ML20206T867
| ML20206T867 | |
| Person / Time | |
|---|---|
| Site: | 07000152 |
| Issue date: | 09/17/1986 |
| From: | Ford F PURDUE UNIV., WEST LAFAYETTE, IN |
| To: | |
| Shared Package | |
| ML20206T833 | List: |
| References | |
| NUDOCS 8610070211 | |
| Download: ML20206T867 (37) | |
Text
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C. RE=EWAL 0, uCENSs NUMetR ATTN: Gordon S. Born, Radiological Control VII1CEE, rnarmaCy DU1101Dg S. ADDRESS (ESIWHERS LICtfetto MAf TRIAL WILL St USIO OR POS$tS$to Purdue University West Lafayette, IN 47907 e
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PRIVACY ACT St ATEMENT Oss THE RivtRSE 9610070211 860917 l
PDR ADOCK 07000152 C
PDR l
Itco 5.
Material to be possoased Maximum amount which Element and Chemical and/or will be possessed Mrss Number Physical Form any one time
- s. Uranium enriched I. Spert fuel rods, enriched not to 81,000 g in the U-235 exceed 4.8 weight percent isotope
- 2. Fuel rods, enriched not to exceed 32,000 g 1.3 weight percent
- 3. Solid helices, enriched not to 200 g exceed 20 weight percent
- 4. Solid discs, enriched not to 10 g exceed 3 weight percent
- b. Plutonium I. Encapulated Pu-Be neutron sources 80 g Monsanto Mount Lab, Ser.#M-343, M-344, M-345 M-346, & M-347 now in possession
- 2. Waste as metal, salts, and nitrate Ig or chloride solution
- c. Natural Uranium
- 1. UO2 pellets clad in aluminum 11,760,000 g
- d. Californium
- 1. Up to 10 doubly encapsulated 0.007 g sources. Oak Ridge National Laboratories Sources, Ser.#NSD 94, 95, 96, & 97 now in possession
- e. Uranium - 233
- 1. plated on platinum
.01 pCi (10.5 pg)
- f. Neptunium - 237
- 1. Prefabricated calibration source 100 pCi
(.014 g)
- g. Plutonium - 238
- 1. Prefabricated calibration source 100 pCi
(.58 pg)
- h. Thorium - 230
- 1. Prefabricated calibration source 100 pCi
(.5 mg)
- i. Actinium - 227
- 1. Prefabricated calibration source 100 pCi
(.14 pg)
- j. Curium - 244
- 1. Prefabricated calibration source 100 pCi
(.12 pg)
Item 6. Purpose for Which Licensed Material Will Be Used The proposed use of U-235 enriched solid helices and discs is to measure the a.
ef fects of rare earth additions on the thermal properties of UO and to measure 2
Typical the ef fects of elevated temperatures on the mechanical properties of UO2 experimental proceduces will involve heating solid discs or helixices of various U-235 enrichment (3-20%) to a maximum temperature of 500*c for differential thermal analysis and 1600*c for thermal diffraction measurements. Helices will be heated in a vacuum furnace for measurement of mechanical properties, b.
Pu-239 will be stored as waste material until it can be disposed of.
The Pu-239 is in the form of metal foils, in solution as chloride or nitrite, or as salts. The material is no longer used for experimental purposes.
The encapsulated Pu-Be neutron sources are employed in activation analysis studies, for instrument calibration, and for neutron studies in a sub-critical exponential pile.
(Note: The natural uranium suberitical pile is separately licensed under Source Material License No.SUD-296) c.
Uranium-235 in the form of Spert fuel rods enriched not to exceed 4.8 weight percent, fuel rods enriched not to exceed 1.3 weight percent, natural UO Pellets 2
clad in aluminum, and californium in up to 10 doubly encapsulated sources will be used in the operation of a suberitical Fast Breeder Blanket Facility (FBBF). The FBBF is a small subcritical facility in which blankets of fast reactors can be mocked up in a realistic geometrical configuration. The FBBF has a central region composed of 4.8% - enriched fuel rods so as to provide the surrounding blanket mock-up with neutron spectrum typical of that found in the core blanket interface of a large LMFER. Natural uranium fuel rods are used in the blanket mock-up.
The 1.3%
enriched fuel rods were not used in the initial FBBF loading. The FBBF will be subcritical with K of less than 0.43.
