactive materials are potentialy volatile at room temperature so we do not believe we have an airborn problem.
l
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C. Area surveys are routinely performed in the source storage area, student lab, and surrounding classrooms at six month intervals. A special survey would be conducted if our program changed significantly or if some unusual event indicated a special survey was needed. A copy of the most recent area survey is attached as Appendix 2. We do not have an air sampling program because we are not currently using materials volatile at room temperature.
We do not routinely perform area surveys in student laboratory work areas because of the activity level of our sources and because of the limited time students work with these sources. Sometimes an area survey will be conducted in the Radiochemistry lab during the course of an experiment both as a teaching mechanim to emphasize the importance of knowing the radiation field as you work and as a safety measure to determine that changes have not occured since the I: st experiment was completed. Records are not maintained for these ' spot' surveys.
D. The records management program is currently being computerized on office CP units [ Appendix 3 gives the computer printout of our leak test records), and we plan to rely on a computer software progarm to alert us when the time dependent parts of our program are due. Original copies of film badge results, leak test results, instrumentation calibration, and other vendor supplied information will be maintained. The Radiation Protection Officer is responsible for keeping and reviewing these records.
E. Leak tests on the Pu-Be source will be at three month intervals. Our commercial vendor for leak test kits and evaluations is Atomic Energy Industrial Labs of the Southwest,Inc 6410 Fannin Street, Suite 107 Houston, Texas 77030-3098 The leak test kit is Model Number A.E.I.L. # 1. Their Texas Agreement State license number is Tx11-1067.
F. Instruction of Personnel. Employees who routinely use rooms CPP-222A and CPP-106 are the approved faculty listed in Item 8. These faculty members are all experienced in the use of radioactive materials, and training sessions are not conducted for them. If the nature of our program were to change and/or if we were to begin new studies, the faculty members involved would be adwsed of the changes and given essential instructions as needed.
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L There are times when personnel and/or visitors wish to briefly j
L' enter CPP-222A, CPP-106, or other areas where there are radioactive materials; we get.high school teachers, visiting chemists, students on special projects, etc. Those are essentially always one-time brief visits, and none of those type of personnel are allowed in.
l the storage rooms unescorted by an approved user.
E L
We do have classes where students use radioactivity, but those l
-- students generally do not visit the storage areas in CPP-106 and L
' CPP-222A. The training we prov;de for those classes depends on the level of use of radioactivity. The most intense student use of
' radioactive materials is probably in the Radiochemistry course. About e
twelve experiments are done over the semester; ten of those are with sealed sources and two are with 32P aqueous sources. The first experiment is RADIATION SAFETY AND MONITORING. A copy is attached as Appendix 4. In other courses, such as the nurses -
course, the prepharmacy Physics course, and General Chemistry ll, l
a single expenment is done in a three hour lab once a semester. We do not conduct formal instructional sessions for those students -
although individual faculty members in charge of those courses often caution students of potential safety problems of radioactive materials
. in much the same way they/or strong bases.
l-would, for example, caution students in the use of strong acids and In nonroutine cases which involve conditions and/or materials which do not ordinarily exist in the storage areas, the Radiation L
Protection Officer personally presents a summary of conditions and safety considerations to those involved; external advice would be -
sought if needed. Most of that type of work is varied and is often a one time experiment. It is much more convenient and economical of time to handle those situations one-on-one as they arise than it is to try to anticipate all possible experiments faculty and students may wish to perform and to anticipate all possible contingencies and wnte comprehensive instructions in advance.
j l
Because our nuclear science program is entirely educational, u
l RDd because radioactive materials are under the direct supervision of
. full time faculty members during those educational uses add because the student population is transient in nature and because the radiation ievels from our sources are small add because our film i
badge records indicate that the most active users of these radioactive j
materials are accumulating exposure at less.than one mrem per i
month, we do not have wntten instructions for those educational i
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activities although we recognize written instructicas would be essential where ernployees, who are unfamiliar with radioactivity, are working day after day and/or where the levels were high and the condi!!ons variable. The Radiation Protection Officer and/or full time faculty members are responsible for perforrning leak tests, maintenance of records, waste disposal, availability and use of personnel monitoring devices, posting areas, storage of radioactive materials, movement of radioactive materials, performing radiation surveys, and supervising the handling of liquid sources of radioactive materials. Perhaps we have placed too much confidence in the fact that all of our approved users are trained professionals and too little confidence in the importance of printed instructions. If that is the judgment of the NRC staff, we will certainly prepare those written instructions.
