ML20148A186
| ML20148A186 | |
| Person / Time | |
|---|---|
| Site: | 07003039 |
| Issue date: | 07/27/1987 |
| From: | Scott L LOUISIANA STATE UNIV., BATON ROUGE, LA |
| To: | Whitten J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20148A139 | List: |
| References | |
| 461601, NUDOCS 8801220492 | |
| Download: ML20148A186 (133) | |
Text
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r Radiation Safety Office
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East Fraternity Circle Ol>
C L O U I S I A N A S T AT E U N I V E R S IT Y m Acarton art m matacAt cotuca BATON ROUGE. LOUIS!ANA. 70803 4301 gg July 27, 1987 M @ E D M F F4
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Mr. Jack Whitten MJG - A 1987 1
Region IV dWI Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000
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Arlington, Texas 76011
Dear Mr. Whitten:
Enclosed are the current procedures for the Louisiana State Univer-sity Radiation Safety Program. Activities licensed under and required by SNM-1966 are conducted in accordance with these procedures except that leak testing of the plutonium-beryllium sources are in accordance with license condition 12.
As far as the procedures are concerned with plutonium-beryllium sources there are only changes (from the original application sub-mission) in two items:
1.
Personnel Monitoring:
a.
Frequency may vary from monthly to quarterly b.
Prior radiation histories are not obtained unless the person of concern has indicated a past exposure in excess of the appropriate limit.
c.
Students in Nuclear Science courses may or may not be monitored depending on the judgment of the Radiation Safety Officer and the instructor.
d.
Records are maintained on a computer file containing the information included on DRC-4 and DRC-5.
e.
Monitoring is not specified to be by film badges.
l 2.
Instrument Calibration a.
Listing of instruments is by typical type.
I b.
Neutron calibration is by a plutonium-beryllium I
source.
Sincerely, S
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L. Max Scott I
Radiation Safety Officer ek 4 /-
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r RADIATION EMERGENCY CHECKLIST CLEAR AREA.........
W v&
go to the closest safe place get everyone out carefully help anyone who is injured SEAL OFF AREA........
post guards to keep people away *eaving turn hoods and water off before.
.close doors behind you CALL FOR HELP........
Radiation Safety Office 388-2163 or 388-4400 University Police 388-3231 UniversityEmergencyNO.388-HELP (4357)
TELL WHAT HAPPENED........
Major spill Exposed source Air-borne contamination Fire or explosion Badly contaminated major injury TELL WHERE........
TELL WH0........
WAIT CLOSE BY........
Tie a hankerchief around your arm for quick identification 0l 9
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TABLE OF CONTENTS CAMPUS RADIATION SAFETY COMMITTEE.................................... i RADIATION EMERGENCY CHECKLIST.......................................
11 TABLE OF C0NTENTS..................................................
111 ORGANIZAT10N........................................................
1 Authorization..................................................
1 Program Structure..............................................
2 Responsibilities and Authority.................................
3 PROCEDURES..........................................................
6 Grant and Contract Proposals...................................
6 User-Project Applications......................................
6 USER-PROJECT APPLICATION............................................
8 Radionuclide 0rders............................................
10 Delivery of Radioactive Materials..............................
11 Radionuclide Disbursement......................................
12 Waste-Handling Procedures......................................
12 RADIONUCLIDE INVENTORY F0RM.........................................
13 Transfer and Shipment of Radioactive Materials.................
15 Storage of Radioactive Materials...............................
16 Radioactive Materials Accountability...........................
17 Registration of Machines Producing lonizing Radiation..........18 New Facilities Approva1........................................
19 Site Monitoring................................................
21 Special Services...............................................
22 PRACTICE............................................................
23 General Rules for Radiation-Producing Machines.................
24 Signs, Notices and labels...................................... 26 i
l General Rules for Animal Handling I nvol ving Ra di oactive Ma terial s................................ 27 General Rules for Field Use of Sealed Padiation Sources........ 29 General Rules for Decontamination..............................
31 APPENDI X - MEMORANDUM FROM THE PRESIDENT, PM-30..................... 32 i
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m, ORGANIZATION The authorization, structure, personnel, and responsibilities of individuals for the radiation safety program for Louisiana State University and Agricultural and Mechanical College at Baton Rouge are described in this section.
The names and telephone numbers of individuals currently involved in the program are listed at the front of this manual.
Authorization Authorization for Louisiana State University to possess, store, and use radioactive materials is stipulated in a broad-scope radioactive materials license issued by the Louisiana Nuclear Energy Division of the Department of Environmental Quality, which has vested responsibility from the United States Nuclear Regulatory Commission within the State of Louisiana or a special nuclear material license issued by the United States Nuclear Regulatory Comission.
The broad-scope license allows the University maximum flexibility in the use of radioactive materials for teaching and research through the operation of an internal radiation safety and control program.
Copies of these licenses are available for inspection in the Radiation Safety Office.
Administrative authorization from the University is contained in Pm-30, issued from the Office of the President.
Included in this document are the responsibilities and authorities of the individuals and committees required by the University's broad-scope license, and the names of the individuals and comittee members.
A copy of the most recent revision of PM-30 is included in this manual as Appendix 1.
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T i-Authorizations for individual campus activities are contained in minutes of the LSU System Radiation Safety Comittee, in campus policy statements, and in approved individual campus radiation safety manuals.
Special authorization for unusual circumstances may be required, and will supersede the contents of this_ manual.
Program Structure The Chairman of the System Radiation Safety Comittee is administratively responsible for the radiation safety programs within the University, and reports directly to the University President.
Direct responsibility for implementation of the radiation safety policies and directives established by the System Radiation Safety Comittee is assigned to the LSU System Radiation Safety Officer.
l Appointment of individual Campus Radiation Safety Officers is authorized in PM-30, and appointment of individual Campus Radiation Safety Comittees has been approved by the System Radiation Protection Comittee.
The Campus Radiation Safety Comittee has the responsibili-l ties for local supervision and control of radiation hazards and will l
direct the activities of the Campus Radiation Safety Officer.
The Chairman of the Campus Comittee will appoint a temporary Campus Radiation Safety Officer when the permanent Campus Radiation Safety Officer is unavailable for periods exceeding one work-day.
It is 1
incumbent on the permanent Campus Radiation Safety Officer to infom the Comittee Chairman when he will be unavailable for periods exceeding one l
day.
The LSU and A & M College Radiation Safety Comittee is composed of l
representatives from the College of Agriculture, the College of Basic t
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Sciences, the College of Engineering, the Nuclear Science Center, the School of Veterinary Medicine, the Agricultural Center and other persons having knowledge in the use of radiation and radioactive materials.
Non-voting members shall include the Director of the Nuclear Science Center, Campus Safety. Officer and Campus Radiation Safety Officer.
Administratively, the Campus Radiation Safety Committee reports to the 2
Vice-Chancellor for Research.
Responsibilities and Authority All persons involved with the handling, use, and storage of radio-active materials and radiation sources have ths general responsibilities to:
1.
Assure that University personnel, studen'ts, and visitors are 7
not subject to undue radiation exposure; 2.
Assure that all federal and state regulations have full compliance; 3.
Assure that all University regulations and policies pertain-ing to radiation safety have full compliance; I
4.
Assure that special project restrictions have full compli-ance; 5.
Assure that University insurance restrictions are met; t
4 6.
Assure that local and state codes and ordinances have full compliance; 7.
Assure that the integrity and usefulness of Univeisity facil-ities are not compromised; j
8.
Assure that maximum standards of good practice and safe handling are maintained.
4 These general responsibilities apply to all individual users, techni-cians, students, and operating personnel.
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Each person who handles radioactive materials or radiation sources must realize that the ultimate success of a rediation safety program lies in responsible actions by individuals in their daily work.
The Campus Radiation Safety Comittee is charged with the respon-sibility and authority to control the use of radioactive materials and radiation sources on a local basis. -The Campus Radiation Safety Comit-tee can expedite action on radiation safety matters because of its intimate knowledge of local situations, and because of the ability to convene quickly.
An executive comittee, consisting of the Radiation Safety Comittee Chaiman, the Campus Radiation Safety Officer, and one other member chosen by the Comittee, is empowered by the full Comittee to act in emergency situations.
The Campus Radiation Safety Comittee has advisory responsibilities for:
1 1.
Assuring that user projects comply with license restrictions, University policies and regulations, and standards of good practice; 2.
Assuring that proposals for grants and contracts do not im-pose unacceptable radiological risks to individuals; 3.
Assuring that new construction and renovation of existing buildings meet standards of good practice for using or stor-ing radioactive materials or radiation sources; 4.
Assuring that University personnc! involved in the control of radiation hazards, including users and their assistants, have i
appropriate training and experience; and 5.
Reviewing the actions of the Campus Radiation Safety Officer.
f The Campus Radiation Safety Officer is appointed by the Chancellor to supervise the radiation safety program in all aspects, with the 1
responsibility for proper control of radiation-related projects on the
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campus and at any other site under campus supervision or control.
As 1
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L specified in PM-30, approval of the Campus Radiation Safety Officer is required for:
i 1.
All matters pertaining to the LSU System radioactive-material license and radiation-source registration; 2.
All requisitions for purchase of radioactive materials and radiation-producing equipment; l
3.
All user projects, including laboratory and teaching uses, research and development projects, and other activities with potential radiological hazards; 4.
All contract and grant proposals involving radioactive mater-i ials or radiation sources; 5.
All personnel who will directly use radioactive materials or radiation sources to assure that they are properly trained; and 6.
All facilities, construction, outfitting, and renovation, 3
including review and approval of construction plans, drawingt and specifications involving radioactive material and radiation sources.
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The Campus Radiation Safety Officer has the vested authority to act l
imediately in all matters pertaining to radiation safety for the l
purpose of assuring individual well-being and the integrity of University property.
The Campus Radiation Safety Officer may appeal I
directly to the Chancellor for support in these actions, which are then I
subject to review by the Campus Radiation Safety Comittee and by the LSU System Radiation Safety Commit' l
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PROCEDURES Specific procedures required for the proper control of radioactive materials and radiation sources at LSU and A & M College are described in this section.
Questions concerning these procedures should be directed to the Campus Radiation Safety Officer.
Grant and Contract Proposals All proposals to outside agencies must be routed through the Campus Radiation Safety Officer if they involve the use of radioactivt materials or radiation sources. The Campus Radiation Safety Officer may approve such applications.
At times when the Campus Radiation Safety Officer is off campus, the Chairman of the Comittee will be the approving authority.
If the Chairman is also unavailable, members of the Committee at their discretion may approve.
When approval is by other than the Campus Radiation Safety Officer, the originator of the proposal shall forward a copy of the proposal and approval form to the Campus Radiation Safety Officer.
The Campus Radiation Safety Officer conducts reviews of proposals for their radiological safety content only.
This review must be completed before the signature of the University President can be obtained. All approvals will be reviewed at the next scheduled Comittee meeting.
User-Project Applications Individuals who wish to use radiation sources or radioactive materials in research, development, teaching, or demonstration projects must obta'n prior approval of the Campus Radiation Safety Officer.
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i A User-Project Application Form (NS1009R) is shown on the following page. -and are available from the Radiation Safety Office.
The date submitted, project title, user's department, and college are to be filled in on the appropriate lines.
In the following space, and on i
additional sheets if necessary, the user must supply information relative to training and work experience in the handling of radiation sources and radioactive materials.
User qualifications must be connensurate with the planned use.
If the application is from a user who has received approval previously on another project, the phrase j
j "Qualifications on file in the Radiation Safety Office" may be inserted for convenience.
User-Project approvals are issued only to principal investigators and group leaders, it is their responsibility to provide proof to the Campus Radiation Safety Officer of radiation safety training for all j
persons involved with radiation related activities under their control.
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Acceptable training includes Nuclear Scienct course work, preferably including laboratory and radiation safety short courses offered by the i
Radiation Safety Office.
The radionuclides or radiation sources required for the project l
must be specified in sufficient detail for radiological safety review.
This listing includes radiation-producing equipment which requires s
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l registration by the Nuclear Energy Division.
For radionuclides, the total activity that the user expects to have on hand at any one time must be indicated.
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Specific information must be supplied on all locations where radioactive materials or radiation sources are to be employed during the j
course of the project. This information is required so that the Campus 1
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BATON ROUGE NUCLEAR SAFETY COMMITTEE Louisiana State University USER-PROJECT APPLICATION Project title:
College:
Department:
Project director:
Training and experience in the handling of radioactive materials and sources:
(Supply the names and qualifications of other project personnel on a separate page attached to this application.)
Radionuclides (identify nuclides, chemical / physical form, total activity): _
Location (identify building and room number, or otherwise identify place of use):
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Schedule (identify expected approximate beginning and ending dates):
Attach a project outline in sufficient detail to permit evaluation 7
of potential radiation hazards, including procedures assuring radiation control, waste handling procedures, etc.
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Radiation Safety Officer can establish that the sites are under the j
i coverage of the Un'iversity's radioactive materials license.
The Campus Radiation Safety Officer is also required to inspect the specified locations to ascertain that the proposed use is consistent with license
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restrictions, federal and state regulations, and University rules and policies.
Expected approximate beginning and ending dates, if applicable for the project, should be indicated in the space provided.
Unless a shorter period is specified, all approvals will expire 3 years from date t
of issue.
The user is to attach to the application form a project outline in i
which the specific details of the planned use are described in suffi-cient clarify to permit review by the Campus Rad'iation Safety Off'cer
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and Campus Radiation Safety Comittee.
In general, this will involve 5
operational details for radiological safety rather than details of j
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experimental planning.
Standard laboratory practice for handling radioactive materials can be assumed, but deviations from standard j
practice must be described.
Waste-handling plans must similarly be described in detail, j
When the User-Project Application is completed, it is to be trans-f mitted to the Radiation Safety Office for review.
This review may
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4 include discussions with the applicant and site visits, with specific l
i suggestions for revision of the application.
It is the Campus Radiation r
Safety Officer's responsibility to assure that the application meets all r
i regulatory standards.
Review of User-Project Applications by the Campus Radiation Safety Officer is restricted to matters of radiological j
i safety only.
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Radionuclide Orders Radionuclides can be ordered only by approved users for a project that has been assigned a serial number. Orders for radioactive materials are placed just as any other materials or supplies are ordered, with the single exception that the approval of the Campus Radiation Safety Officer is required on the purchase requisition. Without such approval, the requisition will not be processed by the Purchasing Department to an off-campus vendor.
The purchase requisition including the name of the approved user is transmitted to the Radiation Safety Office. The Campus Radiation Safety Officer will review the requisition to assure that the purchase will not exceed the license-limits and that the radionuclides are authorized for that particular project.
The purchase requisition will be stomped and signed by the Campus Radiation Safety Officer, and the requisition will be forwarded to the Purchasing Department for processing.
If the radioactive material is to be purchased by either a blanket purchase order or a standing purchase order, approval may be obtained to cover the order for the period up to the end of the fiscal year in which the order was originally initiated.
Prior approval will be granted for blanket orders of radioactive materials if requested by letter to the Radiation Safety Office.
Standing order will be approved in the same manner as any purchase order.
When radioactive material is ordered by either method, the individual ordering must provide written notice to the Radiation Safety Office as to what, and how much is being ordered and the name of the vendor.
The purpose of this notification is to ensure that the shipments are properly handled and available to the user in a timely fashion.
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1 Purchase requisition approval is also required for any equipment containing radioactive sources, such as gas chromatographs equipped with-l electron-capture detectors, j
Delivery of Radioactive Materials J-All radioactive materials arriving on the campus are to be de-livered to the Radiation Safety Office.
There are only two allowed exceptions to this requirement:
i 1.
By prior approval of the Campus Radiation Safety Officer, a user may be permitted to retrieve a very-short-lived (less than 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> half-life) radionuclide shipment di;'tetly from the carrier; and 2.
By prior approval of the Campus Radiation Safety Officer large pieces of equipment containing radioactive materials e
may be delivered direct 1/ to the building where they are 4
to be installed.
In both instances, the Campus Radiation Safety Officer must be notified promptly upon arrival of the radioactive material so that proper i
inventory and receipt procedures can be completed.
Delivery of all other radioactive materials to the Radiation Safety 4
Office is required to insure adequate inventory control, and to allow proper initial radiation monitoring of packages.
Federal and state regulations require that the University be able to verify at any time j
the total quantities of radioactive materials on hand, and to be able to i
show an inspector the physical location of each individual shipment or i
prove that it has been properly removed or shipped for disposal.
Monitoring of packages before distributing them to individual users is required to prevent release of material from broken or otherwise contam-inated containers, and to allow notification of excessive working radiation levels when the packages are handled.
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After inventory forris and package monitoring have been completed, 4
i the individual who ordered the radioactive material will be notified by telephone that the material is available for disbursement.
The inventory record to be completed by the Radiation Safety Office is form NS-1020/1021, which consists of a cover sheet to be distributed l
to the user at the time of disbursal, and a second page that provides internal records for the Radiation Safety Office.
The second page,
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which provides space for detailed ' inventory information is filed according to a serially-assigned number when the shipment is received.
l This serial number identifies the radioactive material throughout its i
stay on the campus.
Radionuclide Disbursement Upon notification of the arrival of radioactive material, the user i
who originated the order may pick it up from the Radiation Safety Office or may send a designated alternate.
At the time of transfer, the l
individual who receives the material must sign for receipt of the material.
When the radioactive material is transferred to the user, the cover i
j sheet of the inventory form (NS-10200) will accompany the material.
The user is required to keep on this sheet cummulative records of withdrawals and ultimate disposition of the material. When the material has been completely used and/or disposed of, the sheet shall be returned i
to the Radiation Safety Office. This procedure will produce an estimate needed for management of the radioisotope inventory, i
Waste-Handling Procedures 1
i State and federal regulations, and the University's radioactive l
l materials license impose severe restrictions on waste-disposal methods.
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Radionuclide Total Actis its krial Nc..
Department Ordering indisidual Purcha,! Order Supplier Catahy No Date Rec'd _
Spesific Actisits Date Assased Total s ol. (w t.)
Fonn Inspected by Radiaison Lesel Smear Test
. Wire no User:
Retord all withdrawals from this sto(L in the space below.