The FBBF will be driven by Cf spontaneous gg fission neutron sources distributed along its center line. Up to a maximum of 0.007g of Cf possession is requested in order that the FBBF can be refueled to or near
4 Item 6 cont.
252 Its original levels of Cf at some time in the future. This would not occur until 252 the original Cf has decayed by about 2 half-lives. Neutron and gamma-ray transport will be studied in the blanket mock-up.
The experimental studies will include measure-ments of neutron spectra, foil reaction rates, fission distribution, and gamma-ray heating.
Procedures used in operation of the FBBF are reviewed for safety for the Radiological Control Committee by the Radiological Control Officer and/or his staff. The Radiological Control Committee is responsible to:
1.
Review plans, specifications, and procedures for operation of the FEBF and take appropriate action on same.
2.
Review any significant proposed changes in design or new operations for the FBBF. Committee approval or Radiological Control Officer approval is required in advance of initiating such changes.
3.
Approve research projects utilizing the FBBF.
4.
Authorize personnel to work in the facility.
5.
Oversee all radiation safety aspects of the operation of the FBBF, including routine surveys, leak tests, personnel monitoring, instrument calibration, emergency procedures, and inventory.
d.
U233, Np237, Pu238, Th230, Ac227 and Cm244 (Sections e-j of Item 5) will be used as calibration sources.
4 G.
S.
Barn, Resume of Training and E::perience Duration On of Formal the Type of Traintna Where Trained Trainino Course Job a) Principles and 1.
Purdue University 2 yrs Yes Yes practices of 2.
Purdue University 19 yrs No Yes radiation protection b) Radioactivity 1.
Purdue University 2 yrs Yes Yes measurement 2.
Purdue University 19 yrs No Yes techniques and i ns trunien ts c) Mathematics and 1.
Purdue University 2 yrs Yes Yes calculations basic 2.
Purdue University 19 yrs No Yes to the use and measurement of radioactivity d) Biological effects 1.
Purdue University 2 yrs Yes Yes of radiation 2.
Purdue University 19 yrs No Yes Statement of E:: per i enc e Where E;:perience Isotopu Manimum Amount was Gained Duration Type of Use_
Fe-55 & 59 3 mci Purdue 1 yr.
Tracer studies C-14, H-3 0 mci, 10 mci Purdue 10 yrs Synthesis 2n-65, Cd-115m 2 mci, 5 mci Purdue 4 yrs Tracer studies Tc-99m 400 mci Purdue 10 yrs Synthesis Z = 3-83 10 mci Purdue 15 yrs Teaching I-125, I-131 10 mci, 10 mci Purdue 10 yrs Teaching
& Synthesis Z = 3-83 High levels Purdue 4 yrs Campus RSO Co-60 7500 Ci Sealed Purdue 4 yrs Campus RSO Source
d Where Course Content Title of Course Trained Duration (See Type of Training)
Isotope Tracer Purdue 1 yr a), b), c), d)
Techniques & Lab Health Physics & Lab Purdue 1 yr a), b), c), d)
Radiation Biology Purdue 1/2 yr a), d)
X-Ray Health Physics Purdue 1/2 yr a), b), c), d)
Environmental Purdue 1/2 yr a), b), c), d)
Radiation Surveillance Additional Comments or Remarkst Radiological Health Fellow, 1964-1966 Taught Radiological Courses for 15 years covering items in Type of Training a, b,
c, and d.
Campus Radiological Safety Officer, 4 years.
r w,
Item 7. Individuals Responsible for Radiation Safety - Their Training & Experience 7.1 The current Radiological Control Officer is Gordon S.
Born. A copy of his resume of training and experience follows.
7.2 SNM for which possession is requested in this application is under the direct control of individuals of the Nuclear Engineering Department who have been authorized by the Radiological Control Committee, except for the Pu-239 (waste materials) which also may be under the control of the Radiological Control Officer and his staff. Direct control over the design and operation of the FBBF and the storage of SNM, source materials and By-Product-Materials will be under the direction of the Department of Nuclear Engineering.
FBBF Project FBBF - Laboratory and Assistant Laboratory Directors will be appointed by the Head of the Department of Nuclear Engineering.
Individuals appointed to these positions will have had formal training in their field and or sufficient practical experience to be considered qualified to assume the duties associated with the appointment. The responsibilities of the Project Director include the definition of the experimental and theoretical research topics, which will be done in cooperation with all principal investigators, and in coordination with specially designated representatives of the supporting agencies (Dept. of Energy and Electric Power Research Inst.).