We do prohibit smoking and eating in all of our laboratory areas,
)
including those where radioactive materials are used, so the possibility of radioactive ingestion under those conditions is practically non existent.
We do have a modest emergency procedure program. We have, for example, alerted the local fire and police departments as well as campus security, of the location of radioactive materia!s in the building, where those materials are located, and have given them a list of people to call in the case of an emergency. We have also posted those lists on the doors of the rooms involved [CPP-325 has not been posted because the radioactivitity is inside an instrument]. We are taking this complete renewal application as the time to update those letters and lists. Copies of those letters are attached as Appendix 5.
In addition, we have had internal discussions about possible emergencies; not only about radioactive materials, but about safety on the campus in general.
We do not order rnany radioactive materials. Faculty members in the Departments of Biology, Chemistry, and Physics and those in the School of Pharmacy are instructed to clear such purchases through the Radiation Safety Committee and to have the Radiation Protection Officer present when those packages are opened. We are using this complete application as the time to restress that to all faculty with a letter. A copy of that letteris enclosed as Appendix 6.
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Waste Management Radioactive wastes are stored in CCP-222A. Since the neutron irradiation of thin foils and other solid samples has not been continued i
ifor long times, only short-lived radioactive nuclides have been M ' produced. Those are stored.for. decay until the next use, usually either a semester or more later. These foils have not been found to have-residual radioactivity when next used.'We have no current plans to.
use other unsealed and/or liquid sources which would generate either' ilquid or solid wastes.To date we have not found it essential to transfer wastes to a commercial firm licensed to receive such wastes because -
ouraccumulation of wastes has been small.
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Appendix 3.
mputer Prinout of Leak T Rssnits Leak test results Pu-239 Sr-90 Ni-63 Co-60 CDV-778 LEAK TEST RESULTS l
DATE Removable Removable Removable Removable
~
Contamination Contamination Contamination Contamination (microcuries)
(microcuries)
(microcuries)
(microcuries) 30 March,1994 0.00000 0.00000 0.00000 16 December,1993 0.00000 27 September,1993 0.00000 0.00000 0.00000 20 April,1993 0.00000 0.00000 0.00000 22 October,1992 0.00000 0.00000 0.00000 22 May 1992 0.00003 0.00000 0.00001 6 December,1991 0.00001 0.00000 0.00000 26 March,1991 0.00007 0.00005 0.00003 25 Octc.,ber,1990 0.00000 0.00000 0.00000 18 December,1989 0.00000 0.00000 0.0J000 10 May,1989 0.00000 0.00002 0.00000 6 December,1988 0.00000 0.00000 0.00000 5 May,1988 O.00000 0.00000 0.00000 19 October,1987 0.00000 0.00000 0.00000 30 May,1967 0.00000 0.00001 0.00000 26 September,1986 0.00000 0.00000 0.00000 24 April,1986 0.00000 0.00000 0.00000 16 October,1985 0.00000 0.00000 0.00000 6 May,1985 0.0001 0.00000 0.0001 25 October,1984 0.00000 0.00000 0.00000 19 June,1984 0.00000 0.00002 0.00000 15 November,1983 0.00000 0.00000 0.00000 24 March,1983 0.00000 0.00001 0.00001 22 October,1982 0.00000 0.00001 0.00000 2 June,1982 0.00001 0.00004 0.00000 14 December,1981 0.00000 0.00000 <0.002 f;om the 7_ October,1980 0.00000 0.00000 manuf. 1/8/82 4 June,1980 0.00000 0.00010 11 October,1979 0.00001 0.00010 24 April,1979 0.00000 0.00000 20 October,1978 0.00000 0.00000 28 March,1978 0.00000 0.00001 6 October,1977 0.00G04 0.00001 1 April,1977 0.00000 0.00000 f
8 October,1976 0.00001 0.00000 1
16 April,1976 0.00000 0.00000 Page 1
Leak test r: cults 30 September,1975 0.00000 0.00000 1 April,1975
'O.00000 0.00000 29 October,1974 0.00000 0.00000 2 April,= 1974 -
0.00000 0.00000 returned to Civil 6 November,1973 0.00002 0.00002 Defense May,197 16 April,' 1973 0.00000 0.00000 0.00000 24 October,1972 0.00000 0.00002 0.00000 i