Record w aste-disposal action on ba(L of this sheet.
Return this sheet to Radiation Safets Ofuer when you are l'intslied with tliis materlJI but Dniened Balance D npened
, \\ ot t a n Dose Lev No in utn it s ke n nis Vol ( = t )
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For this reason, waste disposal is centralized through the Radiation Safety Office.
Exceptions to this policy are specifically and indi-vidually considered.
Waste materials can be generally classified as:
1.
Miscellaneous solid waste (glassware, paper towels dissecting instruments, gloves,etc.);
2.
Major aqueous-solution waste (reaction solutions, primary dilutions of stock solutions, residual stock solutions, etc.);
3.
Minor aqueous waste solutions (third rinses from glassware, radioactively decayed solutions containing less than micro-curie amounts of activity, etc.);
4.
Major organic-waste solutions (see 2, above);
5.
Minor organic-waste solutions (see 3, above, and liquid scintillation counting solutions);
6.
Animal carcasses; 7.
Animal excreta, botanical wastes; bedding and 8.
Permanently contaminated equipment.
The only uncontrolled waste materials are minor aqaeous waste solutions (item 3. above), which may be disposed of directly to the sanitary sewer system via laboratory sinks (disposal through toilets and washroom basins is not pertnitted).
Wastes in user laboratories shall be stored only in approved and appropriately labeled containers.
Waste shall be segregated by solid, aqueous liquid, organic liquid and animal carcasses, excreta and bedding.
Radioisotopes with half-lives greater than 150 days may be combined provided no chemical hazard is created.
Radioisotopes with shorter halt-lives should be stored separately.
Each container of waste shall have a label to indicate the isotope (s) total content in millicurie and for short lived material the date the material was placed in the container ssould be included.
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The Radiation ' Safety Office on a routine basis will schedule radioactive waste pickups at the generating laboratories.
By prior arrangement wa:te may be brought to the Radiation Safety Office.
Waste will be disposed of in le of the following manners.
1.
Shipment to a radioactive waste burial site: Solid and organic radioactive waste with half-lives greater than 100 days will be disposed of in tiiis manner. Cost of disposal will be borne by the generator.
2.
Held for decay:
Solid, organic liquid, aqueous liquid radioactive waste and radioactive animal carcasses with half-lives of less than 100 days will generally be disposed in this manner. After holding for 10 half-lives, the material can be disposed of as ordinary waste. Note radiation labels shall be removed before placing this type waste into a radio-active waste container.
3.
Dumped to the sanitar.v sewer:
Water soluable radioactive waste, i.e., aqueous liquids can be disposed of in the sanitary sewer. The concentration of the radioactive waste and total millicurie quantity disposed per year is governed by state regulations. Note prior to disposing of radioactive waste in this manner the generator shall inform the Radiation Safety Office to assure that the concentration and annual quantity are not being exceeded.
4.
Designated as Hazardous Non-radioactive Waste:
Organic 3cingliatifE5 'nedium containing 0.05 microcuries of H'
C or I or less per gram of material may be disposed of as hazardous waste without regard for the radioisotope content. Note this is limited to the three radioisotopes listed above.
5.
- cineration: Disposal by incineration will be the favored method of disposal when incinerator facilities are available.
Note sealed sources and large pieces of glass and metal shall be segregated from other dry waste.
Disposal of radioisotopes by any of these methods requires that records of the amount of material disposed be kept.
It is the user's responsibility to keep a record of the source number from which the waste was generated and the amount generated.
Transfer and Shipment of Radioactive Materials Federal and state regulations restrict the transfer of radioactive materials, except in certain carefully specified situations, to persons holding valid radioactive materials licenses. A copy of the receiver's 15
license must be provided to the Campus Radiation Safety Officer before the shipment or transfer can be authorized.
The Radiation Safety Office will assist in the transfer, including providing specific information on packaging and labeling packages for i
shipment, and advice on acceptable shipment methods and applicable regulations and restrictions.
The department from which the shipment originates is expected to pay the cost of the transfer.
Records of l
transfers are maintained in the Radiation Safety Office.
When i
particularly hazardous shipments are received ce sent, records of personnel exposures, shipping-cask
- smears, and other pertinent i
information are maintained in the Radiation Safety Office.
Storage of Radioactive Materials j
Individual users are expected to keep on hand in their laboratories j
only those radioactive materials which they are actively using, or those s
which they feel must receive personal attention.
The intent of this policy is to reduce as far as possible the number of places on the I
campus where the security of radiological materials might be jeopardized in emergencies such as fires or explosions.
Space is available through i
the Radiation Safety Office for storage of radioactive materials which
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users wish to keep but are not actively using, or wish to submit to the 4
general University inventory stock.
All storage locations must be posted with approved radiation i
j warning signs, which are available from the Radiation Safety Office. No storage of radioactive materials in locations where food or beverages are also stored is pemissible.
Room 52 in the basement of the Nuclear Science Center is employed for 1,ng-term storage of small quantities of radionuclides, and for storage of all intense radiation sources that are not permanently l
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installed in separate locations.
The storage room is under the direct supervision of the Radiation Safety Office, from which permission must be obtained to remove radioactive materials and radiation sources.
Radioactive Materials Accountability The University is req"ired by the terms of its radioactive mate-rials license, and by state and federal regulations to be able to account for all radioactive materials under its control.
Records are maintained in the Radiation Safety Office of receipts, disbursals, transfers, and ultimate disposals of radioactive materials, as described in preceding sections of this manual.
Records in the Radiation Safety Office must reflect known locations and known users.
Individual users are expected to keep internal records of the radioactive materials they receive from the Radiation Safety Office, how they are used, what the current content of each individual bottle or vial is, and what material has been returned to the Radiation Safety Office. These records need not be highly formal nor extremely detailed, but they must provide the necessary information when it is requested by the Radiation Safety Office. The Radiation Safety Office performs a physical inventory each six months to verify records.
The Radiation Safety Office must be notified of exchanges of radioactive ma te rials among users, which requires approval of the Campus Radiation Safety Officer, and when radioactive materials are moved to a location other than shown on tSe disbursal record.
Certain specified materials on loan from the f?deral government require additional accountability procedures, which are the responsibil-ity of the Radiation Safety Office.
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Registration of Machines Producing Ionizing Radiation Regulations of the Nuclear Energy Division require that all equip-ment that produces ionizing radiation must be registered with the Division, which then issues a certificate of registration to the owner of the equipment.
The certificate must be posted on or near the machine.
The Radiation Safety Office has the responsibility for submitting registration applications.
Machine sources included under the regist.'ation requirement are diagnostic X-ray machines of all classes (e.g.,
field-portable, fluoroscopic,special-procedures, panoramic-dental,cystological,etc.),
therapeutic X-ray machines of all classes (e.g., deep-therapy, superfi-cial-therapy, supervoltage, etc.), industrial X-ray units, analytical instruments (e.g., diffraction, fluorescence, etc.), imaging instruments (e.g.,
scanning electron microscopes, etc.), and accelerators (e.g.,
Cockcroft-Walton, electron-therapy systems, etc.).
Although the Radiation Safety Office has the responsibility of completing registration forms, it is incumbent upon individuals initiat-ing purchase of radiation producing equipment to notify the Radiation Safety Office of the arrival of such equipment.
Such purchases must have been approved previously by the Campus Radiation Safety Officer and the Campus Radiation Safety Comittee through a
User-Project Application.
When an instrument is moved to a new location, or is transferred from the campus, the Radiation Safety Office must be notified to assure that records are current.
Physical inventories of radiation producing equipment will be made on an annucl basis.
Movement of a radiation producing machine from one location to another requires prior 18
authorization from the Campus Radiation Safety Officer, which will be granted only after preliminary safety and shielding analyses have been completed.
New Facilities Approval New buildings or renovated areas in old buildings in which radioac-tive materials or radiation sources are to be used must be approved by the Campus Radiation Safety Officer, the Campus Radiation Safety Comi ttee.
Additional review by the LSU System Radiation Safety Committee may also be required in certain instances.
Radiation safety personnel should be involved as early as possible in the planning of new facilities.
P, er design considerations can resul t in sigr ficant savings to the University by reducing initial costs and avoiuing expensive corrective alterations later.
Personnel Monitoring Every employee of the University and its consultants handling radioactive materials or using radiation sources of types and quantity such that it is possible to receive an exposure equal to or greater than 10% of the applicable radiation dose standard specified by the state of l
Louisiana shall be included in the radiation monitoring program.
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Long-term visitors, post-doctoral fellows and other such persons working with radiation as described above shall also be covered by the program.
Students who are enrolled in courses involving the handling of j
l radioactive material or use of radiation sources may be assigned to the radiation monitoring program.
The decision to assign or not to assign will be a joint decision between the instructor and the Campus Radiation l
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Safety Officer.
If a decision cannot be reached, the Campus Radiation Safety Committee will make the determination.
When persons are assigned to the monitoring program they will be asked if they know or have been told that they had received an over exposure of radiation.
If the answer is ' affirmative, the person will not be allowed to work with radiation until the past radiation exposure records have been obtained and evaluated.
For other persons, prior exposure histories will not be obtained unless they receive an exposure at LSU and A & M College of greater than 25% of the applicable radiation dose standard.
Body and extremity dositeters will be exchanged on a frequency from monthly to quarterly depending on the exposure potential and type radiation being monitored.
Good practice dictates, and state and federal laws require, that the University provide information to users that their radiation doses are within regulatory limits, and also that individuals be notified if their radiation doses exceed radiation protection guidelines.
The monitoring program includes, where applicable, personal body dosimeters, personal direct-reading pocket dosimeters, personal extremity dosimeters, rate-sensitive area monitors, portable survey instruments, portable and fixed air-sampling instruments, surface smears, and bioassay procedures.
'ersonal dosimetry devices are avail-able for detection of beta, X and gamma, and neutron radiations; supporting techniques allow assessment of alpha inhalation hazards.
At the time of approval, the Campus Radiation Safety Officer will determine what monitoring techniques are to be used for a project.
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Excessive exposure detected on a personal dosimeter requires immediate notification of the wearer, initiation of any appropriate medical assistance, and a determination of the cause of the exposure.
When necessary, Nuclear Energy Division and United States Nuclear Regulatory Commission offices will be notified of the incident.
These agencies can be of assistance in assuring the best available medical care, and also in procuring support personnel for fac ilities recovery.
Anyone who suspects an over-exposure should report this insnediately to the Campus Radiation Safety Officer, who can be reached at the telephone numbers listed at the fror,t of this manual.
Records of individual radiation dose histories are maintained in the Radiation Safety Oftice.
Incividuals are encouraged to check their records.
The Radiation Safety Office will respond to request for radiation exposure histories from employers after an individual leaves the campus.
Site Monitoring The Radiation Safety Office has the responsibility for monitoring all locations where radioactive materials and radiation sources are used or stored.
Site-monitoring checks normally are made at approximately three-month intervals; no notification for such a check is given.
More frequent site-monitoring checks will be made if unusual hazards exist, or if a significant change from the previous check is detected.
Users may request special checks on a one-time basis, or may request more frequent routine checks.
Site-monitoring checks include smears to estaolish removable contamination levels and where applicable portable-survey-meter 21
~'
measurements of radiation levels and surface contamination levels.
Checks also include visual inspection of working conditions, observations of operating techniques, storage of waste, labeling of containers, posting of warning signs, radioisotope disbursement records, instrument calibration and discussions with site personnel to suggest improvements in radiation safety practices.
Because Radiation Safety Office personnel cannot be present for frequent monitoring in every laboratory, users are encouraged to monitor their own facilities on schedules tailored to their special needs.
Records of laboratory monitoring by users must be maintained in the laboratories; these will be reviewed periodically by the Campus Radiation Safety Officer.
Corrective recommendations in writing will be sent to the principal investigator.
Memoranda to the Radiation Safety Committee may however, become necessary in the event of persistent problems.
Special Services Personnel in the Radiation Safety Office and the Nuclear Science Center are available for consultation on all problems related to radiation hazards and their control.
l l
l I
f 22
PRACTICE I
)
Guidelines, policies, and rules for the practice of radiation safety on the LSU and A & M College are presented in the following sections of this chapter.
General Rules for Radioactive Materials 1.
Eating, drinking, smoking, or the application of cosmetics are not pemitted in areas where radioactive materials are used or stored.
2.
Personnel monitoring devices (TLD badge, pocket dosimeter, finger badge, wrist badge) prescribed for the area must be worn.
3.
Protective clothing (gloves, laboratory smock, coveralls, respirator, shoe covers, etc.) prescribed for the area must be worn.
4.
Proper containment (absorbent paper,
- trays, secondary liquid containers) required for the operations must be in place.
5.
Fume hoods are to be used for all operations that potentially involve release of air-borne materials, iaciuding gases, volatile compounds, and dusts and aerosols (minimum air flow shall be 85 fpm).
6.
Prescribed radiation detection equipment and calibrated survey instruments must be available and known to be working.
7.
Work areas should be monitored when an operation is completed, or at the end of the work period.
8.
Radioactive materials must he stored and shielded in the manner prescribed for the area, and secured to restrict unauthorized persons from using or removing the material.
9.
All
- bottles, jars,
- boxes, and cabinets containing radioactive materials must be clearly labeled as to the radionuclide, quantity, and date, and initialed by the responsible person.
- 10. All entrances must be properly labeled with signs appropriate to the hazard, and posted with the names and telephone numbers of individuals to be contacted in emergencies.
11.
Initial runs on new procedures should be made with non-radioactive materials or less than 10 microcurie amounts of radioisotopes.
23
- 12. Procedures should be designed to reduce to a minimum transfers from container to container, bench to bench, and room to room as a means of reducing spills.
- 13. Radiation levels in' work areas should be determined before an operation is begun so that proper shielding and remote-handling equipment can be employed to reduce individual exposures.
14.
Individuals unfamiliar with radiation hazards and emergency proce-dures must not be permitted to work with radioactive materials.
- 15. Pipetting by mouth in areas where radiation materials are being used is forbidden.
- 16. All equipment, glassware, and other contents of an area in which radioactive materials are being used, or have been used, should be considered as contaminated until properly monitored.
- 17. Any injury, no matter how slight, involving radioactive materials must be monitored to determine if the wound is contaminated.
General Rules for Radiation-Producing Machines Electron microscopes, microprobes, and other instruments in which electrons are accelerated to energies in excess of 10 kev require registration by the State of Louisiana.
Many such instruments pose minimal radiation safety hazards.
Instruments in this class must be monitored annually and after maintenance which involves the radiation producing chamber.
Operators should, however, be thoroughly familiar with potential problems, and should request assistance if they believe that a problem has develcped.
The following rules apply to machines which yield intentionally externalized beams of ionizing radiation:
l l
1.
All operating personnel must be intimately familiar with the principles of operation, principles of radiation safety, and potential general and specific hazards of their particular
(
machine.
2.
Radiation surveys must be made annually, whenever beam-target 1
-specimen-detector geometry is changed, or whenever shielding l
arrangements are altered and after maintenance work, i
f 24
3.
System interlocks must be installed to assure that the equipment cannot be operated in an unsafe manner or when personnel are in exposure areas.
4.
For irradiation vaults, target rooms, and X-ray therapy and diagnostic rooms, both voice and visual comunication are desirable.
5.
Master-switch keys and secondary keys should be in the possession of the first person entering an exposure room, and that person should be the last to leave the room.
6.
Situations which require interlocks to be temporarily disabled requires prior approval of the Campus Radiation Safety Officer.
7.
For multiple-beam-port instruments, beam-port shields should be brightly colored to allow quick visual checks that they are properly positioned.
8.
All radiation-producing equipment inust have clearly visible warning lights to indicate when the equipment is generating radiation.
Additional caution lights are recorrrnended as a
redundant system for showing the machine status.
Warning-light systems should be wired to indicate when a light is not operational.
9.
Permanently installed radiation monitors and portable survey instruments prescribed for the installation should be available and known to be calibrated and functioning when the equipment is goiag to be activated.
- 10. A log of operations, in which both routine procedures and unusual situations are recorded, should be kept.
- 11. All operating personnel must be properly badged with individually assigned integrating dosimeter devices.
- 12. A written and oral practical examination, with results kept on file for new operating personnel is desirable before a new operator is allowed to work without supervision.
l
- 13. Operators should check radiation levels with portable survey instruments before entering an irradiation room.
14.
Emergency notification procedures must be posted, and l
emergency resonnee procedures should be reviewed with all l
persone:1 periodically.
- 15. Approved warning signs indicating the nature of the hazards must be posted at entrances to hazard areas, and the instrument console must be posted with a plaque indicating the nature and quality of the radiation produced.
25 l
16.- Unusual operations or unexpected machine behavior must be reported to the Campus Radiation Safety' Of fice imediately.
Signs, Notices and Labels Regulations of the Nuclear Energy Division require that signs be posted to inform the public of-the existence of a hazard in areas where radioactive materials and radiation sources are used and stored.
Posted sign: must comply with federal regulations, which are in agreement with international symbols for recognition of hazards.
These signs are printed with magenta ink on a yellow background, and bear the work "caution" at the top, the standardized three-bladed "propellor" symbol for radiation in the center, and a descriptive prescribed phrases denoting the magnitude of the hazard at the bottom.
The prescribed phrases are "RADI0 ACTIVE MATERIALS" for areas in which an individual is unlikely to receive a radiation dose in excess of 5 millirems in an hour, "RADIATION AREA" for situations in which dose rates are between 5 and 100 millirems per hour, and "HIGH RADIATION AREA" where dose rates are possible in excess of 100 millirems per hour.
Radiation Safety Office personnel will determine which regulation signs are appropriate for a location, and will supply the signs to the users. Users are required to notify the Radiation Safety Office prompt-ly if a sign is removed or defaced so that it can be replaced.
Two modiffr.ations of the legal signs are permitted under the cadiation safety program.
These include the addition of the phrase "X RADIATION" across the bottom blade of the propellor symbol on a radiation-area sign to be posted where X rays are present in an external beam, and the phrase "CONTAMINATION ZONE" across the bottom of the symbol on a radiation-area or high-radiation-area sign to be posted 26
where unco".i.ained radioactive material exists in a hazardous condition.