The Laboratory Director and his Assistant are responsible for devising and performing the experiments on the FBBF, including the FBBF operation. The safety and security responsibilities of the Laboratory Director and his Assistant include:
- 1. Insuring that the FBBF facility is operated in compliance with license.
- 2. Preparing procedures for Radiation Control Committee approval.
- 3. Assuring that personnel have been approved by Radiological Control, and
- 4. Maintaining Physical inventory and daily records.
In matters regarding radiation safety, the line of authority for reporting purposes
F.
M. Cliteman, Resume of Tr ai ni ng and Enperience Duration On of Formal the lyoe of Traininn Where Trajned Trainino Course J o b_
(a) Principles and 1.
Montana State College 1/2 yr.
Yes No practices of radi-2.
Iowa State University 8 yrs Yes Yes ation protection 3.
Mass. Institute of Tech.7 yrs No Yes 4.
Purdue University 14 1/2 yr.
No Yes (b) Radioactivity mea-1.
Montana State College 1/2 yr.
Yes No surement techniques 2.
Iowa State University 8 yrs Yes Yes and instruments 3.
Mass. Institute of Tech 7 yrs No Yes 4.
Purdue University 14 1/2 yr.
No Yes (c) Mathematics and 1.
Montana State College 1/2 yr.
Yes No calculations basic 2.
Iowa State University 8 yrs Yes Yes to the use and 3.
Mass. Institute of Tech 7 yrs No Yes measurement of 4.
Purdue University 14 1/2 yr.
No Yes radioactivity (d) Biological effects 1.
Montana State College 1/2 yr.
Yes No of radiation 2.
Iowa State University 8 yrs Yes No Statement of Engerience Where Experience Isotope Ma::imum Amount was Gained Duration Type of Use Pu-Be 10 Ci Iowa, MIT, 29 yrs Activation Purdue
- analysis, reactor physics Uranium and Multitans MIT 7 yrs Enponential enpts.
Fission Products Z = 3-83 High levels Iowa, MIT, 29 yrs Reactor associated Purdue physics with reactors H-3 5 Ci MIT 7 yrs Neutron generator Uranium, nat.
Multitons Purdue 7 yrs Subcritical pile 1.3 L 4. O*/.
Enrichment Cf-252 4 Milligrams Purdue 7 yrs Subcritical pile 10 10 n/ set Reactor 1 twatt Purdue 14 yrs Operating a
Item 7 cont.
s is directly to the Radiation Safety Conunittee through the Radiation Control Officer. The current project director is Frank M. Clikeman. A resume of his training and experience follows.
s
Item 8.
Training for Individuals Working in or Frequenting Restricted Areas 8.1 Individuals.(new employees and/or students) are required to receive training in radiation safety. This radiation safety training consists of a training package (slides and tape,) which was developed by the Radiological Control Of ficer and his staf f, and is required viewing for all users of radioactive materials on campus. The contents of this training film meet the requirements stated in 10 CFR 19.
In addition, students in Nuclear Engineering associated with the FBBF facility receive the didactic instruction and laboratory training in traditional nuclear engineering courses. Evaluation of the didactic instruction is by examination since the material is covered in existing formal courses in Nuclear Engineering, and the students receis? college credit for their e f forts.
No refresher training course is planned for personnel since their usual stay the University is limited to a time span that precludes the need for retraining.
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Item 9.
Facilities and Equipment 9.1 SNM will be used and/or stored in three locations on the Purdue University campus. The three buildings are the Duncan Annex, the Pharmacy Building, and the Physics Building. Their location is marked on the map of the Purdue University campus.
(Figure 1.)
In addition, other locations may be used from time to time when approved by the Radiological Control Committee.
- a. Duncan Annex Storage Facility:
SNM are stored in Room B-84 of the Duncan Annex which is attached to the Electrical Engineering Building. The storage room is approximately 18 ft. 4 in. by 30 f t. 8 in. by 23 ft. high, as shown in FiFure 2 and 3.
The floor level is about 9 ft. below the outside ground level. The building is constructed of steel frame with concrete and brick and no window openings.
