ML20206E270

Application for Renewal of License SNM-95,authorizing Use of U-235,UO2,U-233 & Pu-239 in Fission Counters & Chambers for Neutron Detection.Supporting Documentation Encl

ML20206E270
Person / Time
Site:	07000113
Issue date:	05/30/1986
From:	Hosler C PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
27071, NUDOCS 8606230258
Download: ML20206E270 (87)

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RETURN TO 396-SS FK THE PEN N SY LVA NI A STATE UNIVERSITY VICE PRESIDENT FOR RESEARCil AND DEAN OF THE GRADUATE SCHOOL 114 KERN GRADUATE BUILDING UNIVERSITY PARK, PA 16802 9

D C. L. Iloster 30 May 86 T* ** "* Vice President and Dean 814-865-2516 k g\\Ng #- 814-865-6331 o i h Jl.~ Director of Nuclear Material Safety and Saft ds pxs [8 cn g U.S. Nuclear Regulatory Commission / f Washington, DC 20555 4 A DocuETED \\\\ d USNRC ~ 0 JUN 91986 ) 12 License SNM-95 p ss Docket No. 70-113 imt sect 10M f Program Code: 21310 C DOCKET CLERK A ~ 4 g\\ Gentlemen: The Pennsylvania State University requests the renewal of special nuclear material license number SNM-95, which expires 30 Jun 86. The University is a non profit educational institution incorporated under the laws of the Commonwealth of Pennsylvania. It is governed by a board of trustees, all of whom are citizens of the United States. The main offices of the University and the main campus are located at University Park, PA. An additional 20 campuses located throughout Pennsylvania and the Milton S. Hershey Medical Center are also part of the University. Supplement A of this application lists the amount, form, use and location of use of the special nuclear material covered by this license. No change has been made from the existing license except for an increase from 1 uCi to 5 uCi of Pu-239 as alpha sources and fission foils and a descrease in the amount of uranium-235 as metal foils to reflect the return of material to the Department of Energy. The use of special nuclear material at the University is regulated by the University Isotopes Committee under the " Rules and Procedures for the Use of Radioactive Material at the Pennsylvania State University", which is included as supplement B to this application. The use of byproduct material under licenses 37-185-4, 37-185-5, and 37-185-6 is covered by the same rules and procedures. Each experimenter using special nuclear material must have an authorization to use radioactive material reviewed by the Health Physics Office and approved by the Univeasity Isotopes Committee. Authorizations are issued for a maximum of 3 years. Each new radioisotope user is required to attend a radiation safety orientation lecture and pass a written examination. Additional training by the Health Physics st F606230258 860530 PDR ADOCK 07000113 -./ AN EQUAL OPIORTUNITY UNIVERSITY

a. Page-2 License SNM-95 Docket No. 70-113 Program Code: 21310 may be required for-experiments. requiring special precautions such as high radiation levels, gaseous' radioactive materials, and fission products. A list containing the. names and training of the University Isotopes Committee members and the University. Health Physicist is included as' supplement C to this application. The facilities for handling radioactive material, instrumentation, calibration, personnel monitoring, and waste disposal are described in supplement D. Leak testing of sealed sources is performed by.or under the supervision of the Health Physics Office staff. The possession and use of the special nuclear material under this license meets the criteria for exemption from licensing and inspection fees as per 10CFR170.11 (a)(4) for non-profit educational institutions for "...special nuclear material to be used for teaching, training or medical purposes, except human use". Please contact this office or R. W. Granlund. University Health Physicist, 228 Academic _ Projects Building,_(814) 865-3459, for any additional information you may' require. Sincerely', Charles L. Hosler -m Vice President for-Research and -Dean'of the Graduate School-enc. Supplement: A, B, C, and D Distribution: NRC (7)- C. L. Hosler ti) W. W. Pratt (1) Health Physics Office (2) Penn State Brenzeale Reactor (2) 2 M r36A

00CHET N0. 2d' // $ CONTROL 110. rM7A(( DATE OF 000. 8E O cfd DATE RCVD. 6d> 8 FCUF /85 POR FCAF LPOR - la E REF, SAFEGUARD 3___ FCTC 0 tiler DATE d b IN!TIAL _h l

The Pennsylvania State University SNM-95 Renewal Page 1 30 May 86 SUPPLEMENT A 1. Description of Special Nuclear Material a. One hundred (100) grams of uranium-235 in any form. b. One thousand and one hundred (1100) kilograms of UO2 contained in 417 Pathfinder Superheat Fuel Elements with 415 elements containing UO2 enriched to 6.95 weight U-235 and two elements containing UO2 enriched to 7.5 weight : U-235. c. Three (3) grams of Uranium-233 in any form. d. One hundred and eighty (180) grams of plutonium-239 contained in sealed plutonium-beryllium neutron sources, a. Five microcuries (5 uCi) of plutonium-239 as plated alpha sources and fission foils. f. Two thousand and five hundred (2500) grams of natural uranium encapsulated in aluminum. 2. Proposed Use of Special Nuclear Material a. The material in item 1.a. is to be used in fission counters and chambers for neutron detection with the Penn State Breazcale Reactor (PSBR, license R-2) and other neutron sources, in fission foils for the fission fragment irradiation of various materials or for flux monitoring, and for various research experiments requiring uranium-235 or the generation of fission products or a fission spectrum of neutrons. The current inventory of such material includes 61.2 grams of uranium-235 as uranium and uranium alloy plates, foils, and scraps; 5.6 grams in fission counters, 21.6 grams as U30s, and 0.3 grams as UO2 for a total of 88.7 grams of uranium-235. The additional amount requested is to allow for replacement of fission chambers or the acquisition of additional material for new experiments and for samples transferred from other laboratories for temporary use. b. The material in item 1.b was to be used in a Fast Reactor Spectrum Assembly (FRSA). That project has been cancelled and the University plans to transfer this material to DOE after approved shipping containers are located and trans-portation arrangements are made.

F"""'""""' Page 2 The fuel assemblies are stored in a 12 foot square room in the basement of the Academic Projects Building. The storage room is part of a large room designed to house a 100 MeV linear accelerator. The locked door to the room is constructed of steel plate and keys are issued only to licensed senior reactor operators. The room is equipped with intrusion alarms wired to a continuously monitored alarm panel. The floor plan for the Academic Projects Building, the storage rack drawing, the floor plan for the fuel storage room, and excerpts from the Pathfinder Atomic Power Plant Safeguards Analysis for the Second Core Loading (ACNP-67525) are included as Supplement A-2 to the application for renewal of Licence SNM-95 dated 21 April 78. Because of difficulty in copying the plans for the storage racks, that supplement is not submitted with this application. The rooms adjacent to the fuel storage room engineering research laboratory are currently used for an and for storage. The area labeled " Linac Machine Room" is used by the Health Physics Office for a radiation calibration room and for radioactive waste storage. The high density concrete shield wall between the two areas essentially isolates the fuel storage room from any radiation sources. The fuel assemblies are stored on the same storage racks previously used by Northern States Power Company under license DPR-ll. Criticality calculations used by the Northern State Power Company show that the storage racks loaded with fuel have a kerr of less than 0.8 when flooded with water. The storage arrangement used by the University should be at least as safe as that used by the Northern States Power Company. An exemption to the requirements of 10CFH70.24 for a criticality monitor in the storage room is requested because the area is not normally occupied and the criticality analysis indicates a kerr of less than 0.8 for the worstcase (flooded storage room). Such an exemption was previously granted under this license, c. The 3 grams of uranium-233 in item 1.c. is to be used in the same manner as described for the uranium-235 listed in item 2.a above. The University currently possesses 2 grams of uranium-233 as powdered metal and foil scraps. d. The plutonium in item 1.d. is in the form of seven Pu-Be sealed neutron sources manufactured by Mound Laboratory. Six of the sources (S/N M102, M103, M104, M105, M106, M187) contain approximately 16 grams of plutonium each and one (S/N M-317) contains approximately 80 grams of plutonium.

SUPPLEMENT A Pnge 3 The sources are used in various experiments to demonstrate the properties of neutrons and moderators, for neutron activation, for neutron detector testing, and for the calibration of neutron monitoring equipment. The six 16 gram sources are used at the Brenzeale Nuclear Reactor Facility and the Academic Projects Building at the University Park Campus. The sources are primarily used in a neutron howitzer or in a suberitical graphite pile, but may also be used in air or in other water tanks. The sources are some-times used in the pool of the Cobalt-60 facility (license 37-185-5) or in the pool of the Penn State Breazeale Reactor (license R-2), but they are not used for in-core experiments. The 80 gram source is used at the Beaver Campus of the University at Monaca, PA., for experiments in an associate degree program in Nuclear Engineering Technology. The source is used in a J. L. Shepherd model 179 neutron howitzer. The source is stored approximately 4 feet underground in a locked storage well. The large source may also be transferred to the University Park Campus for the same type of use as the six smaller sources. e. The material in item 1.e is in the form of plutonium plated on metal backings to form alpha sources and fission foils. The alpha sources are used for the calibration and testing of alpha radiation detectors and for demonstrations of the properties of alpha particles. The University currently has 10 such sources manufactured at the Savannah River Plant with a total activity of about 0.12 uCi of plutonium (2 micrograms). These sources may be used throughout the State of Pennsylvania as part of' educational programs or to check instruments. The fission foils are used for neutron flux measurements with the Breazeale Nuclear Reactor und other neutron sources. The current inventory includes 3 foils with an activity of 3.8 uCi (61 micrograms). f. The material in item 1.f is to be used in a natural uranium and graphite subcritical pile. The pile is used for student laboratory experiments in nuclear engineering. It has been used for this purpose for many years without incident. In general operation doses from the operation of the pile have been less than the minimum reportable value (10 mrem) of the dosimeter processor. For a pile loaded with four 16 gram Pu-Be sources the dose equivalent rate is 0.2 mrem /hr or less at 6 feet fr'om the source face of the pile and less than 0.1 mrem /hr at 6 feet from other sides of the pile. The pile is described in the attachment to this supplement. The suberitical pile is located in the Academic Projects Building but may also be used at the Penn State Breazeale Reactor facility. Wa

P The Pennsylvania State Univ. SNM-95 Renewal 30 Nav 86 (en c re Supplenent A ) Cera. ) pay A UNEQU2 SUBCRETZCAL Enkow-

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undIr FORREST J. REMICK The State University of Pennsylvania Pay-INTRODUCTION The advantages of the suberitical reactor and the sigma pile as pedagogical devices are well known and have received attention throughout this conference. Their use as tools for the edu-cation and training of nuclear engineers was demonstrated quite early at the Oak Ridge School ~ of Reactor Technology,1 at the Argonne School of Nuclear Science and Engineering,8 and at several universities.3 Because of this demonstrated usefulness and also because the State University of Pennsylvania was engaged in teaching nuclear engineering to foreign engineers and scientists in a branch of the International School of Nuclear Science and Engineering, it w.s deemed advisable to supplement the reactor laboratory portion of this program by the acdition of a suberitical reactor-sigma pile combination. Prior to this a swimming pool re-setor, in operation since 1955, was tre only nuclear multiplying system used in the reactor 1:baratory program at the State University of Pennsylvania. In 1957 the design of a suberitic:J reactor-sigma pile combination was undertaken.' A graphite-natural-uranium type assembly was selected because of its adaptability to student. experiments resulting from relatively large neutron-transport distances. Funds for the con-struction of this assembly were provided'by the U. S. Atomic Energy Commission as a part of its Equipment Grant Program. The construction of the assembly was completed in early 1958, and it has proved to be an extremely valuable educational tool. DESIGN The criteria for the design included that (1) the assembly should be a combination sub-critical reactor and a sigma pile so that the natural-uranium fuel could be removed and the resulting vacancies filled with graphite stringars; (2) the assembly should be of sufficient size to provide an extensive region over which an exponential flux variation could be observed; (3) the assembly thould be so designed that several fuel loadings would be po sible near and at the optimum ratio of fuel and moderator but providing cases of both over and under modera-tion; (4) the assembly sh,ould be capable of being pulsed by use of one of the horizontal beam ports of the swimming-pool reactor; and (5) the location of the source plane, as well as the position of the neutron source or sources in the source plane, should be capable of being - varied. To be able to pulse the assembly with a horizontal beam port from the swimming-pool reactor, it was decided to make the axis,.which is perpendicular to the source plane, hori-zontal in contrast to classical assemblies of this type in which this axis is vertical. Thus in-J 89 S o i

1 stead r.f 1:.e nr...a'y being built on top of a moderating pede.v.... it as placed on its side with the pede.C sar...ng oi.e end of the auembly. To avoid buildmg an expensive and cumbersome gamma shleid around this exposed pedestal, the use of plutonium-beryllium neutron sources r j was planned for the design. The decision to build the assembly on its side, so to speak, has } proved to be a tremendous asset in its classical use and its adaptability to use with the port-l able neutron generators currently available commercially. The assembly is shown conceptu- ] ally in Fig.1. l i f cADungu 4 t ALuuWyM cover i 4 i f NN I j \\9 y ) i h 'T' esouRcc l x. s4R l 4 t 1 f f ~ r* s i l s\\.

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..J ~ ^ 1 NL' M'== AtuuiNuu cover F SUPPORT GRID l Folt STRINGER FUCL SLUG l rig.1-$uberltical reactor Loading 1. )+ During the early stages of the design, it was known that natural-uranium-fuel rejects would be available for use, but it could not be determined whether they would be solid or a hollow fue; slugs or what the actual diameter would be. Therefore, in the design four separate fuct sizes were assumed based on the best information available in the unclassified literature about typical natural-uranium fuel-slug dimensions. These fuel radii were 1.27 cm (1.00 in. in diameter),1.33 cm (1.04$ in. In diameter),1.40 cm (1.10 in. in diameter), and 1.43 cm (1.125 in, in diameter). The detailed analytical design is described in reference 4 to this paper. l Both the effect of air gaps and the absorption due to the aluminum cladding on both hollow and t solid slugs were incorporated in the calculations. The results of these calculations for the i solid-fuel-slug case appear bricily in Figs. 2 to 4, where R is the solid-fuel-slug radius and l R is the lattice equivalent-cylindrical-cell radius. The hollow-slug case is not considered of l t 3 interest in this paper because solid slugs were eventually supplied for the assembly. In the early stages of the design of the reactor, it was desired to obtain graphite bars that i l f would be approximately 70 in in length. Only 3 of Il graphite supp!!ers contacted could manu-I facture reactor grade graphi, and only one of these claimed the capability of supplying bars i of the desired length. However, during the final stages of this design, the supplier declined i the original offer of supplying graphite bars in 70-in. lengths. Because all three suppliers were e { capable of manufacturing bars in lengths in the general range of'51 to 54 in., the final design l l 90 I 1 I t 1 I l u 4 l

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04G 3 0 8u l.030 - 0.3 t 020 - 0.2 1.0t0 - Of O t 2 rutp SLUG RADIUS, CW 3 Fig. 2-Fast-fission effect. was based on two bars of lengths of $2'/2 and 17' in. as a means of obtaining the desired 70-in. parat] / atura length. These particular lengths were selected as a means of reducing machining waste and 8 3 in, thus the over-all cost. The 52 /-in. lengths were readily obtained from 54-in.-long rough bar stock. Similarly three 17'/-in. machined bars were obtained from 54-in.-long rough bar a pap:r. stock without unusunble short lengths remaining. and The reactor design in which two graphite bars must be used to obtain the desired bar length is not the most desirable design because in fabrication and lattice changes it is neces- ., e uand sary to handle approximately 25 per cent more pieces, flowever, the decreased weight per cd cf bar offers some advantage in assembly. The assembly length is 104 in. and two separate bars each 52 in. long are used. By the method of laying these b'ars crosswise relative to those bars containing fuel openings, no other 1 th t keying or supports are required for the assembly. manu. bars The only sizes of rough bar stock originally available were 4.37 and 4.50 in, squares. The ed maximum sizes of machined bars obtainable from this rough stock are 4.00 and 4.33-in. square bars. Later in the design period, rough bar stock in larger sizes became available through the s w:ra dp previously mentioned suppliers. 91 e mu

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v i y A, t3 i .a ... t. r t NN - A, e s.43 9a f A, e 1.43 A, e t.33 k$ i. Ase t.27 - 5' c.4 3.e l a d g } E f ,i y l' i i 1 t I { I' I I I I I I I I ar ) l a to t2 44 46 5 EQutVALENT CtLL AaDaus. A.CM I l 3 .I Fig. 3-Thermal ut!!! stion and resonance escape for various ce!!s. 1 ei f I uo I I I I l l I l l 1 i } e e f a g / g A. a t.43 e I o A, e t.40 - b h t.416 = I A, e t.33 o Cg Ree s.21 f e 5 0 s h 1 5 1 s s i i., t.00 j t, i c .i i E e 1 .I i i I I I l i I I i t f a 50 te se is s +l touiv4 LENT CCLL AA0lus, A,CM *

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I l l 1 From the early design calculaimns in which data on the fuel slugs provided by the Atomic Energy Commission (1.27 < R: < l.43) were used, it became obvious that the use of bars in t sizes of 3.50 by 3.50 in and 3.50 by 1.75 in, would provide four separate lattices with k > 1 and that the values of k,. would be distributed fairly uniformly arocnd the optimum condition. Ilowever, because of the waste involved in machining the avail:.b!c bars of these sizes, the calculations showed that approximately 30 per cent more rough graphite stock would be re-quired than would be required if the 4.00.in. bars were used for the proposed reactor and that the machining cost would be increased more than 30 per cent because, in addition to more bars being used, each bar would require more machining. The cost of a reactor with these smaller bars was therefore found to be too expensive. It was found that 4.00- by 4.00-in. machined bars would require the minimum number of rough bars and the minimum amount of machining and would provide five separate lattices with k, > 1 and that, although values of k. would be obtained on both sides of the optimum condition, none would be very near the optimum condition. In fact, two separate sets of the points would so closely coincide that, in effect, only three different lattices with'k > 1 would result if these bars were used. Ilowever, further investigation resulted in the selection of bars 3.88 by 3.88 in.' and 3.88 by 1.875 in. These sizes are a compromise of the advantages and disadvantages of the 3.50- and 4.00-in. sizes. Although these bars require more rough stock and machining than the 4.00- by 4.00-in. bars, the estimated cost was within the funds available for the graphite and its machin-ing cost (S29,500). These bars offer five separate lattices with k > 1. 'One of the points essentially coincides with the optimum condition. Although the remaining four points are dis-tributed with one point below and three points above the optimum condition, they are so spaced that this is not a serious disadvantage. For these reasons the bar sizes of 3.88 by 3.88 in. and 3.88 by 1.875 in, were selected. It is pointed out that, in addition to these five lattices with k > 1, innumerable lattices exist where k < 1, especially for lattices that are overmoderated. Each fuel slug is 8'/,in. long, and eight of these slugs are placed in a fuel channel. This gives a fuel-channel length of 68 in. Eccause of the manner in which the reactor is constructed, it is necessary that the width be some multiple of 3.88 in. Eighteen of these bars, the number that constitutes the total bar width, have a width of 69.84 in. Therefore, with allowances for tolerances on width and bar warpage, the width of the reactor was made to be 70 in., as pre-( vlously mentioned. The eight fuel slugs in a fuel channel are loaded into a 6061-T6 aluminum tube that has an outside diameter of 1/ in. and a wall thickness of 0.058 in. This metho 8 loading expedites the changing of fuel lattices since eight slugs can be handled at one time. The added aluminum present in the ce!! from this tube increases the absorption of neutrons, but this absorption does not appear to be excessive. These tubes can be readily plugged and - water filled to observe the effects of a water coolant for the fuel slugs if desired. The two major loadings possible with the assembly are shown in Figs.1 (Loading 1) and 5 (leading 2). The three separate lattices with k > 1 usable in leading 1 and the two lattices with k > 1 usable in loading 2 are shown in Fig. 6. Loading 1 is in the most general use since it offers a point near optimum condition and points below and above optimum cell size. The information pertinent to the dimensions of these various lattices is contained in Table 1.