Hand-lettered-signs bearing other phrases are not acceptable substitutes.
In addition to signs indicating the presence of a radiation hazard, each area must be marked with a notice identifying individuals to be called in an emergency, and their current telephone numbers at the University and at home.
Individuals to be listed on the notice include:
1.
Principal user 2.
Alternate person knowledgeable of the specific area (if possible) 3.
Campus Radiation Safety Officer Emergency notices will be supplied by the Radiation Safety Office, which should be informed promptly of any changes.
_Ge_neral Rules for Animal Handling Involving Radioactive Materials Because of the variety of experimental animals and locations where they are employed for radioactive studies, only guidelines for handling such animals can be covered in this manual.
It is the responsibility of each user to supply detailed procedures with the User-Project Application.
General rules for the use of radioactive materials in experimental animals are:
1.
All project personnel, including animal
- handlers, fann
- workers, students, and technical personnel, must be fully in form the hazards posed by the project specifically, and radioactive materials generally; emergency procedures; and restrictions on areas, waste handling, carcass disposal, and procedures for cleaning facilities when the experiment is tenninated.
27
2.
All areas where experimental animals are housed, including holding pens, must be clearly posted with proper signs com-mensurate with potential hazards.
3.
No animal is to be kept, even temporarily, in an area not previously designated and posted for radioactive-materials use.
4.
Each cage, pen, or stall in which an animal dosed with radioactive materials is held must be clearly marked as to the nature, quantity, and date of administration of the material.
5.
Cages, pens, and stalls must be designed to facilitate thorough collection of excreta to reduce contamination levels.
Additional measures may be required for control of special hazards, such as feather dust from poultry or saliva from cattle.
6.
Dirt-floored holding areas are not acceptable for animals dosed with radioactive materials.
7.
Unless specifically authorized for a project, animais dosed with radioactive materials may not be pastured.
Similarly, small animals may not be returned to stock colonies.
8.
Animal sacrifice is permitted only in an area previously designated for this purpose and properly outfitted with nec-essary decontamination gear and waste-handling facilities.
Unless specifically exempted, blood cannot be drained to the sanitary sewer for disposal.
9.
All personnel must wear approved work clothes and protective equipment when handling radioactive animals and excreta, or working in the area where dosed animals are beir,g held.
10.
Portable survey meters sensitive to the emitted radiation from the radioactive materials must be available, calibrated and known to be in working order, and all personnel must be capable of using and interpreting the readings from these instruments.
- 11. All wounds on animals incurred in posted areas must be moni-tored for radioactive centamination, and reported innediate-ly to the Campus Radiation Safety Office if contamination is detected.
12.
Specific instructions for the collection, storing and dis-posal of excreta and carcasses must be approved for each user project.
- 13. Animals dosed with radioactive materials may not be sold, nor may they be used for human food.
28
- 14. Milk from lactating animals must be treated as excreta, and may not be sold or consumed.
- 15..treas where animals are dosed with radioactive materials mest be checked frequently for contamination by instrument surveys and wipe tests according to approved procedures.
General Rules for Field Use of Sealed Radiation Sources Sealed sources constitute a class of radioactive materials in which the radionuclides are compacted as high-integrity solids, and then encapsulated into two successive and independently sealed capsules to prevent the escape of the central radiation source.
These capsules are designed to allow useful radiation to penetrate the walls, while con-taining the radioactive material.
Both gama-emitting and neutron
-emitting sources are in the possession of the Universi ty, and are available for both laboratory and field experimental uses.
Gamma sources, and neutron sources to a lesser extent, designed for field use offer intense radiation fields, and therefore require special precautions, prticularly when exposed in open areas such as rice ponds and forest plots.
Field uses include radiographic insoections of the interior of test specimens, determination of soil density, and the estimation of soil moisture content.
Although gamma-emitting (cobalt-60, cesium-137, fridium-192, and radium-226) sources and neutron-emitting (polonium-beryllium, radium
-beryllium, plutonium-beryllium, americium-beryllium, and californium-252) sources are designed and utilized for a wide variety of procedures, similarities in field use exist.
The following general rules are applicable, subject to specific stipulations by the Campus Radiation Safety Officer and Campus Radiation Safety Comittee after review of a user's application form:
29
^
1.
Two individuals (e.g., a principal user and a helper) must be present whenever a sealed source is being used in normally uncontrolled areas.
2.
All personnel who may be involved as principal users and helpers must be trained in the operation of the exposure de-vice, and in the specific hazards relating to the device.
3.
Appropriate survey instruments, known to be calibrated and operational. ::.ust be in the possession of the source users in the field. Users must be capable of operating and interpre-ting the readings of the instruments.
4 The principal user must be capable of predicting and deter-mining the extent of radiological exclusion areas for the specific source in use.
5.
Signs reading "CAUTION, RADIATION AREA" must be posted at distances from the exposed source where readings indicate a dose-equivalent rate of 5 millirems per hour. A physical barrier (e.g., high-visibility rope) must be placed to en-close the area in which the dose-equivalent rate may exceed 100 millirems per hour, and signs reading, "CAUTION, HIGH RADIATION AREA" must be posted at this perimeter.
6.
Either the principal
- user, the helper, or a knowledgeable alternate must be within controlling distance when the source is in their possession in the field, and must have visual l
supervision of the source when it is exposed.
7.
A source must be logged out of and back into a storage area by the principal user.
8.
Sources must be locked and the keys to source locks must be in the possession of either the user or helper whenever a
(
source h not under visual supervision.
9.
The user and helper, and any other alternates, must be i
provided with badges (filn or TLD) and/or pocket dosimeters appropriate for the radiation emitted by the source.
t l
- 10. Vehicles may require warning signs and contain shipping l
documents when sources are moved between the storage location j
and the use site. This will be determined at the time the user-project application is approved.
r
- 11. Users, helpers, and alternates must be knowledgeable of pro-per emergency procedures for the source in their possession.
l 12.
Personnel in the Radiation Safety Office are available for discussion of special hazards, rules, regulations, and standards of good practice for field use of sealed radiation sources.
I 30
I 1
~
13.
Field use of unsealed sources cannot be undertaken without specific approval of the Campus Radiation Safety Officer and Campus Radiation Safety committee following review of envir-onmental impacts for the use.
General Rules for Decontamination Although Radiation Safety Office personnel are available to assist in decontamination operations, it is standard policy of the nuclear industry that the person who is responsible for contamination has the obligation to assume primary responsibility for decontamination.
Inmediate reaction to a contamination situation frequently can prevent serious side-spread problems. The order of priorities is:
1.
Well-being of involved individuals 2.
Prevent spread of contamination 3.
Decontamination of individuals 4.
Decontamination of facilities and equipment.
31
TH E LC C [5i.C. A 3 TATE C N i\\ E ?J !T' s u r ac pic;;-;pe...nc u t: +nce.u cc.. c 3 :
2 tu 39 ; N t y ! -r $ 6 * . A ' E 3 ra o R E O A t V c 70803-0101 LO Ci51 AN A 3ATON ROUCE errice or mc paesi:ce s e c ai s e e-a m October 17, 1986 Mr. William Spell Box 14690 Nuclear Energy Division Baton Rouge, LA 70898
Dear Mr. Spell:
Enclosed is the application for renewal of the broad scope by-product material license LA-0001-L01 issued to Louisiana State University.
It was our attempt te make this a complete. application and the renewal should be based on this submission and any future submission required for clarificatien or to accommodate progran changes.
It is our desire not to be bound by any submission prior to this date.
In our application, LSU is requesting the authority to incinerate radioactive waste at the Dental School at New Orleans (currently approved), the Medical School at Shreveport (the incinerator approved under the current license is no longer in operation), and at LSU and A&M College at Baton Rouge.
A ti=ely review and approval of that portion of the application pertaining to incineration of radioactive vaste at Shreveport and Baton Rouge will result this fiscal year in a saving of $10,000 - $30,000, depending'on when approval is received.
I leave it to your judgement as to whether this approval should be issued as an amend =ent to the current license or by some other administrative procedure.
The previous license permitted extensive laboratory teaching utilizing radiography sources and the operation of a Cockcroft-Walton 3
neutrun generator using R targets.
These activities ' are no longer conducted, nor are there any plans for such activities.
If plans change, a license acendment application will be submitted.
This application was coepiled by Dr. L. Max Scott, System Radiation Safety Officer, and was approved by the Systen Radiation Safety Committee.
If additional information is needed, please contact Dr. Scott directly; he will prepare the response and direct it through the System Radiation Safety Coe=ittee to this office for formal submission to you.
Sincerely, i
Allen A. Cop g
President Enclosure i
I 0FFict ust oNLY
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Supplement Index Pages Supplement to Item i 1
Supplement to Item 3 2-4 Supplement to Item 4 5-25 Supplement to Item 5 26 Supplement to Item 6 27-28 Supplement to Item 7 29 Supplement to Item 8 30-36 Supplement to item 9(a)
Administrative Structure 37-41 Radiation Safety Program Scope 42 General Objectives 43 44 Restrictions Procedures for Control of Radioactive Materials 45 49 Appreval of Users 50-54 Control of Radiation Exposure 55-61 Emergency Procedures 62 i
Approval of New Facilities and Renovations 63 Supplement to Item 9(b) 64-66 High Intensity Gamma Irradiation Facility 67-72 Subcritical Assembly 73-75 Supplement to Item 10 76-78 79 Supplement to Item 11 Supplement to DRC 13 80-83 Exhibit 1 Item 4 84-E8 Exhibit 1 Item 9a 89 Exhibit 2 Item 9a 90-91 Exhibit 3 Item 9a 92 Exhibit 1 Item 9b 93
- em 1.
The listed telephone number is for the Louisiana State University System Radiation Safety Officer, Center for Energy Studies, Baton Rouge, Louisiana, who has liaison responsibility with state and federal agencies on matters pertaining to radiological protection.
The Chairman of the Louisiana State University System Radiation Safety Comnittee may be reached at:
Louisiana State University LSU Medical Center Department of Biochemistry 1901 Perdido Street New Orleans, LA 70112 Area Code:
504 Telephone Number:
568-6585
l i
Item 3.
Radioactive materials will be used and stored at locations within the legal properties, auxiliary facilities, and rental properties of Louisiana State University, and at additional sites as listed below:
Louisiana State University and A & M College Baton Rouge, Louisiana 70803 including:
Ben Hur Plantation Perkins Road Farm (Agronomy)
Perkins Road Farm (Poultry)
Punnington Biomedical Research Laboratory Louisiana State University at Eunice Eunice, Louisiana 70535 Louisiana State University at Alexandria Alexandria, Louisiana 71303 Louisiana State University at Shreveport 8515 Youree Drive Shreveport, Louisiana 71105 University of New Orleans Lake Front New Orleans, Louisiana 70148 i
r including: Main campus East campus Louisiana State University Medical Center School of Medicine (New Orleans) 1901 Perdido Street New Orleans, Louisiana 70112 i
[
School of Dentistry i
1100 Florida Avenue e
New Orleans, Louisiana 70119 Florida Avenue Research Campus l
1100 Florida Avenue New Orleans, Louisiana 70119 i
4 6
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n
Item 3. (continued)
School of Medicine (Shreveport) 1501 Kings Highway Shreveport, Louisiana 71130 Agricultural Center Baton Rouge, Louisiana 70803 including: Burden Research Plantation Baton Rouge, Louisiana 70809 Dean Lee Research Station Alexandria, Louisiana 71302 hammond Research Station hammcnd, Louisiana 70401
!beria Research Station Jeanerette, Louisiana 70544 Idlertild Research Station Clinton, Louisiana 70722 Calhoun Research Station I
Calhoun, Locisiana 71225 Northeast Research. Station St. Joseph, Louisiana 71366 Hili Farm Research Station Femer, Louisiana 71040 Macon Ridge location, Northeast Research Statfori Winnsboro, Louisiana 71295 Pecan Research - Extension Station Shreveport, Louisiana 71135 Citrus Research Station Port Sulphur, Louisiana 70083 l
i 3
i Item 3. (continued)
Red River Research Station Bossier City, Louisiana 71113 Rice Research Station Crowley, Louisiana 70527 St. Gabriel Research Station St. Gabriel, Louisiana 70776 Southeast Research Station Franklinton, Louisiana 70438 Sweet Potato Research Station Chase, Louisiana 71324 Rosepine Research Station Rosepine, Louisiana 70659 Louisiana State University Memorial Forest Sheridan, Louisiana 70427 Louisiana Universities Marine Conso-tium Marine Research and Education Center Star Route Box 541 Chauvin, LA 70344 i
l Item 4 Members of the Louisiane. State University System Radiation Safety Committee, in addition to Paul M. Hyde, Chairman, are:
University of New Orleans, 1 member:
Gary C. Allen (Vice-Chainnan)
Director of the Nuclear Science Center, Baton Rouge:
Edward N. Lambremont (Secretary)
LSU System Radiation Protection Officer:
L. Max Scott Louisiana State University at Alexandria, 1 member:
James Marler Louisiana State University and A & M College (Baton Rouge), 1 member:
Donald L. Thompson Louisiana State
- iversity Agricultural Center,1 member:
Jerry B. Gr,ves Louisiana State University at Eunice,1 member:
Bayani I. h mirez Louisiana State University Medical Centers, 2 members:
William R. Gallaher-(New Orlearls)
Mary J. Wood (Shreveport)
Louisiana State University at Shreveport, 1 member:
Joseph W. Goerner Appointment of the members is accomplished through Memorandum from the President, PM-30.
A copy of this Memorandum is attached as Exhibit 1 of Item 4.
l 5
Item 4 (continuec)
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME: Dr. Paul M. Hyde POSITION:
Chairman, LSU System Radiation Safety Committee GENERAL EDUCATION:
School, College, or University Degree Year University of San Francisco BS 1947 University of California (Berkeley)
MS 1950 St. Louis University Ph.D.
1953 FORMAL RADIATION TRAINING:
Title or Descriotien Duration Dates (See attached sheet)
RADI0 ISOTOPE EXPERIENCE:
Description Isotope Max. Activity RADIOLOGICAL SAFETY EXPERIENCE:
(See attached sheet)
Item 4. (continued)
P.AD10'mTOPE EXPERIENCE: Dr. Paul M. liyde, Chairman, LSU System Radiation Safety Consnittee Experience Isotope Max. Amount Where experience Duration of Type of Use was Gained Experience mci St. Louis University 3 years tracer synthesis 14C* 3H University of Washington 4 years tracer research LSUMC 29 years tracer synthesis and research p
mci LSUMC 15 years student radiochemistry 2
laboratory s
5 mci LSUMC 15 years student radiochemistry s
laboratory 131 g, 1251 mci LSUMC 20 years student radiochemistry laboratory CS mci LSUMC 20 years student radiochemistry.
I laboratory i
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u.w.
- h sy.y y
Item 4. (continued)
FORMAL P.ADIATION TRAINING: Dr. Paul M. Ilyde, Chairman, LSU System Radiation Safety Committee Training Type of Training Wh?re Trained Dura tion On the Job Formal of Training Course i
a.
Principles and St. Louis University 3 years Yes No practice of radio-chemistry and rad-University of Washington 4 years Yes iation control Louisiana State University 29 years Yes Medical Center b.
Radioactivity St. Louis University 1 iear Yes Yes "3
measurement as,d University of Washington 4 years Yes monitoring techniques LSUMC 29 years les at.d instruments c.
Mathematics and St. Louis University 1 Year Yes Yes calculations basic University of Washington 2 Years Yes to the use and LSUMC 29 Years Yes measurement of radioactivity d.
Biological effects St. Louis Univer sity I Year Yes Yes of radiation University of Washington 4 Years Yes LSUMC 29 Years Yes
1 Item 4. (continued)
RADIOLOGICAL SAFETY EXPERIENCE:
Dr. Paul M. Hyde l
Dr. Hyde received his Ph.D. from St. Louis University in 1953 in Biochemistry.
During his tenure as a graduate student, he worked as an I4 AEC research assistant utilizing radioisotopes in the synthesis of C
labeled steroids.
Dr. Hyde ;oined the faculty of the University of Washington Medical School in Seattle as an Instructor in the Department o# Medicine responsible for radiochemistry studies in animals. He was the radiation safety instructc" for the department f aculty there for 4 years.
Dr. Hyde moved to Louisiana State University School of Medicine in 1957 and was chairman of the Isotope Committee locally and a member of the LSU Systen Nuclear Safety Committee for 1958 to 1965.
He started teaching Radioisotopes in Biological Research (including laboratory) to graduate students in 1963 and has taught it 22 semesters since then.
He was made chairmar of the LSUMC Radiation Protection Committee in 1977 and Radiopharmacologist at Charity Hospital in New Orleans.
In 1983, he was appointed Chairman of the LSU System Radiation Protection Committee.
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3
University of New Orleans Item 4. (continued)
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME:
Dr. Gary C. Allen POSITION:
Vice-Chairman, LSU System Radiation Safety Committee GENERAL EDUCATION:
School. College, or University Degree Year Stanford University BS 1961 Rice Uriversity MA 1963 University of North Carolina Ph.D.
1968 RADIOLOGICAL SAFETY EXPERIENCE:
Dr, Allen is a geochemist-petrologist who has over 24 years of experience in x-ray diffraction and spectrography. He is also conducting research in laser applications to mineral studies. Additionally he served 4 years as the Radiation Safety Officer for the University of New Orleans.
i 4
10
/
Item 4 (continued)
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME:
Dr. Edward N. Lambremont POSITION: Committee Member, Secretary, LSU System, Radiation Safety Comittee Director, Nuc', ear Science Center, LSU and A & M College GENERAL EDUCATION:
School, College, or University
. Degree Year Tulane University BS 1949 Tuhne University MS 1951 Ohio State University Ph.D.
1958 FORMAL RADIATION TRAINING:
Title or Description Duration Dates Radiotracer Techniques, LSU 4 mo.
1962 U.S. Dept. of Agric. Research training and experience 4 yr.
1962-66 Nuclear Science Center, Professor of Nuclear Science 20 yr.
1966-present Oak Ridge Assoc. Univ., Visiting Scientist 20 mo.