15 April,1972 '
O.00000 0.00000 0.00000 17 October,1971 0.00000 0.00000 0.00000 l
27 April, '1971
'O.00001 0.00000 0.00001 30 September,1970
< 0.005
~< 0.005
< 0.005 21 March.11970
. < 0.005
< 0.005-
< 0.005 30 September,1969
< 0.005
< 0.005
< 0.005 29 Marchi 1969
< 0.005-
< 0.005
< 0.005~
l 26 October,1968
< 0.005
< 0.005
< 0.005 17 July,1968
< 0.005 29 April,1968
< 0.005
< 0.005-24 February,1968
< 0.005
{
4 October,1967-
< 0.005
< 0.005 30 September,1967 -
< 0.005 4 April,1967
< 0.005
< 0.005 29 March,1967
< 0.005 7 October,1966
< 0.005
< 0.005-
< 0.005 7 April,1966
< 0.005
< 0.005 i
,+.
l-
. Page 2 i
l
_ _j
___y EXPERIMCT 1:
Radiation safetand Monitorina
~
(
QBJECTIVE: To become acquainted with the unicue problems associated with handling radioactivity and to become familiar with the elementary methods of radiation safety.-
GENERAL: Most of you are aware of the public controversy about the possible health hazards from nuclear power electrical generating stations and other sources of radioactivity. We will consider that debate in more detail later'uhen we talk about biological effects of radiation and nuclear fission. The public concern is orompted by the fact that nuclear radiation does have a detrimental effect'on !!ving organismo, at least at high exposures, and the crucial debate point seems to be the degree of danger i
in relation to the expected benefit. In this experiment, we will not try to resolve the debate; rather, we will simply say that radioactivity is potentially harardous and should be handled carefully.
Nuc!es radiation transfers energy to an organism, and the damage mechanisms are generally considerec to be by ionization, dissociation, excitation, and/or atomic displacements within the molecu!es of the organism. The alteration of a molecule which performs a particular organism to perform that function, and thus,y reduces the ability of th biological function for the crganism obviousl damages the organism. In perspective, there are probably numerous other agents which also interfer with normal function. The amount of damage and the ability of the l-organism to overcome the damage are related, among other things, to the intensity of the radiation exposure. Other important factors are the density of the ionization, the type of radiation, the essentiality of the irradiated organ, the dose rate, the rate of biological elimination of internal radioactivity.
Students of chemistry have already encountered hazardous chemicals in the lab (i.e. strong acids and bases, very reactive elements, combustible compounds, etc) and have leamed how to take some
' precautions in the use of such chemicals (saefty goggles, lab aprons, etc) to increase the safety factor. Work with radioactive materials may be carried out with increased safety also, but the precautions, methods, and legalities may be different.
In this country, the Nuclear Regulatory Commission, or NRC,is responsible to the nation for work with radioactive materials; many states and other governmental units may also have established rules and regulations.The NRC regulations," Standards of Protection Against Radiation", are given in Part 20, Title 10, of the Code of Federal Regulations. Additional regulations are given in other parts of Title 10.
Those regulations are legally binding, and violations may be punished by fine and/or imprisonment.
'(
One of the responsibilities of the NRC is to control the distribution and use of radioactive materials. This is done through a licensing system. The
^
so called "generalI nse" allows possession of sm amounts of some radioactive nuclides without filing formal application with the NRC. The
" specific liscense" is rec;uired for larger quantities and/or more hazardous I
types of radioactivity. Tae specific license requires approval by the NRC of a formal application, and the specific license will identify the types and amounts of radioactive materials the licensee may possess and how that may be used. Essentially all of the work in this lab will be with general license quantities.