• l ii Table 1-CELL GEOMETRIES

~ 1 Fuel to fuel Cell-radiue loading Cel! Volume of moderator designation geometry Cm In. Cm In. per cm of length, cm8 'I 1-A Square 14.6 5.76 8.26 3.25 - 200 .I l 1-B Square 29.2 11.51 16.52 6.50 843 1-C Hexagonal 20.7 8.14 11.67 4.60 2-A Square 19.4 7.63 10.95 4.31 362 413 2-B Hexagonal 27.4 10.79 15.47 6.10 737 e 93 4 e ..m

r CADwlUM ALU M IN UM cot 1E k i 1 e 1 [ I i { I i I I .i q l TFili3d 11 .= CADWiUM l ALUMINUM =d o COVER ALUMINUM FOIL STRINGER 1 ? SUPPORT GRID FUEL SLUG Fig. S-Subcritical reactor Loading 2. i i A B C I E M s l didir ll ll di li e i l j f dIdIe M! II n iI dI LOADING t 1 4 I t l 4 A B i f i dll d ll e llidil-4 dll d ll o dll lli e 1 W ll J ll e lll JlI _ a LOADING 2 i 3 i Fig. 6-Five possible lattice arrangements. 1 f i 4-h. G4 I r .i 4. l j o 6 e >~ w. B

Tr.c different type grapr.::e L.ir.- v.nich are required to provide two separa:e sut./ritical !cair.gs with invc separate lattice:..s e shown in Fig. 7. Table 2 provides information about the number and actual dimensions of.s!! these bars. TaL!c 2-GitAPHITE BAR REQtJIREMENTS Number Type bar required A B C D Detall A 22 3.t 5 3.65 52'/ A bar 3 AA 22 3.M 3.88 17'/a A bar A-1 8 ' 3.d5 3.S5 52'/. A bar 3 8 AA-1 8 3.d5 3.65 17 / A bar 3 8 A-2 137 3.es 3.86 52/ 1.50 x 1.50 A-2 bar 3 8 A A-2 137 3.56 3.65 17 / 1.50 x 1.50 A-2 bar 3 A-3 17 3.h6 3.86 52/ 1.50 x 1.50 A-3 bar 3 AA-3 17 3.e 5 3.56 17'/ 1.50 x 1.50 A-3 bar 3 8 A-4 1 3.b5 3.65 4G.56 1/ D x 1.80 A-4 bar 2'/ D x 1.80 A-5 2 3.85 3.85 46.56 l'/ D x 3.305 A-5 bar 81/ D x 1.80 A-6 bar A-6 1 3.55 3.85 23.44 8 A A-6 2 3.85 3.85 23.44 1/ D x 3.305 A-6 bar B 462 3.86 1.675 52 B bar . B-1 220 3.86 1.875 52'/ D bar 3 8 BB-1 220 3.86 1.875 17 / B bar 3 B-2 4 3.86 1.875 52 1.50 x 0.755 B-2 bar 8 B-3 2 3.65 1.844 52, 1/ x 1.844 B-3 bar C 2 1.45 1.45 52 C bar 8 C-1 171 1.45 1.45 52 / C bar CC-1 171 1.45 1.45 17'/2 C bar The assembly is covered with sheets of cadmium to guarantee the b' re boundary condi-a tions assumed in the analytical design. To provide strength to the 0.020-in. cadmium used, it is sandwiched between two riveted aluminum sheets that are each 0.063 in thick. An actual photograph of Loading 1 is seen in Fig. 8, and the assembly with its cover is shown in Fig. 9. Eighteen foil-stringer positions are present which have hinged cadmium-lined trap doors through the outside covers, and there are eight source bars that are machined slightly under-size in order that essentially any source configuration utilizing from one to five plutonium neutron sources can be used. Several alterntiv(s were possible to provide openings in the graphite into which the fuel could be inserted. One method is to drill holes from either end of the graphite bars, which is very expensive and which usually allows a slid t offset from " tool wander" in the center where h the two drilling tools meet. Another method is to chamfer the edges of four adjoining graphite bars. This is a rather simple operation, but it requires four separate setups per opening. Cost estimates indicated that it would be cheaper to machine a square 1.5-in. corner off the square bars. Cut for cut this is more expensive than chamfering the edges, but because only one-fourth as many cuts need to be made, this method is substantially cheaper (approximately 50 per cent, according to the supplier) than both the drilling and chamfering procedures. By the procedure of removing the fuel slugs from these openings and replacing them with graphite-stringer inserts, a complete graphite sigma pile is obtained for use in measuring the graphite diffusion length, the age, and for pulsing experiments. The sigma-pile loading is shown in Fig. 10. Specini graphite stringers have been fabricated for holding indium foils with thin aluminum backing, minute BF and fission chambers, etc. Several of these stringers are shown in Fig.

11. Also in this figure, viewing from the top to the bottom of the figure, the following struc-E 95 e

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M' D b is, c / ' >o o o j' t t y A-4 B AR y A-5 BAR 3 A-6 B AR I f b k / l c c c c x ^ B BAR 4 B-2 B AR ( B-3 BAR C BAR p N N', a a Fig. 7-Graphite-har dimensions and designations. Measureme,ts are in inches. tures can be seen: the aluminum tube that holds eight fuel slugs; the graphite stringer that holds a plutonium-beryllium source in one end and slots for cadmium-covered indium foils for age measurements; the two halves of the graphite stringer that contains a minute BF 3 counter in its aluminum protective cover; a small graphite stringer that holds indium-aluminum foils for extrapolation-distance measurements; cadmium boxes for foils; and a canned cylindrical fuel slug. Because the assembly is horizontal, it is a simple matter to conduct an exponential ex-periment without the need of climbing on top of the assembly or with,out the need of winches, etc., to position the detector. In addition, since a through-hole exists along the transverse axis (perpendicular to the source plane), the, detector can always be followed by calibrated graphite stringers that indicate the detector position and prevent neutrons streaming out of the hole. Graphite stringers are provided which enable the flux to be plotted near the assem-l bly boundaries in order that the extrapolation distance can be readily obtained. The special l stringer that contains a plutonium-beryllium source and numerous cadmium-covered indium foils is inserted in the }ransverse axis so that the source can be positioned in the center of i i the sigma pile for age measurements in an infinite moderator or offset from the center if the I 1 effects from the use of a finite moderator are to be observed. .l UTILIZATION l i f The suberitical-s,igma pile assembly described in this paper has proved to be a valuable tool for teaching reactor faboratory courses. It also has proved to be quite flexible, being readily conyerted from one subcritical fuel loading to another in about half a man hour or to a 1 { sigma-pile configuration in about two man hours. 3 As a sigma pile the assembly is used to compare measured flux plots along all major axes with the calculated distribution, to measure diffusion length, extrapole. tion distance, Fermi Age, and to observe flux distribution as a function of source configuration or as a function of the position of absorbing material in the assembly. A typical student experiment conducted t 96 i i 1 j f t w

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• i s,,_.....

pe ,.,... - M ' [.. i /, ~~~~-. W-N 6, ",,#. r~,, p p ,.py dig s 7"p / m-a' ,s p.g In - t %.. _..s; ~ s SUL Fig.11-D e tec tors. r00 ass 98 J .W 0 w

l with the sigma pile is included as Appendix I to this paper. In Fig.12 the plotted 4 diffusion-length experiment are given. I I O I I l I -- to,ooo y ,, I 4 k-h' 4E g b ~ ~* t - A y stoPC e -o.o3tG2 a 1 8 1000 r t E g a g j 3 G i 5 i i g p ^ t b E l ( ' S co r 4 5 s - .E a o; e [ I e s i I I I I II .a ,o o 60 12o 18o 24o DISTANCE FRoM SOURCE PLANC, CM = 1 Fig.12-Diffusion length in graphite experimen't. O. data points. A. least squares fit, i l l i As a suberitical reactor the assembly'is used to measure extrapolation distance a i rial buckling of the lattice. This measured information is used to calculate the age a { e. sion length in the suberitical assembly, infinite multiplication factor (k ), nonleaka i j abilities, effective multiplication constant (kerg), and suberitical multiplication. All the l measured and calculated for various fuel to moderator lattices. One of th t periments has been that of conducting an exponential experiment with Imading 1-C, kg of natural uranium are in the assembly. In a following f a ditional 1195 kg into the assembly by removing the remaining graphite stringers ( i They find that in this case k.,is much lower than with the previous loading contain In Fig.13 the results of a typical exponential experiment wi /

SUMMARY

j At the State University of Pennsylvania, a flexible graphite-natural-urantam suberitic j . reactor-sigma pile has proved to be a valuable laboratory education and research tool. T assembly, which is approximately 6 by 6 by 9 ft. is readily converted from a sigma p i 99

l l 0 gy a e c r s g 4 6 l-I s '-- E l 4 / y 1000 h 8 g o 6 g SLOPE = -oo237 t 4 h \\x t W \\x r N e g i too R 8 : m 6 4 g' } t 8 i i t I l I I ! ! I i f I I I I f I ,o o 3o Go 9o 12o 150 DISTANCE FROM INTERFACE, CM i e Fig. I't-Exponential experiment. x. data putnis. A. least squares fit. t subcritical reactor. As a suberitical reactor, five lattices with k greater than unity are avail-ab!c. These lattices provide conditions near the optimum fuel to moderator ratio for the partic-ular fuel slug (1.30-cm radius) as well as lattices that are under and over moderated. Tne assembly is u,niquely positioned on its side in comparison to the classical position of similar assemblies. This adds to the flexibility of the assembly and makes it readily adaptable to pulsed or continuous neutron-source experiments in which either horizontal beam ports from other critical assemblies or separate neutron generators that are currently available commercially are utilized. 4 + REFERENCES

1. Oak Ridge School of Reactor Technology, Tennessee, Reactor Physics Laboratory Manual, a

USAEC Report TID-5202, July 1955.

2. A. B. Smith, An Experimental Study of Heterogeneous Exponential Assemblies, USAEC Re-port M-6246 (Includes TID-5025), School of Nuclear Science and Technology, Lemont,111.,

June 1955.

3. L. B. Borst, Suberitic'al Reactor in a Pickle Barrel-NYU's Training Tool, Nucleonics, 14: (8), 66-68 (August 1956).

j

4. F. J. Remick, A Graphite-moderated Subcritical Reactor-Sigma Pile, M.S. Thesis, The State University of Pennsylvania,1958.

T I i 1 100 l t s A w

The Pennsylvania State Univ. o SNM-9S Renewal .d 30 May 86 SUPPLEMENT B O RULES AND PROCEDURES for the USE OF RADI0 ACTIVE MATERIAL at the PENNSYLVANIA STATE UNIVERSITY by Tile UNIVERSITY ISOTOPES COMMITTEE JULY 1980 l D. V A copy of this manual is issed to each person (supervisor) authorized by the University Isotopes Committee to use radioactive material, The supervisor is responsible for making the manual available to anyone exposed to radiation or radioactive material under the supervisor's control. The supervisor is also responsible for inserting any revisions and additions to the manual upon receipt from the IIcalth Physics Office. All persons using radioactive material must be familiar with sections 0-17, those sections (18-27) dealing with their specific use, the federal regulations, and any radioisotope fact sheets for the radioisotopes they are using. It is suggested that copies of the authorizations from the University Isotopes Committee issued to the supervisor also be kept in this binder. /U

i l t TABLE OF CONTENTS I SECTION 'SECTION 0 EMERGENCY TELEPfl0NE NOTIFICATION LIST....... 0 1 PURP0SE..................................... 1 2 SC0PE................p...................... 2 f 3 ADMINISTRATIVE CONTROL..................... 3 4 UNIVERSITY ISOTOPES C0bNITTEE............... 4 S IIEAL'111 PHYSICS 0FFICE....................... S 6 RADI0 ISOTOPE LABORATORY SUPERVISOR,,,..,, 6 7 AUT110RIZATION TO USE RADIOACTIVE MATERIAL,,. 7 8 INSTRUCTION AND TRAINING.................... 8 j 9 PERSONNEL DOSE LIMITS....................... 9 i i 10 PERSONNEL MONITORING........................ 10 11 RADIATION AND CONTAMINATION LIMITS.......... 11 1 12 RADIOISOTOPE LABORATORY RULES............., 12 13 SURVEY PROCEDURES........................... 13 14 WASTE DISPOSAL.............................. 14 ] IS EMERGENCY PROCEDURES........................ IS .i 16 PURCl!ASE, TRANSFER, OR SilIPMENT OR RADIOACTIVE MATERIAL 16 1 j 17 RECEIPT OF RADIOACTIVE MATERIAL SHIPMENTS... 17 18 RADI0 ISOTOPE NEUTRON SOURCES................ 18 j 19 GAhNACELL IRRADIAIDRS....................... 19 20 ALPflA SOURCES (SEALED)...................... 20 2 21 SPECIAL NUCLEAR MATERIAL CONTROL PROCEDURES, 21 22 SOURCE MATERIAL,..........................., 22 23 ACTINIDE SERIES IS0 TOPES.................... 23 24 GAS C11ROMATOGRAPil SOURCES................... 24 2S !!UMAN USE OF RADI0 ACTIVE MATERIAL,.......... 2S ~ 26 FIELD USE OF RADIOACTIVE MATERIAL........... 26 1 27 USE OF RADI0 ACTIVE MATERIAL AT T11E C0bNONWEALTil CAMPUSES...................., 27 l FEDERAL REGULATIONS 10CFR19 Notices, Instructions, and Reports To Workers; } Inspections j 10CFR20 Standards For Protection Against Radiation l 10CFR21 Reporting Defects and Noncompliance RADI0 ISOTOPE FACT SIIEETS i

_ _ ~ 4 J l EMERGENCY TELEP110NE NOTIFICATION LIST Fire or Accident: Police Services: l University Park Campus. .110 University Park Campus.. 863-1111 State College Fire Department.. 234-0234 State College Police. . 234-0234 Ritenour Health Center. .865-6537 State Police. 863-4G46 centre Community Hospital 238-4351 Ambulance Services: Ritenour Health Center.. 110 or 8G5-6537 Borough of State College. 234-0234 Health Physics Office: 228 Academic Projects Building 865-3459 T l l. R. W. Granlund, University Health Physicist Home Phone: 238-2952 l 2. W. T. Ford, Jr., Associate Health Physicist Home Phone: 355-1811 3. E. C/ Augustine, Health Physics Assistant j 3 Home Phone: 234-2889 1 1 1 4. D. H. Hollenbach, Health Physics Assistant O He-: Phene: 832-88o8 5. W. E. Johnson, Health Physics Assistant Home Phone: 238-2308 i 6. If no members of the Health Physics Staff are available, request Police Services to contact someone on the Penn State Breazeale Reactor emergency duty schedule. U.S. Nuclear Regulatory Commission Commonwealth of Pennsylvania Region I Department of Environmental Resources Office of Inspection and Enforcement Bureau of Radiation Protection i 631 Park Avenue P.O. Box 2063 i King of Prussia, PA 19406 Harrisburg, PA 17120 Phone: 215/337-5000 Phone: 717/787-3720 4 ~ (dial 8-447-3720 from PSU phones) After hours: 717/783-8150 4 Department of Transportation Hazardous Substances Transportation Board Washington, D.C. Harrisburg, Pi 17120 Phone: 202/426-1930 Phone: 717/787-7445 l (dial 8-447-7445 from PSU phones) C) \\ 0-1 j i i IMW 2/86 a.t.. =. -. ~, .a.

t i Section 1 PURPOSE A The rules and procedures in this document have been adopted by The Pennsylvania State University to provide for the safe use of radio-active material by University personnel. The rules are necessary to meet the requirements of federal and state regulations, license and insurance conditions, and University control. It is the intent of the University that these rules and procedures allow as much freedom as possible for experimenters while assuring that the release of radio-active material and the exposure of personnel to ionizing radiation be kept to a minimum. It is the policy of the University that the release of radioactive material and the exposure to ionizing radiation be kept as far below the regulatory limits as is reasonably achievable, f3 L,] ,s 1-1

Section 2 /~N SCOPE O 2.1 These rules and procedures cover the possession, use, and trans-fer of all radioactive material on University-controlled property by University personnel or others and by University personnel at other locations. This includes the University Park campus and nearby University-owned land, the Commonwealth campuses, and other locations named in the University licenses, but not the Milton S. Hershey Medical Center. The Medical Center is covered by rules and procedures which are administered by a committee separate from the University Isotopes Committee. 2.2 It is not the intent of these rules and procedures to cover nat-urally occurring radioactive materials in the normal concentration and chemical state or those materials such as smoke detectors, luminous dials, etc. acquired under a general license. However, the University Isotopes Committee may require authorization to possess or use such material if the potential hazard is compara-ble to other licensed material. Examples are static eliminators, ion generating tubes, and relatively large quantities of uranium or thorium bearing ores or chemicals. In general,use of those materials with radiation levels in excess of 5 mrem /hr at any accessible surface or which could produce an inhalation or in-gestion hazard will require authorization from the University Isotopes Committee. The Health Physics Office should be con-sulted before acquiring such materials to determine whether an authorization is required. 2.3 These rules and procedures do not apply to the operation of the University nuclear reactor except as specifically made a part of the reactor operating license. Radioactive material contained in the reactor fuel elements, operating components, or supporting structure is exempted from these regulations and is covered by the reactor operating license. Other radioactive material produced by the nuclear reactor shall come under the control of the Univ-ersity Isotopes Committee upon removal from the reactor pool. 2-1

Section 3 ('l %./ ADMINISTRATIVE CONTROL 3.1 The Vice President for Redcarch and Graduate Studies has bee ignated by the President of the University as the person responsi-ble for licensing and the radiation safety programs for radioac-tive material. The Vice President appoints the University iso-topes Committee to control the use of radioactive material within federal, state, and University regulations and to perform those functions required of a radiation safety committee by the regula-tions. 3.2 The Health Physics Office, one of the Intercollege Research Pro-grams, is also administered by the Vice President for Research and Graduate Studies to provide radiation safety services. The University Health Physicist is in charge of the Health Physics Office and is responsible for those duties assigned to the radia-tion safety officer by the regulations. J. 3-1 2 f

4 Section 4 /N b UNIVERSITY ISOTOPES C05NITTEE 4.1 The University Isotopes Committee is responsible for adminstering the licenses issued to the University for the use of radioactive i materials and for insuring that such use meets the requirements of the University, state, and federal regulations. The Committee shall maintain an active membership of at least five persons. At least two thirds of the members shall be from those colleges which are the predominate users of radioactive material. At least two thirds of the members shall have sufficient training and experi-ence to evaluate the technical aspects of proposals to use radio-active material. If possible, the Committee shall include a phy-sician or other person with medical training and a member from the University administration, preferably the Office of the Vice Pres-ident for Research and Graduate Studies. The Committee shall meet at least semi-annually. A quorum shall consist of 60% of the mem-bers, excluding those who may be on sabbatical or leave of absence. 7S The Committee members and the Chairman shall be appointed by the kl Vice President for an indefinite term, unless a definite term is stated. The Chairman may designate an acting chairman to conduct Committee business in the Chairman's absence. 4.2 The Committee has the authority and responsibility to review all proposals for the use of radioactive material (Request for Author-ization to Use Radioactive Material) and to approve or disapprove such requests. The Committee also has the authority to withdraw its authorization to use radioactive material and to order an experimenter to take whatever action the Committee considers nec-essary to correct a situation which could produce a hazard to per-sonnel, property damage, or violation of a license or regulation. The Committee shall request a review by the Health Physics Office of all requests for authorization to use radioactive material prior to action on the request by the Committee. The Committee may seek assistance from other experts in the review of proposals involving areas outside the expertise of the membership. The [} Nuclear Reactor Safety Committee is to be consulted on the review 4-1

of proposals involving significant quantities of special nuclear material or source material for recommendations on criticality control. 4.3 The Committee shall meet for the review of all requests for auth-orization to use radioactive material that could present unusual hazards or that involve unreviewed procedures that could result in significant personnel exposure to radiation or release of radi-onctive material. Requests for the routine use of radioactive material may be approved by the Committee Chairman after notifying the other members by mail or telephone of the request and allowing at least seven days for them to register a negative vote or to request a meeting of the Committee for review of the request. The Committee Chairman is authorized to amend a previously approved authorization to use radioactive material on the recommendation of the IIcalth Physics Office to increase the possession limit up to five times the original activity, to allow minor changes in procedure, or to add radioisotopes similar to those previously approved. Authorizations shall be approved for a specific time g period not to exceed three years. 4.4 The Committee is responsible for and has the authority to specify the requirements for training radioisotope users, to specify the requirements for radiation and contamination surveys, to review the radiation safety program, to formulate the University rules and procedures for the use of radiation material, and for the approval of University license applications for possession, use, or transfer of radioactive material. The Committee may authorize the Chairman to review and approve these items without review by the full Committee. 4.5 The Committee Chairman shall call meetings of the Committee as he deems necessary but at least semi-annually. The Chairman shall also call a meeting of the Committee as soon as convenient after receiving a request from any Committee member, the University ifealth Physicist or any experimenter who desires a full Committee review of any action taken by the Committee or the Health Physics Office. 4-2

