ML20137V626
| ML20137V626 | |
| Person / Time | |
|---|---|
| Site: | 07002003 |
| Issue date: | 04/25/1985 |
| From: | Jeffries J HIBBING-TACONITE CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20137V618 | List: |
| References | |
| 78816, NUDOCS 8510040085 | |
| Download: ML20137V626 (2) | |
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Material Licensing Section 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Ladies and Gentlemen:
We would like to renew our Special Nuclear Materials License No. SNM-1558.
Enclosed is a check in the amount of $120.00 to cover the renewal fee.
We would like to continue to operate under our current license. We will use and possess the licensed material in accordance with statements, representations and procedures contained in our letters dated April 3, 1980, October 11, 1982 and December 27, 1984, applicable NRC Regulations and license conditions.
If you have any questions in this regard, please contact Mr. R. C. Ives at (218) 262-5970.
Very truly ycurs,
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Apg 3 REQ 3 LIC7o ppR S SS5 sc-tsee coNTROLNO. 7 8 816 The Agent is actmg only for and on behalf of Hibbmg Taconste Company, a Joint V. era consisting of Bethlehem Hebbing Corporation (50% enterest), Hibbmg Develo; ment Corripany. a Mmnesosa general partnership (33 3333% mterest). Pickands Mather & Co t 10% meerest) end Ontario Hibbmg Company (6 6667% enterest).
The hatWaty of Bethlehem Hibbmg Corporation m respect of any obhgation hereunder shall be fim ted to 4)% thereof, the habelsty of Hibbmg Development enmpany art respect of any obhgat60n hereunder shall be 16msted to 33 3333% thereof, the habshty of Peckands Matner 4 co in respect of any obligation hersunder shall be hmited to 10% thereof, and the habihty of ontario Hsbbing Company in respect of any ot*gation hereunder shall be hmited to 6 0661% thereof 0272.USN
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U. S. Nuclear Regulatory Cornission Region III Material Licensing Section I
799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Ladies and Gentlemen:
We would like to renew our Special Nuclear, Materials License No. SNM-1558.
Enclosed is a check in the amount of $120.00 to cover the renewal fee.
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We would like to continue to operate under our current license. We will use j
and possess the licensed material in accordance with statements, representations j
and procedures contained in our letters dated April 3, 1980, October 11, 1982 and December 27, 1984, applicable NRC Regulations and license conditions.
If you have any questions in this regard, please contact Mr. R. C. Ives at i
(218) 262-5970.
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t, The Agent #s acting only for and on behast of Hibbing Tacomte Company, a Jomt Venture. consist.ng of Bethlehem H'Obmg Corporahon (50% interest), H,bbing l
Cevelopment Corecany. a Minnesota generaf partnership (33 3333% mterestf. Pick ands Mather & Co (10% enteresti and Ontario Hibbmq Company (6 6667% mterest)
The l'armhty of t$etniehem Hibbing Corporation m respect of any obhgation hereunder shall be hmsted to 50% thereof, the liabelsty of H<bbing Development Company in respect of any obhgatton hereuncer snail be temited to 33 3333% thereof. the leabelity of Picaands Mather & Co. in respect of any obhgation hereunder shall be hmited to 10% thereof. and the habihty of Ontario Hibbing Corepany in respect of any obhgation hereunder snail be htmted to 6 6667% thereof.