A second responsibility of the NRC is to establish permissible levels of radiation exposure or dose for individuals working with radioactive materials. These limits apply to persons who work with radioactivity in their fobs and is known as occupational exposure. (The NRC also considers imits for non-occupational exposure, the release of radioactivity into the environment, and the disposal of radioactive wastes.] Two basic considerations have governed the exposure limits established. First, the expc<sure limits shall be such that those exposures willl not appreciably affect the person's life; i.e. somatic effects. Second, the limits shall ba such the the biolo workers, i.e.gical effects will not significantly affect the progeny of those genetic effects. As an aside, we note that much of the current debate about the use of nuclear energy and the possible hazards relates to the use of words such as appreciably and significantly;do not.some people believe only zero exposures meet those conditions and others man). You will also notice, in this experiment, as well a(s in a lot of theThe leg
(.,,
literature, the units roentgen, R, and milliroentgen, mr, are used. Both are defined units, and at this point we will not give those definitions except to say they are intended to permit us to measure and quantify radiation exposures.
The mathematical equation for the accumulation of radiation dose is, Maximum Permissible Accumulated Dose = MPAD = 5{N - 18} rem, where N is the individual's age in years, and the MPAD is the number of rems that person may accumulate by that age. Note the MPAD for people under age 18 is negative; people under 18 are not allowed to be occupationally exposed. There are additional limitations to this equation.
Suppose, for example, a person 28 years old, who had never been occupationally exposed, began work with radioactivity for the first time.
Solutic.n of the above equation gives the MPAD of 50 rem; the person could have received 50 rem by age 28, but had not received any. An employer may not, however, place that employee in a job situation where 50 rern are received the first day!
Examination of the above equation shows that radiation dose may be accumulated at the rate of 5 rem per year. If we assume that every worker
(
gets 2 weeks vacation per year, the weekly dose is 0.100 rem, or more commonly,100 mrem / week. While that number is not an absolute number in all situations, the number 100 mrem / week is a convenient one to
'rerhemb r while wortg with radioactivity. Not becat there are no possible variations irlTie number, but because it willW.ow you to sort of
' keep score" of the approximate levels of radiation exposure during our g
experiments.
Each site (business, hospital, college, etc) doing work with radioactive materials is required to have a radiation safety officer who has the task, among other things, of maintaining complete records of radiation exposures to each employee as required by law. The sources used in this course are usually low level compared to the legal limits. You certainly are encouraged to develop the habit of checking each source you use to determine its radiation level, and to report any conditions which appear unsafe to you.
Employees who work with radioactivity must be continuously monitored so the dose received by each wilibe known if the exposures are reasonably expected to be above certain values. Devices to monitor work with radioactivity are generally divided into two categories.
Personal monitorina devices are worn by individuai employees to measure their exposure only.
The film badae is the legal method of measuring individual exposures. The badge is worn by the individual for a specified period of time (i.e. a week, a month, three months. A single fi'm badge may contain several different pieces of film such)as gamma film, neutron film, and so C
forth. Radiation darkens the gamma film, and the more radiation the film receives, the darker the film. Calibration curves which relate film darkening with known exposures are prepared, and the darkening on the individual films is evaluated from the calibration curve. Neutrons leave " tracks" in the film emulsion, and the number of tracks per unit area is related to the neutron dose. Once again, calibration is rec uired. Specialized equipment and training are required to evaluate these films, and many sites send their film badges to a commerical vendor.
The.closimeter is an electroscope which is charged (i.e. zerced) electrically. The passage of radiation through the dos,imeter produces ionization which discharges the electroscope. The more radiation the dosimeter (e.g. the employee) receives, the more completely the dosimeter is discharged since the radiation dose and tha discharge of the electroscope are directly related. Many dosimeters are self reading. Thus, the dosimeter may provide a rapid, on the job, method of dose determination while the film badge must be taken to a separate area for evaluation and will take a loncer period of time. The film badge, on the other hand, has a wider range and is more accurate.