Section 5 b) ~' 11EALTil PliYSICS OFFICE 5.1 The llealth Physics Office is one of the Intercollege Research Programs administered by the Vice President for Research and Graduate Studies. It is under the direction of the University Health Physicist and was established to provide radiation safety services for the University. 5.2 The Health Physics Office has the responsibility and the author-ity for the following: (a) Review all requests for authorization to use radioactive material for the University Isotopes Committee and pro-vide the Committee with recommendations for approval, disapproval, or conditional approval. (b) Review orders for the procurement of radioactive mater-ial to insure that the material is within the limits of the University license and the Committee authorization. (c) Provide a central receiving for all incoming shipments of radioactive material and survey such shipments for leakage, damage, and contamination. (d) Process all transfers and shipments of radioactive mater-ial to insure that the material is properly packaged and the recipient is authorized to receive the material. This includes the transfers between University experimenters. (c) Provide assistance and consultation to experimenters as needed. (f) Conduct radiation and contamination surveys of radio-isotope laboratories as needed. (g) Provide training and instruction in radiation safety for radioisotope users. (h) Calibrate survey instruments. A (,; 5-1

(i) Provide a central temporary storage location for radio-active material which is not in use but might be valuable h for future experiments. (j) Conduct or supervise the required leak testing of scaled sources. (k) Provide personnel monitoring, including bioassay, for University personnel exposed to ionizing radiation or radioactive material. ~ (1) Provide assistance and supervision in radiological emer-gencies. (m) Provide for the disposal of radioactive waste which has been properly prepared and labeled by the user. 5.3 The Health Physics Office maintains a central file of the records required by the various regulations and licenses. These include the following: (a) Personnel dosimetry records such as radiation dosimeter reports, bioassay results, dose estimates from radiation h surveys, and reports of investigation of incidents. (b) An inventory of the radioactive material acquired under the various licenses. This inventory shall be corrected at least annually for decay and disposal. (c) Records of the disposal or transfer to other licensees of radioactive material. (d) Records of radiation protection surveys. (c) A file of the current authorizations to use radioactive material as approved by the University Isotopes Committee. O 5-2

2 4 5.4 The staff of the !!ealth Physics Office has the responsibility and authority to enter any radioisotope laboratory for the purpose of inspection or surveys to determine compliance with the licenses, regulations, or the user's authorization to use radioactive mater-ial. The University llealth Physicist has the authority to require the immediate termination of activities and/or corrective action l in any situation which, in that person's judgment, could lead to the unnecessary exposure of personnel to ionizing radiation, the i release of radioactive material, the loss or damage of property, or noncompliance with a license or regulation. a f () 1 I t .5-3 I. :., -... - _ -.., = _. - - =.

Sec. tion 6 RADIOISOTOPE LABORATORY SUPERVISOR 4 6.1 The radioisotope laboratory supervisor is the person (s) who ap-plies to and receives approval from the University Isotopes Com-mittee for authorization to use radioactive material. The super-visor shall be a member of the University faculty or staff (includ-ing emeritus members). The supervisor is responsible for all 4 activities using radioactive material obtained under the super-visor's authorization to use radioactive material. The responsi-bilities of the supervisor include the following: (a) The supervisor shall insure that personnel engaged in activities covered by the supervisor's authorization to use radioactive material are instructed in radiation safety and that they are informed of and abide by the regulations and the conditions of the authorization. (b) The supervisor shall notify the Health Physics Office immediately in the event of any radiological emergency. (c) The supervisor is responsible for the decontamination of any facilities contaminated by material used under the supervisor's authorization to use radioactive material. The Health Physics Office will supervise and assist in such decontamination. (d) Supervisors are responsible for maintaining a current record of the radioactive material in their possession and for the secure storage of such material. (e) The supervisor is responsible for preparing, classifying, and describing radioactive waste, as required by the Health Physics Office, prior to collection of the waste for disposal. (f) The supervisor is responsible for directing all orders, transfers, and shipments of radioactive material to the i O 6-1

Health Physics Office for processing or approval. O (g) Supervisors shall notify the Health Physics Office and arrange for someone to assume responsibility for their authorizations prior to terminating employment at the University or leaving for an extended period (in excess of six consecutive weeks). (h) Supervisors shall report to their laboratory i:amediately upon notification of an emergency (fire, contamination, flood, equipment malfunction, etc.) and render all pos-sible advice and assistance with regard to the hazards from radiation or radioactive material. O O 6-2

Section 7 p). ( AUTHORIZATION TO USE RADIOACTIVE MATERIAL 7.1 University faculty or staff wishing to use radioactive material should request permission to do so by submitting the form " Request for Authorization to use Radioactive Material" to the University Isotopes Committee. The request should be submitted in the name of the individual (s) who is directly responsible for the direction of the work. That person will be named the laboratory supervisor and is responsible for those items listed in section 6 of this document. Forms may be obtained from the Health Physics Office. The forms are to be completed by the applicant and then submitted to the Chairman of the Committee or the Health Physics Office. It is suggested that applicants discuss the proposed use with a mem-ber of the Committee or the Health Physics staff prior to submis-sion of their request. 7.2 Requests for authorization for more than one radioisotope may be () submitted on the same form if the activities of each are relatively low, the proposed use is routine, and the control procedures are similar (i. e. 2"C and 35S). A separate authorization and written procedure request should be submitted for experiments involving large activities, special procedures, or radioactive material in the form of gases, aerosols or powders, which could become airborne. For example, a separate authorization would be required for a radioiodine experiment, an experiment with 25 mci of P-32, or a device using a 10 mci Co-60 source. 7.3 Requests for authorizations will be reviewed by the Health Physics Office and returned to the Chairman of the University Isotopes Committee with a recommendation for approval, disapproval, or approval with conditions. 7.4 The applicant will be notified of the Committee action by the return of a copy of the authorization request signed by the Com-mittee Chairman and noting the action taken. A copy will be returned to the Health Physics Office for filing and a copy of I 7-1

approved requests will be sent to the University research reactor, if it is listed as a supplier of the radioactive material or the place of use. 7.5 Approval of an authorization request by the University Isotopes Cor:mittee for use or production of radioactive material at the University research reactor does not commit the reactor facility to provide the material or allow the use of the reactor facility, Arrangements for this must be made directly with the reactor fa. cility staff. 7.6 Requests for authorization shall be approved for a specific time period, not to exceed three years. A new request is to be sub-mitted on expiration of an authorization for continuing work. This requirement is to ensure that the authorization is period-ically reviewed and reflects current usage. O i 7-2 1

Section 8 () INSTRUCTION AND TRAINING 8.1 All persons using radioactive material under an authorization issued by the University Isotopes Committee are required to attend t a radiation safety lecture. This includes faculty, staff, students, and any others who might be exposed to radioactive material or ioni-zing radiation in a restricted area. It is not meant to include l persons under the direct supervision of an authorized radioiso-tope user, except as required by the University Isotopes Committee,

i. e. students in laboratory courses, tour groups, maintenance personnel, etc. The Committee may require additional instruction or training of persons working under specific authorizations which present unusual radiation safety problems.

8.2 Instruction of-personnel will normally be done by the llealth Phy-sics Office staff but may be performed by others, as approved by the University Isotopes Committee. Instruction shall include the regulations in 10CFR19, 10CFR20, and 10CFR21 plus the rules and O procedures in this document. 1 4 4 ) O 8-1

~ Section 9 ( ) PERSONNEL DGSE lit!ITS 9.1 The limits specified in this part are the maximum allowed by the regulations. As stated in section 1 of these rules and procedures, the University is committed to the principle of maintaining radi-ation doses and the release of radioactive material to as low as is reasonably achievable for each use, regardless of the limits. For the purpose of these rules and procedures a person is assumed to have received a dose equivalent of 1 rem if exposed to a radi-ation level measured as: (a) An exposure of 1 roentgen of xy or gamma radiation (b) An absorbed dose of 1 rad of x, gamma, or beta radiation (c) An absorbed dose of 0.1 rad of neutrons or high energy protons ( a quality factor based on neutron energy or a neutron rem meter may also be used to determine dose equivalent for neutrons) (n (d) An absorbed dose of 0.05 rad from particles heavier than s-protons and with sufficient energy to reach the lens of the eye. 9.2 For adults (age 18 or older) working in radioisotope laboratories the maximum dose equivalent which can be received in one calendar quarter is as follows for the' various parts of the body: (a) h' hole body, head and trunk, active blood-forming organs, lens of the eye, or gonads 1.25 rem (b) Hands and forearms or feet and ankles 18.75 rem (c) Skin of the whole body 7.50 rem 9.3 The dose equivalent to the whole-body may be increased to 3 rem / quarter if the individual has a complete radiation history on i file and the accumulated dose equivalent does not exceed 5(n-18) rems, where N is the individual's age in years at the last birth-date. 9-1 \\ l I

9.4 The concentration of airborne radioactivity in radioisotope lab-g oratories shall be controlled so that adults are not exposed in excess of the limits in 10CFR20.103. The concentration of radio-active material in unrestricted areas shall not exceed the limits in 10CFR20, Appendix B, Table II (concentrations may be averaged over one year). The Health Physics Office is to be consulted before conducting any experiments involving the release of radio-active material. 9.5 Radiation levels shall be controlled so that the dose equivalent received by minors in radioisotope laboratories or any person in an unrestricted area does not exceed 10% of the limits specified in paragraph 9.2. Minors may not be exposed to concentrations of radioactive material in radioisotope laboratories in excess of those in 10CFR20, Appendix B, Table II (concentrations may be averaged over one week). O O 9-2

~ Section 10 PFRSONNFI. MONITORING 10.1 The University is required to supply personnel monitoring equip-ment to any adult who receives or might receive a dose equiva-lent in excess of 25% of the limits in paragraph 9,2 or in excess rx 4 -7 of those limits for persons under 18 years of age. Personnel monitoring equipment if also required for each person who enters a high radiation area (in excess of 100 mrem in one hour). Even though it is unlikely that any University personnel would receive in excess of 25% of the limits in section 9.2, personnel monitoring is required in many instances in order to record and evaluate the dose received. The Health Physics Office will determine the type of personnel monitoring equipment that is required and will supply it to the user. Individuals who have been provided with personnel monitoring equipment are required to use it as specified. Person-nel monitoring equipment includes film badges, thermoluminescent dosimeters, pocket dosimeters, or other devices designed to be O) U carried or worn by an individual to measure the dose received. Dosimeters should be stored in an area away from radiation sources when not in use. 10.2 Personnel monitoring devices will usually consist of a film badge or thermoluminescent dosimeter, which is changed and read monthly. Dosimeter records are maintained by the Health Physics Office and are available to each individual upon in-person or written request. Individuals will be notified by the !!ealth Physics Office if their dosimeter has a reading in excess of 10% of the average limit in section 9.2, i.e. greater than 40 mrem in one month. Dosimeters should be returned to the Health Physics Office as soon as a re-placement is received, even though the individual may not have worked with radiation during the issue period. This is to insure f that the University has a continuous record for the time period during which the individual might have been exposed to radiation. The Health Physics Office is to be notified to terminate dosimeter fh 10-1

service prior to the time an individual leaves the University or discontinues activities which require personnel monitoring. h 10.3 Personnel monitoring devices are insensitive to low energy beta 3 S S radiation, such as that emitted by H, I4C, S, or Ca and dosimeters will not be issued to persons exposed to such radiation only. 10.4 Under no circumstances are personnel monitoring devices to be tampered with or exposed to radiation so as to give a false or inaccurate measurement of the personnel dose. This is considered a very serious violation of University rules and could result in action by the University Isotopes Committee to prohibit the indi-vidual involved from further work with radioactive material. 10.5 For some personnel it may be necessary to perferm bioassays to determine whether exposure to concentrations of radioactive mate-rial has been within the permissible limits. Bionssay require-ments will be established by the Health Physics Office to insure compliance with the regulations and license conditions. Persons using radiciodine in amounts greater than 1 millicurie at a time h shall have bioassays within three months of the date of exposure or on a quarterly basis for continuous use. The bioassay will normally be performed by measuring the radiation emitted by radio-iodine in the thyroid gland. Persons using in excess of 100 mci of tritium in unsealed form at one time (not including tritiated foils) must submit a urine sample to the Health Physics Office for assay within seven days of the exposure. 10.6 The Health Physics Office may require bionssays for other radioiso-topes based on the type of experiment and the results of surveys for contamination and airborne radioactivity. In general bio-assays will be required if the surveys indicate that a person may have been exposed to a concentration of radioactive material greater than 25% of the permissible limit. O 10-2

Section 11 RADIATION AND CONTAMINATION LIMITS j 11.1 Radiation levels in radioisotope laboratories shall be kept to a. minimum through the use of suitable storage and working area 1 shields. Radiation levels in unrestricted areas or offices in radioisotope laboratories shall not exceed 2 mrem in one hour or 100 mrem in-seven consecutive days. T 11.2 Transferable contamination caused by beta or gamma ray emitting radbisotopes shall not exceed 100 disintegrations per minute (dpm) 2 per 100 cm. A smear or wipe is assumed to cover an area' of 100 2 2 cm. For alpha emitters the limit is 10 dpm/100 cm. Higher levels may be permitted in special areas, as approved by the Univ-ersity Isotopes Committee. Facilities, equipment, clothing, or other personal articles may be released for unrestricted use if it meets the above limits for transferable contamination. 11.3 Radiation levels from fixed contamination on facilities, equip-ment, or the outside of shoes should not exceed 0.5 mrad /hr for unrestricted release. The radiation level inside of shoes or clothing should not exceed 0.1 mrad /hr. The Health Physics Off-ice should be consulted before releasing any contaminated cloth-l ing as higher or lower limits than the above may be more appro-priate, depending on the circumstance's. 11.4 Contaminated areas are to be cleaned as soon as possible after the contamination is discovered. If the contamination is wide-spread and exceeds the above limits by a factor of 10 or more the laboratory is to be completely decontaminated immedia'tely. 4 4 r 11-1 y-~_,._ r,--m-

. ~- Section 12 t O a^o1o'soroes t^8oa^ roar autes i 12.1 Radioactive material may only be processed or used according to an authorization by the University Isotopes Committee. 12.2 Persons working in radioisotope laboratories must be familiar with 4 the regulations and radiation safety procedures. New personnel f should contact the Health Physics Office to arrange for instruc-tion in radiation safety. 4 I 12.3 Orders for radioactive material, shipments to and from the Univ-ersity, and transfers between persons within the University must be processed through the Health Physics Office. 1 12.4 Inventory forms for radioactive material should be kept current as the material is used. Completed inventory forms should be returned to the Health Physics Office when the material has been completely used or has decayed to an insignificant activity (less than 1 microcurie). O 12 s eersees #si 8 reaieective meteri 1 re resve# sis 1e fer roetime surveys to detect excessive contamination or radiation. 12.6 Persons using radioactive material are responsible for the imme-j diate decontamination of facilities contaminated in excess of permissible icvels. 12.7 Pipetting by mouth is prohibited in laboratories where unsealed radioactive material is used, except for laboratories with a "hTIITE" emergency classification. The University Isotopes Com-mittee may authorize mouth pipetting in special circumstances, if adequate control procedures are utilized. 12.8 Eating, drinking, or the storage of food or beverages is prohib-ited in laboratories where unsealed radioactive material is used, except for laboratories with a "h11ITE" emergency classification. L 12.9 All containers of radioactive material, which are left unattended, are to be labeled as such with the radiation caution symbol, the i radioisotope, the activity and the date. Lead shicids, cabinets, refrigerators and other storage areas for radioactive material-12-1 i I =.

should also be conspicuously labeled. Labels and tags may be obtained from the llealth Physics Office. O 12.10 Radioactive material is to be stored in a manner that will min-imize the risk of breakage, Icakage, or theft, 12.11 Report all accidents or unusual conditions involving radioactive material to the llealth Physics Office and the laboratory super-visor immediately. In case of fire or injury follow normal re-porting procedures and inform the fire department or the health center that radioactive material is involved. O O 12-2

Section 13 [] SURVEY PROCEDURES 13.1 Surveys are performed to determine the radiation and contamination levels in a laboratory or on a piece of equipment or to measure the concentration of radioactive material in air or water. Radia-tion surveys are made to measure the radiation levels in an area due to the presence of ionizing radiation, which does not neces-sarily mean that contamination is present. Contamination implies the presence of radioactive material where it is not wanted. It may be fixed to a surface or transferable. 13.2 Radiation surveys should be made with an instrument calibrated for the intensity, energy, and type of radiation being measured. The simple Geiger-Mueller survey meter (GISM) usually does not meet these requirments but,at intensities of a few mrem /hr or less,it is acceptable for approximate measurements of most gamma and beta radiation. If low-energy radiation is present, i. c. from C-14, Ca-45, I-125, a thin window detector should be used. Radiation surveys should be performed when using more than 0.1 millicuries of unshielded, high energy, beta and gamma ray emitters, however, even a few microcuries of such material in the form of thin films on planchets or petri dishes can produce significant radiation levels in work areas. The Health Physics Office should be contacted to perform radiation surveys with calibrated instruments, if sig-nificant radiation IcVels are found by radioisotope laboratory personnel. Radiation levels in unrestricted areas must be kept below 2 mrem in one hour and 100 mrem in seven consecutive days. Work areas in ra oisotope laboratories should also be kept below these levels. 13.3 Transferable contamination is detected by taking a " wipe" or " smear" of the suspected area. A wipe is taken by rubbing the area with a tissue, paper towel, cloth,.etc. to remove loose rad-ioactive material. The wipe is then checked for activity with a radiation detector, typically a GISM. A smear is taken by rubbing the area with a small piece of paper, cloth, glass fiber, styro- ) n-13-1

foam, etc. and then checking for activity by counting in a shielded laboratory counter. Contamination may also be detected by surveying the area directly with a G1SM or other portable radi-g ation detector, flowever, this method does not distinguish between fixed and transferable contamination, is not useable in areas where the background radiation is high, and has a minimum detectable level that is orders of magnitude higher than the permissible level of 100 dpm/100 cm for transferable beta or gamma ray emitters. h' hen 2 using a survey meter, it is important that earphones or a speaker be used with the instrument. The audible indication is not subject to the response time of the meter and allows free use of the detec-tor without continuous observation of the meter. 13.4 Rad'oisotope users should take wipes of their work area (counter-top, sink, hood, floor, etc.) after using unsealed radioactive material. The wipe is a relatively sensitive survey technique for contamination and it is rapid and convenient enough for every day use by the experimenter. Ilands, clothing, and shoes should be checked with a survey meter when leaving the laboratory after handling unsealed radioactive material. This does not apply to tritium users bccause there are no convenient portable detectors for tritium radiation. Tritium users should use smear surveys (see section 13.5) to check their work areas. 13.5 The smear survey is about the most sensitive technique for detec-ting transferable contamination. It is primarily used by the Health Physics Office forperiodic radioisotope laboratory surveys to determine that laboratory personnel are maintaining contam-ination levels below the prescribed limits. Paper smears (circles of a hard filter paper) are the most common but cloth is useful for rough or wet surfaces and styrofoam is convenient if the smear is to be assayed in a liquid scintillation counter. Smears for tritium should be counted in a liquid scintillation counter or a windowless proportional or geiger counter. Sodium iodide or liquid scintillation detectors n*e preferred for I-125 smear counting, because of the low detection efficiency of geiger or proportional counters for this isotope. Smear survey results are 2 usually reported as disintegrations per minute (dpm) per 100 cm, 13-2