1967-present Sabbatical, leave, ) year, 1977 ORAU - Nuclear Power Training Course 1 wk.
1975 Isotcoe Max Activity Description 3
10 mci Tracer applications and research in H
I 10 mci the life sciences, physiological C
and bior.hemical processes 32 20 mci P
35 1 mci 5
SI 10 mci Cr 65 20 mci Zn 66 10 mci Rb 13I 20 mci I
60 kilocurie Radiation biology of insects Ce Neutron Sources (HPRR)
Radiation effects on insects 1.
a.
,-g 4
La.
45
>s u
_a--.J Item 4. (continuec:
RADIOLOGICAL SAFETY EXPERIENCE:
Dr. Edward N. Lambremont I
Dr. Lambremont has worked for 25 years with millicurie amounts of 3, 14C, 32p, 65Zn and other nuclides in physiological and biochenical g
research, and has advised and consulted with students and other scientists and practicing physicians during thi: period in isotope applications in the biomedical sciences. He has taught basic and advanced Nuclear Science courses at Louisiana State University since 1967.
In addition to the above radioisotopes he has had experience in research and teaching using 22Na, 353, 36C1, K, 56Mn, 09Fe, 60Co 6534, 90Sr, 99MTC, 1253,137mB2, 137Cs,140La, 23 ), 210Pb, 2269a, Radium daughter Cf and numerous other f
252 7
nuclides and radiation sources including X-ray machines and kilocurie cobalt-60 irradiators.
He has variously held positions at the Nuclear Science Center of associate professor and professor of nuclear science, and presently is serving as the Director of the Nuclear Science Center, a position held since 1974 He serves as a radiation consultant to several corporations 4
and agencies in the private sector including the River Bend Nuclear Station i
of Gulf States Utilities, Inc. Flav-o-Rich Foods, Standard Brands Foods, the Ethyl Corporation, Dow Chemical Corp. and the U.S. Committee for Energy e
Awareness.
He holds the permanent position of visiting scientist with the Medical and health Sciences Division of Oak Ridge Associated Universities.
2 Biological Chemistry Laboratory and has represented ORAU by eight years of i
i.
service as the LSU councilor ar.d six years on the board of directors.
He also is a member of the medical staff of Mary Bird Perkins Cancer Center (a radiotherapy center) in Baton Rouge, La.
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Item 4. (continuec; RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME:
Dr. Louie Max Scott POSITION: LSU System Radiation Safety Officer GEf4ERAL EDUCATION:
School, College or University Degree Year Texas A & M College B.S.
1955 Purdue University M.S.
1959 Purdue University.
Ph.D.
1961 FORMAL RADIATION TRAlft!NG:
Title or Description Duration Dates (see attached sheet)
RADI0 ISOTOPE EXPERIENCE:
Isotoce Max. Activity Description (see attached sheet)
RADIOLOGICAL SAFETY EXPERIENCE:
(see attached sheet) e 4
13
Ite
'. (u n N e:
l RADIATION SAFETY EXPERIENCE W'TH FOLLOWING RADI0 ISOTOPES:
Dr. L. Max Scott Where Exo.
Duration of Radioisotope Max. Amount Was Gained Experience Tyoe of Use 3 H 100 mci LSU, Gulf 9 years tracers 50 Ci Gulf 8 years generator targets 10's Ci Union Carbide 16 years weapon related 14 C 10 mci LSU, Gulf 9 years tracers 22Na 1 mci LSU 1 year tracers 32 P 10 mci LSU 1 year tracers 35 5 5 mci LSU 1 year tracers 45 Ca 1 mci LSU 1 year tracers 51 Cr 1 mci LSU 1 year tracers 54Mn 1 mci LSU 1 year tracers 55 Fe 1 mci LSU 1 year tracers 59 1 year tracers Fe 1 mci LSU 57 Co 40 mci LSU 1 year Mossbauer effects 60 Co 4000 Ci LSU 1 year irradiator 100 Ci Union Carbide 16 years radiography 100 Ci Gulf 8 years static electricity eliminator 63Ni 30 mci LSU, Gulf, electron capture Union Carbide 25 years detectors 652n 1 mci LSU, Gulf 9 years tracers 86 Rb 5 mci LSU 1 year tracers 0
Item 4. (centinued' RADIATION SAFETY EXPERIENCE WITH FCLLOWING RADICISOTOPES:
Dr. L. Max Scott (continued) 90Sr 2 Ci Gulf 8 years petroleum research 50 mci LSU 1 year irradiator 125 I 125 mci LSU 1 year tracers I34 Cs 25 Ci Gulf 8 years irradiator 137 Cs 1000 Ci Gulf 8 years irradiator 600 Ci L S'J 1 year irradiator 192 Ir 100 Ci Union Carbide 16 years radiography 220 Ra 20 mC1 LSU, Gulf 9 years neutron sources 2"Th 10's Ci Union Carbide 16 years weapon related 233 U IC's Ci Union Carbide 16 years weapon related I
234 U 10's Ci Union Carbide 16 years weapon related 235 U 10's Ci Union Carbide 16 years weapon related 238U 10's Ci Union Carbide 10 years weapon related 23S Pu 10's Ci Union Carbide 16 years weapon related 239 Pu 10's Ci Union Carbide 16 years weapon related 10 Ci LSU, Gulf 9 years neutron sources 2#1 Am 1 Ci Gulf 8 years analytical instru-ments neutron sources 100 mci LSU 1 year neutron sources 10's Ci Uni:n Carbide 16 years weapon related 252Cf 200 mci Unicn Carbide, LSU, Gulf 25 years neutron sources e =
Item 4. (continuec' RADIATION SAFETY EXPERIENCE:
Dr. L. Max Scott (continued)
Eouipment Medical X-Ray NA Union Carbide health services LSU, Gulf 25 years Analytical X-Ray NA Union Carbide, analytical chemis-try LSU, Gulf 25 years Industrial X-Ray NA Union Carbide, LSU, Gulf 25 years radiography, Linear Accelerators NA Union Carbide radiography, neutron LSU, Gulf 25 years generators 16
Item *. (continued)
RADIATION SAFETY TRAINING: Dr. L. Max Scott Duration of Formal Type of Trainine Where Trained 7rainina On the Job Course
- a. Princioles Union Carbide 16 years yes and practices East Tennessee Chapter-Health 2 weeks yes Physics Society Western Penn.
Chapter-Health 2 days jes Physics Society yes
- b. Radioactivity Health Physics Measurement, Society 2 weeks yes Monitoring tech. Union Carbide and instruments Y-12 Plant 16 years yes Oak Ridge Assoc.
University 1 day yes
- c. Mathematics Purdue Univer.
4 semesters yes
& calculations basic to the use I
and measurement of radioactivity l
l
- d. Biological Batelle Northwest Effects of Lab.
4 days yes Radiation i
l
(
- e. Packing and Nuclear Energy 3 days yes Transportation Waste Consultants of Radioactive materials
- f. General Topics Health Physics Approx. 20-30 Professional different sessions Enrichment and ranging from 1 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> yes Continuing Education 17 i
Item 4 (continued)
RADIOLOGICAL EXPERIENCE:
Dr. L. Max Scott Dr. Scott worked as a health physicist for Union Carbide for sixteen years.
During portions of this time, he was administratively and technically responsible for internal and external radiation dosimetry and X-ray and radiography safety.
From 1977 to 1985, he was corporate director of radiation health physics for Gulf 011 Corporation.
In this position, he had audit and technical responsibility for some 30 state and federal licenses in Canada and the USA, and he was the Radiation Safety Officer for a large research center and a uranium mining and milling complex.
Since 1985, he has served as Radiation Safety Officer for LSU and A & M College at Baton Rouge and as Radiation Safety Officer for the statewide LSU system.
?
Item a. (continued)
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME: Dr. William Richard Gallaher i
POSITION:
Committee Member 1
GENERAL EDUCATION:
School, College, or University Degree Year Saint Peter's College BS 1966 Harvard University Ph.D.
1972 FORMAL RADIATION TRAINING:
Radioisotopes in Research, Harvard University 3 mos.,1967 RADI0 ISOTOPE EXPERIENCE:
Isotope Max. Activity Description 3 H 10 mci Tracer in Cell Culture Biochemistry 14 C
5 mci 35 5
1 mci 32 P
5 mci Labeling of Cell Culture and Animal lipids with Inorganic Phosphate l
51 Cr 1 mci Irracellular Labeling and Metauoproteins 125 1
1 mci L'abeling of Proteins in vitro.
RADIOLOGICAL SAFETY EXPERIENCE:
Dr. Gallaher has worked with radioisotopes in cellular biochemistry continuously since 1967.
Since 1973 he has been independently approved for radioisotope usage at LSU Medical Center, where he is currently Associate Professor of Microbiology, Immunology and Parasitology.
He
[
j has been a nember of the Campus Radiation Safety Committee for the i
i Medical Center since 1980, has served temporarily as acting RSO on an ad l
hoc basis at the request of the RSO, and has repersented the Campus Committee on the LSU System Ccmmittee since 1983.
i
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19 J
- en 4 (continued)
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME:
Joseph W. Goerner POSITION: Committee member GENERAL EDUCATION:
School, Colleoe, or University Dearee Year Rice University BA 1957 Louisiana State University Ph.D.
1966 FORMAL RADIATION TRAINING:
Title or Description Duration Dates RADIO!S0 TOPE EXPERIENCE:
Isotope Max. Activity Description PADI0 LOGICAL SAFETY EXPERIENCE:
Dr. Goerner has been Chairman of the Chemistry Department at Louisiana State University in Shreveport since 1968.
Prior to that tire he taught at the school of the Ozarks in Missouri, and served as the National Science Foundation Coordinator for summer teaching programs at LSU in Baton Rouge, which required frequent direct association with the Nuclear Science Center there.
He has had industrial experience with Dow Chemical Company and Shell Development Company.
r
Item 4. (continued)
RADIOLOGICAL OUALIFICATIONS AND TRAINING NAME: Jerry B. Graves POSITION:
Committee Member GENERAL EDUCATION:
School, College, or University Degree Year Mississippi State University BS 1955 Mississippi State University MS 1958 Louisiana State University Ph.D.
1962 FORMAL RADIATION TRAINING:
Title or Descriotion Duration Dates Radioisotope Methodology 1 sem.
1962 e
RADI0IS0 TOPE EXPERIEt:CE:
Isotope Max. Activity Description 14-C 10 mci Biological tracer,1 year RADIOLOGICAL SAFETY EXPERIENCE:
Five publicatic'.s on effects of gamma ra-diation and incorporaticn cf racioisotopically lateled substrates in insects.
C1
Item 4. (continued)
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME: James E. Marler POSITION:
Committee Member GENERAL EDUCATION:
School, College, or University Degree Year University of Miami (Florida)
BS 1962 University of Texas MS 1965 LSU Ph.D.
1969 FORMAL RADIATION TRAINING:
Title or Cescriotion Duration Dates Nuc Sci 4101 (LSU) 1 sem.
1968 Research Prob. Course (UT) 2 yrs.
1963/4 NSF Summer Fellcwship 3 mo.
1970 i
RADI0 ISOTOPE EXPERIENCE:
Isotope Max. Activity
Dr. Marler, as a microbiologist, has worked with the above isotopes in conjunction with various research projects.
Currently there are no isotope users at LSUA with the exception of sealed sources for Physics Lab calibration of intruments.
Item 4 (continued)
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME:
Dr. Donald Lynford Thompson, Jr.
POSITION:
Committee Member GENERAL EDUCATION:
School. College, or University Degree Year Rutgers University BS 1973 Colorado State University MS 1976 Colorado State University Ph.D.
1979 FORMAL RADIATION TRAINING:
1.
Formal coursework taken at Colorado State University, required for work with radioisotopes:
1977 R 400A Radiation Physics 1.0 cr.
R 4005 Radiochem. Tech. 1.0 cr.
R 400C Radiotracer Tech, 1.0 cr.
2.
Previous experience with radioisotopes:
15 1-labeled and
}rainedasgraduatestudentintheuseof H labeled compounds for radioimmunoassay at Colorado State University Have performed radiciodinations and have used radioimmuncassay techniques in research for the past 9 years at Colorado State University, Johns Hopkins University and Louisiana State University Have served on LSU and A & M College Campus Radiation Safety Comittee since October 1985 and currently Chairinan of this committee 2d
Item 4
( c on t i nue d ',
RADIOLOGICAL QUALIFICATIONS AND TRAINING NAME: Bayani I. Ramirez POSITION: Committee Member GENERAL EDUCATION:
School Degree Year Ateneo de Manila University BS 1969 University of Houston Ph.D.
1976,
FORPAL RADIATION TRAINING RADIO!S0 TOPE EXPER.ENCE Ameririum-241 Graduate work (Compton Scattering)
RADIOLOGICAL SAFETY EXPERIENCE e
/
2d
Item 4, (continuec)
RADIOLOGICAL OUALIFICATIONS AND TRAINING NAME: Mary J. Wood POSITION:
Committee Member GENERAL EDUCATION:
School. College, or University Degree Year University of Kentucky BS 1948 University of Arkansas Medical School MD 1966' FORMAL RADIATION TRAINING:
Title or Descriotion Duration Dates Radiology Resident 1968-71 Diagnostic 2 yr.
Therapeutic 9 ma.
Nuclear Medicine 3 mo.
(Formal Teaching Courses)
Physics of Radiology 1 yr.
Radiation Biology 3 mo.
Nuclear Medicine 1 yr.
RADI0IS0 TOPE EXPERIENCE:
Isotope Max. Activity Description I-131 Medical Diagnostic Amounts 1-123 Tc-99m Se-75 Ga-67 In-111 T1-201 Xe-133 Yb-169 Cr-51 1-125 RADIOLOGICAL SAFETY EXPERIENCE:
Dr. Wood has worked with medical diagnostic quantitics of isotopes since 1971 at the Confederate Memorial Mcspital, which later became the LSU Medical Center Hospital in Shreveport.
Dr. Wood is currently Chief of the Division of Nuclear Medicine and is responsible for the safety, supervision of isotope laboratory and technologists as well as interpretation of scans and in vitro tests.
She has her boards in American Board of Radiology and in the American Board of Nuclear Medicine.
i
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E5
i Item 5(a)
Radiation monitoring for LSU faculty, staff and students is con-ducted at LSU and A & M College, LSU Medical School (New Orleans, Shreveport) and the University of New Orleans.
Specific details are included in the radiation safety manual for each location (Appendix).
i l
Item 5(c)
The quantities cf radionuclides handled are such that there is no need for routine bioassay.
If as the result of an accident, bicassay is needed, services will be obtained from a commercial vendor.
The Nuclear Energy Division will be advised as to the vendor when bioassay is
(
conducted.
^6
Item 6(a)
Both direct probe measurements and smears for removable contamina-tion are employed for contamination surveys.
Routine probe measurements for radionuclides which emit beta radiation with a maximum energy greater than 0.2 MeV and gama emitters are made with a Geiger-Muller d;tector equipped with a 1.4-mg/cm window.
Smears are routinely taken with a polystyrene-fcan pad or absorbent paper.
Smears for beta enitters are measured by liquid-scintillation 3H, 14C and high energy beta dis-counting with the instrument set for crimination. Smears for gamma emitters are measured by gama counting
$ ).
with settings dictated by the suspected contaminant (usually 1
(
The person with primary responsibility for a given area will be 2
rctified promptly of contamination levels exceeding 100 pCi/100 cm (beta) or 25 pCi/100 cn2 (alpha).
Similar notifications will be made if direct measurement results exceed 50% of applicable allowable reading fcr the area based on the posted radiation warning signs.
Twenty-four hour notification to the Nuclear Energy Division will be given for incidents in which removable levels or survey readings are in excess of 100 times the internal notification levels, and imediate notification will be given to the Division for levels in excess of 1000 times internal notificatien levels.
27
Item 6(a), (continued)
University personnel are expected to request smear tests on all equipment transferred from areas where unsealed sources of radioactivity are handled.
Records of smear and survey results are maintained by the Campus Radiation Safety Officer on forms appropriate to each respective campus.
Permanently installed area monitors are considered essential for particularly hazardous locations where significant radiation levels could develop from loss of shielding or source rupture. Area monitors 60 are currently installed above the 00 irradiator pool at the LSU and A & M College Nuclear Science Center at Baton Rouge.
28
l ten 7.
Sealed beta sources larger than 100 uCi which are not stored under the direct control cf the Campus Radiation Safety Officer are leak tested at six-month intervals.
At the time sources are removed from storage, they are leak tested.
Sealed alpha sources larger than 10 uCi are leak tested at three-month intervals. Certain sources will be leak tested either more or less frequently at the stipulation of the Nuclear Energy Division.
Records of sealed-source leak tests are maintained by the individual Campus Dadiation $6fety Officers.
Analysis of leak test will be by procedures and instrumentation documented to have a limit of detection of less than 0.005 pCf.
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i. :-
- 2 I!a9 3.
Wa: a-:i::::a. :acnniques em loyec :y L:ui:iana Sta:e University include transfer ic a c:=ercial burial site, cecay in storage, incin-eration, as na:arcous waste, and dilutien to the sanitary sewer system.
Classification of Radioactive Waste.
For the purposes of dis-cussion in the licea.se-renewal applica:icn, the folicwing classification of wasta c:ntaining radicactive materials will be emolcyec:
1.
Waste centaining short-lived radionuclides.
II.
Very icw-specific-activity waste materials c:rsisting of acuecus and water-miscible crganic solutions.
III.
Inter ediate-and icw-specific activity wastes censisting of aquecus solu;iens and liquid crganic ma:erials.
IV.
Inter ediate-anc icw-specific-activity aas;e c:nsisting of miscellane:us solid refuse.
V.
In;armediate-arc icw-specific-activity wastes ::r.sisting of ger.eral biological materials, including be:anica'. materials, animal beddi'.g and animal excreta.
VI.
Animal carcan ts.
VII.
Waste materials requiring special handling, irclu:ing those presenting unusual radiatien hazards, explosive and combustible materials, toxic and pathogenic materiais, c:ntaninated large or heavy ecuipreent, and lar;e :uantities of mi'.d'.j-contaminated wastes.