Neither the film badge not the dosimeter provides the dose rate, only the total accumulated dose. It should be noted that both measure the
.(
radiation dose to the part of the body where worn and should be placed somewhere on the trunk of the body for most work.
Area monitorimm devices sometimes calle urve meters, are
' instruments, either %able or stationary, to measu adia ion levels in a particular arca and not to an individual although if an individual wera to stand where the instrument was, that individual presumably would receive I
the exposure measured. They are used primarily to establish the radiation level in a work area and to determine changes in the radiation level as work is carried out. Note different types of radiation may require different types of instruments; there are gamma survey meters, neutron survey meters, and so forth. Always be sure the instrument you select is the proper one for the radiation you wish to measure!
Survey instruments generally measure dose rates such as mr/ hour or R/hr, and the total projected dose must be calculated from the dose rate and the expected time of exposure. For example, if a gamma survey instrument reads 60 mr/hr, you would receive about 60 mr if you worked in that field for an hour; thirty minutes wouid be about 30 mr of exposure; and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> would be about 120 mr of exposure. NOTE that exposure values determined with survey instruments may not be used as individual exposures for record purposes.
EXPERIMENTAL: A Civil Defense Survey Instrument which reads in mr/hr will be used. The radiation detector is a Geiger-Mueller tube which is generally known as a " Geiger" counter or as a GM tube. The GM tube is sensitive to any type of radiation which can penetrate the walls of the tube (alphas can not) and still have sufficient energy to produce ionization inside the tube. The GM tube is a hollow, gas filled metal cylinder with a wire down C
the middle of the cylinder. The center wire is positively charged and the wall charge. When radiation enters the tube, it of the cylinder is negatively (atoms) to produces electrons and posit t
I ionizes the gas molecules (i.e. ion pairs]. The electrons flow toward the positive center wil e and the positive ions flow toward the negative cylinder nall. This movement of charge is electrical current which is measured on the meter. In this l
experiment, we will be working with alpha, beta, and gamma emitters. Since i
alphas do not have sufficient energy to penetrate the walls of the GM tube, the survey instrument we will use,is pnmarily a " beta-gamma" instrument; beta is understood to mean both betas and positrons.
Two precautions should be observed in using the instrument. Elmi, I
the meter needle; i.e. driving the i
care should be taken to avoid " pegging'icularly susceptible to this since needle off scale. This instrument is part there is a time lag in its response. Thus, the GM tube should be brought up to any source rather slowly. Also, it is generally better to " scale down" the j
settings rather than to " scale up"; i.e. begin with the least sensitive settings and go to more sensitive settings rather than the other way. Obviously, if you should accidentally " peg" the meter needle, you shou d allow the instrument time to stabilize before you take numerical data. Second. the l
meter shows instantaneous values and the readings will vary from instant to l
instant so the needle will fluctuate with time. You should attempt to estimate
(
a time average reading for each source. Do not spend a great deal of time, therefore, wa, ting for the instrument to " settle down" on a single value i
because it never will! It is a qualitative instrument.
I 1
Check the ope ion of the instrument with the urce on the side of the instrument. The reading should be between 1 and 2 mr/hr.
I Several sources have been placed on the lab bench. Obtain an open window and a clo. sed window reading on each source. Tabulate the data in your lab book.
Carefully measure the open window reading for one of the more active sources ( USE " NUCLEAR B") at several known distances {use 1 cm,5 cm 10 cm,15 cm,20 cm,25 cm,35 cm, and 50 cm}. Prepare two graphs of these data. (a) plot the dose rate in mr/hr on the y axis and the source to detector distance on the x axis, and (b) plot the dose rate in mr/hr on the y axis and the inverse of the source to distance squared [i.e.
2 1/d ] on the x axis. Briefly discuss the offect of increased source to detector distance on the dose rate.
Measure the open window reading for two of the more active source on the lab bench with and without two different lead absorbers of different thicknesses between the source and the detector. Try to keep the distance constant for all of these readings. Why? Briefly discuss the effect of lead, and other materials, on the dose rate from a given source of radioactivity.