A smear is assumed to remove the transferable contamination from 2 100 cm of area. This requires that the observed count rate (cpm) be corrected for detection efficiency and background. gross epm - backgrotind cpm = dpm cpm per dpm 13.6 Fixed contamination is present when radiation is detected with a survey instrument but a wipe or smear test shows no transferable contamination. The immediate hazard of fixed contamination is the radiation level adjacent to the contaminated surface, but there is the possibility that the contamination will become loose at some later time. Thus, even fixed contamination should be reduced to the lowest possible level. In some cases it may be necessary to permanently fix the contamination with paint, tape, or other coat-ings to prevent the later spread of the material. Disposal may be required for materials with long half-life fixed contamination. 13.7 Surveys to determine the concentrations of radioactive material are usually confined to air sampling and are performed by the n ( Health Physics Office. The radioisotope user's assistance may be necessary in such surveys, to wear sampling equipment or to turn it on and off at desired times. Samples may be taken at fixed sites or with co11cetors worn on the body in the " breathing zone"(lapel). Typical' sample collection methods are particulate filters, activa-ted carbon (radiciodine), gas washers (HTO), chemical traps (HT or 2"CO ), and trapped gas samples. The concentration of radioactive 2 material in the air is determined and compared with the permissible concentration levels to decide what control procedures and bioassay requirements are necessary. 13-3

Section 14 KASTE DISPOSAL fsU 14.1 The University provides for the disposal of radioactive waste in a variety of ways, including incineration, storage for decay, release to the sewer, and shipment to commercial burial sites. The latter method is used for most of the waste but it is not suitable in all instances. All the waste disposal methods are costly and time consuming and disposal expenses often exceed the original cost 1 of the radioactive material. There fore, it is imperative that experimenters procure only as much radioactive material as is required for their experiment and minimize the amount of waste produced. 14.2 The authorization to use radioactive material issued by the University i l l Isotopes Committee may contain maximum quantities of material that can be released to the sanitary sewer. These limits are intended to O cover only occasional inadvertent releases of very low activity material as a result of glassware washing, aspirator operation, etc. No radioactive material is to be released to the hood exhaust or sink drain expressly for disposal purposes without prior approval of the Health Physics Office. The University is comnitted to minimizing the release of radioactive material to the environment and only that waste with a low concentration of radioactive material will be released. Releases of properly assayed, low activity material will normally be performed by the Health Physics Office. 14.3 Solid and liquid waste must be kept separate in the containers provided by the Health Physics Office. No liquids or containers with free liquid in them may be placed in the solid waste container. (')N I (_ Revised 1 Jan 85 14-1

~ Small volumes of liquids may be solidified in the kits provided by V( the Health Physics Office and then put into the solid waste container. Solid and liquid waste containers are to be kept capped at all times. Each container is supplied with a card or tag, on which the description and activity of the waste are to be recorded when material is placed in the container. This record is to be kept current. When a waste container is full, notify the Health Physics Office, and the full container will be collected and replaced with an empty one. A waste container will not be collected if the contents are not listed or if it contains materials which are not permitted (see section 14.4). A charge may be levied by the llcalth Physics Office for the cost of disposal of waste which is unusual in volume or which requires special treatment. Waste containers may not be stored in hallways or other unsecured areas. Non-radioactive waste may not be put into radio-() active waste centainers. 14.4 Because materials which are explosive, pyrophoric, carcinogenic, or a biological hazard are genera 11y'not accepted at commercial radio-active waste burial sites, the Health Physics Office must be consulted before starting any experiment which will produce such hazardous wastes contaminated with radioactive material. The waste collected from the various laboratories is hand sorted by the Health Physics staff when the solid material is compacted into steel drums and the liquid is combined and solidified. Thus it is important that the Health Physics Office be notified of any waste which might require special handling when it is processed. Hypodermic needles must be shielded, broken, or separated from syringes before disposal. Radioactive waste which is*a biological hazard must be inactivated \\' before placing it in the waste container. Volatile radioactive waste 14-2 Revised 1 Jan 85 i

l s ~ should be sealed in plastic bags or other containers or solidified () before being discarded to minimize the airborne radioactivity in the laboratory and during later processing of the waste. 14.5 Animal carcasses, bedding, excreta, blood, milk and other biological materials contaminated with radioactive material require special handling for disposal. In general, biological waste containing I C-14 or H-3 will be incinerated and that containing short-lived radioisotopes such as Ca-45, P-32, I-125 etc. will be stored for i decay. Some waste may require packaging with preservatives for shipment to a commercial burial site. The amount of activity which may be incinerated is limited, as are storage facilities for waste held in decay. It is therefore essential that arrangements for disposal be made with the Health Physics Office prior to initiating experiments which will produce biological waste. The experimenter ( is responsible for providing suitable storage of such waste to prevent decomposition before it is collected by the Health Physics Office. 14.6 Liquid radioactive waste should be segregated by using separate containers for aqueous waste, organic materials, and liquid scintillation fluid. Liquid waste containing radiodine is t'o be stored in special 4 containers provided by the Health Physics Office that contain chemicals to inhibit the fornation of iodine vapors. Liquid waste containing milk, blood, homogenized tissue, etc. should be kept frozen or treated with chemicals to inhibit decomposition until it is collected. 14.7 Short-lived radioactive waste (half-life less than 100 days) should be segregated from long-lived material. This will allow storage for decay and eventual disposal with the non-radioactive trash. The Health Physics Office will provide separate containers labeled for use' with O 14-3 Revised 1 Jan 85 {

with specified short-lived radioisotopes, eg. P-32, S-35, I-125. It.is very important that the experimenter provide an accurate estimate of the activity in these containers so that release limits f will not be exceeded. 14.8 Liquid scintillation counting waste must be kept separate from i' other waste. Vials are to be emptied and the fluid put into a liquid waste container marked for " Liquid Scintillation Fluid Only", t The empty vials and caps should be dried by evaporation in a hood i then placed in a drum separate from the normal solid radioactive waste. The number of the liquid waste container holding the liquid from the empty vials should be recored on the drum card for the drum with the empty vials. No scintillation fluid or container that i has held scintillation fluid may be put into the regular radioactive 1 waste because of restrictions at the commercial burial grounds. ( 1 1 a 4 1 4 'l i i l i ( )- j ,14-4 Revised 1 Jan 85 .e . i

1 Section 15 ,O V EMERGENCY PROCEDURES 15.1 Each radioisotope laboratory is classified and posted according to the relative hazard which might exist in the event of a fire or other emergency, The classifications are: White Area: No significant hazard. Normal fire fighting procedures may be used. There is a possi-bility of low level contamination so all personnel and equipment rhould be checked before leaving the scene. Yellow Area: Moderate to serious hazard. Respiratory protection required. Except for short term emergency action or for fires which do not involve radioactive material, a health phys- ~ icist or the laboratory supervisor should be consulted before entering the arca. /~') \\_/ Red Area: Possibility of extreme hazard. Respiratory protection required. Such areas should not be entered without' consulting a health phys-icist or the laboratory supervisor. A list of University radioisotope laboratories with the classifi-cation and the name and telephone number of the supervisor is provided to fire, safety, security, and maintenance personnel. In the event of an emergency contact the emergency operator (dial 110 on University telephones) and report the emergency and indi-cate that it involves a radioisotope laboratory. The following actions and precautions should also b-taken. (a) Contact health physics percon .1 or the laboratory super-visor. (b) Do not enter areas without some knowledge of the actual hazards which might be involved. If possible, be accom-panied by a person who can monitor for contamination and g-)/ high radiation IcVels. 15-1

e (c) Wear respiratory protection. A self-supplied air or oxygen mask is preferred, but a respirator with a filter or chem-lll ical cartridge will be sufficient for most emergencies. (d) Do not handle or come in contact with radioactive materials or their containers. (e) Keep all personnel not absolutely needed out of the area. A person who has been in an area containing radioactive material should be checked for contamination before leav-ing the scene of the emergency. (f) Be on the alert for signs and alarms which warn of high radiation levels or unusual hazards. Do not defeat or destroy any interlock or safety system without consulting a health physicist or the laboratory supervisor. (g) Use protective clothing, if it is available. (h) Keep all equipment used in contaminated areas separate until checked by health physics personnel. 15.2 The following is an outline of steps to be taken in the event of llh accidents involving radioactive contamination or radiation expos-ure of personnel in conjunction with injuries reouiring medical treatment and/or hospitalization. IF THE PATIENT IS SERIOUSLY INJURED, PRIORITY SHOULD BE GIVEN T_0, LIFE SAVING MEASURES: i. e., STOP BLEEDING, START RESPIRATION, TREAT FOR SHOCK, MOVE TO A SAFE AP.EA, ETC. I. Initial Action. Move the victim to a safe area to prevent further contamination and radiation exposure. If this is not possible, then first aid should be administered quickly to minimize the exposure to the victim and to those persons providing assistance. Decontamination should commence immedi-ately. When this is not possible because of the type or severity of medical injuries, precautions must be taken to prevent the spread of contamination from the patient to other personnel or facilities. O 15-2

II. Ritenour llealth Center Alert. If the victim requires hospital e i \\/ care, the health center must be notified immediately to pre-pare for the reception of a radiation accident casualty. See the first page of this document for the health center tele-phone nunber. Request the health center to activate the radiation emer-gency plan. Give the number of casulaties to be sent, types of medical injuries, and type and degree of contamination. Re-quest that hospital personnel be equipped with protective clothing and radiation detectors. Necessary equipment and instructions are located in the decontamination kit in the emergency room at the health center. No special preparation is required for casualties which are not contaminated. Confirm the health center entrance at which casualties will be received. III. First Aid For External Radiation Exposure 1. Evacuate from radiation field to a non-radiation area; ( use stretcher if necessary. 2. Treat for shock (place patient in horizontal position and keep warm). 3. Notify the health center and request ambulance service (see section II). IV. First Aid For Contaminated Personnel. Personnel suspected of being contamination with radioactive material should be isola-ted and quickly surveyed to determine the location of areas with large amounts of contamination. Priority for treatment or decontamination should be determined by the seriousness of any injuries, the radiation dose being received from skin or clothing contamination, and the possibility of entry of radio-active material into the body through contaminated wounds. A. Gross Whole Body Contamination 1. Remove clothing. (G_) 15-3

2. If small areas with high levels of contamination are ggg found, mark and localize. 3. Open wounds should be scaled with adhesive tape to prevent contamination being washed into wounds. 4. Clean small areas containing large amounts of contam-ination first, then clean entire body (shower or sponge bath) with warm water and mild soap. Do not abrade or irritate the skin with excessive scrubbing or harsh cleaning materials. 5. When body contamination has been sufficiently decreased, begin decontaminating the wounds. 6. Coveralls, gloves, shoe covers, sheets, etc. can be used to prevent the spread of contamination while transporting the casualty. B. Contaminated Wounds 1. Encourage bleeding to flush wounds ( unless there is danger to the patient). 2. Irrigate with copious amounts of water. 3. Decontaminate the skin around wound, being careful not to wash contamination into the wound. 4. Resurvey the wound at periodic intervals using an end-window G-M counter. Record readings. 5. When wounds and surrounding skin are decontaminated, seal areas with adhesive tape. V. Health Physics Office Responsibilities. The Health Physics Office should be contacted immediately in the event of any emergency involving radiation or radioactive material. The health physics staff will perform the following duties in such emergencies: 1. Estimate the amount of radioactive contamination or radiation exposure. 2. Order the procedures of decontamination and/or control of ggg radiation. 15-4

T l l i-3. Determine the shielding, protective clothing, and () dosimetry necessary for personnel providing emer-l gency assistance such as doctors, nurses, ambulance drivers, etc. I 4. Assist in surveys, decontamination, and transporta-tion of casualties. i 5. Determine the type, location, and frequency of surveys, environmental samples and bioassy samples to be taken for documentation and further investi-4 gation of the incident. + l 6. Notify the proper state and federal agencies of the incident, as required, and request emergency assis-tance, when needed. T i a 4 ! O J l 4 3 i () ~ i 15-5 i l )

t Section 16 PURCHASE, TRANSFER, OR SHIPMENT OF RADIOACTIVE MATERIAL 16.1 Persons purchasing radioactive material or receiving it as a gift or loan must first receive authorization to possess the material from the University Isotopes Committee. This requirement applies to transfers from sources within or outside of the University. The Health Physics Office must be notified of all transfers so that the proper entries can be made on the inventory records. This notification is provided by form HP-10 (see below) for purchases made with the regular University purchase order form. 16.2 Orders for radioactive material from commercial suppliers should be made on the regular University purchase order. Orders from some of the federal government contractors, such as Oak Ridge National Laboratory or Mound Laboratory, may require an additional order fom. A copy of form HP-10 (a yellow 3 x 5 card which can be obtained from the Health Physics Office) with the pdrchaser's 3 ] name and University Isotopes Committee authorization number should be attached to the purchase order. Instructions for completing form HP-10 and the routing for the order form are printed on the back of form HP-10 and in the UniversiJy General I Forms Usage Guide. The order is forwarded to the Health Physics Office for approval and entry in the records after approval by the Department Head and Dean. The order then goes to the accoun-ting and purchasing departments. An order for radioactive mater-ial will not be processed by the Purchasing Department until it has been approved by the Health Physics Office. All radioisotope orders are to be delivered to the Health Physics Office at 228 Academic Projects Building and that delivery address should be used on the purchase order. The procedure for receicing ship-ments is given in section 17. 16.3 Suppliers of radioactive material are required to have written assurance that the recipient is licensed to. receive the material (10CFR30.41). The Health Physics Office will provide this infor-O metien te serriiers eed meintei e fi1e ef sech essurences frem licensees who receive material from the University. Individual 16-1

users should not provide suppliers with the University license numbers or copies of the license, 16.4 The llealth Physics Office must be notified prior to any transfer of radioactive material between University personnel. This is to insure that the recipient has the proper authori::ation from the University Isotopes Committee and so that the inventory records can be adjusted. The supplier of the material is responsible for the notification, 16.5 The transportation of radioactive material is stringently regula-ted by the federal and state departments of trar.sportation and by other agencies involved in transportation by highway, rail, air, or water. The requirements for containers, labeling, mark-ing, and shipping papers are too complex to enumerate in this document. All shipments of radioactive material from the Univer-sity are to be checked and approved by the licalth Physics Office. This includes shipments using the U. S. Postal Service, common carriers, and University vehicles. The Health Physics Office will provide the necessary labels, shipping papers, and placards. University personnel should not use private vehicles for the transportation of licensed radioactive material. i O' 16-2

Section 17 /T U RECEIPT OF RADIOACTIVE MATERIAL SHIPMENTS 17.1 All shipments of radioactive materials for the University Park campus are to be received at the llealth Physics Office, 228 Aca-demic Projects Building. Specific shipments may be delivered to other locations, if prior arrangements are made with the Health Physics Office. If radioactive material is delivered directly to an experimenter, the Health Physics Office should be notified immediately, before the package is opened. 17.2 Immediately upon delivery of a shipment to the Health Physics Office, the package should be inspected for damage and transferable contamination. Transferable contamination should not exceed 2200 dpm/100 cm. If transferable contamination and/or damage is found, 2 it should be explained to the carrier representative and noted on the shipping papers. An offer to check the carrier's vehicle and the hands and clothing of the carrier representative should be made to the carrier representative, if transferable contamination \\~/ in excess of the limits is found. A damaged and/or contaminated shipment should not be returned to the carrier until it is re-packaged to meet DOT requirements. The check for transferabic contamination is not required for ship-ments containing only tritium, carbon-14, sulfur-35, or iodine-125 with a total activity less than 10 mci, packages containing only radioactivity in gaseous form, or other packages containing no more than the quantities listed below. GROUP I....................... 0.01 mci Group 1I...................... 0.1 mci Group III, IV, V, VI.......... 1.0 mci Group VII..................... 25.0 mci Special Form.................. 1.0 mci 17.3 Following acceptance of a radioisotope shipment, a member of the health physics staff will perform a contamination survey of the s) shipping container and any inner containers and enter the results of the survey on the inventory form (HP-20). If transferable 17-1

contamination in excess of the 100 dpm of beta-gamma or 10 dpm of alpha activity per smear is present on the inner container, an attempt should be made to decontaminate it. Nonessential pack-aging material, which is contaminated, may be discarded as radio-active waste. If there is excessive contamination or evidence of Icakage or damage to the inner container, notify the purchaser and request a replacement shipment from the vendor. The presence of transferable contamination which cannot be removed from the inner container should be noted on the survey form (IIP-20). After the package has been checked and the inventory form completed, the package will be delivered to the purchaser by health physics per-sonnel. 17.4 Each package containing radioactive material in excess of Type A quantities (49CFR173.389) shall be surveyed for radiation levels within 3 hours of receipt (18 hours if received after normal work-ing hours). Radiation icvels on the external surface of the pack-age (2 inches) shall not exceed 200 mrem /hr or 10 mrem /hr at 3 feet from the external surface of the package. 17.5 Shipments which show exterior contamination or radiation levels in excess of the above limits shall be reported immediately by the IIcalth Physics Office to the final delivery carrier, the Nuclear Regulatory Commission, the Department of Transportation, and the shipper. Notice to the carrier and the NRC shall be by telephone and telegraph. O 17-2

Section 18 RADIOISOTOPE NEUTRON SOURCES 18.1 Radioisotope neutron sources contain radioactive material such as Cf-252, which emits neutrons spontaneously, or a source which pro-duces neutrons by a secondary reaction such as the alpha-neutron or gamma-neutron reaction with beryllium. These sources are pri-marily used for neutron experiments and as a component part of moisture gauges. The request to the University Isotopes Committee for permission to use a neutron source shall describe the source, the intended use, shielding, storage, estimated dose rates, and the procedures for handling the source or the device containing it. Sealed neutron sources purchased or transferred to the Univ-ersity from other licensees must be accompanied by a certificate showing that the source meets Department of Transportation speci-fications for special form radioactive material. 18.2 The following conditions apply to the use of all scaled radioiso-tope neutron sources. f- \\~/ a) The source is not to be opened or the seal modified in any way. Sources may not be machined, ground, drilled, or tapped. b) The source is to be handled with tongs or other remote de-vices as specified in the authorization from the University Isotopes Committee. Sources are not to be removed from the shielding in moisture gauges unless the operation is under the direct supervision of the Health Physics Office, c) Sources may not be subjected to unusual conditions such as exposure to corrosive chemicals, dirt, abrasion, mechanical shock, temperature extremes, or high pressure unless the experiment has been reviewed and approved by the University Isotopes Committee. d) Sources may be used and stored only in locations specified in the University Isotopes Committee authorization. (v~') e) Anything unusual pertaining to the source must be reported immediately to the Health Physics Office. This includes loss 18-1

of the source, mechanical shock or accidental exposure to any of the conditions in item (c). f) The source or the device in which it is used or stored must have a " radioactive material" tag stating the radioisotope, activity, and date attached to it, g) Sources are to be leak tested by the Health Physics Office at least once every six months unless the source has not been used. 18.3 Persons using neutron sources or devices containing neutron sources shall wear personnel monitoring devices if the dose equivalent rate exceeds 100 mrem /hr at one foot from the source or device. The type of monitoring equipment will be specified by the Health Physics Office. Monitoring equipment may be required for lesser dose equiv-alent rates depending upon the type of use and the exposure time. 18.4 The University is licensed to use moisture gauges containing neu-tron sources throughout Pennsylvania. However, the University Isotopes Committee must approve all locations for use for each ex-llh perimenter. The experimenter must also have the permission of the property owner, if use is on non-University land. The shipment or transportation of neutron sources or moisture gauges must be approved by the Health Physics Office (see section 16.5). 18.5 Neutron sources containing special nuc1 car material (plutonium-beryllium sources) may only be used in approved material balance areas (MBA's) under the control of the MBA supervisor.