30
- tem 8.
(continuec}
Disposal by Storace and Cecay.
Category I waste materials may be stored under suitable cenditions for a time sufficient to allow radioac-tive decay of the included materials to reduce the specific activity to exempt concentration, as defined in Louisiana Radiation Regulations Part C, Section C.4, paragraph (b), and tabulated in Schedule B of Part C.
For this purpose, the specific activity is calculated by the radioactive decay equations, and is based upon the average for all contents of a single container.
For mixed radionuclides in a single container, the decay calculation will be for the longest-lived substance, or the limit of disposability will be established for the most hazardous substance.
When the contents of a container meet the exempt-concentration criteria stipulated above, the container is checked with a survey meter to assure acceptable radiation levelt, as predicted by calculation, and then is treated as non-radioactive waste'for permanent disposal.
In general, radionuclides with half-lives shorter than 100 days are candidates for decay disposal, with stcrage times being on the order of ten half-lives.
Suitable conditions for storage include refrigeration or freezing for wastes subject to putrefaction, prevention of volatili:ation of low-boiling-point organic liquids, and similar pre-cautions to assure that inadvertent release of material prior to accept-able radioactive decay does not occur.
Dilution to ',he Sanitary Sewer System.
All Category :: and aqueous category III waste materials are generally disposed of t) dilution to the sanitary-sewer system.
Pricr tc cis;csal, the Ca-m Padiation Safety Of'icer verifies that tre racieruclide when dilu'.ec does not 31
5 Item 8. (continued) exceed either the concentrations tabulated in Louisiana Padiation Regulations Part 0, Appendix A, Table I, Column 2 or 10 times the tabulated amount in Louisiana Radiation Regulations, Part 0, Appendix B,
~
i ard that such disposal will not result in the total discharged for the year exceeding 1 curie (1 Ci).
In the dilution calculation it is assumed that 75% of the average daily water consumption is discharged to the sanitary-sewer systen.
Methods of discharge whether via laboratory sink or central dis-charge varies among the campuses.
Records of discharge are to be maintained by each Campus Radiation Safety Officer.
Because of the geographical separation of each of the major units of the University, and the improbability of compounded ha:ard to the general public by multiple discharges from each of the campuses, the restriction of Fart D., Section D.303, paragraph (r. 4), Louisiana Radiation Regulations, to one curie per year is interpreted to apply independently to each of the following operational units of the Univer-sity:
Medical and Dental Schools at New Orleans and University of i
New Orleans.
LSU and A & M College and Pennington Biomedical Research Laboratory at Baton Rouge.
l 1
Medical School at Shreveport.
The following units of the University are each restricted to sani-tary sewer disposal of cre-tenth (0 '.) curie cumulative per year:
LSU at A'.exardria; LSU at Eunice; and
~
LSU at Shreve:ert.
32
Discosal as Hazardous Non-radioactive Waste. Organic solvents in 125 3H,1 C and 1 in concentrations of not Category III which contain mere than 0.05 microcuries per gram of mediun may be disposed as hazardous waste without regard to its radioactivity in accordance with Louisiana Radiation Regulations Part D, Section D.306. The respective Campus Radiation Safety Officer maintains records of quantities of I
material disposed by this method.
Commercial Discesal Service.
Radioactive waste generated by the Universitywhichcannotbedisposedofbfothermeansisdisposedby transfer to a licensed commercial burial agent. Currently, the service i
l is provided by ADC0 Services, Inc., Tinley Park, Illinois 60477.
Competitive-bid regulations for the Universit; make the stipulation of a single company impossible.
It is ' anticipated that competitive bids for an annual contract will be sought; in such case, the Division of Rediation Control will be notified when the vendor changes.
6 Discosal by Incineration.
Combustible waste of any category is generally disposed of t., incineration.
Incineration takes place at the LSU Dental Schcol - Nee Orleans, LSU Medical School - Shreveport and LSU t
33 l
l Item S. Icentinued) and A&M College - Baton Rouge.
Charging of the incinerator is controlled such that no more than 50% of the allowable air concentration for any given radioisotope as spec;fied by Louisiana Radiation Regulation Part D Appendix A Table II will be released and that the mixture of radioisotopes will not exceed the results of the formula specified by Louisiana Radiation Regulations Part 0 Appendix A page 39-0.
To be conservative, when determining the allowable charge concen-tration it is assumed that only 50% of the rated stack flow is actually occurring.
Pertinent information for the incinerators are as follows:
LSU and A&M College:
I Location:
North of the Veterinary Medicine School Intersection of River Road and South Stadium Drive Model:
Consumat 550-P Waste Combustion Corporation Richmond, Virginia Capacity:
1080 pounds of Type IV waste 0
Operating Temperature:
1400 F i
Stack Flow Rate:
1105 cfm I
Stack Height:
22 feet above burner level Meteorological Data:
Prevailing wind from south and southeast at approximately 3 miles per hour.
Operational Constraints:
Radioactive waste incineration is limited to nights and weekend.
l 1
1 l
3;
Item S. (continvec)
Medical School-Shreve: ort:
Location:
Corner of Kings Highway and Linwood Avenue s
Model:
Consumat 225-P Waste Con,bustion Corporation, Richmond Virginia Capacity:
588 pound of Type IV waste 0
Operating Temperature:
1400 F Stack Ficw Rate:
1000 efm Stack Height:
36 feet above ground Meteorological Cata:
Prevailing wind from south at approximately 9,5 miles per hour Operational Constraints: None Cental School - New Orleans Location:
Roof of Dental School Building Model:
P-150 LA Inferno Associates New Orleans, Louisiana Capacity:
150 pounds of Type IV waste 0
Operating Temperature:
1400 F Stack Flow Rate:
1860 cfm Stack Height:
7 feet above roof (167 feet above ground) 1 Meterorological Data: Wind from the south at approximately 5 miles per hour I
Operational Constraints: None Disposal of radioactive waste by incineration is under the supervision of the Campus Radiation Safety Officer who is responsible for control of types and quantities of radioactive waste treated, for assuring that regulatory restrictiers are met and for maintaining all l
records pertaining to disposal ey incineration.
Daily operations are acco plis*ed by persons specifically trainec for this purpose, and authcrized by the Radiation $afety Officer.
3E
Revision 2 '.5-27 In addition to basic radiation safety training, the operation of the incinerator will be trained in the use of radiation survey meter, safe handling of radioactive waste and constraints of incinerator charging.
Incinerators are cleaned before and after each use for radioactive i
waste materials with the ash from such burns being storec in clearly and properly marked cans.
Crab samoles are taken and assayed for radioac-tive content so that the ash may be properly disposed, I
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Iten 9(a).
The radiation safety program for Louisiana State University is
. designed to meet the needs of a broad-scope radioactive materials license which encompasses the entire University System. The concept is that of maintaining careful control of all sources of ionizing radiation, while simultaneously providing maximum flexibility for the use of such sources in research and teaching activities.
Administrative Structure. Ultimate responsibility for radiation safety under the broad-scope license concept resides in the Office of the President of the University. The President has by official memoran-dum (see Item 4, Exhibit 1, Memorandum frnm the President, PM-30) designated the Chairman of the Louisiana State University System Ra-diation Safety Comittee as his authorized representative, and has made the Chairmar, administratively responsible for the radiation safety programs of the University.
This memorandum also has established the Louisiana State University System Radiation Safety Comittee to advise the Chairman of the Comit-tee in his administration of the radiation safety program. The Commit-tee is composed of representatives of the individual campuses of the University System, who are selected from the major disciplines in which L
radioactive materials and radiation sources are most likely to be used.
The System Radiation Safety Committee advises in the establishment of policies, rules, and guidelines for maintaining an effective radiaticn control pragram which is consistent throughout the University, and 37
Item 9(a). (continued) reviews and advises on activities of the Louisiana State University System Radiation Safety Officer.
The Committee r.ormally meets once during the fall semester, once during the spring semester of each academic-calendar year and once during the sumer, with additional meetings scheduled as required to discharge its responsibilities.
Emergency matters, and trivial business may be handled on an interim basis by an Executive Committee, consisting of the Chairman, Vice Chairman or Secretary, and the System Radiation Safety Officer, with all actions of the Executive Committee subject to review by the System Radiation Safety Committee in full at its next official meeting.
Meeting minutes are taken at each meeting and are maintained as permanent records.
Each campus on which there is a major use of radioactive mste-ials and radiation sources is authorized by pM-30 to establish a Campus Radiation Safety Committee to expedite action on matters pertaining to radiation safety on that campus.
The responsibilities of a Campus Radiation Safety Committee include approval (concerning radiation safety only) of grant and contract proposals to agencies outside the University, approval of user project's, approval of new construction and renovations, and review of the actions of the Campus Radiation Safety Officer.
The Campus Radiation Safety Committee may also establish special policies, rules, and guidelines for activities under its particular jurisdiction.
All actions of the Campus Radiation Safety Committees are subject to review by the System Radiation Safety Committee and by the System Radiation Safety Officer.
38
Item 9(a). (continued)
The following campuses have established Radiation Safety Comittees:
School of Medicine at New Orleans, jointly with the School of Dentistry School of Medicine at Shreveport University of New Orleans Louisiana State University and A & M College Louisiana State University at Shreveport
. :h Campus Radiation Safety Comittee must have a minimum of three members, but may have more members if the activities of the campus so Changes in the membership of a Campus Radiation Safety Comit-warrant.
7 tee may be authorized by the System Radiation Safety Comittee without notification of the Louisiana Nuclear Energy Division, and without requiring license amendment,
~
Each Campus Radiation Safety Committee meets as required to accom--
4 plish its responsibilities, but not less than once in the fall semester and once in the spring semester of each academic-calendar year. Meeting minutes are taken at each meeting and are maintained as permanent records. A Campus Radiation Safety Comittee may establish subcommittees composed of no less than three persons to provide efficient review services, with the actions of all subcomittees subject to review by the Radiation Safety Comittee, and all subet inittee actions being a part of the official Committee business.
Implementation and review for compliance with policies, rules, and guidelines established by the System Radiation Safety Committee has been f
39
Item 9(a). (continued) specifically assigned by the President of the University to the System Radiation Safety Officer.
The System Radiation Safety Officer-is vested with authority to act immediately in all matters adversely pertaining to radiation scfety involving University personnel engaged in Universi-ty-sponsored activities, or any other individuals on University proper,
ty. His review and approval are required on matters which may alter established practices and procedures for. control of radiation hazards within the University, including Campus Radi6 tion Safety Committee policies, rules, or guidelines that may conflict with those established by the System Radiation Safety Committee. The System Radiation Safety Officer is responsible for coordination of activities of Campus Radiction Safety Officers to assure uniform implementation of University-wide standards for radiation control.
Specific duties of the System Radiation Safety Officer include:
1.
Coordinating all licensing actions throughou't the University system, including the preparation of amendment applications and maintaining current valid licenses; providing liaison between regulatory agencies and campus committees, and personnel concerned with radiation safety; and ass $ ring that regulatory compliance is consistent and complete throughout the University system.
2.
Two site visits per year to each rampus where a radiation safety committee has been established. During these visits, a complete radiation safety program audit is conducted to ensure that license f
ccrditions, System Radiation Safety Committee policies and procedures and Campus Radiation Safety Committee policies and 40
5 l -
Item.9(a). (continuec) procedures are being complied with and/or followed.
Results of the audits with any recomendation are conveyed in writing to the Chairman of the Campus Radiation Safety Comittee and to the Chairman of the System Radiation Safety Comittee.
3.
Provide technical assistance and advice to the System and Campus Radiation Safety Comittees and Campus Radiation Safety Officers..
The actions of_the System Radiation Safety Officer are subject to review by the System Radiation Safety Comittee.
He is a permanent member of that Comittee.
4 The System Radiation Safety Comittee may authorize the appointment of one or more Alternate System Radiation Safety Officers to assure
(
continuity in the radiation safety program when the System Radiation Safety Officer is temporarily away from the University, i
With the approval of the System Radiation Safety Committee, a Campus Radiation Safety Officer may be appointed for each campus where radioactive materials or radiation sources are in use, or where the use is reasonably anticipated. Each Canipus Radiation Safety Officer is vested with the authority to act imediately to assure the well-being of l
individuals and the integrity of facilities within the jurisdiction of the campus. Tne Campus Radiation Safety Officer has responsibility for proper control and supervision of radiation sources and radioactive I
meterials within the carpus jurisdiction, and for approval of matters j
pertaining to licensing, users and assistants, proposals for grants and contracts, user projects, procurement, and facilities.
Actions of a I
41
1 Item 9(a). -(continued)
Campus Radiation Safety Officer are subject to review by the Campus Radiation Safety Committee, the System Radiation Safety Committee, and System Radiation Safety Officer.
A summary chart of Committee and Radiation Safety Officer orga-nization and inter-relationships is presented in Exhibit 1 of Item 9(a).
All Committees which have been authorized are shown.
Radiation Safety Program Scope. The Louisiana State University radiation safety program includes surveillance of:
1.
All radioactive materials, including natural and synthetic radionuclides in any chemical or physical form, except those specifically exempted in Part B, Sections B.4, B.5, and 8.7, and certain Generally Licensed Devices listed in Schedule A of Part B of the Louisiana Radiation r
Regulations:
2.
All radioactive materials, including natural and synthetic radionuclides, in the form of sealed sources unless specifically exempted by the Louisiana Radiation Regulations; 1
and f
f 3.
All radiation-producing instruments and devices which yield ionizing radiation, including X-ray diffraction and fluorescence instruments, electron microscopes, electron microprobes, and other electronic instrumentation which may potentially emit X-radiation incidental to its operatien.
l Generally Licensed Materials, according to System Radiation Safety Committee desires, are considered as being included in the sco:e c'
- tem 9(a). (continued)
-s surveillance of the radiation safety program where there is a possibil-ity that uncontrolled use would lead to possession exceeding applicable
-limits.
Exempt devices may also be included in the scope of surveillance if they are deemed to offer potential hazards for use within the University environment.
Surveillance is construed to be inclusive of all aspects of the control of radiation hazards to assure the well-being of University personnel and the integrity of University properties, and compliance with all applicable state and federal regulations, in keeping with standards of good practice.
General Objectives. The general objectives of the radiation safety program are:
1.
Assurance that all applicable state and federal regulations have full compliance; 2,
Assurance that University insurance restrictions are met; 3.
Assurance that state and local codes and ordinances I
have full compliance; 4.
Assurance that the integrity and usefulness of University facilities and properties are not compromised; 5.
Assurance that University personnel, students, and visitors are not subject to undue radiation exposure from radioactive materials or radiation sources; 6.
Assurance that the general public will not be subject to undue radiation exposure from activities on the l
University properties; 43
^
Item 9(a). (continued) 7.
Assurance that releases of radioactive materials to the environment are minimized, in keeping with "as-low-as-reasonably achievable" concepts of radiation control; and 8.
Assurance that maximum standards of good practice and safe handling of radioactive materials and radiation N
sources are maintained throughout the University System.
Members of all University System radiation safety committees, the System Radiation Safety Officer, individual Campus Radiation Safety Officers, and individual users are expected to maintain awareness of the general objectives. Users who fail to support the program objectives will not be permitted continued access to radioactive materials or sources.
Restrictions.
The broad scope by-product license radiation safety program at Louisiana State University specifically prohibits:
1.
The use of radioactive materials in any chemical or physical form, whether sealed or unsealed, for the intentional exposure of patients for the purpose of medical diagnosis or medical therapy of human beings; 2.
The possession of sufficient amounts of fissile (i.e.,
Special Nuc. lear Material) substances to achieve a critical mass in any gecretry, regardless of the geo-graphical separation of individual small accurts of fissile materials; l
- = -,
~ Item 9(a). (continued) 3.
The combination of fissile substances with neutron-energy-moderating substances in any amount or geometry capable of yielding a self-sustaining nuclear-fission chain reaction; and 4.
The use of students or University employees for the purpose of practice patients in the training of individuals in diagnostic X-ray techniques, unless there is legitimate need as determined by an attending physician or dentist.
The Louisiana State University System Radiation Safety Committee or a Campus Radiation Safoty Comittee may authorize, af ter appropriate study, additional general or local restrictions.
Procedures for Control of Radioactive Materials.
Control of radioactive materials within the Louisiana State University System'is maintained through review of grant and contract proposals, user proj-ects, ordering, receipt and distribution, individual use, storage, and waste disposal.
Cetails of the procedures for such controls vary from campus to campus because of local needs, including forms, reviews, supervision, and inspection.
Individual campus Radiation Safety Manuals appended to this anendment application contain descriptions of local practices.
(See Appendix) j It is a uniform policy of the University that individuals who anticipate the use of radioactive materials or radiation sources in the course of research or teaching activities, and seek funds from outside agencies to support such uses, must submit copies of the proposals to the Campus Radiation Safety Officer and to the Campus Radiation Safety 45
_. ~
y; s
' f:'
Item 9(a)
(continued) l Committee for'their reviews.
Reviews are specifically limited to matters dealing with radiation safety.
When an individual is awarded a grant or contract involving the use of radioactive materials or radiation sources, or when an individual wishes to initiate a research or teaching project supported by Universi-ty funds, the individual is required to submit a user-project application to the Campus Radiation Safety Officer and/or to the Campus Radiation Safety Committee for their reviews.
Reviews are for matters of radiation safety only. An individual user will be notified promptly of the decisions of the Radiation Safety Officer and the Connittee, with suggestions for revision if the review decisions are unfavorable.
(
An individual must receive approval for a user project before an i
order for radioactive materials can be placed, or before a radiation producing machine may be ordered.
Requis'itions are transmitted through regular campus channels, with the exception that the routing for radioactive materials orders must include the Campus Radiation Safety Officer for his review and signature.
The review includes determing that the originator has been approve'd for use, that the use is consis-
'N tent with the anticipated procedures described in the user-project z
application, and that the purchase will not lead to violation of license restrictions.
Purchasing agents and their administrative personnel have been alerted to question orders clearly stipulating radioactive mate-rials, and orders which are suspected to include radioactive materials, and to refuse to acce;:t a purchase requisition unless it has been 3
reviewed and signed as authorized material by the Campus Radiation 46
Item 9(a). (continued)
Safety Officer.