- b. Pharmacy Building Radiological Dispensing Facility:
Pu-239 waste materials will be stored in C-59 of the Pharmacy Building in a wall isotope storage vault Cat. No.310, Serial No.N-8938 and was manufactured by Ray Proof Corp Norwalk, Connecticut or in B-84 of the Duncan Annex (see above) in a safe.
- c. Physics Building Fast Breeder Blanket Facility Laboratory:
This laboratory will be operated as part of the School of Nuclear Engineering.
The laboratory is located in rooms in the Physics Building on the Purdue Campus.
(Figure 4.)
The building is constructed of steel frame with concrete and brick. The floor plan of the laboratory is shown in Figure 5.
The steel fuel storage cabinets (Figure 6 & 7) are fastened to the south-west wall of room B28 and are surrounded by a wire-mesh cage. The dimensions of room B28 are approximately 51 f t.
by 50 f t. by 20 ft. high. The floor level is about 8 ft. below the outside ground level and is about 30 inches above the floor level of the newer portion of the Physics Building.
The Fast Breeder Blanket Facilicy is located in room B28C as shown in
Item 9 Cont.
Figures 5 and 8.
The fueled portion of the facility is cylindrical with an outer diameter of 58 inches and a height of 48 inches. The facility is set on a concrete base approximately 24 inches below the floor level of room B28. The center of the facility is approximately 32 ft. 11 in. ~from the center of the nearest steel storage cabinet.
Room B28C is a concrete housing constructed within room B28 to enclose the FBBF. The walls and roof of room B28:have been designed so that radi-ation levels outside of room B28C will be acceptably low.
9.2 Criticality Alarms Two of the Remote Area Monitors are installed in the FBBF to serve as a radiation and criticality accident alarm system to meet the require-ments of 10 CFR 70.24 and ANSI N16,1969. Four criticality dosimeters are used to monitor the area. These dosimeters are Reactor Experiments type 708 dosimeters (or equivalent) containing six activation foils for neutron dosimetry and a thermoluminescent dosimeter (TLD) for gamma-ray dosimetry in accordance with requirements stated in 10 CFR 70.24.
9.3 Request for Exemption to 10 CFR 70.24.
We request an exemption to 10 CFR 70.24(a)(1) requiring an area monitoring system for the storage facilities for SNM located in Duncan Annex and the Pharmacy Building. The exemption is requested on the basis that the facilities are for storage only of the fuel, the helixis, and the waste plutonium. Numerous survey meters are available in the area at all times.
Item 10.
Radiation Safety Program 10.1 Personnel Monitoring Devices Film badges are generally used as personnel monitors of radiation exposure. Any person working with SNM is required to wear personnel monitoring devices whenever entering a restricted radioisotope area under conditions where he is likely to receive, in an calendar quarter, a dose in excess of 25 percent of the MPD based on a quarterly whole body MPD of 1.25 rems.
In addition, pocket dosimeters should be worn by personnel in addition to film badges in cases where exposure in excess of 25 percent of the daily MPD are anticipated. Pocket dosimeters may be utilized in lieu of film badges for individuals entering restricted areas on an infrequent or temporary basis. Criticality foils are re-l quired when an individual enters the room housing the FBBF assembly.
The film badges are read monthly. An annual review, not to exceed fourteen months, is made of personnel exposures.
In cases where individual monthly doses exceed 100 millirem, the Radiation Control Office will notify the individual (or his supervisor) of the exposure as a means of alerting the individual to the occurrence of the dose.
10.2 Bioassays No formal bioassay program has been established for individuals working in the FBBF facility.
Bioassay can, however, be required of certain individuals who work with SNM depending upon the level of activity and circumstances of use.
The Radiation Control Officer or his staf f may establish the need for such bioassay evaluation which t
could include analysis of urine or other excreta, depending on the nuclide, its chemical and physical form, and the mode of intake. The Radiation Control Officer is authorized to require the submission of other excreta (such as fecal samples, nose wipes, or breath samples) in addition to or in lieu of urine samples.
13 s
Item 10 Cont.
10.3 Surveys & Monitoring Surface contamination surveys are conducted at the FBBF facility every month, not to exceed six weeks, to determine levels of removable 2
contamination.