Storage, use and transfer of such sources must be in conformity with the "Special Nuclear Material Control Procedures" (see section 23).

18.6 Radiation surveys shall be made by the Health Physics Office of neutron sources in storage locations and typical configurations of use. Surveys shall measure both gamma and neutron radiation. i 18-2

..=.. - - 4 i t Section 19 i l GAhNACELL IRRADIATORS i I 19.1 The procedures in this section apply to the use of Atomic Energy ] of Canada (AECL) Gammacell Irradiators. The user is required to I obtain permission to use the irradiator from the supervisor of the unit and to read the operating instructions thoroughly. The l supervisor is responsible for instructing users in the proper operation of the unit and indicating in the logbook the names of those persons who are authorized to use the irradiator. 19.2 The sample drawer is controlled by the "up" and "down" push but-tons after power has been applied to the unit through the key I switch. The timer may be set to automaticaly raise the drawer ) at the end of a preset time or the unit may be operated manually. ) In case of a power failure the drawer may be raised with the hand i crank. If the hand crank is used the drawer should be raised to i the upper limit so that the safety stop engages. Do not attempt to lower the drawer with the hand crank. If use of the hand crank is necessary report the condition to the supervisor immediately. Any indication of corrosion, sticking of the drawer, oil leakage, cable failure, or other unusual condition should also be reported to the supervisor. i 19.3 A logbook containing the names of the authorized users and the dates, length of irradiation, type of sample, and user for each I trradiation is to be kept at the irradiator. Each user is respon-sible for making the appropriate logbook entries. 19.4 The irradiation of sampics which could damage the irradiator must be approved by the supervisor and the University Health 4 1 Physicist. Explosives may not be irradiated. It is the respon-f sibility of the user to notify the supervisor of hazardous samples 1 before using the irradiator. Such samples include: (a) Any materials corrosive to stainless steel, such as strong 4 l acids and bases, chlorine, strong oxidants, etc. !O 19-1 4 4 -,-, _ -.._

(b) Substances which might expand during irradiation and break h the sample container or cause binding of the drawer. (c) Substances which could boil or volatilize during irradiation and spill or give off corrosive vapors or gases. (d) Substances which might react with the sample container during irradiation and leak into the irradiation chamber. (e) Substances which might form excessive pressure during irradiation. 19.5 Samples must be small enough that the irradiation chamber cover can be replaced witrauc forcing it. No irradiation is to be per-formed without the irradiation chamber cover. 19.6 The helical irradiation tube shall not be used without written permission of one of the supervisors and the University llealth Physicist. 19.~ The irradiator shall not be used in any manner which requires the defeat of any safety switch or interlock, except as required for ggg maintenance or repair. 19.8 No lubricant is to be applied to the sample drawer. Lubricants will polymerize when irradiated and cause sticking of the drawer. 19.9 Shield plugs for access tubes to the sample chamber must be in place before lowering the drawer to the irradiate position. 19.10 The drawer should not be stopped in a partially raised position as the sample chamber cavity reduces the amount of shielding and high radiation IcVels may be present around the top of the irradi-ator. 19.11 When the irradiator is left unattended the control key should be removed and/or the room locked. 19.12 Routine leak tests of the source will be performed by the Health Physics Office. Radiation surveys shall be conducted after any change in location of the unit, replacement of sources, or modi-fication of the shielding. 19-2

Section 20 ALPHA SOURCES (sealed) I 20.1 Sealed alpha sources are generally manufactured by plating an alpha-emitting radionuclide such as Ra-226, Pu-239, or Am-241 on a metal j backing plate and coating with a very thin layer of gold or other f metal. In some cases the alpha emitter may be covered with a very I thin metal foil or it may be incorporated in an inert ceramic matrix (Microspheres). All alpha sources must be handled with j extreme care so that the cover is not damaged and so that no radio-j active material is dislodged from the surface. The surface of the source must not be touched because finger prints could lead to corrosion of the source cover and because of the high dose rates on contact with the source. 20.2 The design of alpha sources or alpha irradiators with an activity J greater than 0.1 millicurie must be approved by the University Isotopes Committee. In addition, alpha sources may require an amend-ment to the University license before the material can be accepted. O reteeti 1 esers of ei he seerces shee1d centact the iieetth Phxsics t i uffice for additional information before making arrangements to acquire alpha sources. 20.3 Alpha sources may not be subjected to unusual conditions, except as authorized by the University Isotopes Committee. This includes 1 exposure to corrosive chemicals, dirt, abrasion, mechanical shock, i high temperatures, low temperatures, and pressures significantly different from atmospheric pressure. 20.4 Anything unusual pertaining to alpha sources such as corrosion, deterioration, suspected Icakage, or accidental exposure to the conditions listed in 20.3 should be reported immediately to the I t j llealth Physics Office. i J i ' O r 20-1 l i 1 -,---..-,..,----g n ,,n-7<.- ,4 ,.---.r- ,.m,. --e e-- y -n,.,, -n~.

Section 21 SPECIAL NUCLEAR MATERIAL CONTROL PROCEDURES .21.1 This section describes the procedures for the control of special nuclear material. The procedures are designed to provide a record of the receipt, use, disposal, or transfer of special nuclear material (SNM) and to detect the loss, theft, or unauthorized use of such material. Terms and abbreviations used in this procedure are defined as follows: a) Item Control Area (ICA): an identifiable physical area where the control of SNM into or out of the area is by item identity and count for previously determined SNM quantities, the validity of which shall be assured by the use of tamper-safe seals unless the items are scaled

sources, b) Material Balance:

a ' determination of material unaccounted for (MUF) or inventory differe,ce (ID) made by subtracting ending inventory (EI) plus removals (R) from the beginning inventory (BI) plus additions to inventory (A). FWF (or ID) = BI + A - EI - R. c) Material Balance Area (MBA): an 'identifiabic physical area for the physical and administrative control of SNM such that the quantity of SNM moved into or out of the MBA is represented by a measured value. d) Material Balance Area Controller (MBA Controller): the individual with the responsibility for maintaining the inventory and control of all items within a given MBA. e) Special Nuclear Material (SNM): plutonium, uranium 233, uranium enriched in the isotope 233 or the isotope 23S, or any material artificially enriched in the foregoing but does not include source material. 21.2 Orders for SNM are to be processed in the same manner as orders for other radioactive material (see section 16). All shipments of l radioactive material and SNM for the University Park Campus are to be delivered to the Health Physics Office. Prior arrangments 21-1

• 16 Dec 81

) J

.= r should be made with the Health Physics Office for the receipt of material at other campuses to insure that the package is properly I checked. Arrangements may also be made with the Health Physics Office to ' receive material at other locations on the University Park campus or by persons other than the health physics staff when necessary. The persons accepting delivery of a package shall inspect it for damage and check the serial numbers of security seals against the shipping orders. Any damage to the package or missing or damaged seals should be noted on the shipping orders. If a person other than a representative of the Health Physics Office is accepting the shipment, that office shall be notified immediately of any damage to the package or seals. The exterior of the package should be checked according to section 17. Pack-ages are to be opened by or under the supervision of a health physics staff member unless prior arrangements have been made with the Health Physics Office for someone else to do this. A physical inventory of the material is to made at the same time and the inventory form completed (form HP-30 or HP-305). Upon completion of the procedures for receipt of the material the package will be delivered to the authorized user at the appropriate MBA. 21.3 Special nuclear material is,to be stored and used according to the authorization issued by the UIC or according to the reactor oper-ating license for material included within that license. Material may not be transferred between MBA's or from one user to another j until authorization to do so has been received from the UIC. Unsealed SNM in quantities greater than 10 grams is to be stored in a secure area with some form of tamper-safe security seal and access should be restricted to those persons named on the UIC authorization for the material. Irra'diated materials which re-quire storage in the reactor pool or in a shielded enclosure are exempt from the requirement for tamper-safe seals. One person is to be designated the MBA Controller for each MBA. That person is responsible for maintaining an inventory of SNM in the MBA and for keeping a record of any transfers or loss of material. Persons authorized to use SNM within a MBA are responsible for notifying 21-2

the MBA Controller of any removals, additions, transfers, or losses of SNM. a 21.4 *The UIC ' tall identify the boundaries of Material Balance Areas and Item Control Areas and shall designate the MBA Controllers for each

• • area. The current Material Balance Areas are listed below.

There are no Item Control Areas. CODE LOCATION MBA CONTROLLER MBA-I University Park Campus Senior Reactor Operator in charge of reactor operations MBA-II 012 Michael Haker Bldg. Authorized user of Pu-Be source Beaver Campus 21.5 Transfers include receipts, shipments to other licensees, movement between MBA's, and transfers between authorized users. New material will be assigned to a MBA and an authorized user upon receipt. Any subsequent changes in authorized user or MBA require completion of the Special Nuclear Material Transfer Form. This form is to be completed by the person initiating the transfer and signed by the authorized user (s), the MBA Controller (s), and a representative of the Health Physics Office. Copics of the completed form are to be distributed to each of the above named individuals. 21.6

• Transfers of SNM between different NRC licensees require completion of DOE /NRC Form 741, the Nuclear Material Transaction Report. Trans fers of certain other nuclear materials, including deuterium, normal and depleted uranium, californium and enriched lithium may also require completion of DOE /NRC Form 741. This form is to be prepared by the Health Physics Office for signature by the Vice President for Research and Graduate Studies. Current regulations require that a licensee supplying nuclear materials prepare and dispatch DOE /NRC Form 741 no later than one working day following shipment of the material. A licensee receiving nuclear materials is permitted 10 calendar days after arrival of the material in which to document its receipt by completion of the receiver's section of the form.

Individuals supplying materials covered by these reporting requirements to other licensees and those receiving such materials from other licensees are responsible for providing the Health Physics Office with the information necessary to complete and submit DOE /NRC Form 741 within the specified time limits. Distribution of this form is to be made in accordance with instructions contained in NUREG/BR-006 or DOE Notice 5630 for privately-owned and DOE-owned nuclear materials, respectively. 21-3

• 16 Dec 81
  • 18 Oct 82
    • 30 May 86

21.7 A physical inventory shall be conducted of the SNM in each MBA at intervals not to exceed 12 months. The inventory shall be initi-

• ated by the Health Physics Office and shall be conducted by at least
• two individuals, including the MBA Controller or his designate and a member of the Health Physics staff.

The inventory shall consist of a visual examination and actual measurement of quantities of unsealed. SNM. Material which has been previously measured and continuously maintained under tamper-safe seal need not be remeasured unless the seal has been broken or damaged. Material which has been ir-radiated and requires shielded stora'ge or containment because of the radiation or contamination hazard need not be visually in-spected or measured, but the presence of the storage container or irradiation vessel must be verified. Each item or container of SNM, except fuel elements, shall be identified by a tag which in-dicates that the item is SNM and includes the item description, isotope, quantity, inventory number, authorized user, authorization number, license number, date, and initials of the person completing the tag. The tag should be attached directly to the item or item container. 21.8 Tamper-safe seals are to be applied immediately upon completion of the operations which establish the SNM content of an item. Serial numbers of seals are to be recorded and checked at the next inventory or when the container is next opened. More than one individually packaged item 'may be stored in a container such as a metal box or vault under the same seal. Seals are to be stored in a locked container accessible to only the MBA Controller and/or the University Health Physicist. The selection and use of security seals should follow the recommendation in NRC Regulatory Guides 5.10 and 5.15. It is recommended that small items of unsealed SNM be kept in, transparent containers with the gross weight and net weight recorded in the inventory so that the material can be visually checked and the amount readily determined by weighing the container, if necessary. 21.9 Scaled sources of SNM such as fuel elements, fission counters, and neutron sources need not be assayed, but serial numbers or other identification should be checked. When the number of similar items ) exceeds 25 a random sampling of at Icast 10', of the items (but not less than 10) may be made to check identifying numbers. 21-4

• 16 Dec 81

W 21.10 The inventory information shall be recorded on a written form and signed and dated by the persons conducting the inventory. The same form may not be used for more than one day or for more than one MBA. Copies of the inventory form shall be distributed to l the MBA Controller and the Health Physics Office. The physical inventory shall be compared with the inventory record and docu-mented by the MBA Controller. 21.11 A review of this procedure and an audit of the material balance for each MBA shall be conducted at intervals not to exceed 12 l months. The review shall be conducted by person (s) who are l independent of nuclear control responsibility and who do not have i direct responsibility for receipt, custody, use or measurement of j SNM. The person (s) to conduct the audit and review shall be designated by the Vice President for Research and Graduate Studies 4 with the concurrence of the UIC. The results of the audit and review and any recommendations for improvements shall be docu-mented and reported to the UIC and the Vice President for Research and Graduate Studies. 21.12 *The University is required to submit quarterly Material Balance 4 1 l Reports (DOE /NRC Form 742) for several categories of DOE-owned nuclear materials to the Chicago Operations Office of the Department of Energy. These reports are to be filed within 10 days of the end of each calenda'r quarter (31 March, 30 June, l 30 September and 31 December). Semiannual material balance re-ports covering DOE-owned SNM as well as privately-owned SNM also must be submitted to the Nucicar Material Control site at Oak Ridge within 30 days following the end of the period covered by j the reports (31 March and 30 September). These reports shall be prepared by the Health Physics Office for submission by the Vice President for Research and Graduate Studies. Each MBA Controller 4 is responsible for providing the Health Physics Office with a material balance for the SNM in his area as of the above dates in 4 sufficient time for the preparation and submission of these reports. ~ Fission and transmutation 1osses in reactor fuel shall be calculated j as described below. s l 21-S I i

• 16 Dec 81

a) The Burn-Up Log, which is kept by the Breazcale Nuclear Reactor, contains the power level and duration of each i reactor run on a daily basis. The number of kilowatt hours of operation for each month are totaled from the 1 daily data. A cumulative total of all kilowatt hours to date is also kept on a monthly basis in the Burn-Up Log. i a I b) Compute total Burn-Up (B) by multiplying the kWh for each month and the total to date by 4.32 X 10-5 grams burn-up/. kWh. [ B (grams) = 4.32 x 10' x kWh. c) Compute the grams of uranium lost (U) by multiplying the burn, B, by 1.077. U(grams) = 1.077 x B. d) Compute the grams of uranium-235 lost (U-235 ) by multi-7 j plying the burn-up, B, by 1.192. U-235 (grams) = 1.192 x B. l 3 5 1 i e i I I i 4 I I J l 21,6 i. 1 ) ..-,...-.-y,_, y y.

Section 22 O SOURCE MATERIAL i j 22.1 Source material is defined (10CFR40) as uranium and/or thorium in i any physical form, or ores which contain 0.05% or more by weight { of uranium and/or thorium. It does not include special nuclear 1 j material (plutonium or uranium enriched in the isotope 233 or 235) but does include depleted uranium. 22.2 The University has a license to possess and use a large quantity of uranium in a suberitical graphite pile. Urar..um' and thorium for laboratory use is obtained under a general license for small quantities (10CFR40.22). This allows the purchase or transfer of i up to 15 pounds of source material at one time and a maximum of 4 j 150 pounds per year. This limit applies to the whole University and not to each individual. Therefore, if more than 5 pounds of source material are to be ordered, the IIcalth Physics Office should 1 J be consulted. There are also exemptions for commercial products containing source material, such as incandescent gas mantles, j vacuum tubes, electric lamps, ceramics, and lenses. l 22.3 Even though small quantities of source material may.be obtained without a specific license, there may be some hazard in using the material or the device containing the material. Source material should not be stored in offices, desks, or other areas where it is in close proximity to personnel for long periods of time because of the elevated radiation levels. Laboratories with large inven-i tories of source material (greater than 5 pounds) should provide I an isolated or shielded storage area. The llealth Physics Office will arrange for storage of source materials on request, i 22.4 The flealth Physics Office should be consulted before using source j material in such a way that airborne contamination could be pro- } duced. Some examples of such uses are machining uranium or thorium I metal or alloys, opening vacuum tubes or thoriated lamps, making refractory materials from thorium oxide, or grinding thorium glass. Users should be aware that uranium metal chips or powder can ignite in air producing airborne contamination and creating a fire hazard. 22-1 m. ,m... n- ---..,-.,,-,,_.._.,....-,,,-#-.-_r...__,,__,___... ,_.,_m..__.. y

The IIcalth Physics Office will evaluate the proposed use, provide monitoring, and assist in obtaining the necessary respiratory pro-tective devices. 22.5 Small quantities of source materials, such as waste urany1 nitrate reagent may be disposed of via the sanitary sewer. Larger quanti-ties will be disposed of by the IIcalth Physics Office. 22.6 The irradiation of source material in the nuclear reactor can pro-duce fission products and transuranic elements. These materials can be very hazardous and may not be covered by existing licenses. Therefore, experimenters proposing to irradiate source material should discuss the project well in advance with the health physics and the reactor staffs. Samples of soil, rock, sediments, etc. may contain enough uranium or thorium to present problems, if irradiated, even though the material is not classified as source material (less than 0.05% U or Th). O llI 4 22-2

4 rS Section 23 \\J ACTINIDE SERIES ISOTOPES 23.1 The actinide series consists of those isotopes with atomic numbers 89-103. All these isotopes are radioactive and include some of the most hasardous known radioisotopes. These materials may only be used under very carefully controlled conditions and requests for authorization to use actinides submitted to the University Isotopes Committee should identify all procedures to be used so that a thorough review and analysis of the hazards can be accomplished. The experimenter must be aware of the regulations and license conditions regarding the use, control, and disposal of this mater-ial. 23.2 In general, the use of unsealed actinide isotopes (other than uranium or thorium) with an activity greater than 0.1 millicurie is to be confined to an isolated room, glove box, or hood. Hoods () and glove boxes should be equipped with absolute filters. The lab-oratory must also be equipped with a survey meter suitabic for checking work surfaces and the hands and clothing of the experimen-ter. 23.3 The predominate hazard in working with unsealed actinide sources is the inhalation of airborne material. Therefore, the experi-menter may be required to operate fixed and/or portabic (breathing zone) air sampling equipment while working. The Health Physics Office will specify the type and frequency of air sampling. If the air samples or other monitoring suggests a possibic uptake of radioactive material in excess of 10% of the quarterly limit, the experimenter may be required to submit samples for bioassay or to undergo external counting. The University Isotopes Committee may also require routine periodic bionssays for actinido users. 23.4 Radioactive waste containing transuranic elements (atomic number greater than 92) in a concentration exceeding 10 nanocuries per () gram must be placed in retrievabic storage. Such waste must be 23-1

segregated from other radioactive waste and the amount should be kept to an absolute minimum, because of the complications and the llh expense of special handling, h'aste should be sealed in bags or other containers before placing in the waste drum to prevent the spread of airborne contamination during later handling of the material. 23.5 Actinide isotopes (other than source materials) are to be stored in a secure area in closed ccntainers. Actinides which are class-ified as special nuclear material (plutonium, enriched uranium) may require special accounting and control procedures, see section 21. O O 23-2