It is general practice to initiate radiation-control record forms at this time to assure that license limits for possession will not be exceeded inadvertently by purchase of other radioactive material through a subsequent order. Requisitions for ra-diation-producing equipment, or instruments containing licensable radioactive materials are expected to follow an identical routing to those for radioactive materials, and to require approval of the Campus Radiatior Safety Officer prior to issuance of the purchase order.
In compliance with law, the System Radiation Safety Officer must either provide for the vendor a copy of the University's radioactive materials license, or determine that a copy has already been transmitted to the vendor.
Emergency telephone orders must have prior oral authorization, verified later by signature on the purchase requisition.
Radioactive materials are expected to be ' delivered directly to the Campus Radiation Safety Officer, and purchase orders are to be so marked.
Exceptions are allowed to this general practice when a very short-lived radionuclide is involved, when the radioactive material is subject to rapid deterioration unles's properly stored, or in situations when an experimental project may fail without immediate application of the radioactive material.
For such cases the Campus Radiation Safety Officer may authorize direct delivery to a user. Those shipments which require package examinations in accordance with Louisiana Radiation l
Regulations Part D, Section 0.205 will be performed by the Campus Radiation Safety Officer or a designated alternate. These examinations include radiation measurement of the exterior of the package to 47
Item 9(a). (continued)
~~
determine the surface exposure rate for verification of the shipper's label, wipe testing the exterior of the' package to ascertain whether removable contamination is present, wipe tests of the interior of the package to check for removable contamination, examination of the contents to establish that the innermost container is intact, and determing the unshielded exposure rate for the innermost package to establish suggested handling precautions for the user.
The Campus Radiation Safety Officer is not responsiole, however, for establishing either authenticity of the packaged material or radiochemical purity except for checking container labelling against the purchase information.
External contamination or unexpected exposure rate at the surface of the package, removable contamination, or obvious damage to the primary container are considered sufficient reasons to stop transfer a
of the material to the user, with prompt notification of both the user and the vendor of the unusual observations. Lack of agreement between the purchase information and container label requires prompt notification of the user, who is then expected to reconcile the difference and to recommend an action.
If the radioactive material is deemed acceptable, the Campus Radiation Safety Officer records the shipment on appropriate Campus i
forms, and assigns an identification number to the containers in the shipment.
The records include sufficient information to establish radiological hazards for the material, the name of the user and the location at which it will be used, and the date of receipt. This record is retained in the files of the Campus Radiation Safety officer until I
l l
48 1
Item 9(a). (continued) the material has been fully used and disposed of, or'has decayed to negligible activity, at which time the record is transferred to an inactive file with a notation of disposal action and date. The purpose of this record is to provide the Campus Radiation Safety Officer with ready information on the nature, amount, and locations of all radioac-tive materials actively in use on the campus, or stored for potential use.
This record also provides information for preparation of inventory lists. Annually, a physical inventory is conducted by either the Campus Radiation Safety Officer or each user to assure that all radioactive material is accounted for.
Physical inventories may be performed at other times, either totally or partly, to verify on-hand materials.
After inventory records have been completed, a shipment of radioac-tive material is transferred to the user, with written acknowledgement of the transfer and the date of the transfer being retained by the Campus Radiation Safety Officer.
The user is informed by the Campus Radiation Safety Officer of any special precautions required for handling the material, or any unusual hazards that may be involved in the planned use of the material.
Direct control of the radioactive material becomes the user's responsibility with transfer of the material into his possession. The l
user is expected to maintain records of withdrawals from stock, applica-tion to experimental animals or other use, and disposal. Although exact material balance is not expected in these records, they must be suffi-ciently complete to permit estimation of the quantity of material in a particular shipment still in possession of the user at any time.
Users' 49
Iten 9(a). (continued) records are subject to inspection by the Campus Radiation Safety Officer or the System Radiation Safety Officer without prior notification.
Waste materials or other materials no longer wanted by a user are returned to the Campus Radiation Safety Officer for disposal.
Full details of waste handling are presented in Item 8 of this license renewal application.
Acoroval of Users.
Individuals who wish to employ radioactive materials and radiation sources on the properties of the University, or to use these materials and sources for official University projects at sites not under the control of the University, must receive approval from a Campus Radiation Safety Committee before the work is undertaken.
If the project involves unusual practices, or initiates a class of uses never attempted previously, the Radiation Safety Ccmmittee may forward the request to the System Radiation Safety Comittee for determination of University-wide policies, rules, or guidelines to be applied to the project or use.
The review process is initiated with applications for contracts or grants to agencies outside the University.
Proposals for such grants and contracts must be provided to the Campus Radiation Safety Officer or the Campus Radiation Safety Comittee prior to the time they are submit-ted for official signature and transmitted to the outside agencies.
Approval is required before the proposal may be signed.
Details of the routing and review process for each campus are contained in the ra-diation safety manuals appended to this renewal application (See Appendix}.
In general, review includes:
50
' Item 9(a). (continued) 1.
~ Determination that the individual submitting the proposal has sufficient experience with radioactive materials or sources required for the work to be able to perform the work safely (or that the individual will receive the proper training and experience before initiating the work);
2.
Determination that appropriate facilities are available to permit the proposed work to be accomplished according to the standards of practice for radiation safety set by the System Radiation Safety Committee and the Campus P.adiation Safety Committee, or that the necessary facilities will be operational before the work is initiated, including
(
written commitments from the University that renovations, new construction, er special equipmerJc will be provided; 3.
Determination that the proposed work is not in violation of license restrictions or state or federal laws (and, in some instances, local ordinances and codes), or that amendnent of the license to permit the work is possible; 4.
Determination that procedures are in keeping with all policies, rules, and guidelines; and 5.
Determination that personnel, other than the originator, who are properly trained in safe-handling practice for the radioactive materials or sources will be available if they are required.
This review is strictly from the view-point of radiation safety, and does not involve review of the scientific merit, quality of the
Item 9(a)
(continued) investigation or use proposed.
If the proposal is found deficient as suomitted, revisions and corrections may be suggested, and the proposal may be resubmitted for review after it has been amended. Written notice of the approval or rejection (with reasons) is provided to the originator, and indication of approval must be transmitted with the proposal to the University administrative offices.
Approval of a proposal to an outside agency is not an authorization for an individual to use radioactive materials or radiation sources.
In order to obtain authorization to actually employ radioactive materials of radiation sources, an individual must obtain approval for a user-project. The information required includes identification of the originator, including departmental and other identification, a descrip-tive title for the project, and the following reviewed information:
1.
Training and experience of the originator and all other individuals who will be handling radioactive materials l
or radiation sources under the project director (originator),
in sufficient detail to establish if the individuals involved l
are competent to accomplish the proposed work safely; 2.
The quantity and form of all radioactive materials expected I
to be on hand at any one time in the life-time of the project, l
with complete identification of the radionuclides present, or identification of the radiation source required for the work; 3.
The location at which the radioactive roterials or radiation source will be used, and any auxiliary locations where succcrting work may be performed; l
5?
4 Item 9(a)
(continued) 4.
Details of the procedures to be employed, facilities necessary for accomplishing the work, radiation safety equipment required, storage locations and security measures to be followed, and waste handling techniques, in sufficient detail to establish that policies, rules, and guidelines, and standards of good practice for radiation safety will be followed; and 5.
Approximate schedules for beginning and ending the program.
The user-project application form containing this information is submitted to the Campus Radiation Safety Officer or to the Campus Radiation Safety Comittee for review sufficiently i
early that questions can be resolved se+.isfactorily before work involving radiation hazards is undertaken, Review includes determinations similar to those for contract and grant proposals, with particular attention directed toward procedures, special-handling techniques, and facilities to be used.
If the project requ' ires amendment of the University's radioactive-materials license, the amendment must be secured prior to completion of the review. Review of a user-project application is for matters of radiation safety only, with comment on the quality of the project being reserved for other channels.
i The user-project must be approved before work may be undertaken.
l The results of tha review are transmitted in writing to the applicant,
[
l with reasons for rejection being provided, or special restrictions being l
el
--~
Item 9(a). (continued) clearly stipulated.
In the event of a rejection, the project director may resubmit the application after it has been revised, or may appeal to the System Radiation System Committee for evaluation of the Campus decision.
Records of all approved user-projects are maintained by the Campus Radiation Safety Officer.
Users are expected to notify the Campus Radiation Safety Officer of terminated projects; records of terminated project are transferred to inactive files for permanent storage.
User-projects may be amended in minor details by letter to the Campus Radiation Safety Officer, and his written concurrence.
Training required for users to qualify to employ radioactive materials and radiation sources in teaching and research projects varies with the nature of the hazards involved.
Inexperienced users normally are permitted to work only with "general-license" quantities under the direction of trained and experienced users; when the necessary expertise has been acquired, the users will be permitted to increase the quan-tities and hazard levels.
Inexperienced users, whether faculty, stu-dents, or technicians, may be required to take formal courses in tracer methodology and radiation safety before undertaking work with radioac-tive materials and radiation sources. Occasional short courses may be offered by senior users or Campus Radiation Safety Officere to af ford
~
workers access to formal training.
In some instances, because of the nature of a project, formal training and extensive experience may be stipulated as a specific requirement for all project personnel.
The level of trafr.ing and experience recuired for a project is judged during the review process. Areas of training shall include.
5a
Item 9(a). (continued) 1.
Principles and practices of radiation safety; 2.
Radioactivity measurements, standardization, and monitoring techniques, and instrumentation; 3.
Mathematics and calculations basic to the measurement of radioactivi ty; 4.
Biological effects of radiation; 5.
Handling and use of radioactive material; 6.
Radiation Limits; 7.
Applicable sections of the Louisiana Radiation Regulations; and 8.
Local campus procedures for management of radioactive materials.
Exemptions from one or more of these training areas may be granted when warranted, or when the user agrees to cooperative direction by a senior user.
4 Cor. trol of Radiation Exposure.
Louisiana State University recog-i nizes that the use of radioactive materials and radiation sources is an essential part of the teaching and'research programs conducted by faculty and students. The University simultaneously recognized its obligation to restrict exposure of personnel, students, visitors, and i
the general public.
In responding to this obligation, the University has adopted the philosophy of maintaining "as low as reasonably achiev-l able" limits (the ALARA concept) on the exposure of individuals to ionizing radiation and on the release of radioactive materials to the l
environrent.
l Control of radiation exposure is accon>plished by imposing an j
extensive radiation monitoring program on the radioactive-materials 95
Item 9(a)
(continued) control program. The latter restricts the uses of radioactive materials and radiation sources to individuals who have been through a comprehen-sive review process prior to authorization for use. This administrative l
process is supplemented by personnel dosimetry, contamination surveys, and radiation-area surveys during the time that the sources and radioactive materials are actually in use. Details of the procedures for these three surveillance techniques are presented in Items 5 (including Supplements to 5(a) and 5(c)), 6 (including Supplements to 6(a)), and 7 (including Supplement 7) of this license renewal application.
Specific campus procedures are included in the Appendix.
Radiation Protection Standards adopted by the University take l
cogni:ance of Louisiana Radiation Regulations (Part 0, Standards for Protection Against Radiation). Operations officially performed under the authorization of the University must'be conducted in such a way that it would be unlikely that an individual would assimilate within a critical organ (by inhalation, ingestion, or absorption) a quantity of radionuclide (or nuclides) that would commit the individual to an organ dose exceeding a specified standard. The Radiation Protection Standards employed by the University are tabulated on the following page for both personnel included under the "controlled" category working in restricted areas, and for the general public in unrestricted areas.
For this i,
purpose, controlled personnel are those individuals whose radiation exposure is monitored, and restricted areas are those ahere control and surveillance of radioactive materials and sources is established; the general public is not monitored, and unrestricted area are those in which there is no control of radiation sources or rad %ctive materials
Item 9(a). (continued)
(surveillance may, however, be maintained in unrestricted areas).
In each column of the table the values given are regulatory maxima, while those enclosed in parentheses are target values which are generally considered practicable with careful attention to standards of good practice.
r M
4 i
Item 9(a). (continued)
RADIATION PROTECTION STANDARDS Controlled Personnel in Restricted Areas Dose Commitment, rem" m
Type of Exposure Expos. Per.:
Year Quarter Emergencyl Whole body; head, trunk, 5 (0,5) 1.25 (0.125) 100 (12) gonads, lens of the eye, red bone marrow, active blood-forming organs Unlimited areas of the skin 15 (1.5) 7.5 (0.5)
(hands & forearms excluded);
other organs, tissues and organ systems (bone excluded)
Bone 30 (1.5) 10 (0.5)
Forearms 30 (1.5) 10 (0,5) 200(50) i Hands & feet 75 (1.5) 18.75 (0.5) 200 (50)
Values in parentheses represent "as-low-as reasonably achievable" a.
target commitments.
b.
Values for emergency-dose commitments are one-time-only life-saving cose comitments; values in parentheses are target comitments for timed entries.
I General Public in Unrestricted Areas Annual Dose Commitments, rem Type of Exposure Individual Population Avg.
Whole body, gonadal tissue, bone 0.5 (0.1)a 0.17 (0.1)a marrow, lens of the eye All other organs 1.5 (0.2)a 0.5 (0.1)a a.
Average annua: gonadal background dose-equivalent rate for Louisiana.
J-3 L
i
_.r_,
Item 9(a) (continued)
To work toward the "as-low-as-reasonably achievable" values tabulated, radiation safety personnel and individual users survey working areas by instrumental monitoring (both portable and fixed) and smear tests.
Specific action values may vary between carrpuses due to differing problems and protection philosophy.
See campus Radiation Safety Manuals (Appendix) for specifics.
Electronic devises that produce ionizing radiation, such as parti-cle accelerators, X-ray machines, electron microscopes, fluoroscope and similar instruments, are included in the radiation control program.
This equipment is thoroughly inspected for leakage radiation and general operational radiation levels when it is installed and annually thereaf-ter.
Checks subsequently are performed after maintenance or repair work, to assure that operating personnel'are not exposed to hazardous radiation levels.
Interlocks and other safety devices are inspected on a.n annual basis.
Diagnostic X-ray machines used in University infirmaries, athletic departments and teaching where human subjects are exposed, are inspected annually to assure that proper collimation and filtration are employed, and that Part F (Use of X-rays in the Healing Arts) of the Louisiana Radiation Regulations has full compliance.
All beginning students and University personnel subject to working
- th and around electronic devices that produce ionizing radiation are pov'ded with general rules for working with radioactive traterials.
A typical set of rules is included as Exhibit 2 of iter 9fa) of this na
9(a). (continued)
. renewal application.
Because of the variety of X-ray-producing equipment used at the University, no general set of rules for such equipment has been devised; however, it is a standard part of operating procedures for each individual with senior responsibility for a particu,-
lar piece of equipment to instruct new workers in safety matters as well as operations.
The Louisiana Division of Radiation Control Form DRC 3, "Notice to Employees", is posted where radioactive materials and radiation sources are used.
Each Campus Radiation Safety Officer has the responsibility of maintaining proper caution signs where radioactive materials and ra-diation sources are used or stored.
Indi'vidual users are expected to notify the Radiation Safety Officer promptly if a sign is removed, damaged, or becomes unreadable. All caution signs and posting rules comply with Part 0, Section 0.203 of the Louisiana Radiation Regu-lations. Additional special signs may be authorized by the System Radiation Safety Committee. All areas, rooms, storage cabinets, refrig-erators, and storage shields are posted.
In addition, users are expect-ed to label all containers of radioactive materials with labels, tags, or tape approved by the Campus Radiation Safety Officer.
Each device containing a radiation source, and each radiation-producing instrument which requires registration with the Louisiana Nuclear Energy Division ca
l Iten 9(a). (continuec) i is labeled with a radiation-warning plaque indicating the nature of the hazard.
Access to areas where radiation exposures might occur is controlled by limiting authorization of individuals; limiting door keys; maintain-ing radioactive materials in lo'.ked storage areas, cabinets, and con-tainers when necessary; requiring redundant safety switches and inter-locks on radiation-producing equipment, and by installing physical barriers when applicable. Additional source-security measures may be required in special situations, including direct observation by posted guards, to assure that unauthorized entry into a hazardous area does not 0 ". C u r.
Personnel dosimetry devices are provided to all persons who may be subjected to radiation exposure of a magnitude such that 10% of the applicable limit might be exceeded. Records are maintained on all monitored personnel. Cumulative radiation exposures are derived from radiation badges.
The Louisiana State University System Radiation Safety Committee, the System Radiation Safety Officer, Campus Radiation Safety Committees, or Campus Radiation Safety Officers may impose additional or alternate methods or radiation-exposure control to assure minimal individual exposures in unusual situations without notification of the Louisiana Nuclear Energy Division prior to the change.
This provisicn is required to permit prompt action in emergency situations, and is not intended to cuviate noti ficaticr, cf permanent policy changes.
i
Item 9(a). (continued)
Emergency Procedures.
It is'the responsibility of each Campus 4
Radia'. ion Safety Officer to establish detailed emergency plans and procedures for installations in which there is a potential for release of significant quantities of radioactive materials or the possibility for significant uncontrolled radiation exposure.
Although general procedures for emergency situations are published in each Campus Radiation Safety Manual (See Appendix), detailed plans f
and procedures which are not of general interest are maintained by the Campus Radiation Safety Officer and by the individual with primary responsibility for a particular installation. These procedures are j
available for inspection, and are provided to all persons working in such an installation.
Each Campus Radiation Safety Officer is required to provide all persons working in restricted areas with general emergency-procedure information. A typical quick-reference checklist is included in this anendment application as Exhibit 3 of Item 9(a).
~
i Emergency procedures developed for each campu. must provide infor-mation for:
1.
Notification of the Campus Radiation Safety Officer or alternate individuals knowledgeable of emergency l
practice in general and of specific local procedures; 2.
Notification of campus security personnel of the t
l occurrence of an emergency invciving radiation or l
i I
Item 9(a). (continued) t radioactive materials, and proper instructions on supporting actions for such emergencies; 3.