Smears are taken of 100 cm areas. Acceptable surface contamination levels are shown in the following table:
j bef bdf bef Nuclide Average
' Maximum Removable a
U-nat 5,000 dpm n /100cm 15,000 dpm a/100cm 1,000 dpm n/100cm 2
U-235 5,000 dpm n/100cm 15,000 dpm n /100cm 1,000 dpm n/l00cm transuranica 100 dpm n /100cm 300 dpm n/100cm 20 dpm n /100cm
- Where surface contamination by both alpha-and beta gamma-emitting nuclides exists, the limits established for alpha and beta-gamma-emitting nuclides apply independently, b As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correct-ing the counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrumentation.
" Measurements of average contaminant are not averaged over' more i
than I square meter. For objects of less surface area, the should be derived for each such object.
average The maximum contamination level applies to an area or not more than 200 cm.
i
A Item 10 Cont.
'The amount of removable radioactive material per 100 cm of surface area is determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known ef ficiency. When removable contamination on objects of less surface area is determined, the pertinent levels are reduced proportionally and the entire surface is wiped.
fThe average and maximum radiation levels associated with surface contamination resulting from beta gamma emitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
When observed contamination levels reach the above levels, decontamination must take place. From an operational point of view, every effort is made to keep contamination levels below those set.forth in the table above. Although not an official action level, in practice, any time removable contamination levels above 10% of the table value is reached, decontamination is accomplished.
No maximum time allowed before decontamination is actually started has been established. Contamination problems are accessed on an 1
individual incident basis and af ter review of the situation a decontamin-ation plan is decided upon. Af ter the tabled levels are exceeded, the area is restricted except for decontamination activities.
f
Item 10 Cont.
Personnel Surveys Protective clothing and/or devices will be used for all mani-pulations with unsealed sources where the possibility of contamination exists.
In particular, suitable gloves will be worn whenever hand contamination is probable. Surgical glove techniques are used for putting on and removing gloves in order to avoid contaminating the inside surfaces.
Thorough monitoring of hands, feet and clothing is mandatory whenever leaving a radioisotope laboratory where work with radioactive materials is in progress. Each individual radioisotope user is personally responsible to check himself for contamination every time he leaves the radioisotope area.
Laboratory clothing or protective garments (such as lab coats) used in radioisotope laboratories are monitored routinely during the course of the work and when work with the radioactive materials is completed.
Such garments will not be released for washing or cleaning until they have been monitored by the user and found to be free of contamination. Cont aminated garments will not be worn elsewhere, (outside the radioisotope laboratory or in " clean" areas.)
Articles which show contamination will be left in the work area, or other areas designated for this purpose.
Such clothing will be marked by the user with his name, date, and the nature and degree of contamina-tion and held for storage until the activity has decayed to background level; or decontaminated; or disposed of as radioactive waste.
In the case of skin contamination, decontamination by soap and water washing will be initiated as soon as is practicable.
In stubborn
Item 10 Cont.
cases, the use of chelating agents, mild oxidents, solvents, and isotope dilution solutions will be used to reduce skin contamination levels to background levels.
Leak Tests Each plutonium source will be tested for leakage at intervals a.
not to exceed six (6) months.
In the absence of a certificate from a transfer indicating that a test has been made within six (6) months prior to the transfer, the sealed source shall not be put into use until tested.
b.
The test will be capable of detecting the presence of 0.005 microcuries of alpha contamination on the test sample. The test sample will be taken from the source or from appropriate accessible surfaces of the device in which the sealed source is permanently or semipermanently mounted or stored. Records of leak test results will be kept in units of microcuries and maintained for inspection by the Commission.
c.
If the test reveals the presence of 0.005 microcurie or more of removable alpha contamination, the licensee will immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in accordance with the Commission regulations. Within five (5) days after determining that any source has leaked, the licensee will file a report with the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, describing the source, the test results,
Item 10 Cont.
I the extent of contamination, the apparent or suspected cause i
of source failure, and the corrective action taken. A copy of the report shall be sent to the Director of the nearest NRC Inspection and Enforcement Office listed in Appendix D of Title 10, Code of Federal Regulations, Part 20.
d.
The periodic leak tests do not apply to sealed sources that are stored and not being used. The sources excepted from this test will be tested for leakage prior to any use or transfer to.another person unless they have been leak tested within six (6) months prior to the date of use or transfer.
e.
Leak tests of the Cf-252 sealed source will be performed only at times when it is removed from the FBBF assembly for purposes of source trans fer, replacement, or similar activities. When the Cf-252 source is leak tested, conditions b and c, above, will apply.