1 Section 24 GAS CIIROMATOGRAPil SOURCES 24.1 Electron capture detectors for gas chromatographs utilize a radio-active source which usually contains II-3, Ni-63, or Ra-226. Under normal operating conditions these sources present very little hazard. Ilowever, the storage, cleaning, or exchange of the sources can produce contamination and radiation hazards. 24.2 The radioactive source, usually a metal foil, may not be removed from the detector cell, except under the supervision of health physics personnel. 24.3 Sources should only be cicaned according the manufacturer's instruc-tions. Abrasives may not be used to clean foils. This will scratch the source coating on radium foils, allowing Icakage of the radio-active material. Abrasives may also remove the Ni-63 plating or material containing 11-3 from other foils. Source foils should be handled with forceps,at the edges only,to prevent scratching the foil surface. O 24.4 Solutions used to cican and rinse detector cells may be contaminated J and should be assayed and disposed of as radioactive waste. If foils are exchanged the old foils are to be returned to the manu-facturer or disposed of as radioactive waste. t i 24.5 Tritium foils or detector cells should be stored in an airtight container when not in use. The container should be opened in a l fume hood to exhaust the tritiated hydrogen gas and water vapor which accumulates in the container. 24.6 Radium detector cells or foils should be stored in an isolated or shicided location to reduce the exposure of personnel to the gamma rays emitted from the source. 24.7 Detector cells containing tritium foils may only be used in con-junction with a properly operating temperature control mechanism. which prevents the foil temperature from exceeding 225'C. O 24-1

Section 25 ( 11UMAN USE OF RADIOACTIVE MATERIAL 25.1 The use of radioactive material in humans for research requires a separate license from the Nuclear Regulatory Commission. In add-ition to the University Isotopes Committee, review and approval by the Biomedical Review Committee (for experiments with human subjects) and a radioisotope human use committee are required. There is no radioisotope human use committee at the University Park campus, but the committee at the Milton S. liershey Medical Center has agreed to review proposed human use radioisotope experiments. Food and Drug Administration approval is also required for experimental radioactive drugs. 25.2 Experimenters who wish to use human subjects for radioisotope experi-l ments should prepare a proposal for such use for the University Iso-topes Committee. The proposal should include all the information required for submission of a license for human use. The !!calth O rarsies office aes cettines of the inform tion reaeired. Tae u=iv-ersity Isotopes Committee will review the project and direct the IIcalth Physics Office to prepare a license application, if the proposal is acceptable. The University Isotopes Committee will also submit the proposal to the IIershey Medical Center human use committee for review. The experimenter is responsibic for sub-mitting the proposal to the Biomedical Review Committee. 25.3 All rules and procedures for ht.ndling radioactive material apply to the use of radioisotopes in addition to the conditions imposed by the human use license. OV 25-1

4 Section 26 ( FIELD USE OF RADI0 ACTIVE MATERIAL 26.1 The University by-product material license prohibits the release of radioactive material in field experiments. Any such experiments would therefore require an amendment to the license. Radioactive material may be used in the field, if it is contained or there is no release. For example, the leaves of plants could be tagged in the field if the contaminated plant material is immediately brought back to the lab, but growing tagged plants in the field where the plants could be eaten by animals or removed by unauthorized per-sonnel would not be permitted. Any field use of radioactive material requires the prior approval of the University Isotopes Committee. I O i I 4 l 26 1

4 Section 27 Lo USE OF RADIOACTIVE MATERIAL AT THE COMIONWEALTH CAMPUSES q 27.1 A limited amount of radioactive material may be used at each of the Commonwealth Campuses. Persons wishing to use radioactive material at these campuses should submit a request for authorization to the University Isotopes Committee as outlined in section 7. An author-l i:ation is required even for license exempt quantities, except for f solid sealed sources used for demonstrations or instrument checks. t 27.2 The Health Physics Office will periodically monitor radioisotope l laboratories at the branch campuses and provide waste disposal, personnel monitoring, and other services, as at University Park. Because of the distances involved, the frequency of the health physics surveys will be much less than for the main campus. Therefore, the laboratory supervisor may be required to perform i periodic lab surveys and report the results to the Health Physics i 1 Office. ' O 27.3 Experimenters at the branch campuses will be restricted by the University Isotopes Committee to those radioisotope procedures 3 for which they have proper facilities,and equipment. Experimenters j should contact the Health Physics Office regarding the loan of equipment or the use of facilities at the University Park Campus for procedures which cannot be performed at their branch campus. ) E 1 1 I () 27-1 H i j

I UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS mtE to. CHAPTER 1. CODE OF FEDERAL REGULATIONS-ENERGY PART NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS: 19 iNSeECriONS ..e. 19.1 Purpose l'8 19.3 Definitions. I number 3150-0044. 19.2 Scope. As used in this parg. 2 (b) De approved Information 19.3 Deftaltions. (a) "Act" means the Atomic Energy a collection requimments contained in this QL8*g"',, Act of 1954. (64 8 tat. 919) including any & prt appearin i 19.13. >te 8 nramar on collection requirements: "means the United States I 10.11 Pasuna of no'ttces to workers. Shucleu iteptatory Cw... 'a i "I 19.11 Posting of notices to workers. 19.12 Instructaons to woraers. R (c) " Worker" means an indinidual (a) Each licenses shan poet current 19.13 Noutications and reports to indirnd. engaged in activities licensed by the Com* rnission and controlled by a licensee.

• copies of the fouowing documents: (1) na.m.

19.14 Preseme of repr%entauves of fleens. but does not include the 11cena2c. M Die regulations in this part and in Part oes and actten due tng inspections. g 20 of this chapter" (2) the ucense, ucense 19.15 Conr,uitation with wortere durms in. # (d)"1.icense" means g license issued z conditions, or documente incorporated as=tsons-101e Requests by workers for Inarctions. under the regulations in Nrts 30 thra.agh

• into a ucense by nference, an 35.40.6o.61.7o or ?2 of thas chapter.

I ments thereto: (3) the operating proco-

including Lceases to operate e dures applicable to licensed activities:

19.30 V1aiaHana

• pursuant to Part 50 of this chapter and radiological workms conditions. proposed 3 production or utillration facility (4) any notice of violauon involving is.31 Applicataon for esera.puons.

z 19.33 Discriminauon prohibited license s to pespess power reactor spent imposh M MH penalty, w Wer 1s- .Maaey: Seas. 51 e181. tos,104,181.19a' sued punuant to Imbpad B M Part 2 of i fuelir. In indepedent spent fuel store 8e K SW. No. 94 935. SE M7,94 96& as this chapter. shd any response from the amended, sec. 234. 83 Stat 444. as amended installation (ISFSI) pursuant to Pett 72 gge,os, (42 USC 3Drs, aost,2111.2133,2134,2301. of this cnapter. "1.lcensee* means the (b) If posting of a document specified 222a,2282k eer act. es Stat 1241 as holder of such a license. tr. paragraph (a) (1). (2) or (3) of this amended by PA L e4 09. as Stat ua (42 L acetion is not practicable. the licensee USC Seatk Pub. L e6-e01, sec. la et StaL may post a notice which describes the - (e) ' Restricted ana" means any ans document and states where it may be 2881I42 U A C 5451k access to which is controlled by the 11* O. Por the purposes of sec. 223, es Saat 96& es censee for purposes of protection of fn- =aramined. amenued (41 USC 22737, il 19.tttak ick (dk and (e) and ',0.12 are leeued ander sec.19th, dividuals from exposure to radiation and radioscure materials. Restrteted area" (c) Each licensee and applicent she!! et Stat. Det as amended (42 USC 2201(b)) shall not include any areas used as rest-et Form NRC-3 (Revision 6-42 or k room or rooms in a residential building a (9uired by P and Ii 18,13 and 18.14(a) are issued ende'

• dential quarters, although a separate tar)"Nottoe to E'mployees.*t as sec.1sta, ts Stat een as amended (42 USC 220tto)k may be set apart as a restricted area.
• M ce

$19.1 Purpose. Eg19.t Interpretations, i 'Itte regulations in thh part establish M Except as specifically authorize'!by the f (d) Documents, notices, or forms requirements for noticss, instructions. Commission in writing no tuterpretation and reports by licensees to individuals of the meanir.g of the regulations in this posted pursuant to this section shall ap-g articipathtg in licensed activities, and part by any omeer or employee of t!<e pear in a sufBetent number of places to p = options stallable to such individuals in Commission other than a written ir" permit individuals engaged in licensed y connection with Committion inspections terpretation by the Osneral Counsel s til activttles to obauve them on the way to . of licensees to ascertain compliance with be recognized to be binding upon the or from any certicular licensed activity g the provisions of the At"mic Energy Act Commission, location to which the document applies, of 1954, as amended. Title II of the En. shad be conspicuous, and shall be re-1 placed if defaced or altered. ) ergy Reorganization Act of 1974, and reg- "39.3 Communications. Je* Commtmaton documents posted 1 ulations, orders, and licenses thereunder regarding radiological working cond!- Except where otherwise spectdui in persuant to paragraph fa)(4) of this J1ons. this part. all communications and ret 2)rts section shan be posted within 2 working g concerning the regulations tu this cart t, days after receipt cf the documents from the Commission; tt.c licensee's response. _ I19J Scope. g should be addressed to the Director. Of* h if any, shau be posted within 2 working fice of Inspection and Enforcement. U.S. ge regu tions in this part appy to all a Nuclear Regwatory Commission. Wash * *g days after dispatch by the licensee. Such g documents shall remain posted for a persons who receive. possess use er g ington. D.C. 20s53. Communications, re-M minimum of 5 working darri or until ac-transfer materiallicensed by the ports, and applications may be delivered tion correcting the violation has been . Nuclear Regulatory Commission in person at the Comm%ston's oSres at coa.pteted, whichever is later.

pursuant to the regulatbns in Parts 30 1717 H Street. NT., Washington, D.C.;

M a M hnue Behsda. 5 RL, hem w Mm g through 35.40.so.6t.70 or 72 of this a chapter. including persons licensed to faryland. All individuals working in or frequent-

• operate a production or utilisation Ing any portion of a restricted area shau

, facility pursuant to Part 50 of:!us N 19.4 kWonnesen essecuen be kept informed of the storage, trans-regukemente:otes appeweL fer, or use of radioactive materials or of chapter and persons licensed to possess Power reactor spent fuelin an (a)De Nuclear Regulato radiation in such pontons of the n-stricted tres; shall be instructed in the irdependent spent fue? "orage

Commission has submitted a health protection problems associated insta!!ation (ISFSI) pursuant to Part 72 g inf restion collection nquinments with exposure to such radioactive mate-

• f this chapter.

contained in this part to the Omce of rials or radiation. in precautions or pro-o ea Management and budget (OMB) for cedures to minimize exposure, and in the { O

• epproval as required by the Paperwork purposes and functions of protective de-

' Reduction Act of 1980 (44 U.S.C. 3501 et vices employed: shall be instructed in. eeq-). OMB has approved the and instructed to obsene, to the extent information collection requirements within the worker's control the applica-ble provisions of Commission regulations contained in this part under control 19 8 May 31.1984

b PART 19 o NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS: INSPECTIONS and !! censes for the protection of per-report shall be transmitted at a time deliberately interferes with a faar and sonnel from exposures to radiation or not later than the transmittal to the orderly inspection. With regard to areas radioactive materials occurring in such Conunission. containing information classi!!ed by an agency of the U S. Oovernment in the areas; shan be instructed of their re. interest of national security, an individ-sponsibility to report promptly to the 11 - (e) At the request of a workerwhois ual who accompanies an inspector may censee any condition which may lead to ter ninahng empiopr.ent m a given have access to such information only if or cause a violation of Commission regu. ca endar quarter w:th tne bcensee in authorized to do so. With regard to any lations and licenses or unnecessary ex. work involving ra6ation dose, or of a area containing proprietary information. posure to radiation or to radioactive ma. terial; shall be instructed in the appro-worker who. wn11e e nployed by another the workers' representattre for that area shall be an individual preMously author-priate response to warnings made in the person. Is termmatmg assigrunent to event of any unusual occurrence or mal. work involving radiation dose in the tzed by the licensea to enter that area, function that may involve exposure to 1: bcensee s facuity in that calendar 9 19.15 Consuhetion with workers dur. ins inspections. radiation or radioactive matertal; and ll quarter, each licensee shall provide to shan be advised as to the radiation ex z" each such worker. cr to the worker s (a) Commission inspectors may con-sult privately with workers concerning posure reports which workers may re. ' designee, at termination a written matters of occupational radiation protec-

report regaring the radiation dose ti n and o r matt s ted to recen ed by that worker from operatterts g

thes rt o s co e su ate with potential radiological health of the beensee durmg that specifically lations and licenses to the extent the in. protection problems in the restsicteG identified calendar quarter or fraction spectors deem necessary for the conduct thereof, or provide a wntten estimate of of an effective and thorough inspection. arti that dose if the finally deter =med (b) During the course of an inspection I 19.13 Notincetions and reports to in. dividuals. personnelInorutormg results are not any worker may bnns privately to the avatiable at that time. Esnmated doses attention of the inspectors, either orally (a) Radiation exposure data for an sha' be clearly in6cated as such. or in writing. any past or present condi-J individual, and the results of any meas. tion which he has reason to believe may urements, analyses, and calculations of lation of the act the regulations in this have contnbuted to or caused any vio. radioactive material deposited or re. tained in the body of an individual, shall j 19.14 Presenre of representatives of be reported to the individual as specified licensees and workers during inspee, chapter. or license condition, or any un. necessary exposure of an individual to in this section. The information reported

tions, radlauon hn ucmed radioach sna-shan include data and results obtained (a) Each licensee shall aford to the a un u e UcensWs contrd Any pursuant to Commission regulations or-Commission at all reasonable times op.

such notice in wnting shall comply with ders or license conditions, as shown in portunity to inspect materials, activities' the requirements of l 19.16(a). records maintained by the licensee pur-suant to Commission regulations. Each facilities, premises, and records pursu-(c) The provtsions of paragraph (b) , notification and report shall: be in writ., ant to the regulations in this chapter, of this section shall not be interpreted as During aninspection. Commission ' authorization to disregard instructions g ing; include appropnate identifying data g (b) s g such as the name of the licensee, the N inspectors may consult privately with N pursuant to 119.12. name of the individual the individual's

• social secunty number; include the indi-g workers as specified in i 19.15. The 11. g g 19.16 Requests by workers foe Inspec.

a: censee or licensee's representative may

gions, F vidual's exposure information; and con g s dur. E tam the following statement:

(a) Any worker or representative of p in workers who beneves that a violation of This report a furnished to you under the prove. aC) If, at the time of inspection, an the Act, the regulations in this chapter. sions of the %ctear Resulatory Cornmission resu-individual has been authorized by the of HCme Conditions exists or has oc. 14 tion 10 CF R Part 19. You should preserve this workers to represent them during Com= curred in license activttles with regard to report for further reference. minion inspections, the Heensee shall radiological working condmm in which (b) At the request of any worker, each notify the inspectors of such authoriza-the worker is engaged, may request an Heensee shall advise such worker annu-tion and shall give the workers' repre. inspection by giving notice of the alleg d vioisten to the Director of Inspecteun and E_e ally of the worker's exposure to radiation sentative an opportunity to accompany n-or radioactive matettal as shown in rec. the inspectors during the inspection og forcement, to the Director of the appne ords maintained by the licensee pursu. physical working conditions. priate Commission Regional Ocice, or to ant to i 20.401ta) and (c). (d) Each workers' repr sentative shall Commission inspectors. Any such notice (c) At the request of a worker former. be routinely engaged in licensed activi. shall be in writing, shall set forth the ly engaged in licensed activities con. ties under control of the licensee and spec 1Ac grounds for the notice, and shall trolled by the licensee, each licensee shat! shall have received instructions as spec, be signed by the worker or representa. furnish to the worker a report of the ifled in i 19.12. tive of workers. A copy shan be provided Worker's exposure to radiation or radio-(e) Dtferent representatives of 11 (h'forcementken5ev IPY the Director of Inspection and active material. Such report shall be fur. censees and workers may accompany the En . Regionsi Office Director, nished within 30 days from the time the inspectors during diferent phases of an request is made, or within 30 days after inspection if there is no resulting inter. or the inspector no later than at the time the exposure of the individual has been ference with the conduct of the inspec. of inspection except that, upon the re. determined by the licensee, whichever is tion. However, only one workers' repre. Quest of the worker giving such netice. later; shall cover, within the penod of sentative at a time may accompany the his name and the name of individuals ~ time specified '.n the request each calen-inspectors. referred to therein shall not appear in dar quarter in which the worker's ac. (f) With the approval of the licensee such copy or on any record published. tivities involved exposure to radiation and the workera' revesentativ= an in-released. or made available by the Com-frorn radioactive materials licensed by dividual who is not routinely engaged mission. except for gond cause shown. the Commission; and shall include the in Heensed activities under control of (b) If. upon receipt of such notice, the dates and locations of Heensed activities the license, for example, a consultant Director of Inspe; tion and Enforcement or Re-in which the worker participated dunng to the licensee or to the acrkws' repre. giunst Office Direcior determines that this pertoci. sentative, shall be afforded the oppor-the complaint meets the requirements set idl When a Heensee is required pur. tunity to accompany Commission 1nspec* forth in paragraph (a) of this section. suant to i 20.405 or i 20.408 of this chap. tors during the inspection of physicaf and that there are reasonable grounds tt, ter to report to the Commission any ex. working conditions. believe that the sileged violation exists posure of an individual to radiation or (g) Notwithstanding the other provi. or has occurred, he shall cause an in-radioactive material the Heensee shan sions of this section. Commission in.ipec* spection to be made as soon as practica-also provide the individual a report on tors are authorized to refuse to permit ble, to determine if such alleged violation his exposure data included therein. Such accompaniment by any individual who exists or has occurred. Inspections pur-September 1,1982 gg4

J PART 19 e NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS: INSPECTIONS suant to this soeuen need met to umned Violations. m mauers referred to Atbe====amt. ,1 g 19.30 An injunction or other court order may r-8 19.17 in. not worrensedt in-m be obtained prohibiting any violation of DEsor fInspection and Enforce y any provision of the Act or Title II of (a) If the Energy Reorganisation Act of 1974. meet or of the appsopnete Ragnamet g or any regulation or order issued there-j QBce h. with 6 2 a m. under. plaint under i19.18. that an inspection la not warranted because there are no A court grounds to betime that a flo-order may be obtained for the payment lenon esists or has occurnd. he shan no* of a civil pensity imposed pursuant to lify the enNainant in writing of such section 234 of the Act for violation of sec-h h = = Nasama* may tion $3, 57. 42, 43. St. 82,101.103,104, obtain metow of such determa=*ha by 107. or 100 of the Act or any rule. Ngula-subsmitung a written statement of post-tien, or order issued thereunder, or any tsoe with the Execueve Duector for

sons, we candluon or haitauon d any 11-son.

20$.' conee' lasued thereunder, or for any flo-w bcense lation for which a license may be revoked Wint a copy W such stateenent by cwu. under section ISS of the Act. Any person Sed mail, esclh at tM w M me who willfuuy vloistes any provisten of cosaplainant, me name M the complain-

• A'I " *"# "8" R *hemundu may be guHty M a crime and, ant. The licensee may submit an oppos-nt ing written statetnent of position with the Executive Duector for Operations who will $ upon conviction, may be punished by Sne psovide the complainant with a copy of such g or imprisonment or boQt as provided by nestement by certified mast. sjpon the request law.

of the complainsat.the Executive Duecsor for APP ration for escenptions. ll Operessons or his designee may $ 19.31 hold an informal conference in which The Commission may, upon applica. 4 the complainant and the licensee may Mon by any licensee or upon its own in-oraHy present their views. An informal luauM. grant such onesupuona from the requirements of the Ngulations in this O quest me beens b d me k identity of the complainant will be made part as it determines am aumorised by e only fonowing recelot of written author-law and will not result in undue hazard

• isation from the complainant. After con-to life or property.