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( Cher!< No....... o f*> > >' (/ /N//4 v /)/N/U/!//' dd/Y8 f,,, g re M W .h. ) 8 }V* December 27, 1984 I L..., s L 6.d.......... g C ) .....\\ F.cccact (3Y j itCCOVED B r 'm r '/ 3 h rate / /. ( a/ ' /B m v ,v ' U. S. Nuclear Regulatory Commission rp k Region III 9." 3 Li hO 799 Roosevelt Road j [', m Cnd 10 Glen Ellyn, Illinois 60137 g n Action Compid<, .7 c:> Attention: Licensing Division 2 G w
Dear Ladies and Gentlemen:
Enclosed is our appliention for the addition of a Texas Nuclear NOLA system to our Special Nuclear Materials License No. SNM-1558. Although the NOLA system is a custom device it has been previously evaluated and licensed many times by the U.S. Nuclear Regulatory Commission. Some of the licenses referenced are a) Reserve Mining Company, SNM-1562; b) Erie Mining Company, SNM-ll78; c) Tilden Mining Compary, SNM-1492; and d) U.S. Steel, 22-02973-01. Enclosed as part of our application is 1) a technical data writeup, 2) two sets of NOLA system location drawings (3 drawings per set), 3) two sets of source capsule and source shield drawings (2 drawings per set) and 4) Special Form Certif-icates for both t'e Pu-238-Be and CS-137 sources. In addition we would like to request that a change in principal officers be reflected as follows: J. R. Barker, Chairman One Lao.'4 ark Square Stamfor., Connecticut 06901 Robert McInnes, President 1100 Superior Avenue Cleveland, 011 44114 R E C E t V E WC 3 J 1934
- 11. P. Whaley, Group Vice President g
l 1100 Superior Avenue l Cleveland, Oil 44114 REGION III <a m isetic e50321 REG 3 LIC70 SNM-1558 PDR Ihe Agent is actmg Only for and ort Dena'f or NeDDeng iaconite Company, a Jomt Venture. Consett,ng of sethlehorft Hibbmg Corporation (50% enterestL Hibbing 02v2iopment Company. a M,nnesota general partnership (33 3333% mterest) Pickands Mather A Co (10% mterestlandOntariaHibbingCompany t6 f(47% interest; Th3 liebehty of Dethlehem Hibbmg Corporation m respect of any obhgation hereunder shall be hmeted to 50% thersof. the liebel ty of Hibbing Development Company m rtspect of any Obi atton hereunder shall be hmited to 33 3333% thereof, the habihty of Pich ands Mather & Ca m respect of an obhgation herau er shall be kmeted to 10% thereof, and t e tiabehty of ontario Hibbmg Company en respect of any obh0at!on hereunder sh t imt t"&O 4 DPA2-12/27.DA-1
r__ (mJ U. m All other conditions of our license should remain the same. Enclosed you will find a check in the amount of $60.00 to cover the license amendment fee. If you have any questions in this regard please contact Mr. K. F. Jopke at (218) 262-5901. Very truly yours, Jo
- . -if Yohn b. Jeffries General Manager JDJ
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N .o o Technical Data This system will be used for elemental determinations in iron ore and is being supplied to Hibbing Taconite Company by Texas Nuclear Corporation 9101 Highway 183, Austin, Texas 78758. The system is shown on a drawing labeled " Schematic Representation of N0LA I". The slurry is cycled continuously through the irradiate cell and the detector for analysis. The general layout of the N0LA System is shown on the drawing labeled "Nola I Silica Analyzer". The system will be installed in the Hibbing Taconite Company Concentrator Analytical Laboratorj as shown on the enclosed drawings Plant Arrangement No. 2200-2A, Concentrating Plant General Arrangement No. 2504-4 and N0LA Installation No. 4-04C1. This room has solid floors and walls and can easily b e secured against unauthorized entry. The environmental conditions at the installation site are regulated to provide a comfortable and safe atmosphere for company personnel and as such will be nondetrimental to the N0LA System. DPA2-12/27.DB-1