Alerting fire-fighting personnel-of the exis.cace of t
a radiation hazard or potential hazard, with instructions on precautionary methods to avoid exaggeration of emergency and to minimize their own individual exposures; and 1
4.
Obtaining medical assistance for exposed or contaminated persons who have been injured, including the names of knowledgeable medical doctors, and precautionary instructions to hospitals where it may be necessary to transfer injured persons.
The Campus Radiation Safety Officer or alternate must be aware of the reporting rer;uirements of the Louisiana Radiation Regulations, Part 0, Sections 0.402 D.403 and 0.404, and is required to comply fully with the stipulations of these sections. Ass'istance from the Louisiana Nuclear Energy Division may be reouested if an emergency situation warrants, or if no University personnel knowledgeable of radiation-emergency handling is availabic.
Aporoval of New Facilities and Renovations. All new facilities to be constructed by the University, and all renovations of existing facilities in whien the use of radioactive raterials and radiation i
sources is planned or articipated must be reviewed by the Campes Ra-c7 a
2 i
9%
Item 9(a). (continued) l System Radiation Safety Officer.
If policy questions are raised by the renovation or new construction, review by the System Radiation. Safety Committee may a!so be required.
The review will consider arrangements of wcrking areas, relation-ships between restricted and unrestricted areas, shielding ol rooms where significant radiation hazards may be expected, problems related to security of radioactive materials, control of accidental releares of l
t radioactive materiais within the 'acility or building, and the consequences of releases nf radioactive materials to the environment.
Item g(b).
(
t i
Through its radiation safety program, Louisiana State University 4
I has established procedures to assure that radioactive m&terials and radiation sources are used and stored in facilities which meet standards i
of good practice for the particular' radiation hazards involved. These t
provide for:
1.
Consultation with Carapus Radiation Safety Officers and l
the System Radiatien Safety Officer during initial l
planning of a new building or rerovation, with input to the selection of fume-hood design, laboratory t
arrangements, shielding, surface materials, and similar
+
matters; 1
l
Item 9(b).-(continued) 1 2.
Critical excmination of architectural drawings and specifications by Campus Radiation Safety Committees and I
Campus Radiation Safety Officers, the System Radiation -
Safety Officer, and for matters of general policy and unusual projects, the System Radiation Safety Committee; 3.
Inspection of completed facilities by the Campus Radiation 4
l Safety Officers and the System Radiation Safety Officer, with recommendations for corrective actions required before use of radioactive materials or radiation sources will be permitted; 4.
Personal examination by Campus Radiation Safety Officers of j
facilities in use to assure that they are being properly maintained, and that unauthorized changes h' ave not been l
made; i
5.-
Establishment of working-level restrictions by Campus l
Radiation Safety Committees and Campus Radiation Safety I
Officers for specific facilities, with particular attention to laboratories or other facilities not originally intended i
for radionuclide or radiation projects; and f
I 6.
Surveillance of facilities by Campus Radiation Safety Officers to assure that administrative restrictions stipulated for each 1 cation have full compliance, 1
Radiotracer apolications which involve especially hazardous nuclides er 'arge quantities of miniral-hazard materials are restricted i
i
Item 9(b).-(continued)
I to laboratories or other facilities specifically designed and construct-ed for such work.
Facilities in which X-ray machine are to be employed are designed according te standards set forth by the National Council on Radiation Protection and Measurements.
Conservative work-load, use, and I
occupancy factors are routinely employed for primary and suondary barrier calculations.
Shielding calculations for gamma emitting sources are based en National Bureau of Standards Handbooks.
For general neutron-shielding calculations, data and procedures from National Bureau of Standards Handbooks are utilized.
Conservative assumptions, as for j
X-ray, are made for gamma-radiation and neutron-radiation shielding calculations. All shielding calculations are veriftad by direct f
physical measurements after a facility has been completed. Whenever i
possible, facilities are inspected while under construction to assure that all shielding specifications are being met, and that shielding is properly installed.
The literature cited in the preceding paragraph, and the general philosophy of laboratory design and shielding calculations are included in this license renewal application'in lieu of detailed description of l
the general facilities of the University in which conventional proce-dures and carefully controlled quantities of radioactive materials are 1
utilized, or in which convention 91 X-ray equipment is installed. The l
Louisiana Nuclear Energy Division is routinely provided with detailed architectural drawings of all inajor construction in which the presence of potential radiation ha:ards is planned, with additinnal required f
information being supplied by the appropriate Campus Radiation Safety l
Of ficer er the System Radiatien Safety Officer.
L e-
Item 9(b). (continued)
In addition to the general facilities, Louisiana State University has established certain special facilities, which are described in the following sections of this Item.
High Intensity Garra Irradiation Facility.
This facility is located in the basement of the Nuclear Science Center LSU and A & M i
College campus. The facility consists of a well in the basement floor 15.5 feet deep by 6 feet in diameter, made of Gunite lined with stainless steel. The pool can be filled to a depth of 15 feet with demineralized water, which is circulated through a mixed-bed ion-exchange / filter column, with make-up weter added to maintain constant level.
The pool is covered with an aluminum walk-on grating, with a single hatch in the center to provide access to the pool during routine use. The grate may be removed for cleaning or sources handling, but only after unlocking padlocks whicn prevent retaining nuts from being removed from studs set into the curb around the top of the pool.
The pool hatch al m is padlocked in place when it is not in use.
L The pool is designed so that a'100,000-curie point source of cobalt-60 placed at a depth of 14 feet will yield a dose rate of less than 2 millirems per hour at critical-organ distance above the grate.
The present inventory (as of April 1,1986) of the two annular source 60 60 arrays, one being 460Ci of Co and the second being 3070 Ci of Co.
i Currently there are two formal source configurations located at the botton of the pool, one in the center and one near the west wall.
)
j i
='
ltem 9(b). (continued)
Each of these configurations is bolted to the bottom of the pool by means of studs fixed to a large source-positioning plate.
l Each of these irradiation assemblies is used by lowing the irra-f-
diation canister throuah the water into the center of the annulus, and retrieving t.he canister after a pre-calculated exposure time.
Both an.
electric hoist and manual handling are employed for lowering and raising the irradiation canisters.
4 An I-beam supported by A-frame members at the ends is positioned over the pool for source-loading and unloading operations.
For i
1 introducing sources into the facility, the shipping cask containing the sources is lowered into the stairwell at the entrance door, and then moved on rollers into the pool room up to the curb and adjacent to one of the A-frame supports.
Chains are attached to lifting eyes on the I
cask and to a hook on a chain hoist supported on the horizontal I beam; a second chain is attached to the lifting eyes on the cask cover and to a second hoist on the I beam.
Bolts holding the cask cover are loosened at this time, but not removed. With the pool grating removed and the l
water level in the pool lowered to accept the displacement of the cask, the cask is lifted and positioned over the center of the pool, and then i
is lowered until it is submerged several feet under the surface of the water. The cover retaining bolts are removed with remote tools, and the cask is lowered to the bottom of the pool. With the second hoist, the f
cask cover is removed to expose the sources, which are then lifted individual by remote tools out of the cask and placed at the side of the l
5 l
pool. When all sources have been removed from the cask, it is lifted 68
4 1
Item 9(b). (continued) out of the pool, after careful verification that it is empty and uncon-taminated, it is re-assembled, and returned to the supplier. The sources left in the pool are then arranged into the desired configuration, and the grating is replaced and locked into position.
l Frequent water samples are taken from the pool after new sources have been introduced for gamma-count checks against leaking or contaminated sources.
Removing sources from the pool for shipment to another location is accomplished by the reverse of the pool loading procedure.
While there is little likelihood that the pool will leak, loss of shielding water is considered as a major accident mode.
As a precau-I tion, a fixed monitor, which will sound a high-audibility horn, is located above the pool to detect loss of shielding and warn personnel.
l Whenever the horn sounds, entering personnel check radiation levels at both the emergency escape hatch in the ceiling of the pool room, and at l
the ma'n basement entrance door, and enter the pool room cautiously i
while continuously checking radiation levels.
If a high radiation level were found, the condition of the pool could be checked safely through the escape hatch, and water could be added with hoses brought in through 1
i the basement entrance should it be needed. A fire hydrant is immediate-l ly available fer introducing large volumes of water if a severe leak were to develop. Lead casks are kept on hand for temporary storage of sources were to become necessary te remove them to repair the pool.
If it were judged that the pool could not be repaired, and the leak was so l
severe tha; ne shielding water c ni: be contained, the sources could
N i
F j<
t i
b Item 9(b). (continued) simply be covered by concrete by their existing locations by remote procedure, or the pool could be filled remotely with sand which could be t
removed subsequently when a source-recovery procedure was developed.
A second maximum-conceivable accident would be'the rupture of one or more sources, and dissolution by corrosion of the radioactive metal, I
followed by collection of the ccbalt on the resin in the ion-exchange bed so that an intense unshielded gamma source would exist in the pool room at floor level.
For the current pool inventory, simultaneous rupture and ccmplete dissolution of two of the 50st intense sources l
would lead to approximately 500 curies of cobalt-60 trapped in'the i
t unshielded resin-bed vessel, resulting in an exposure rate cf approxiinately 400 mP./hr through the ceiling to the floor of the offices j
{
immediately above, and approximately 41 k/hr at both the escape-hatch cover and at the entrance to the pool room. Several options are i
i available for recovery from this tituation, including competitive
{
desorption of the cobalt from the resin and returning it to the pool, from which it could be recovered in' controlled quantities; remotely cutting the plastic piping loose from the resin-bed vessel and dumping it into the pool, where it could be dismantled remotely and the resin loaded into burial containers in small quantities; or the vessel could I
be cut 'cose, removed from the basement intact and placed into a large l
shipping vault constructed on a flat-bed truck, and transported under r
escort to a het cell for dist antling and removal of the contaminated i
resin in small batches for subsequent disposal, The likelihood of this I
madrum incice-: is remote to the extent of being nearly impossible
.n
I rh Item 9(b). (continueo) 4 because of the improbability of flash-dissolving' cobalt metal in i
distilled water.
The maximum probable incident for this facility is the corrosion penetration of a weld to allow leakage of the cobalt into the.circulat-
~
ing pool water, which would be detected before external radiation levels became serious. The difficulty here is how to determine which source i,s leaking so that it could be removed from the pool, and then decontaminating the pool water or otherwise disposing of it. Each individual source holder would be checked by placing it into a submerged isolation chamber, removing the water, and then pressurizing with pure r
helium to a pressure of 100 PSIG for 30 minutes. Then the helium would be removed by a nitrogen purge and a vacuum pulled to approximately 50 microns of mercury absolute pressure. At this time the gas removed from the isolation chamber would be routed to' Helium Mass Spectrometer leak Dectector for analysis. The integrity of the source holder would be determined by comparison of the helium concentra; ion vs. time plot with results from a similarly tested stainless steel bar. This process would l
be repeated until the leaking source was located. The source would then be transferred remotely into an uncontaminated isolation container and then into a cask for shipment to a processor for disposal. Once the 4
leaking Source had been removed from the pool, the pool-water decontamination process could be undertaken.
Circulating the water i
through small disposable cation-exchange columns would be the most attractive option, with each column being carefully monitored to deter-j nine when a prescribed external radiation level had been reached. The i
column would then be replaced with a fresh one, and the radioactive 71
4 i
-Item 9(o). (continued) column would be placed into a shielded container for shipping to a disposal site. This process would be repeated until the remaining pool water was essentially free of cobalt.
The pool may be also used for storage of both cobalt-60 and cesium-137 sources not arranged into specific configuration.
Such sources would be available individually or collectively to experimenters for special irradiations. Only authorized personnel would be permitted i
to move these sources, using 20-foot-long handling tools.
Because the ceiling of the pool room is only 10 feet high, handling tools would be 4
manipulated into a vertical position up through the escape hatch before being introduced into the pool through the grating hatch.
Once the l
tools were introduced into the pool, the* escape hatch in the ceiling would be closed and sealed, thereby preventing the tools from being i
j removed from the pool.
Under these conditions, a source could not be brought closer than 10 feet below the surface of the pool, and i
I accidental exposure of handling pers'ennel thus avoided.
i Under special conditions, experimenters are permitted to modify the i
top of an irradiation canister to provide gas flow or coolant flow into the canister when it is in the irradiation position. This will intro-I duce channels which penetrate the shielding water, creating potential 6
e radiation-streaming conditions.
To avoid this problem, experimenters would be required to flex supply and exhaust lines into S curves or wide 1
arcs to assure tortuous streaming paths.
)
~
i r
I
' tem 9(b)
(continued)
[
i User-projects which employ the pool irradiator must be approved by the Campus Radiation Safety Officer.
The Campus Radiation Safety Officer maintains a file of_ individuals who have been trained and d
authorized to use the facility without direct supervision; all other e
1 users are required to work under the supervision of a staff member of the Nuclear Science Center or an authorized user.
Suberitical Assembly. A suberitical assembly has been established in the Nuclear Science Center LSU and A & M College.
It is fueled with aluminum-clad natural-uranium slugs (Savannah River Model MK Vita) with hollow centers for threading onto support members, and are moderated 4
with light water; conventionally, they are driven by isotopic sources (either plutonium / beryllium or californium-252) with neutron yields on 6
8 i
the order of 10 to 10 neutrons /second, and are operated at ambient l
temperature.
The device is not capable of sustaining a critical state.
1 The effective multiplication factor is approximately 0.88.
The location of the assembly is,as shown in Exhibit 1 of Item 9(b).
This assembly consists of a 1,100-gallon aluminum tank, coated on the l-inside with heavy epoxy-resin paint, into which individual rods containing five fuel slugs each are hand loaded. Gecmetrical i
positioning of the fuel rods is accomplished by a grid plate located in the bottom of the tank, with holes to receive the ends of the rods i
drilled in a hexagonal array. When fully fueled, the suocritical i
I i
l 73
T 4
a
!!em 9(b). (continued) assembly contains 225 fuel rods representing a total mass of 2,500-4 kilograms of uranium. When not in use, the rods are locked in a cabinet. The maximum background dose rate from the uranium is
~
approximately 5 mrem /hr at one foot from the cabinets.
l To reduce potential radiation problems, the water introduced into the tank is carefully de-ionized by circulated through a mixed-bed ion-exchange resin / filter unit. This system is designed so that the i
tank cannot be drained accidentally, s
With the suberitical assembly fully fueled and moderated, and 7
containing a driver source emitting approximately 10 neutrons /second, the dose-equivalent rate at the surface of the tank in the working area l
will not exceed 13 millirems / hour. This'value is based upon interpretation of neutron and gamma survey-meter readings, and calculations of prompt-gamma, fast-neutron, and capture-radiation dose i
l rates.
Because student class-room exercises with this subcritical assembly are limited to six consecutive hours, and the assembly is j
utilized for only part of planned laboratory activities, total semester exposure for a single student is not expected to be greater than 125 I
millirems.
The suberitical assembly does not present any severe radiation i
problem. The most extreme ha:ard is due to the driver source; these are, however, low-intensity sources for general use, and there'ere can i
i be handled safely by even inexperienced persons.
Loading and unloading the uranium slugs could lead to hanc deses (i.e., to the skin on the j
I IS i
Item 9(b). (continued) palm of the hand) of up to 300 millirems for an individual; therefore, it is standard practice for working personnel to share handling, particularly for the large assembly where doses are likely to be the greatest, and thereby reduce individual doses.
However, an experience, faculty or staff member is always present during the source transfer to and from the assembly.
e
I
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Item 10.
General Health Physics Instrumentation: 'The instrument inventory at Louisiana State University is quite large and due to the dynamics of research programs is continually changing.
Rather than provide a detailed listing of instruments, a general description of type of instruments is more appropriate as follovs:
=
Minimum Dose Rate Range Covered Instrument Type Number by Combination of Instruments Geiger Muller 25 0.1 mR/hr to 1.0 R/hr i
I Ion Chambers 5
0.1 mR/hr to 25.0 R/hr Bonner Ball (Neutron) 2 0.1 mR/hr to 10 R/hr Micro R Meter 1
0.01 mR/hr to 3 mR/hr P
Air Proportional (alpha) 1 NA l
Gas Proportional (alpha) 1 NA j
Instrument Calibration.
Portable survey meters employed for radiation-field measuraments where whole-body or partial-body personnel exposure may occur from either gamma-emitting or neutron-emitting sources are calibrated at approximately six (6) month intervals.
It is standard practice to calibrate a survey instrument whenever it is f
4 repaired.
Records of survey reter calibration are maintained by each Campus Radiation Safety Officer for the instruments on the campus.
These records, and the instrure"ts themselves, are subject to inspection i
by the System Radiation Safety Officer.
'E-
b Item 10.
(continued) i i
Three calibration sites have been established-for the University, located at the Medical Center at New Orbcis (providing service for the School of Medicine, the School of Dentistry, and the University of New Orleans), the Nuclear Science Center at the LSU and A & M College (providing service for all of the Baton RNge complex, and for Louisiana State University at Eunice, Louisiana State University at Alexandria),
and Pennington Biomedical Research Laboratories and the School of Medicine at Shreveport (providing service to the Medical School complex, and to Louisiana State University at Shreveport),
t Survey-meter calibration is performed with either cobalt-60 or-1 l
cesium-137 sources at Baton Rouge, with cesium-137 at Shreveport, and I
with radium-226 at New Sleans.
Source 1ntensities are known to within j
t10%, based upon published specific-gamma-ray constants (Radiological Health Handbook,-Revised Edition, 1970; p. 131).
For calibration, an instrument (or its radiation-sensitive element) is placed at a calculat-i ed distance fron the source such that the meter icading should be
)
i approximately two-thirds of full scale, the source is exposed, and the l
l actua'. reading is noted.
If the observed reading deviates by more than 15% of full-scale reading, the calibration potentiometers in the instru-i ment will be adjusted until an acceptable meter reading is obtained.
in many instances the calibration cotentiometers are adjusted to obtain the proper readirg even though the 15" criterion is not exceeded.
For routine survey instrument ct!ibration, the procedure is used to f
check a sirg'e point on the highest-range scalc. An optioral precedure I
t J'
Item 10. (centinued) is often followed, however; this includes two-point calibration on each scale, and a complete linearity determination for the scale which includes 5 milliRoetgens per hour.