10.4 Radiation Detection Instruments Contamination Detection Instrumentation Various contamination detection instruments are used at the FBBF and Reactor where SNM is used.
The following table summarized the equipment:
Rad.
Type No.
Detected Sensitivity Range Alert Set Pt.
CM Portable Meters 5
6y 0 - 20 mR/hr n/a ion chamber I
6y 0 - 2500 mR/hr n/a Remote Area Monitors 3
y log scale to 50 mR/hr 7.5 mR/hr Zn S(Ag) Portable Meter I a
0.20 mR/hr n/a Constant Air Monitor I
aSy 0 - 50 K cpm low level 20Tepm high level 20,C00cpn
i Item 10 Cont.
The above instrumentation is calibrated every six months (not to exceed seven months) using the following calibration secondary standards:
Isotope Activity Manufacturer Serial #
Date of Calibration Cs-137 2 Ci U.S. Nuclear L-501 7/7/65 Cs-137 l<48 mci Tech / Ops 5484 5/7/84 Co-60 1663 Ci A.E. Canada GBS-40 2/18/69 Co-60 1 Ci ICN 1071 1/28/77 T1-204 65 pCi 7/l/78 Am-241
.05 pCi NES 302 4/1/69 Co-60 10 Ci Gamma Ind.
809 6/20/72 The above instruments and sources are listed as examples only. Equivalent equipment may be used from time to time as the need arises.
10.5 Radiation Safety Program Purdue University is committed to a policy of making every reasonable effort to keep radiation exposures as far below the specified regulatory limits as readily achievable. Thus, the underlying philosophy of the Radiological Control operations of the University will be to maintain radiation exposures "as low as reasonably achievable." This philosophy, referred to as "ALARA," is in keeping with the recommendations of the National Council on Radiation Protection and Measurements, the National Academy of Sciences-National Research Council, and other independent scientific organizations. The principle of ALARA is also codified as part of the Nuclear Regulatory Commission regulations in Section
- 20. l(c) of Title 10, Part 20, Code of Federal Regulations, which states that licensees should ".....make every reasonable e f fort to maintain
9 Item 10 Cont.
radiation exposures, and releases of radioactive materials in effluents to unrestricted areas, as far below the limits specified in the part as practicable.
The Radiological Safety Committee, was established by the President of the University on February 19, 1951.
In February 1957 the Committee's name was changed to the Radiological Control Committee.
Duties of Radiological Control Committee In accordance with Purdue Executive Memorandum Number B-14 (dated May 15, 1973) the Committee has the responsibility to perform the following duties:
- 1. Assume responsibility, from the standpoint of radiological safety, for all University programs involving radioactivity or radiation producing devices.
Radioactivity refers to any material, solid, liquid, or gas, that emits radiation spontaneously.
Radiation, as used herein refers to both ionizing and non-ionizing radiation including, x-rays, gamma rays, alpha and beta particles, high speed electons, neutrons, protons, and other nuclear particles, microwaves and laser light, but not sound or radio waves, i
or visible, infrared, or ultraviolet light associated with devices other than lasers.
Radiological safety refers to the safe use and handling of radioactivity or radiation in any application, including but not restricted to teaching, research, development, and medical diagnosis and therapy.
Item 10 Cont.
- 2. Review and grant permission for, or disapprove the use of radio-activity or radiation producing devices within the institution from the standpoint of radiological safety.
- 3. Review and prescribe special conditions, requirements, and restrictions as may be deemed necessary to protect University personnel and the general population from health hazards associated with radioactivity and the operation or use of radiation producing devices on the Purdue University campus and other Purdue operated properties, including but not restricted to accelerators, reactors, x-ray devices, microwave ovens and laser devices. Such conditions, restrictions, and requirements shall in all cases be made in accordance with any existing Federal or State regulations governing such devices. Committee approval of health and safety measures must be obtained before any project involving radioactivity or radiation producing devices is initiated.
- 4. Serve as the University's sole liaison with the Indiana State Board of Health and the U.S. Nuclear Regulatory Commission in matters of registration, licensing, and radiological control.
- 5. Prescribe special conditions and requirements as may be necessary (such as physical examinations, additional training, designation of limited area or location of use, disposal methods, etc.)