~ .O O The principal hazards of concern in this system are: a) Exposure to radiation outside the shield under normal operating conditions; b) Failure of the source capsule inside the shield; c) Exposure to radiation under emergency conditions; d) Disposal of the activated materials. Density Channel The density channel is shown in the drawing titled "Nola I Density Gauge". The 5176 source head acts as a complete storage container for the 500 mci Cs-137 sealed source, Texas Nuclear Model 570-57157C, both prior and subsequent to installation of the system. The radiation levels one foot from any accessible surface are less than 0.5 mR/hr. In the event work must be done inside the detector box, the shutter will be closed and locked before such work begins. This source will be leak tested at least once every six months in accordance with leak test procedure QT/lK (see appendix). No waste disposal is involved. If the use of the gauge is discontinued, the source will be returned to Texas Nuclear for disposal. Silicon Channel The construction of the shield is detailed on the drawing titled " Neutron Source Shield" (see appendix) and schematically shown in the figure titled "Nola I Irradiator". The source is threaded onto a stud at the botton of the inner cell. The irradiate cell slips over the source and can be installed and removed without moving or unshielding the source. l q)tgg0,Ltio. 7 8 0 4 9 l DPD2-12/27 DC 1
SLURRY HANDLING SYSTEM r-----------------------7 l SAMPLE l IRRADIATOR R PUMP ..m-m- -y TIME y RECIRCULATE C -o <f k O_ _ - o SEQUENCE CONTROL TWO-WAY Q~ g VA LVE 7 ~~ w { p_f;* ~ ~ D O-- DENSITY 4 CHARGE-FLUSH NEUTRON _ _ -~ g !*tEj j,] SOURCES 1 ppppppppp DENSITY GAUGE DETECTOR j [~~~~ ~7 ELEC g _.o [s ' g i i 'g _g W g i o- .o SOURCE l r-samummensumumenkwT y-RAY + ~~ e. g ~ ~ ~ ~ ~..o DATA r O g s ~ COMPUTER] INTERFACE h 2. .h
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\\ f' um, - n PR TER b T CONTROL T A Rx AND DATA ACQUISITION l pETECTOR SCHEMATIC REPRESENTATION OF NOLA I
d \\ DENSITY GAUSE g r ~ E l g# (; S g ,_p ,q l-O 3* Mvg j :[ % k g g g* %l [. Q. y '= A l(1 5 e f? I HANOUNG -. i 8 L,N [ -L. o 4 h.'A ja COUNTER CONTROL AND DATA ACQUISITION UNIT NOLA I SILICA ANALYZER 9 Et
4 + l SLURRY LOOP TUBIN G NAI(TI) y RAY DETECTOR 1 i \\ e g \\ f ~ / / \\ ~. ) W,. /, ej ~/ l TUNGSTEN NUCLEAR CHICAGO COLLIM ATOR MODEL 517 6 LEAD DENSITY GAUGE HEAD COLLIM ATOR NOLA I DENSITY GAUGE
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~ x f ACTIVATION N CELL 's N ') \\ SOURCE \\ TANK 'N x .x \\ s NOLA I IRRADIATOR ~
O O The Plutonium 238-Beryllium neutron source contains approximately 2.9 grams of Plutonium-238 as an oxide mixed with 15.2 grams of Beryllium. The neutron 8 emission rate of the source is 1.1 x 10 n/sec., and the source was fabri-cated to the specifications shown on the drawing labeled "Pu8Be-Source Cap-sule" by Monsanto Research Corporation, Dayton, Ohio. An analysis of pressure build-up due. to alpha particle decay of the contained Pu-238 was made. This analysis was based upon a maximum loading of 4.24 grams of Pu0, 80% enriched in Pu-238 at an initial pressure of one atmosphere. We 2 assumed that the Helium obeyed the Ideal Gas Law and that ambient temperature was 70"C. We additionally said that 30% of the internal volume was void due to, the approximate 70% compaction of theoretical density that one gets after Jpressing the pug -Be pellet. 2 'I[n the activation analysis system one can estimate the useful life of the source to be 80 years, based on the required sensitivity of the measurement. This would mean a pressure build-up of approximately 400 psia. One can calcu-late the bursting pressure of the inner capsule, using the tensile strength of 304 SS as 85,000 psi, to be greater than 6,400 psia. Prototypes of this capsule have been tested under American National Standards Institute proced-ures and classified E43333. Radiation exposure rates outside the neutron source shield are shown at typi-cal survey points on the drawing labeled " Neutron Source Shield". The source itself is shielded as shown, with lead and water on all sides except the top, which is covered by 33 inches of oil. 'This filling insures access to install i or remove the teflon irradiation cell without undue radiation exposure,(ref-erence Cell Check and Removal Procedure). The cover plate has a cable and i lock to insure that only authorized personnel have access to the cell. As { usual, the shield is massive and the exposure rates are very low due mainly to the high sensitivity of the system detectors rather than personnel exposure considerations. The sensitivity of these detectors also provides an additional margin of safety, since' they will indicate a change in performance if some abnomality occurs. Clearly, exposure to radiation outside the shield is mini-mal.