I M -sidering all written and oral views pre-1". seated, the Executsve Director for Operations g 19.32 Discriniination preliihited. shall affirm. needsfy or reverse the determine. No person shall on the ground of s4K s tion of the Dwector of Inspection and Enforce, be excluded from participation in, be de-E*'e$'1 urna'h'N*M'platnant and nied the benefits of, or be subjected to the licensee a written notiScauon of his discrimination under any program or ac-J decision and the reason therefor, tivity licensed by the Nuclear Regulatory (b) If the Disector of laspection and Enforce. Commission. This provision wi!! be en. 1 i sneat or of the appsopnate Regional % forced through agency provisions and J OtBee determines that an inspection is 3 rules similar to those already established, not warranted because the requiremente z with respect to racial and other discrim-d instion, under title VI of the Civil Rights of I 19.18(a) have not been met, he shall *S Act of 1964. This remedy is not exclu-noufy the complainant in writing of such determinsuon. Such determination sive, however, and will not prejudice or I shall be without prejudice to the filing of cut off any other legal remedies avail-a new complaint meeting the require-able to a discriminatee. ments of 919.18(a). 9 NJe Empseyeepressenen. Employment discrimanation by a h licensee or e contractor or subcontractor 3 of a licensee against an employee for engaging inprotected activities under s "* this part or Parte 30,40. SIL 00. 70, y2. or {100 of this chapterla prohibited. 19-3 December 30,1982(reset)

9 ..d' UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS TITLE 10. CHAPTEA 1. CDDE OF FEDERAL REGULATIONS-ENERGY V i P STANDARDS FOR PROTECTION AGAINST RADIATION shculd, in addition to complying with PAR? 20- STAND ARD5 FOR E"romerwest the requirements set forth in this PROTECTION AGAINST RADIATION 20 sol vioittions, part. make every reasonable effort to APPENDtx A-fReserved) maintain radiation exposures, and re-OrwnAL Ptovtstoms APerwarx B-ConcEwTmations IN Ata AFD leases of radioactive materials in ef-8'.C-Warta Asort Narcan BAcusacews fluents to unrestricted areas as low e4 20 1 Purpose Arrrwaix C is reasonably achievable. The term "as e 20.2 Scope. 3,,tyntz D-Unstro Starts Necttra Rzec-low as is reasonably achievable" means 20.3 Definitions. 3.aroav Coweisstow InkrscrioN AFs EN-as low as is reasonably achievable {n ta radia d roacturnt Rrcan At, Orrters taking into account the state of tech-20 8 Interpretauona. Amihasty: Sea, sa, es, et et. tot 104 tel. nology, and the economics of improve-20.7 Commumcations. es Seat set een set set est. set as ments in relation to benefits to the bl20.s informanon coueetmo requirements: amended,(es USC aors, anse, aest 211L public health and safety, and other so-OM8 spproval. alaa,2134 23Dik asco. ast. aem 20e cietal and socioeconomic consider-Praunstats Dosts.14vrLs ANs att Pub,I. es-est se Seat tast tant taet' ations, and in relation to the utiliza-ConexwTaATIops Pek 1. e6-F% as Stet 413 (M US(*. seat, g g gg gg 20.101 Radiation done standards for indi. seet seeth viduals in restricted areas. For the purposes of ese,231 et Stat een se Jerest. 20.102 Determinauon of prior done. amended les USC 22rsk ii aatet.atos, 9 20.2 Scope. 20.103 Exposure of individuals to concen. Miasta)(bh and(fk ab.tes(alaad(bh trations of radioscure matertals in air in an.10e(bk aatostak 2DJet, mane (sk naos, The regulations in this rart apply to restrteted areas. maer. nset, naos, naos and maos are all perscns who receive. possess, use. 20.104 Exposure of minors. lassed ender sec.10th, es samt 904 se or transfer material licensed pursuant 20.105 Permissible levels of radiation in un-asseded, (43 USC 2aot(bin and il salat. to the regulations in Parts 30 through nstricted ants. aa100(ekaatet-Jaeor amene(b)andaa400 I af.40.60.68.70.or72 of this chapter. in- .0.1 Rad oacurity in effluents to unres-are loseed ender ear.1ste6 es Sant est u 5 cluding persons licensed to operate a I'8 UA 238H'E 20.107 Medical diagnosas and therapy. s production or utilization facility pur-20.104 Orders requinns furmsning of bio- 'suant to Part 50 of this chapter and O assay services. Oc rtaAL Paovtstows 9 persons licensed to possess power reac-p 20.1 Purpon. tor spent fuel in an indepencent spent Pascactionaar Paocznenzs fuel storage installation (ISTSD puru-The lat ns in this part es-20.201 Surveys. t sant to Part 72 of this chapter. .L a protection 20.202 Personnel monitortng. 20.203 Cauuon signs, labels. signals and e against radiation hazards arising out controls.

• of activities under licenses issued by 20.204 Same: excepuons.

g the Nuclear Regulatory Commission 20.205 Procedures for picting up, recemng, and are issued pursuant to the Atomic $ 20.3 and opening packages. Energy Act of 1954. as amended, and 20.206 Instruction of personne!. the Energy Reorganization Act of 8 20.3 Definitions. 20.207 Storage and control of licensed me-1974. tertals in unrestrteted areas. (a) As used in this part* Wast Disposal to) The use of radioactive material (1) 'Act" means the Atomic Energy 20.301 General requirement. or other sources of radiation not 11-Act of 1954 (68 Stat. 919) including 20.302 Method for obtaming approval of censed by the Commission is not sub-any amendments thereto, proposed disposal procedures, ject to the regulations in this part. Ap (2) " Airborne radioactive materi 20.303 Disposal or release into sanitary However. It is the purpo? e of the regu. e means any radioactive material dis- ,, lations in this part to control the pos, e persea in the air in the form of dusts. sewerage systems. a O session, use, and transfer of licensed " material by any licensee in suc 20.305 Trettmera or disposal by inciner. f suon. (3)" Byproduct material means any a 20.306 Disposal ot specifie rastes. manner that the total dose to an indi, radioactive meterial (except special 5 20.31 Transfer for disposal and manifests. ? vidual (including exposures to licensed nuclear material) yielded in or made Recomas. RzromT$. AKs Nottricanon anc unlicensed radioactive material D g', D the p of t g 20.401 Records surveys, radistica moni-u g or utMg Mclal ndear ma-d o w eth e o 20.402 Reports of theft or loss of licensed the licensee or any other person, but matertal. not including exposures to radiation g4).. Calendar quarter" means not Sec. from natural backgrout2d sources or less than 12 consecutive weeks nor 20.403 Notifications of incidents. medical diagT10 sis and therapy) does more than 14 consecutive weeks. The A404 (Resen ed) not exceed the standards of radiation first calendar quarter of each year si e eYan concent YuorE d 'x **'

1. rotection prescribed in the regula*

20 4(,6 tReserved! tions in this part. . shall begin in January and subsequent calendar quarters shall be such that a 20.407 Personnel moniterms repor.s* l (c)In accordance with recommenda. no day is included in more than one .0 408 Reports of personnel morutortng on termmation of employment or work. ,s tions of the Federal Radiation Coun a' clusion within a calendar quarter. No calendar quarter or omitted from in-g cil, approved by the President. persons h licensee shall change the method ob-20.409 Notdicauons and report.s to indmd. uals. engaged in activities under licenses 3,n.ed by him of determining calendar Issued by the Nuclear Regulatory quarters except at the beginning of a ExcrrTrows AND AnnrTronat RzectaruzwTs o Commission pursuant to the Atomic 1'nd 20 501 Amphcauons for exempuons. Energy Act of 1954. as amended, and .0502 Add.tions! requirements. the Energy Reorganization Act of 1974 g May 31,1984

PART 20 o STANDARDS FOR PROTECTION AGAINST RADIATION (5) " Commission" means the Nuclear (13) " Radioactive material" includes at 1237, 42 U.S.C. 5814) and retran.4-Regulatory Commission or its duly au-any such material whether or not sub-ferred to the Secretary of Energy pur-thorized representativer ject to licensmg control by the Com. - suant to section 301(a) of the Depart-

mission, 2 ment of Enetgy Organizatif n AF (Pub. L. 95-91. 51 Stat. 565 at 577-57 (6)" Government agency" means any

~ area access to which is controlled by (42 U.S.C. 7151). (14) " Restricted area" means any executive department, commission, in-dependent establishment, corporation, the licensee for purposes of protection r-- wholly cr partly (,wned by the United (19), Termination,, means the end States of America which is an instru j of individuals from exposure to radi. l of employment with the licensee or. in mentality of the United States, or any 5 ation and radioactive materials. "Re ; , board, bureau. division, service, office. z stricted area" shall not include any g the case of individuals not employedby th h officer, authority, administration. or *$ areas used as residental quarters, al z signment in the licensee's restricted other establishment in the executive though a separate room or rooms in a.2 areas in a given calendar quarter, 5 branch of the Government; residential building may be set apart without expectation or specific sched-(7) as a restricted area: uling of reentry into the licensee's re-being." Individual" means any human g stricted areas during the remainder of (8) " Licensed matertal" means that calendar quarter. source material. special nuclear mate-rial. or by. product material recetted. (b) Definitions of certain other possessed. used, or transferred under a words and phrases as used in this part general or specific license issued by are set forth in other sections, includ-the Commission pursuant to the regu. (15) " Source material" means: (1) ing: -lations in this chapter; Uranium or thorium, or any combina-(1) " Airborne radioactivity area" de-e tion thereof,in any physical or chemi-fined in i 20.203; 5 cal form: or (11) ores which contain by (2) "Raciation area" and "high radi- = weirht one twentieth of one percent ation area" defined in i 20.202: [ (9) " License" means a !! cense issuco k th'or or ( a-co in n ere ment defined in i 20.202. E mb 7 under the regulations in Parts 30 g' s (41 " Survey" defined in i 20.201;

through 35.40.60.6t to or ?2 of this special nu 'M ter a '

(5) Units of measurement of dose chapter. " Licensee" means the holder (rad. rem) defined in i 20.4; w of such license; (6) Units of measurement of radicac-L tivity defined in i 20.5. "'" (10) " Occupational dose" includes f 20.4 t' nits of radiation dose. exposure of an individual to radiation - (a) ' Dose." as used in this part le (1) in a restncted area; or (ii) in the (16) "Special nuclear material.. the quantity of radiation absorbed, h course of employment in which the in. means: (i) Plutonium, uranium 233. Y unit of mass, by the body or by an, .r uranium enriched in the isotope 233 or @ dividual's duties involve exposure toradiation. provided, that " occupational ; m the isotope 235, and any other ma ;8 p tions in this part specify a dose during f dose" shall not be deemed to include ; tenal ahich the Commission. pursuant ; a period of time, the dose means the o any exposure of an individual to radi = to the provisioris of section 51 of the 4 total quantity of radiation absorbed. act determine to be special nuclear " (tion for the purpose of medical diag. ; ma,enal. but does not include source per unit of mass, by the body or by nosis or medical therapy of such indi 8 t any portion of the body during such matenal; or (11) any material artificial- ,, yldual. period of time. Several different units ly enriched by any of the foregoing of dose are in current use. Definitions but das not inclu& source matenat of units as used in this part are set (11) " Person" means: (1) Any individ-ual, corporation. partnership, firm, as. forth in paragraphs (b) and (c) of this sociation, trust, estate public or pri, f (17) " Unrestricted area" means any section. vate institution group. Government area access to which is not controlled (b) The rad, as used in this part,is a N agency other than the Commission or h by the licensee for purposes of protec-measure of the dose of any ionizing ra-the Department (except that the De : tion of individuals from exposure to diation to body tissues in tenns of the partment shall be considered a person - radiation and radioactive materials, energy absorbed per unit mass of the within the meaning of the regulations 4 and any area used for residential quar-tissue. One rad is the dose correspond-E in this part to the extent that its facil. { ters. ing to the absorption of 100 ergs per a ities and activities are subject to the 11 gram of tissue. (One millirad 5 censing and related regulatory author-(mrad)=0.001 rad.) (18).. Department" rneans the De-(c) The rem, a used in this part is a e ity of the Commission pursuant to sec. " tion 202 of the Energy Reorganization partment of Energy established by the measure of the dose of any ice.izi.,g ra. Act of 1974 (88 Stat.1244)), any State. Department of Energy Organization diation to body tissues in terms Cf its Act (Pub. L. 95-91. 91 Stat. 565. 42 estimated biological effect relative to a any foreign government or nation or any political subdivision of any such U.S.C. 101 et sec.) to the extent that dose of one roentgen (r) of X rays. the Department, or its duly authorized (One millirt'm (mrem)= 0.001 tem.) government or nation, or other antity; and (11) any legal successor, repre-representatives. exercises functions The relation of the re n to other dose sentative, agent or ageftcy of the fore- ; formerly vested ir. the U.S. Atomic units depends upon the biological going.

Energy Commission. ts Chairman.

effect under consideration and upon members, officers and components and the conditions of trradiation. For the (12) " Radiation" means any or all of :, transferred to the U.S. Energy Re-purpose of the regulations in this part, Fthe following: alpha rays, beta rays. search and Development Administra-any of the following is considered to i gamma rays. X. rays, neutrons, high-tion and to the Administrator thereof be equivalent to a dose of one rem: E speed electrons, high speed protons, pursuant to sections 104 (b), (c) and (1) A dose of I r due to X-c, e and other atomic particles; but not (d) of the Energy Reorganization Act gamma radiation; 3 sound or rartio waves, or visible, in-of 1974 (Pub. L. 93-438, 88 Stat.1233 (2) A dose of I rad due to X. frared. or ultraviolet light; gamma, or beta radiation: N December 30,1982 20 2

.f PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION ~ (3) A dose of 0.1 rad due to neutrons 1 20.6 Interpretations, fC" or high ener rot .due to particles Except as specifically authorized by $ calendar quarter from radioactive ma-to ece e y period f one 4 d heavier than protons and with suffi. j the Comrnission in writing, no inter ~ terial and other sources of radiation a - pretation of the encaning of the regu 6 total occupational dose in excess of cient energy to reach the lens of the E lations in this nrt by any officer or A the standards specified in the follow-eye: If it is more convenient to mets-ute the nectron flux, or equivalent, g employee of the Commission other Ling table: than to determine the neutron dose in than a written interpretation by the rads, as provided in paragraph (c)(3) Oeneral Counsel will be recognized to,p Atws atm CALENoAn QUAmita of this section, one rem of neutron ra be binding upon the Comrnission. g ) diation may, for purposes of the teru-e' g,,,,, @ %.s.,.*,c"Q*7,1 lations in this part, be assumed to be n, equivalent to 14 million neutrons per k: ..y.. ..n .ne.. i s '. s.n on co. noor.- N square centimeter incident upon the 120J Communications. t body; or, if there exists sufficient in-Except where otherwise specified in formation to estimate with reasonable i this part, all communications and re-(b) A licensee may permit an individ-1 accuracy the approximate distribution ports concerning the regulations in <. ual in a restricted area to receive a in energy of the neutrons the incident 2 this part should be addressed to the : total occupational dose to the whole number of neutrons per square centi 2 Executive Director for Operations. : body greater than that permitted meter equivalent to one tem may be

• U.S. Nuclear Regulatory Commission, a under paragraph (a) of this section, estimated from the following table:
• Washington, D.C. 20555. Communica ' provided:

I NEUTPoN Flux Dest EcurvaLENis tions, reports, and applications may be

• tl) During any calendar quarter the delivered in person at the Commis-total occupational dose to the whole sion's offices at 1717 H Street NV7 body shall not exceed 3 rems and I

, M 7, ' a,. m,. Washington D.C.; or at 7920 Norfolk y,

• Jg
• Avenue. Bethesda. Maryland.

"~ (2) The dose to the whole body, ,f * "'" " ,.ww to.. noss when added to the accumulated occu-i 9'*g"'. '"'Q *" ' pational dose to the whole body, shall k_l20.4 Informemen esescuen not exceed 5 (N-18) rems where "N" I ce ] f requiremonte: Code approval. equals the individual's age in years at aT? .to ". toi (a) De Nuclear Regulatory his last birthday; and 3 o ca._.. _ _ _. s s7o Commission has submitted the (3) The licensee has determined the o oes oo se* aso information collaction requirements

individual's accumulated occupational Is

~ contained in this part to the OfBce of 2 dose to the whole body on Form NRC-lic* i g 7-Management and Budget (OMB) for g 4. or on a clear and legible record con-e s s oo= to approval as requtred by the Peperwork , taining all the information required in 4 so _ s. io* is Reduction Act of 1980 (44 U.S.C. 3501 et a that form; and has otherwise complied q 7s. .. ice ir 24 io' if seq.). OMB has approved the with the requirements of I 20.102. As

o

4. ic to information collection requirements used in paragraph (b). " Dose to the o m se whole body" shall be deemed to in-contained in this part under control clude any dose to the shole body.

(d) For determining exposures to I number 3150-4014-gonads. active blood-forming organs, or gamma rays up to 3 Mev the dose (b] De approved information limits specified in ll 20.101 to 20.104. A collection requirements containedin this head and trunk. or lens of eye. I inclusive. may be assumed to be equiv i part appearin ll 20.102.20.103. 20.105. alent to the " air dose' For the pur ** 20.108.20.203.20.205. 20.302. 20.311. I 20.102 Determination of prior dose. pose of this part " air dose" means that E 20.401.20.402.20.403. 20.405. 20.407 (a) Each licensee shall require any the dose is measured by a properly e calibrated appropriate instrument in l 20.408. and 20.400. individual, prior to first entry of the ' (c) Dis part contains information individual into the licensee *s restricted air at or near the body surface in the collection requirements in addition to area during each employment or work _ region of highest dosage rate. those approved under the control assignment under such circumstances number speciMed in paragraph (a) of this that the individual will receive or is section. These information collection likely to receive in any period of one i 20.5 ll nits of radioactivity. requirements and the control numbers calendar quarter an occupational dose (a) Radioactivity is commonly, and under which they are approged are as in excess of 25 percent of the applica-for purposes of the regulations in this follows: ble standards specified in i 20.101(a) part shall be, measured in terms of dis. (1]In il 20.101 and 20.102, Fonn and i 20.104(a) to disclose in a writ-1 A integrations per unit time or in curies. NRC-4 is approved under :ontrol , tes sigred statement, either: (1) That

• the individual had no prior occupa-E number 31N

One curie = 3.7 x 10 " disintegrations tional dose during the current calen-(2)In l 20.401. Form NRC41s k per second (c.ps)=2.2x10" disintegra-2 dar quarter, or (2) the nature and tions per mmute (dpm). Commonly 8PProved under control number 31505-

". a*tovnt of any acc t;*ational dose 1: sed sJbmultiples of the curie are the 0006-which the individual may have re-millicurte and the microcurte: } telved dur9g that specifically identi-t (1) One millicurie (mCl) ' = 0.001 Fraxisstat.z Do;Es. LzvrLs. AffD fled Current Calendar quarter from curie (C1) 5 3.7 x 10' dps. CoNCE2tTRATIoNS (2) One microcurie (pC1) i=0.000001 trolled by other persons. Each licensee _curte = 3.7 x 10

• dps.