- 6. Pass judgment in advance of the construction of new structures or the remodeling of existing structures in which the use of radio-activity or radiatior. producing devices is contemplated. Written approval of proposed building or remodeling plans for such facilities must be obtained from the Radiological Control Committee prior to construction.
Item 10 Cont.
- 7. Prepare and disseminate information on radiological safety and the practices and procedures, and rules related thereto, for the use and guidance of staf f and students.
- 8. Approve or disapprove the actions of departmental representatives or departmental committees within the University in matters pertain-ing to radiological safety. Such actions as are taken by departmental representatives and/or the minutes of meetings of departmental committees shall be submitted to the Radiological Control Committee for final approval.
- 9. Keep a record of the actions taken in approving the use of radioactivity and radiation producing devices and of other trans-actions, communications, and reports involved in the work of the Committee.
Actions taken by the University Radiological Control Committee may be appealed by the staff member or department concerned to the President of the University for final decision, with the knowledge and consent of the Dean or Director of the school or division involved.
The Chairman of the Radiological Control Committee shall serve as the administrative officer in promulgating the policies established by the Committee and, accordingly, is authorized to appoint a qualified individual to serve as the University Radiological Control Officer.
The Chairman of the Committee and the Control Of ficer, or their duly authorized representatives, are authorized to act (under policies established by the Committee) for the Committee between meetings, reporting their actions to the Committee for review at appropriate intervals.
Item 10 Cont.
In particular, as action consistent with the radiological protection of University personnel and the general population, authorization is granted to:
- 1. Carry out unannounced inspection and radiation surveys of any University facility.
- 2. Order immediate shutdown or cessation of work in any facility where it is evident that health hazards exist to the extent of endangering life or property or to the extent that continued operation would result in violation of existing Federal, State, or University regulations.
Frequency of meetings I.
The Radiological Control Committee will meet 3 times a year.
The meetings will normally be scheduled at the discretion of the Chairman of the Radiological Control Committee. Generally, I meeting will be scheduled each semester.
2.
Additional meetings may be called from time to time at the request of any member of the Committee to consider any problems, policies or other phases of the Radiological Control Program.
3.
Upon receipt by the Radiological Control Officer of any request or application to use radiation or radioactive materials for a purpose or in a manner which is at variance with exiscing university policy, a.
b.
involves unusual amounts or kinds of radiation or radioactive materials, or
- c. requires amendment of the NRC license, the Radiological Control Officer shall request a meeting of the Chairman to consider the request.
Item 10 Cont.
There is no set composition for the Radiological Control Committee and therfore, the membership may vary in number from time to time.
The Committee consists of the Chairman of the Radiological Control Committee who is appointed by the President upon joint recommendation of the Vice Presidens for Physical Plant and for Research of the University, the Radiological Control Of ficer, and other individuals as are appointed by the President upon recommendation of the Vice Presidents for Physical Plant and for Research, and the Radiation Control Committee Chairman.
Individuals appointed to the Committee must be persons knowledgeable in the safe use of radioactive materials or individuals whose expertice may be of value to the Committee as 1
a whole. Examples of such other individuals might include representatives of management, safety and security, or the police department.
Radiological Control Officer The Radiological Control Officer, a qualified health physicist, functions under the jurisdiction of the Radiological Control Committee and is a member of the Committee.
The Radiological Control Officer has been delegated the following responsibilities:
1.
Dissemination of information on radiation safety and health phys ic s.
2.
Reviewing all proposals for isotope usage.
3.
Inspection of facilities and equipment for the Control Committee.
4.
Approving construction of all new radioisotope and radiation facilities.
5.
Obtaining all Nuclear Regulatory Commission licenses and State registrations for the University.
Item 10 Cont.
6.
Ordering, receiving, storing, processing, and dispensing all radioisotopes, including records of same.
7.
Radiation surveys and monitoring of all radioisotope and radiation facilities.
8.
Disposal of all radioactive waste.
9.
Personnel monitoring including film badge processing and exposure records and bioassay.
10.
Overall administrative direction of the University radiation l
safety program.
The Radiological Control Of ficer may hire or otherwise obtain the services of qualified individuals to assist in carrying out his l
l l
l duties, including laboratory monitoring, waste disposal, personnel i
monitoring and the ordering and dispensing of radioactive materials.
l Individuals serving in this capacity constitute the Radiological l
I Services Staff.