.- = o o The large water shield also had a low water warning system consisting of a Cutler-Hanner Level Probe, located approximately one-half inch below the tank top, and connected to a Cutler-Hammer standard duty fail safe relay. The alarm circuit will indicate when the water level is approximately one inch below the tank top. At that time, one would not observe any appreciable increase in the dose rates as presented. Lights on the control panel indicate the status of the water level. A contact closure is also provided for remote alanns if desirable. The water' shield has a chemical additive to inhibit corrosion and organic growth identified as NALC0 39-L, and supplied by 1 Nalco Chemical Company 5757 Bellaire Blvd. Houston, Texas. ~ Nater replenishment, if ever necessary, would be a manual operation as there is no provision for automatic filling. The physical location of the sample room,the building construction and gene-ral house-keeping conditions make it unlikely that conditions could exist which would endanger the shielding properties of the primary container. Al-though we cannot envision the accident, if such occurred.we would attempt to evacuate personnel from the area of the source, notify the Radiation Safety Officer and Texas Nuclear Health Physics, and await instructions and/or the arrival of trained personnel to evaluate the situation. However, the dose rates are not so high as to preclude maintenance on the tank. One can esti-mate the unattenuated dose rate at a meter to be slightly more than 100 mrem /hr by using: 8 a) neutron emission = 10 n/sec, b) average first collision dose in tissue = -9 2 4.0 x 10 rad /n/cm, c) mean quality factor = 8.5 for Pu8-Be neut'rons, d) adding the ganma contribution from both the 4.43 MeV state of C-12 and the 2.2 MeV emission from neutron capture in Hydrogen. n. +
O O ~ Additionally, note that the source is not unshielded if all the water is out of the tank. There is a 5 inch oil bath plus the irradiation cell and the 20 inch 0.D. lead half-annulus to consider. In fact, except for near the floor level, and the tank end away from the large crystal detector, the total dose rates would not exceed 15 mrem /hr at the nearest point of the shield tank. with no water. Failure of the source inside the shield is rer:ote at best. This type of cap-sule construction has been used for some time with few failures. Also. a failure of the source would change the optimized geometry and this would im-mediately affect the operation of the system. Therefore, we propose to leak test this source using the procedure entitled " Leak Test of Activation Analysis -Sources", (see Appendix) at least once every six months under normal conditions, and at any other times the operational data lead us to suspect that some source o[r, cell abnormality has occurred. In the event the leak test is positive, we will discontinue use of the sy. stem, secure the room and await further instruc-tions from Texas Nuclear and the Hibbing Safety Officer. We believe that even a ruptured source could be safely contained for some time in the shield with little probability that contamination would be a hazard outside the container. The following are additional items that are an integral part of our program: a) The system will be installed by trained personnel of Texas Nuclear Corporation. b) Personnel will receive training in the operation and hazards of the acti-vation analysis system by Texas Nuclear personnel. c) Radiation surveys will be made at the time of installation by Texas Nuclear and copies will be retained for inspection. d) Personnel working around the activation analysis system will not use per-sonnel monitors. It is unlikely that any individual can approach a whole body dose of 0.125 rem per quarter. e) Personnel will not remove the source from the primary shield. In the event that circumstances lead us to believe that the shield is no longer an integral unit, personnel will be removed from the area and Texas Nuclear will be notified. l CONTROLtiO. 7 8 0 4 7 t (
. =. O O f)' The pumping system will not be turned off with material in the irradiate cell during nonnal operation. Prior to shutdown, we will flush the sys-tem with water. To insure that no material remains in the irradiate cell, we will continue to flush and drain until the gamma spectrometer count rate approaches background. g) In the event the use of the system is discontinued, the removal and dis-posal of the radioactive material will be handled by Texas Nuclear. l These points and included procedures will be incorporated in the operations manual pr6vided by Texas Nuclear. There is only very low-level radioactive waste generated in this system. In operation (reference " Schematic Representation of Nola I") a small sample of iron ore slurry is recirculated through the activate cell and count cell for five minutes. It can then be dumped either into