Neutron-sensitive portable survey instruments are calibrated with a plutonium / beryllium neutron source.
The procedure for neutron sur-vey-meter calibration is essentially the same as that for gama-sensitive instruments.
(
/
, 1 b
3 A%
Item 11.
i 1
All general instrumentation at Louisiana State University is available to the radiation' safety program on a priority basis. Current r
general-purpose nuclear instrumentation is extensive, including lig-4 uid-scintillation spectrometers; single-channel analyzer systems; multichannel analyzer systems coupled to NaI(Tl or GeLi) detectors;
-l automatic gamma-counting systems; and a variety of proportional count:rg systems (boththin-windowandwindowless),end-windowGeiger-Muller counting systems, fillable ionization chambers for direct gas counting, r
high-geometry detectors, and supporting electronic equipment and general t
I laboratory preparative equipment.
Specific general-purpose equipment used frequently in the radiation safety program include liquid-scintillation counter for smear counting l
for hydrogen-3, carbon-14 and high energy beta emitters.
To assist in analyzing and identifying gamma-emitting radionuclides found on surface and sealed-source smears, the LSU and A & M College 2
Campus Radiation Safety Office has available automatic ganna counters and multichannel analyzers coupled to either sodium iodine or germanium i
detectors.
l i
L
)
v r
1
Supplement CRC 13.
Louisiana State University is requesting by this license renewal i
application an increase in the possession limits for general radionuclides with atomic weight from 3 through 226, inclusive, from 600 millicuries to 3000 millicuries of each, except as specified in the first section of Form ORC 13.
This possession limit is for the University in its entirety, and will be subdivided by the System Radiation Safety Comittee into pos-session limits for the individual campuses.
The current allocations for general radionuclide possession made by the Comittee are:
P LSU and A & M College, 925 millicuries of each Pennington Biomedical Research Laboratories radionuclide and LSU at Alexandria and Eunice Medical Center:
School of Medicine at New 925 millicuries of each Orleans, including the radionuclide i
i School of Dentistry l
School of Medicine at 925 millicuries of each l
Shreveport radionuclide LSU at Shreveport 25 millicuries of each radionuclide University of New Orleans 100 millicuries of each Uncommitted reserve 100 millicuries of each radionuclide i
It is the responsibility of each Campus Radiation Safety Officer to I
maintain records and to exercise controls to assure that the allocated possession limit for the campus is not exceeded.
If the use of radioac-I tive materials on a campus increases to a point that the general radionuclide allocation is restrictive, the Campus Radiation Safety Comittee may petition the System Radiation Safety Comittee for l
3[
r
k Su:pler.ent 3RC 13. (continued) an additional allocation. Normally, the increased allocation will be made from the unconnitted reserve, but it may also be withdrawn from another campus allocation if the use-level of radionuclides there is less than anticipated, i
j.
In addition to the increased general radionuclide possession i
limits, the University is requesting by this renewal application larger quantities of certain radionuclides in the general-radionuclide category, and additional radionuclides with stomic numbers greater than t
- 83. These additional quantities and additional radionuclides are
- pecified in the first section of Form DRC 13.
The possession limits for cobalt-60 and for cesium-137 of, respectively, 5 and 15 curies, in any form are requested to permit flexibility in the acquisition, use, and disposal of small sealed sources of these radionuclides and also to l
permit preparation of special-geometry s,ources for research purposes within the properties of the University.
Included in these uses are l
i special dosimetry calibration sources from commercial vendors.
l i
The request for hydrogen-3 is reduced from previous possession f
limits.
This quantity is adequate to cover tritium-labeled compounds
(
for general research purposes and gas-chromatographic detectors.
By this renewal application Louisiana State University is i
i requesting revision of previous seal-source possession limits as i
follows:
i' 1.
Radioactive material contained in soil and surface I
moisture / density gauges manufactureo and distributed by Troxler Electronic Laboratories, Inc. or Campbell Pacific l
Nuclear Corporation.
The maximum acti.ities and sealed sci.rce l
I I
61
~
trw Supplement DRC 13. (continued) identifications shall be limited to those specifically authorized for the device by the manufacturer's distribution license.
2.
Increase from 15,000 curies of cobalt-60 to 30,000 curies.
The current inventory consists of approximately 460 curies in t
the form of AECL Type A-CP-17-C encapsulated sources secondarily encapsulated by Budd Corp. according to LSU Drawing 108, 2120 curies in the form of Brookhaven National j
Laboratory Strip Source configuration, encapsulated by j
Lockheed Georgia Corp. according to LGNL Procedure Co-60-1; and 950 curies in the form of AECL Model C158 encapsulated j
sources.
This material is housed in the water-shielded gamma-irradiation facility des,cribed in detail in Item 9(b) of this amendment application. The University anticipates later 5
acquisition of cobalt-60 to increase the inventory to approximately 30,000 curies, but the quantity, supplier, and encapsulation details are not currently available.
l 3.
Cesium-137 sources in the fom of cesium chloride encapsulated in annular right cylinder according to Oak Ridge National I
l Laboratory Drawing B-RD-1430, to a total of 580 curies, i
4.
A possession limit of 230 micrograms (approximately 0.13 i
l curies) of californium-252 in the form of doubly encapsulated l
sources by Mound Laboratory.
i n-n-- - - - - - -.
in_ - - - - ~,
Supplement CRC 13. (continued)
Louisiana State University also requests continuation of its possession limit of 5,056 pounds of natural uranium in the form of hollow metal slugs clad with aluminum.
These slugs are for use in suberitical light-water moderated assentlies, and for other neutron-multiplication or shielding experiments reviewed and approved by the Campus Radiation Safety Officer and Campus Radiation Safety Committee.
At the present time the use of these aluminum-clad uranium slugs is restricted to the LSU and A & M College campus, specifically in the Nuclear Science Center.
Physical inventories (by count) are made each six months, and records of the inventories are maintained by the campus Radiation Safety Officer. No utilization records are routinely maintained, but unusual observations or occurrences are noted in full l
and filed by memoranda with the campus Radiation Safety Officer.
Details of the subcritical assemblies employed for laboratory demonstrations of nuclear-reactor properties are provided in Supplements, Item 9(b), of this amendment application.
\\
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THE L O 'J : 5 : A N A $ TATE U NIVE R SIT Y A N D A Q 4 6 l k = * = 9 A L A N o M E O M A % l C A ;is 00LbE0ESYSTEW at,Siv t e$ltv b a s tl=O n t :: mis t p
BATON R O U C E e L O U 151 A N A e ? 0 8 0 3 0101 ie.....
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October 1, 1986 MEMORANDUM TO:
Chancellors Bogue Caffey, Firnberg, Hawkland Mackin, Mu=phrey, Rigby and Wharton
SUBJECT:
LSU Systen Radiation Protection Program This memorandue supersedes FM-30 dated August 16, 1983.
1.
An LSU System Radiation Saf ety Co==1ttee is established to develop and implement a program to assure the proper and safe usage of radioisotopes, and other sources of ioni:ing ar.d non-ionizing radiation within the LSU System.
The position of Coordinator is created to control and coordinate the University Syste:r's radiatier. saf ety program.
2.
Membership on the LSU System Radiation Safety Committee shall be as follows:
I A.
the Coordinator of the LSU Syste: Radiation Safety Program, B.
the Chairpersen from each of the campus radiation safety co=mittees, or the equivalent, C.
the Director of the ';ucle a r Science Center located on the Baton Rouge campus, and D.
the Syste Padiatien Safety Officer.
3.
The Coordinator shall serve as Chair an of the Coc=ittee.
A Vice Chairman shall be elected from those te:bers of the Committee representing another ca: pus of the University System.
The Director of the Nuclear Science Center shall serve as the Secretary.
The Coordinator. Vice Chairman, Secretary and System Radiation Safety Officer shall serve as an Executive Cot-ittee with authority te conduct official business after polling the other corrittee =e=bers by tele;hene or mail.
The President shall lesignate as Coordinator any cember of the University System Faculty who is knowledgeable in the use of radiation and radioactive raterials.
The Coerdinator shall be administrative 1y responsible for the of radiation and radioactive caterials radiation saf ety necessary in the use l
required in the University System research, instructional, and service programs. This requires surveillance of all properties owned or controlled by l
the Unitersity System ami all persennel on or about these properties where the l
pcssibility of occupati m i e:< p o su r e to radiatirn or radioactive caterials I
exists.
i
i s
4 o
)
PM-30 October 1. 1986 Page 2 When medical exposure to patients occurs in University-ovned facilities for the purpose of diagnosis and/or therapy, the arount of exposure to the L
patient is the responsibility of the administering physician.
The overall radiation safety program for all other personnel, including the attending l
physician (s), is vested in the Campus Radiation Safety Officer of that campus.
The individual Chancellors, with the approval of the Coordinator of the System radiation safety program, shall appoint a Campus Radiation Safety Officer and a Campus Radiation Safety Committee if nuclear materials or other sources of ionizing or non-ionizing radiation are in use on the campus. These indivicuals shall be selected from those f aculty and staf f members having t
knowledge and work experience in the areas of radiation and radioactive materials. The Campus Radiation Safety Officers and Campus Committees will be i
j responsible to the System Coordinator for the proper control and supervision of projects utilizing radiation and/or radioactive materials on his/her campus.
On campuses where the only sources of radiation and radioactive l
materials consist of small teaching sources or those in analytical i
instruments, the Chancellor is only required to appoint a person responsible f
for radiation on campus, LSU System Radiation Saf e ty Cor.~ittee shall have direct responsibility f
i 1
for (a)
Licensing - all catters requiring and/or affecting the campus use of the t!niversity System's license or registration, and (b)
Supervision - of the i
activities of each of the Campus Radiation Safety Cormittees and of the i
j Radiation Safety Of ficer en those campuses without a Committee.
j i
j l
Approval of the Campus Radiation Safety Officer and the Campus Radiation I
Safety Cemmittee are required in:
i e
1 all responsible persens desiring to use radioactive i
a.
Personnel j
materials and radiation shall have acceptable training or f
g experience, i
all requisitions for radioactive materials and j
b.
Procurement radiation sources.
l Projects - all academic programs, research and developeent projects c.
and other University activities involving radiation and radioactive f
eaterials, all contracts and grants requiring use of
.I d.
Contracts and Grants q
radiation or radioactive materials.
f J
I Facilitier and Radiation Monitoring Equipmen_t,-
all University t
l e.
j activities requiring radiation or radioactive materials shall have i
suitable facilities and radiation eenitoring equipment to provide j
j i
acceptable radiation safety, r
i i
,. - - -,- -. - n
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PM-30 October 1, 1956 Page 3 f.
OSHA Regulations Pertainine to Ionizing Radiation - all University activities falling within the purview of the Occupational Safety and Health Act. Section 1910.96, entitled "Ionizing Radiation" are the responsibility of the ca= pus Radiation Safety Officer.
all g.
OSHA Regulations Pertaining to Non-ionizing Radiation University activities falling within the purview of the Occupartonal Safety and Health Act.
Section 1910.97 entitled "Non-Ionizing Radiation" are the responsibility of the Campus Radiation Safety
- Officer, h.
Imple=entation of Portions of the Electromagnetic Radiation all University activities utilizing equipment which Act (1968) potentially generates ionizing radiation incidental to its main purpose, such as microwave devices, video display terminals and television monitors, are the responsibility of the Campus Radiation Safety Officer with regards to occupational radiation safety.
5.
The LSU System Radiation Safety Officer is directly responsible for imple:entation and review of compliance with the regulations and policies established by the Syste: Coordinator and the System Radiation Safety Co==ittee.
The System Radiation Saf ety Of ficer is vested with the authority to act i= mediately in all matters pertaining to radiation safety involving LSU System personnel engaged in University sponsored activities or any other personnel on University property.
His/Her authority and actions, as defined in this memorandum, are subject to review by the System Radiation Safety Coccittee.
This assigned authority shall not relieve the individual fro = the normal review and authority of his/her depart = ental administration.
6.
An annual operating budget shall be prepared by the Executive Committee and submitted to the Office of the President no later than April 30 for the upcoming fiscal year.
This budget shall reflect all anticipated legitimate expenses related to regular meetings of the Co=nittee as-a-whole, meetings of the Executive Ccemittee, and duties of the System Radiation Safety Officer, as well as such emergency funds as may be required during the course of the fiscal year (esticated to be 10% or less of the total of the other expenses).
Said budget shall reflect reasonably equitable travel requirements of J
Coecittee members for the purpose of attending scheduled
- meetings, necessitating selection of meeting sites well in advance of each fiscal year.
Control cf she budget shall re=ain wichin the Office of Vice President for Acade:ic Affairs.
7.
Periodic revisiens of PM-30, when necessary, shall be accomplished after consultation with the LSU Systen Radiatien Safety Ce==ittee, since the me:bership of that Co==ittee is comprised of persens with experience, training, restensibility and authority necessary to implement the University Systet's radiation safety pregram.
PM-30 October 1, 1986 Page 4 8.
A current list of the individual members of the LSU System Radiation Safety Corr:ittee and their telephone numbers is attached to this memorandu= as an "ADDENDUM".
Ad &
hllenA. Copping'/
President 9
cc:
System Offices
"d-30 October '
'.9S6 Page 5 ADDENDUM TO PM-30 The following appoint =ents are made to the LSU Radiation Safety Co==ittee for t e r=s ending on September 30, 1988.
Previous addenda are hereby superseded.
Office Home Campus Telephone No.
Telephone No.
Coordinator and Chairman Paul M. Hyde MED CTR - NO (504) 568-6585 (504) 688-8321 Vice Chairman Gary C. Allen UNO (504) 286-6798 (504) 242-5026 Secretary Edward.N. La:bre=ont LSU-BR (504) 388-2163 (504) 766-4192 System Radiation Safety Officer Max Scott LSU-BR (504) 38S-2163 (504) 167-5519 Caepus Radiation Safety Cor=ittee Chairpersons Gary C. Allen UNO (504) 286-6798 (504) 242-5026 William R. Gallaher MED CTR-NO (504) 568-4076 (504) 242-2047 Joe Goerner LSU-S (318) 797-5087 (318) 868-9825 Jerry 3. Graves AC CTR (504) 388-1832 (504) 766-1632 Ja:es Marler LSU-A (315) 473-6431 (318) 443-5184 Bayani L. Ramirez LSU-E (315) 457-7311 (318) 457 1258 Donald !1. Tho pson LSU-BR (504) 389-4011 (504) 769-2630 Mary J. Weed MED CTR-SHREV (318) 674-6216 (318) 93S-7516 AP E R0'J ED :
v
[1 6 U jFFM October 1 1Gi' Allen A. Copping /. Tresi ent Date
/
thhibit I, it era (%: ;
President Chairman System Radiation System Radiation Safety Safety Officer Cornai t tee LSU and A & M College University of New Orleans Radiation Radiation q
g tiedical School Medical School I.SU Shreveport Radiation Safety Conuni ttec *
- Radiation Safety rkw Oricans Shreveport Consni ttee Conrni t tee Radiation Safety Radiation Safety Coneni ttee*
Consni t tec rch Laboratory Joint with the School of Dentistry and Pennington Biomedical Re.
e Joint with the Agricultural Center es
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E:,M ib i t 2 !!c 9 L2 h
t Nucietr Science Center Lt: oratory Rules j
1.
Radiation-exposure-history forms are to be completed or already on file before permission to work in the Laboratory can be granted.
l (Persons under 18 years old, or persons with known excessive i
i exposures must notify the instructor imediately.)
2.
Film badges must be worn in the laboratory, 3.
Appropriate protective clothing must be worn when loose radioactive materials are being handled.
4 4.
Protective clothing is to be left in the laboratory.
Do not wear potentially contaminated gloves, lab coats, etc., in the counting room.
5.
Working surfaces and protective clothing are to be surveyed for contamiration at the end of each work period, or at any time you l
suspect a spill. Report contamina icn imediately.
l 6.
It is mandatory that hands, shee soles, and street garments be checked for contamination before you leave the laboratory.
If l
contamination is detected, re;crt it imediately to the instructor while you are still in the laboratory.
7.
Operations while working in the laboratory:
a.
There will be no eating, drinking, use of cosmetics, or i
j cooking in the laboratory.
l b.
Assume that everything in the ' laboratory is potentially l
contaminated.
Monitor i.
l c.
Do not assume that the radiation level is safe.
Check l
it yourself.
r d.
Never pipette by mouth.
Use the various suction devices provied.
All potentially contaminated items, (glues, beakers, etc.)
e.
are to be disposed of into the "Hot Waste" can.
f.
Radioactive solutions are to be disposed of only in the "Fot Waste" bottle.
l j
l t
Consult the instructor for procedure before you clean any g.
contaminated equipmen*
a t
l h.
All radicactive preparations must be identified. Each l
bottle, flask, beaker, sealed counting source, etc., you prepare must bear the fclicwing information:
Radienuclide l
i Amount 7
l Cate prepare:
t J
icur name, l
l
(
l
. ~
2-1 Never work in the laceratory alone, j.
Do not operate ecuipment with which you are not familiar
, unless an instructor is present, k.
Report all personal injuries and emergencies to the instructor irrrnedia tely.
1.
Respect your co-workers, and keep good housekeeping in mind at all times, i
I I
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E'..h ib i t 3 Item 9(a)
TJ.DIATIO:: EYE 2GENCY CEEC'. '.3T r
O CLEAR AREA...........
go to the closest ' safe place f
get everyone out carefully help anycne who is injured OSEAL OFF AREA..........
post ;;uards to kaap people avr.y turn hoods and vatar of f baf ora leaving close doors behind you
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OCALL ICR EELP..........
Nuclear Saf ar-Office 383-n53, 385-5040 355-3231 University Police l
382-HELP [4357)
University Energency No.
- TELL WA* HAPPENED.........
Major spill Exposed source L
Air-borne centamination i
Fire or explosion Badly contaminated eajor injurf 1
f f
l
- TELL WHERE..............
1
- TELL WHO.........
l
- WAIT C:.C S E EY...........
Tie a handkore..ief around your arn f:: quick identification
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