Radiological Services Staff The membership of the Radiological Services Staf f will be dependent upon the needs of the program. The current staf f organization is described.
l f
I.
Associate and Assistant Radiological Control Officers The Associate and Assistant Radiological Control Officers shall be qualified health physicists and shall be delegated the authority to act for the Radiological Control Officer in his (the Radiological Control Officer's) absence. They shall otherwise assist in the normal administration and operation of the health physics programs and carry out such duties as the Radiological Control Officer may delegate to them from time to time.
Item 10 Cont.
Individuals serving in the capacity of the Radiation Control Officer, the Associate Radiation Control Of ficer, and the Assistant Radiation Control Officer, must have received post baccaloriate degree training, as well as having met adequate experience re-quirements.
Individuals in these positions should have 30 credit hours (450 contact hours) of health physics training in the following subjects and related areas or its equivalent through job experience:
I.
Principles and practices of radiation protection 2.
Radioactive measurements monitoring techniques, and instrumentation 3.
Mathematics and calculations basic to the use and measure-ment of radioactivity 4.
Biological effects of radiation In addition, persons filling these positions should have a minimum of two years practical experience in the safe use of isotopes and/or practical health physics experience.
2.
Profession Health Physicist (s)
Day to day health physics responsibilities for the Radiological program may be delegated to qualified professional health physicists.
Such individuals may assist the Radiological Control Of ficer in implementing the specified duties as required. A professional health physicist must have, as a minimum, a BS degree in health physics (or the equivalent) and suitable experience in health physics practices. The Radiological Control Officer will be responsible to determine that individuals serving in this capacity are qualified.
Item 10 Cont.
3.
Health Physics Assistants Assistants trained in radiation monitoring and hazard evaluation may be utilized by the Radiological Control Officer and the Professional Health Physicist in carrying out the duties of monitoring and waste disposal. Such technicians are authorized to enter restricted areas at unannounced times for purposes of monitoring, provided such entry is made at reasonable times and in a safe manner.
Such technicians are authorized to render immediate or urgent advice on radiation safety within their area of competence, but are not authorized to make interpretations of the Radiological Control Committee policies and regulations.
4.
Radiological Service Professionals and Assistants Individuals trained in the radiation monitoring and surveying may be utilized to assist in carrying out routine radiation safety services.
Procedures Procedures for the handling and processing of radioactive materials associated with the SNM license must be approved by the Radiation Control Committme. As a practical matter procedures are prepared by the FBBF Laboratory Director or the Assistant Laboratory Director and Submitted through the Radiation Safety Of ficer. The Radiation Safety Officer reviews the procedure for i
radiation safety considerations and then approves the procedure for the Radiation Safety Committee or, if deemed necessary, has the chairman of the Radiation Safety Committee call a special
t Item 10 Cont.
meeting for formal procedure approval. Procedures for other SNM handling are submitted by respective project directors in a like manner. The above method serves as a control to ensure adequate review for adopting and issuing operation, maintenance, and test procedures have taken place. Changes in safety related procedures, new activity procedures and new activities involving nuclear materials, are subject to Radiological Control Committee approval.
Inspection Inspections of on site facilities and SNM are conducted as required to insure that the facilities are safe from a radiological health viewpoint. At a minimum the facilities are inspected once each quarter or more frequently as may be required in the judgment of the Radiological Control Of ficer.
Item 11.
Waste Management Air contamination is not generated per se in the operation of a.
the FBBF facility, but could result from leakage of the various sources of SNM.
To monitor for air contamination an isokinetic probe is used to sample exhaust from the FBBF inner room before and after a HEPA Filter which is located in the exhaust train. Air filters of the isokinetic sampler are counted weekly (not to exceed 10 days) to monitor for leakage of radioactivity. The HEPA filters are to remove potencial leakage product. Air dispersal of radioactivity will not exceed limits established in 10 CFR 20.
l b.
Liquid Waste - In general liquid wastes are not generated, but such wastes could result from decontamination procedures and other unanticipated procedures. Liquid wastes may be disposed of by release into the sewage system in conformity with the regulations of 10 CFR 20 or fixed for disposal by land burial.
c.
Solid Wastes - Solid wastes are removed from work areas as required, to prevent excess build up of waste materials in the FBBF facilities. Solid wastes are disposed of, after volume reduction when possible, by land burial. Land burial is accomplished at commercial sites in comformity with appropriate regulations.
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