a waste line or back into the produce line. None of the activated material is ever released to any area that directly connects to any life support chain. The iron ore slurry has as its principal constituents Fe 02 3 (60-70%) and SiO2(3-20%). Table I lists some data on the' more prominent activation re-actions possible. Consider that in operation we put in 100 grams of iron ore for a five minute irradiation every cycle. For neutron irradiations of this type, the formula Nn oS where A = Activity in curies A= f (3.7 x 1010) n = Heutron flux f S = Saturation factor - (1-e-At) N = Number of target atoms available o = Activation cross section will estimate the amount of activity produced per irradiation within an order of magnitude. However, experimentally it has been determined, in a five minute count period, that the Si28 (n,p)A128 -2 28 reaction produces about 1.5 x 10 Ci of A1 in the system. w r
U (} O All the other reactions, except Fe54(n,y)Fe55 have comparable cross-sections, but will not produce as much radioactive material as the above reaction be-cause their half-lives are long compared to the irradiation time. Therefore, the saturation factor for these reactions is much smaller. In summary, we propose that no significant hazard exists either to employees or the general public, in the routine release of the amounts of radioactive s..aterial produced in this system. We, therefore, will not make routine moni-toring or, sampling part of our safety program. CJOROLNO. 7 8 04 y
== Elcment Isotope Activated Type of Reaction Activation Product Half-Life Gamma-Ray Energie~s, and Abundance and Cross Section. Threshold Nuclide of (MeV) and at 14 MeV (mb) (MeV) Activity Relative Abundances 16 (99.8%) (n,p), 40 10.0 N 7 14 sec 6.1, 7.1 6 O. 0 s 28 (92.2%) (n,p), 160 3.8 Al 2 3 min 1.77 si s1 31 30 (3 09%) (n,y), llo
- s1 2.62 hrs 1.26 ( O.1) si si 55 54 (5.82%)
( n, y), 2500
- Fe 2 7 yrs o.006 Fo Fe 54 (n,p), 375 2.0 Mn 290 days Cr X-rays 56 56 (91 7%)
(n,p), 110 39 Mn 2 58 hrs 0.845 (100) Fa Fe 1.81 (30) 2.13 (20) 0 Thermal cross section TABLE I
U
SUMMARY
OF RADIATION SAFETY PRECAUTIONS A. NOLA Density System 1. Cs-137; 500 mci in a lead-filled source head. 2. Radiation survey provided at installation and need not be repeated. 3. Leak test once every three years. (QT/1K)
- 4.
Insure that the source shutter is closed during all maintenance on the electronics and leak testing. B. NOLA Activation Analysis System 0 , 1., Pu-238-Be emitting 1.1 x 10 n/sec. 2. Radiation survey provided at installation and need not be repeated. I 3. Leak Test once every six months. (Leak Testing of Activation Analysis Sources)* 4. Radiation fields under normal conditions of use are very low. 5. The source is affixed to a plate at the bottom of the oil bath. 6. Loss of the entire water shield does not preclude repair with the source in place. The maximum radiation levels without the water shield would be approximately 15 millirem per hour at the tank. 7. Hibbing Taconite will not remove the source. 8. The slurry loop is always to be flushed with water prior to any shutdown. 9. Removal of the irradiate cell requires the handling of slightly radioactive materials. The activation products built-up will not create radiation fields that are high in terms of significant dose. One should be aware of them and, if appropriate instrumentation is available, monitor these fields during handling of the irradiate a cell. Gloves should be worn during handling and the hands washed upon completion. All components should be cleaned and stored away from occupied areas until reassembly. Familiarization with the " Cell Check and Removal Procedure" is advised. i
,r, A (~') Os v APPENDIX TABLE OF CONTENTS Item No. 1 Drawing - Pu238-Be Source Capsule 2 Drawing - Neutron Source Shield 3 Leak Test Procedure QT/lK (Cs-137) 4 ' Cell Check and Removal Procedure 5 Leak Test of Activation Analysis Sources ' G 4 4
p V ~ LEAK TEST PROCEDURE - QT/1K The gauge will not be dismantled or disassembled in order to leak test. Testing of the external seams, flanges and end plate is adequate. 1. Position the shutter actuator to the closed position. In the event that the shutter actuator is frozen, or appears damaged, notify the manufacturer of the density gauges. 2. Refer to " Calculations for Leak Testing" before proceeding. Remove the end cap from the end window of the G. M. Survey Meter, Eberline Model E-530 with HP-190 Probe, and with the use of the appropriate certified standard source, calibrate the unit on the proper scale. Insure that the most active side of the source faces the meter (the labeled side). 3. Obtain as many cotton-tipped applicators as indicated on the applicable drawing and slightly moisten. (Use water, alcohol or other solvent.) 4. With the shutter closed, wipe the areas of the source housing assembly at the locations designed on the appropriate drawings (care should be taken not to touch the Q-tips with the fingers following wiping operation). 