I Obtain a " background" reading in the hall outside the lab.
Room 222A in the back of room 222 is used for the storage of C
radioactive sources. survey the room and locate the highest radiation level you can find. Also identify the source of the highest reacing and give the dose rate you measured. Do not move anything or open anything during your survey.
QUESTIONS: 1. What influence does closing the window have on the meter readina? Account for this. Does closing the window have the same % effect on all of the sources you measured? Account for this.
f
- 2. Readings on several different sources should be made only with l
quite a bit of distance between them. Why?
- 3. Briefly discuss two ways you might reduce your exposure dosa while working with a given source of radioactivity.
- 4. What is the MPAD for an individual 24 years old? 42 years old?
- 5. You perform an experiment with 2 microcuries of radioactivity.
When the experiment is over, the radioactivity is in 400 mL of 1
aqueous solution. If the maximum legal concentration of this radioactivity in the sanitary sewer system is 0.007 microcuries/mL, may you legally flush this waste down the drain? Why or why not?
k
- 6. How lono could you work befora you received your weekly limit of exposure if the radiation field was 20 mr/hr? 75 mr/hr? 2.5 R/hr?
Appendix 5.
Letters d Door Sign for Location Radioactive Materials.
RADIOACTIVE MATERIALS l
A number of radioactive materials ate stored in this l
room. In the event of an emergency such as a fire, storm, i
explosion, etc, it is important that those radioactive materials be treated as potentially hazardous substances and that every effort be made to keep them from being lost and/or coming in contact with the general public.
In case you are the first person to arrive in an emergency situation, probably the best action is ISOLATION of the area and materials in this room. The potential hazard is small several feet from the materials. The following individuals should be called in the order given until one of them is available to evaluate the radiological safety of the area.
IN CASE OF EMERGENCY CALL
[In the Order Given]
- 1. Charles Rogers:
Work (- 774-3108j Home
- 2. Bobby Gunter:
Work
- 774-3121 Home[
j
- 3. Blake Sonobe:
Work - 774-3264 HomeC
]
- 4. Garabed Armoudian:
Work
- 774-329 Home[
- 5. Donald Hertzler:
Work - 774-3266 HomeC
_]
^
o o
November 23,1993
. Mr. Dean Brown, Chief Weatherford Fire Department.
{
118 North Kansas I
Weatherford, Oklahoma
Dear Dean:
I had written the Fire Chief several years ago about some radioactive materials which are stored in the CHEMISTRY, PHARMACY, PHYSICS building on the campus of Southwestern. This letter is to update that letter.
None of these sources are high levels of radioactivity, but we wanted you -
to know about them in case an emergency (fire, storm, etc) came up where
. members of the fire department needed to be in the building and might see the radiation signs on doors.
L These sources are stored primarily in room CPP-222A (second' floor)
L although some might be found in CPP-106 (first floor), and CPP-325 (third floor). The source in CPP-325 is in a Hewlett Packard gas chromatograph and l
presents no hazard if left in that instrument. If someone from the department
- would like to visit and get these sources located, have some discussion about l
i them, and tiie level of potential hazard they present, please let me know.
In the avent of an emergency call the following people in the order given for assistance in handling thase materials.1. Bobb GunterC
] 2.
J Blake Sonobe C J3. Charles Rogers -L,
_14. Don Hertzler
[
~
~J5. Garabed Armoudian J. I will post this list on the doors of the rooms where radioactive m[aterials are stored.
Let me empahsize that we have not added any new radioactivity to our
. inventory; this is simply an update.
Many thanks for the fine work the department doe.s! _
Sincerely, l
Bobby Gunter, Chairman Radiation Safety Committee
\\
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I
L L
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.o 1
l November 23,1993 i
- Mr. Paul Gaines, Chief Weatherford Police Department
^
201-SW Main Street Weatherford, Oklahoma
Dear Chief Gaines:
I had written the Police Chief several years ago about some radioactive materials which are stored in the CHEMISTRY, PHARMACY, PHYSICS building on the campus of Southwestern. This letter is to update that letter.