5. Carefully place the swab end of each Q-tip as close to the window of the G. M. Tube on the Survey Meter as possible and read the results. The degree of removeable contamination may be readily evaluated by the liethod referenced above. 6. A leak test certificate will be completed and filed as a permanent record of the leak test. Amounts of radioactivity found will be recorded in microcuries (uCi). 7. One should send the wipes to a counting laboratory, such as Texas Nuclear, for additional analysis if any contamination appears on the wipes. 8. Note: Generally, it is advisable to use a certified standard source containing the same isotope as that being tested. However, this is y t always y necessary where the isotog is g2 energetic gag emitter, e.g., Cs standard will work for Co , Ir , etc. A Cs standard source will be used. The following " Calculations for Leak Testing" can be used to assess the presence of small amounts of radioactive material necessary during leak testing of gauging devices, using an Eberline Model E-530 with HP 190 Probe Portable Survey Meter that has a demonstrated sensitivity of 0.005 uCi or less of the radioactive source being leak tested. 1. Turn on unit; check battery, verify unit operation using the supplied check source; and remove end cap from G. M. Tube. C_0NTROLNO. 7 8 0 4 y, DPD3-7/11.CA-8
sU ll f~',, "j v s LEAK TEST PROCEDURE - QT/1K (continued) 2. Place the appropriate certified standard source (Cs-137) disk on a clean flat surface and position the open end of the G. M. Tube over it. Set the range selector to give an approximate mid-scale reading. Note and record the cbserved readings; My (in either c/m or mR/hr). 3. Remove the standard source away a few feet. With the G. M. probe in the same position, note and record the background (Bkg.) radiation in the same units as M. y 4. Each swab end of the cotton tipped applicators used in wiping the gauge is in turn placed in the same geometrical position as the above noted standard. Note and record the observed meter reading, M. M and M must be taken in 2 y 2 the same units. 5. To determine the degree of contamination in microcuries, a simple expression of proportionality is used: where M -Bkg. P -Bkg. y 2 A = activity of certified standard source in microcuries (uCi). C = amount of removeable contamination in microcuries (uCi). M = survey meter reading with calibrated source in place in 1 either milliroentgens per hour (mR/hr) or counts per minute (cpm). M2 = survey meter reading with swab in place in either milli-roentgens per hour (MR/hr) or counts per minute (cpm). Bkg.= survey meter reading with neither source nor swab near the G. M. probe in either milliroentgens per hour (mR/hr) or counts per minute (cpm). ) DPD3-7/11.CA-9
0 D O CELL CHECK AND REMOVAL PROCEDURE This procedure is utilized only after the counting data leads one to believe that some abnormality has occurred to the source or irradiate cell. 1. The operator should shut off the input of slurry, actuate the main valve, and open the water flush valve to clean the system. 2. Ldak test the source according to,the Leak Test Procedure, and do not proceed on cell removal until the results of the test are received. 3. If leak test results are negative, proceed with cell removal as outlined below and in the section titled " Removal of Activate Cell (reference Inner Source Shield Assembly Drawing). -4. Cover the working area at the top of the tank with absorbent material. 5. Position a plastic pan nearby so that the encapsulation cell can be lifted up through the oil and placed in the pan with no spillage. Handle the' cell with rubber gloves which can be easily washed. 6. Measure the radiation exposure rates from the encapsulation cell to insure that the levels are low enough to proceed. For example, exposure rates at the surface of the cell up to 25 mR/hr should be considered acceptable. 7. The components of the encapsulation cell assembly should be monitored as disassembly proceeds, and all parts should be cleaned thoroughly as soon as practicable.
L-) \\ l,'- ([) Texas Nuc1 car Corp ration LEAK TEST OF ACTIVATION ANALYSIS SOURCES The system should not be dismantled to leak test the source. 1. Check the oil level with the dip stick. In the event the oil 1cyc1 is significantly below normal, close and lock the cover and notify Texas Nuclear Corp. IIcalth Physics, immediately. Area code 512 - 836-0801, extension 310. 2. With tbc source and cell in position, dip out two to four ounces of shiel,d fluid from down near the top of the ccll, and pour it into the sampic bottle supplied with the test kit. Close and lock the top cover plate. 3.. Cap the bottle and tape the top closed to provide a positive scal.
- 4. ' Fill in the provided sheet with full identification, including model number, serial number, and date.
5. Place the bottle in the mailing tube and send as follows: Texas Nuclear Corporation P. O. Box 9267 Austin, Texas 78766 ATTN: IIEALTil PIIYSICS Upon receipt of the oil sample, the fluid will be diluted in IICL (1-normal) and then filtered. It will then be evaporated to dryncos and counted for alpha contamination. If found free of contamination, a notice will be sent via air mail, in the form of a leak test certi-ficate, that the source is leak free. If the oil is found to contain detectable amounts of alpha contamination, notification will be sent, via telephone or telegram, advising that the oil bath should not be opened and that an additional leak test sample is to be taken and sent by air to Texas Nuclear for analysis. If the accond sample contains alpha contamination, notification will be sont adviuing that Texas Nuclear personnel will be sent to remove the source for return to the manufacturer. Under no circumstances is the shield to be opened during i this period of time. L
t L) ,~ > o ' L) L.) 400 Sevenm Street SW Q$ t wasNngton D C M 90 gg Rosearch and Special Programs IAEA CERTIFICATE OF TMPETDC AL7rilORI'IY Administration _Special Ibm Padioactive tutcrial Encapsulation Certificate 1 umber USA /0240/S Bevision 0 'Ihis certi'fies that the encapsulated source, as described, wt.2n loaded with the authorized radicactiw contents, has toen demonstratul to reet the regulatory requiranants for special fom radicactive material as prescribed in IAEA 1/ and USA 2/ regulations for the transport of radioactive raterials. I. Source Description - The sour descrihx1 by this certificate is ident.ifica as Fbnsanto Research Corp ttdel rio. 24173 which is a tungsten-inert-gas welded double encapsulation constructed of stainless steel which measures.868" in dianater by 4.13" in length and is constructed in accordance with MRC drawing A24173-AA00. II. Radioactive Contents - The authorized radioactive contents of this source consist of not more than 55 curies of Am2ricium-241 or Plutonium-238 as oxide p. der mixcd with a neutron production target pxler. III. This certificate, unless rencvxi, expires December 31, 1986. This certificate is issued in accordance with paragraph 803 of the IAEA Regulations 1/, a:x1 in response to the tbva-1:cr 23,1961 petition by Fbnsanto Pasearch Corporation and in consideration of the associated info: ration therein. Certified bj: Omn en2 M I wi R. R. RAKL (DATE) Chief, Radioactive Futcrials Branch Office of l'azardous Fbterials Regulation Futcrials Transportation Bureau 1/ " Safety Series tb. 6, Regulations for the Safe Transport of Radioactive Fhterials,1973 Revised niition", publishod by the International Atcmic Energy Agency (1AEA), Vienna, Austria. 2f Title 49, Code of Ibderal IMgulations, Part 170.-178, USA. I
P I ( O 1, i' ,] O US Department 400 sevenin streei s w Washegion. D C 20590 ofionsportofm Researchand SpecioI Programs IAEA CERTIFICATE OF COMPETENT AUTHORTTY Administration Special Form Radioactive Materials Encapsulation Certificate Number USA /0042/5 (Revision 3) This certifies that the encapsulated source, as described, when loaded with the authorized radioactive contents, has been demonstrated to meet the regulator y requirements for special form radioactive material as prescribed in IAEA l_/ and USA 2] regulations for the transport of radioactive materials. I. Source Description - The source described by this certificate is identified as Texas Nuclear Model 37137C which is a welded, double encapsulation constructed of stainless steel with external dimensions of 12.7mm (0.5 inch)in diameter by 19mm (0.75 inch)long. The source is fabricated in accordance with 3M Company Models 4F6S or 4D6L specifications. II. Radioactive Contents -The authorized rac" active contents of this source consist of no more than 10 Ci of Cesium-137. III. This certificate, unless renewed, expires April 30,1989. This certificate is issued in accordance with paragraph 803 of the IAEA Regulations 1/, and in response to the April 6,1984 petition by Texas Nuclear, Austin, Texas, and in consideration of the associated inf ormation therein. Certified by: dk/ M M8# Richard R. Rawl (Dak) Chief, Radioactive Materials Branch Office of Hazardous Materials Regulation Materials Transportation Bureau 1/ "Saf ety Series No. 6, Regulations for the Saf e Transport of Radioactive Materials, 1973 Revised Edition (As Amended)," published by the International Atomic Energy - Agency (IAEA), Vienna, Austria. 2/ Title 49, Code of Federal Regulations, Parts 100-199, USA. Revision 3 - respecified description; extended expiration date. CO?gROL NO, 7 8 0 4 9'}}