None of these sources are high levels of radioactivity, but we wanted you to know about them in case an emergency (fire, storm, etc) came up where members of the police department needed to be in the building and might see the radiation signs on doors,-
These sources are stored primarily in room CPP-222A (second floor) although some might be found in CPP-106 (first floor), and CPP-325 (third floor). The source in CPP-325 is in a Hewlett Packard gas chromatograph and presents no hazard if left in that instrument. If someone from the department -
would like to visit and get these sources located, have some discussion about them, and the level of potential hazard they present, please let me know.
In the event of an emergency call the following people in the order given
~~ior assistance in handling th se materials.1. Bobby GunterC 3 2.'
Blake Sono I.
- 3. Charles Rogers J4. Don Hertzler
"~
C
- 5. Garabed ArmoudianC*
I will post this list on the
. doors of the rooms where radioactive materials are stored..
Let me empahsize that we have not added any new radioactivity to our inventory; this is simply an update.
Many thanks for the fine work the department does!
5
' Sincerely,
.,1 Bobby Gunter,. Chairman
- Radiation Safety Committee x __- _ _ _ -.
i
l November 23,1993 Mr. Don Groth, Chief Campus Security Southwester Oklahoma State University i
Weatherford, Oklahoma
Dear Chief Groth:
I had written the Campus Security several years ago about some radioactive materials which are stored in the CHEMISTRY, PHARMACY, PHYSICS building on the campus here at Southwestern. This letter is to update that letter.
None of these sources are high levels of radioactivity, but we wanted you i
to know about them in case an emergency (fire, storm, etc) came up where.
)
members of the campus wcurity needed to be in the building and might see the radiation signs on doors,
)
These sources are stored primarily in room CPP-222A (secor'd floor) although some might be found in CPP-106 (first floor), and CPP-325 (third floor). The source in CPP-325 is in a Hewlett-Packard gas chromatoprapn and presents no hazard if left in that instrument. If someone from the campus security would like to visit and get these sources located, have some discussion about them, and the level of potential hazard they present, please let me know.
In the event of an emergency call the following people in the order given
- for assistance inJandling these materials.1. Bobby GunterC 32.
- 33. CharlesfogersC]l will post this list on the Blake Sonobe L_
]4. Don Hertzler C
- 35. Garabed ArmoudianC
[
doors of the rooms where radioactive materials are stored.
Let me empahsize that we have not added any new radioactivity to our inventory; this is simply an update.
Many thanks for the fine work the campus security does!
Sincerely, Bobby Gunter, Chairman Radiation Safety Committee
)
' ' ' =
Appendix Letter.to Faculty for os ing-Materials.
l 1
i November 22,1993 To: Faculty members in the Departments of Biology, Chemist Physics and in the School of Pharmacy.
p
$ [g g g From: Radiation Safety Committee Colleagues:
N Please remember if you intend to purchase any radioac lak!sr any souloment which contains a source of radioactive material. such as a calibration source or a detection device, that purchase needs to be cleared thru the RADIATION SAFETY COMMITTE for several reasons. The first of these is to insure the safety of personnel. In addition, we could accumulate radioactivity in small amounts which surpass the amounts we may legally have which would place Southwestern in violation of NRC regulations and could jeopardize all of our educational uses of radioactive materials. If you need such a source and place an order without clearance from the Radiatbn Safety Committee, you place Southwester in violation of our NRCtense. Finally,
]
your work could be delayed for many weeks while we tried to obtain a license i
for the material, if one is needed. Actually, commercial vendors will not ship I
some sources without a license number, and the vendor will hold the item until a license is obtained. It is much better to start efforts to secure a license when you start planning the other aspects of your work with radioactive materials.
l l
In addition, it is essential that the Radiation Protection Officer be present i
with radiation detection instruments at the time the package is opened to assure
[.
that dangerous levels of radiation do not exist.
Your continued cooperation in these matters is appreciated.
Many thanks!
I l
Bobby Gunter, Chairman Radiation Safety Committee 4
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