$ 20.101 Radiation dose standards for in. s au ma.2 reWds of sud staw 2 dividuals in restricted areas. men a misskn amhoo a izes their disposition. ( ) cordance Mth the provisiom (b) Before permitting, pursuant to (H IDeleted do FR So7o41 of I 20.102(a), and except as providec a i 20.101(b), any individual in a restrict. (c) (Debted 39 FR 2399o.1 in parp@ d) of this setm. no 11-O.- ed area to receive an occupational ra-censee shall possess, use, or transfer 11-censed material in such a manner as to diation dose in excess of the standards specified in i 20.101(a), each licensee shall: 20 3 May 31,1984

PART 20 o STANDARDS FOR PROTECTION AGAINST RADIATION (1) Obtain a certificate on Form NRC-4. or on a clear and legible O record containing all the information required in that form, signed by the individual showing each period of time after the individual attained the age of 18 in which the individual received ., an occupstional dose of radiation: and f (2) Calculate on Form NRC-4 in ac-E cordance with the instructions appear- ! ing therein. or on a clear and legible g record containing all the Information required in that form. the previously accumulated occupational dose re-ceived by the individual and the addi. tional dose allowed for that fr dividual under i 20.101(b). (cx1) In the preparation of Form NRC-4. or a clear and legible record containing all the information re-quired in'that form. the licensee shall make a reasonable effort to obtain re-ports of the individual's previously ac-cumulated occupational dose. For each period for which the licensee obtains O v 1 1 l 20-3a May 31,1984

PART 20 oSTANDARDS FOR PROTECTION AGAINST RADIATION such reports, the licensee shall use the manner as to permit any ind!vicualin would result from inhalation of such dose shown in the report in preparing a restricted area to inhale a quantity material for 40 hours at the uniform the form. In any ca.se where a licensee of such material in excess of the concentrations specified in Appendix is unable to obtain reports of the indi. intake limits specified in Appendix B, B. Table 1. Column 1 as is reasonably vidual's occupational dose for a previ. Table I. Column 1 of this part. If such. achievable. Whenever the intake of ra. cus complete calendar quarter,it shall soluble uranium is of a form such that

• dioactive material by any individual be assumed that the individual has re-absorption through the skin is likely,2 exceeds this 40-hour control measure.

(J.tved the occupational dose specif.ed individual exposures to such material z the licensee shall make such evalua-in whichever of the following columns shall be controlled so that the uptake I tions and take such actions as are nec-apply: of such material by any organ from - essary to assure against recurrence. The licensee shall maintain records of either inhalation or absorption or such occurrences, evaluations, and ac. [ c eai- ! C*aa 8-both routes of intake

• does not exceed tions taken in a clear and readily iden-

'NE lI e'UU. ^*"'" that which would result from inhaling such msterial at the limits specified in tifiable form suitable for summary + review and evaluation. g d*% i"aN Appendix B. Table I. Column 1 and u met. '9aaas oa footnote 4 thereto. l %'.Y,7 (3) For purposes of determining e compliance with the requirements of (c) When respiratory protective i this section the licensee shall use suit-equipment la used to limit the inhalation O "c* eaaam I no* of airbome radioactive matenal of radioactive materials in air for de-; pursuant to aragraph(b)(2)of thia able measurements of concentrations S.') 7 # " j 3,j section, the icensee shall use equipment m tecting and evaluating airborne radio-;; thatis certified or had certification activity in restricted areas and in addi tion, as appropriate. shall use meas-g extended by the Netionalinstitute for Occupational Safety and Health /Mine [ (2) The licensee shall retain and pre- ' urements of radioactivity in the body. % Safety and Health Administration measurements of radioactivity excret-g serve records used in preparmg Form ed from the body. or any combination (NIOSH/MSHA).The licensee may RC-4 until the Commission author-

• f.zes their disposition.

of such measurements as may be nec. make allowance for this use of g" essary for timely detection and assess. re8piratory protective equipment in estimating exposures ofindividuals to gment of individual intakes of radioac. this material provided that: tivity by exposed individuals. It is as-u*:umed that an indWidual inhales ra- 'If calculation of the individual's accu-f dioactive material at the airborne con- ,8 fi or trt mulated occupational dose for all peri- ; centration in which he is present ggj",'Qh'.,conQa$n s, ,a ods prior to January 1.1961 yields a unless he uses respiratory protective skm absorption and inhalation. the total 9: result higher than the applicable accu-equipment pursuant to paragraph (c) intake perrnitted is twice that shich aould g mulated dose value for the individual of this section. When assessment of a

• result from inhalation alone at the concen.

active material is necessary, intakes,j tration specified for H 3 S in Appendix B. particular individual's intale of radio- , as of that date, as specified in cara. Table 1. Column 1 for 40 hours per week for

• graph (b) of I 20.101, the excess may be disregarded.

less than those which would result = 13 weeks. 'For raden-222. the limiting quantity is from inhalation for 2 hours in any one ; hat inhaled m a penod of one calendar ~ t day or for 10 hours in any one week at 5 20.103 Esposure of individuals to con. uniform concentrations specified in

3. *us the otoYe$olu n of the tat e centrations of radioactive materials in Appendix B. Table I. Column 1 need the concentration value specified is tased air in restricted areas.

not be included in such assessment, provided thr,t for any assessment in upon exposure to the material as an exter-(aX1) No licensee shall possess, use* excess of these amounts the entire nal radiation source. Individual exposures to or transfer licensed material in such a these materials may be accounted for as amount is included. manner as to permit any individualin part of the limitation on Individual dose in (bX1) The licensee shall, as a precau-l 20.101. These nuclides shall be subject to a restr:cted area to inhale a quantity tionary procedure, use process or the precautionary procedures required by of radioactive material in any period other engineering controls, to the i 20.103(b x1L of one calendar quarter greater than extent practicable, to limit concentra. ' Multiply the concentration values spect. the quantity which sould result f/om tions of radioactive materials in air to fled in Appendix B. Table I. Column 1. by inhalation for 40 hours per wee 4 for levels below those which delimit an 6.3x10* ml to ottam the quarterly cuantity 13 weeks at uniform concentratiens of airborne radioactivity area as defined ht. Multiply Me e neentration value spec. radioactive material in air specified in i e in ex B. Table I. Column 1 by in i 20.003(dXIX11)' practicable to applylint for nY22 Appendix B. Table I. Column 1. 5 8 8 If (2) When it is im the radioactive material is of such process or other engineering controls 'Significant intake by ingestion or injee. form that intake by absorption to limit concentrations of radioactive tion is presumed to occur only as a result of through the skin is likely. Individual material in air below those dsfined.n cecumstances such as accident. inadver. exposures to radioactive material shall i 20.203(dXIXii), other precautionary tence, poor prbcedure. or similar special be controlled so that the uptake of ra. procedures, such as increased surveil, conditions. Such intakes must be evaluated % dioactive material by any organ from lance.12nitation of working times, or pfro du b t et g either inhalation or absorption or provision of respiratory protective stances of the occurrence. Exposures so both routes of intake " in any calen. equipment, shall be used to raairtain evalasted shall be included t t determining e dar quarter does not exceed that intake of radioactive mat,erial by ar'y whether *be tim;tation on indivioual expo. I which would result from Inhahr.g such individual within any period of seven sures in i 20.103(ax1) has t,een exceeded. radioactive material for 40 hours per consecutive days a.s far below that ' Regulatory guidance on assessment of in-week for 13 weeks at uniform concen. intake of radioactive material which dividual intakes of rad.oactive material is gnen in Regulacry Guice 8.9. "Arceptable trations specified in Appendix B-Concepts. Models. Equations and Assump-Table I. Column 1. tions for a Bloassay Program." single copies (2) No licensee shall possess, use. or cf which are available from the office of transfer mixtures of U-234. U-235. and Standards Development. U.S. Nuclear Regu. U-238 in soluble form in such a latory Commission. Washington. D.C. 20555 upon written request. September 1,1982 20 4

PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION (1) The licensee selects respiratory those specifiedin Appendix A of this (c) The provisions of ll 20.103(b)(2) protective equipment that provides a part in selecting and using respiratory , and 20.103(c) shall apply to exposures protection factor greater then the Protective equipment. De Commission g subject to paragraph (b) of this see-multiple by which peak concentrations may authorize s licensee to use higher 3 tion except that the references in of airborne radioactive materials in the protection factors on receipt of an il 20.103(b)(2) and 20.103(c) to Appen-working area are expected to exceed the application (1) desaibing the situation ,, dix B. Table 1. Column 1 shall be values specified in Appendix B. Table L for which a need exists for higher . deemed to be references to Appendix Column 1 of this part. The equipment so protection fa,ctors, and (2) demonstrating B. Table II. Column 1. selected shall be used so that the that the neparatory protective average concentration of radioactive equipment will provide these higher materialin the air that is inhaled during protection factors under the proposed conditions of use. l any period of uninterrupted use in an 1 20.105 Permissible levels of radiation in ,, airborne radioactivity area, on any day. (e) Where equipment of a particular ,g,g,,, 'qpge sp d y (a) There may be included in any ap-ex e d e tu m Appendix B. Table L Column 1 of this NIOSH/MSHA.or where there is no plication for a license or for rmend-11 nse propo ed lirnit u 2 part. For the purposes of this paragraph, existing schedule for test and {en of

• the concentration of radioactive

certiScadon of certain equipment. the areas resulting from the applicant's materialin the air that is inhaled when I licensee shall not make allowance for respirators are worn may be estimated this equipment without specinc possession or use of radioactive mate-by dividing the ambient concentration in f authorisation by the Commission. An rial and other sources of radiation.

air by the protection factor specified in

application for this authorization must Such applications should include in.

Appendix A of this part. If the exposure include ademonstration by testigor formation as to anticipated averste ra-le later found to be greater than on the basis of reliable test information, distion levels and a sticipated occupan-estimated the corrected value shall be that the material and performance cy times for each t nrestricted area in-used: if the exposure is later found to be characteristice of the equipment are volved. The Cornmfuion will approve less than estimated, the corrected value capable of providing the proposed the proposed limits if the applicant may be used. desmo of protection under antidpated demonstrates that the proposed limita (2) The licensee maintains and conditions of use. are not likely to cause any individual implements a respiratory protection (f) On! equipment that has been to receive a d se to the whole body in program that includes, as a minimunu ,p,cifge hy certified or had certification any udod of m calendar year in air sampling sufficient to identify the extended for emergency see by NIOSH/ , excess of 0.5 rem. hazard, permit proper equipment MSHA shall be used as emergency jCommission pursuant to paragraph (a) (b) Except as authorized by the selection and estimate exposures: y O .e f this section, no licensee shall pos-surveys and bioassays as appropriate to o m e neensee shall nottfr. in writ. evaluate actual exposures; wntten ing. the Director of the appropriate Nu-

• sess, use or transfer licensed material procedures regarding selection. fitting, clear Regulatory Commission tnspectton Nin such a manner as to Create in any and maintenance of respirators, and and Enforcement Resional Of!!ce listed unrestricted area from radioactive ma-testing of respirators for operability in Appendix D at least 30 days before the terial and other sources of radiation in immediately prior to each use: written d'$g *h*[rs ed u$d!r tYe pr'ovts his possession:

ns procedures regarding supervision and of this section. (1) Radiation levels which. If an indi-training of personnel and Isauance vidual were continuously present in records; and determination by a the area, could result in his receiving a physician prior to initial use of dose in excess of two millirems in any respiratore, and at least every 12 months one hour, or thereafter, that the individual user le (2) Radiation levels which. if an indi-I '8-vidual were continuously present in physically able to use the respiratory protective equipment. (a) No licensee shall possess, use, or the area, could result in his receiving a (3) A written policy statement on transfer licensed material in such a dose in excess of 100 millirems in any respirator usage shall be issued covering manner as to cause any individual seven consecutive days. within a restricted area who is under such things as: use of practicable e ' ee ' controls insteed of 18 years of age, to receive in any [ (c) In addition to other requirements pri i m ca ndar quarur from t no use of respirators; and radioactive material and other sources l: of this part, licensees engaged in ura-re ret routine nonroutine, and nium fuel cycle operations sub.Het to em T1 & D D e 8n888 D 886 i the provisions of 40 CFR Part 190 pen s oi respirame use and re' ef from i respirator use. The licensee shall advise ft DecIfie$. the t b e d smental R dia 10 te tion 1. each respirator user that the user may f paragraph (a) of 5 20.101'ossess. use or l Isave the area at any time for relief from (b) No !!censee shall p respirator use in the event of equipment 2 transfer licensed material in such a malfur.ction. physicat or psychological manner as to cause any indbridual 3 10.166 Radion(tivity in effluents to un-distress. procedural or communication within a restricted area, who is under restricted areas. failure. significant deterioration of 18 years of age to be exposed to ai - (a) A licens'ee dall not possess, use operating conditions, or any other borne radioactive matertal possessed j or transfer licensed material so as to' condition that m'ght require such relief. by the licenset in an average concen-i release to an unrestricted area radioac-(4) The licensee uses equipment tration in excess of the limits specified 6tive material in concentrations which within limitations for type and mode of in Appendix B. Table II of this part. exceed the limits sp'cified in Appen-use and provides proper visual. For purposes of this paragraph, con-e dix B. Table II of this part, except as communication. and other special centrations may be averaged over peri-

• authorized pursuant to { 20.302 or capsbilities (such as adequate skin 0,,ds not greater than a week.

2 paragraph (b) of this section. For pur-O protection) when needed. ' poses of this section concentrations (d) Unless otherwise authorized by may be averaged over a period not greater than one year. l the Commission. the !!censee shall not assign protection factore in excess of 20 5 September 1,1982

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION O

l a endment includ p posed centrations of radionuclides. PRICAUT1oNARY PaocrDrRIs (7 A description of the waste treat. limits higher than those specified in paragraph (a) of this section. The ment faci!! ties and procedures used to $ 20401 Surs eys. reduce the concentration of radionu* Commission will approve the proposed clides in effluents prior to their re. (a) As used in the regulations in this limits if the applicant demonstrates: lesse. asrt " survey" means an evaluation of (1) That the applicant has made a (d) For the purposes of this section Ethe radiation hazards incident to the reasonable effort to minimize the ra. the concentration limits in Appendix -pr duction, use. release, disposal. or ~ dioactivity contained in efnuents to B. Table II of this part shall apply at pesmce d ramam materials or unrestricted areas; and the boundary of the restr eted area. other sources of radiation under a spe. l (2) That it is not likely that radioac. The concentration of radioactive ma-acific set of conditions. When appropri-a l tive material discharged in the efnu. terial discharged through a stack, pipe ate. such evaluation includes a physi-l ent would result in the exposure of an or similar conduit may be determined cal survey of the location of materials individual to concentrations of radio. with respect to the point where the and equipment, and measurements of active material in air or water exceed. material leaves the conduit. If the con-levels of radiation or concentrations of ing the limits specified in Appendix B. duit discharges within the restricted fadioactive matnial cresent. l Table II of this part. A area, the concentration at the bound-(c) An application for higher limits ; try may be determined by applying appropriate factors for dilution, dis-pursuant to paragraph (b) of this sec. ; persion, or decay between the point of f(b) Each licensee shall make tion shall include information demon. m strating that the applicant has made a g discharge and the boundary. -cause to be made such surve s as ( reasonable effort to minimize the ra. (e) In addition to limiting concentra. ;"*I be necessary for the licensee to a dioactivity discharged in effluents to tions in effluent streams, the Commis-geompyy with the regulations in this unrestricted areas, and shall include, sion may limit quantities of radioac. Spart, and (2) are reasonable under the as pertinent-tive materials released in air or water fircumstances to evaluate the extent (1) Information as to flow rates. during a specified period of time if it lof radiation hazards that may be pres. I total volume of effluent, peak concen. appears that the daily intake of radio- [ent, tration of each radionuclide in the ef. active material from air. water, or food fluent, and concentration of each radi. by a suitable sample of an expored i 20.202 Personnel monitoring. onuclide in the effluent averaged over population group, averaged over a l & period of one year at the point period not exceeding one year would (a) Each licensee shall supply appro-l where the effluent leaves a stack, otherwise exceed the daily intake re. priate personnel rnonitoring equip-l tube, pipe, or similar conduit; sulting from continuous exposure to ment to, and shall require the use of ( (2) A description of the properties of air or water containing one-third the such equipment by* I ? the effluents. including-concentration of radioactive materials (1) Each individual who enters a re-i (i) Chemical composition; specified in Appendix B. Table II of stricted area under such circumstances I (11) Physical characteristics, includ-this part. that he receives, or is likely to receive,

ing suspended solids content in liquid f

a dose in any calendar quarter in 6 I geffluents. and nature of gas or aerosol excess of 25 percent of the applicable l fer air effluents; " (f) The provisions of paragraphs (a) value specified in paragraph (a) of l ( 111 ) The hydrogen ion concentra. through (e) of this section do not i 20.101, tions (p") of Ilquid effluents; and apply to disposal of radioactive materi. (2) Each individual under 18 years of (iv) The size range of particulates in al into sanitary sewerage systems, age who enters a restricted area under effluents released into air. which is governed by 1 20.303. such circumstances that he receives. l (3) A desenption of the anticipated - (g) In addition to other require. or is likely to receive, a dose in any cal-human occupancy in the unrestricted i ments of this part, licensees engaged,endar quarter in excess of 5 percent of area where the highest concentration. In uranium fuel cycle operations sub. -the applicable value specified in para-of radioactive material from the efflu.

• ject to the provisions of 40 CFR Part Egraph ta) of i 20.101, ent is expected and. in the ase of a 190. " Environmental Radiation Protec-E (3) Each individual who enters a river or stream, a description of water tion Standard for Nuclear Power Op-
• high radiation area.

uses doutstream from the point of re. e, rations " shall comply with that part. f (b) As used in this part. lease of the effluent. (1) " Personnel monitoring equip-(4) Information as to the highest concentration of each radionuclide in 5 20.107 3fedical diagnosis and therapy. ment" means devices designed to be g q an unrestricted area including antici-Nothing in the regulations in this the purpose of measuring the dose re-pated concentrations averaged over a part shall be interpreted as limiting ceived (e.g., film badges. pocket enam-period of one year-the intentional exposure of patients to bers, pocket dosimeters, film rings. i (1) In air at any point of human oc-radiation for the purpose of medical ete,); cupancy:or diagnosis or medical therapy. (2) " Radiation area" means any (ii) In water at points of use dost-area, accessible to personnel, in which stream from the point of release of 3 20.105 Orders requiring furnish;ng of the effluent. bio. assay services. there exists radiation, originating in whole or in part within licensed mate-(5) The background concentration of Where necessary or desirable in rial, at such levels that a major por-radionuclides in the receiving river or order to aid in determining the extent tion of the body could receive in any i stream prior to the release of !! quid ef-E of an indh-idual's exposure to concen-one hour a dose in excess of 5 mil-fluent. trations of radioactive material, the lirem or in any 5 consecutive days a (6) A description of the environmen-g Commission may incorporate appro-dose in excess of 100 millirems; tal monitoring equipment, including priate provisions in any license, direct-(3) "High radiation area" means any sensith'ity of the system and proce-ing the licensee to make available to area, accessible to personnel,in which dures and calculations to determine the individual appropriate bio-assay there exists radiation originating in concentrations of radionuclides in the services and to furnish a copy of the whole or in part within licensed mate-unrestricted area and possible recon. reports of such services to the Com-rial at such levels that a major portion mission. of the body could receive in any one hour a dose in excess of 100 millirem. September 1,1982 20 6

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION

" (11) Be equipped with silditional con-(2) Each entrance or access point tcP trol devices such that upon failure of a high radiation area shall be: the entry control devices to function (D Equipped with a control device as required by paragraph (c)(6MI) of which shall cause the level of radi-this section the radiation level within ation to be reduced below that at the araa, from the sealed source, shall 3 20.203 Caution signs. labels, signals and which an individual might receive a be reduced below that at which it

• • • • I'*

dose of 100 millirems in I hour upon would be possible for an individual to ive a dose exc of 00 m L entry into the area: or j (a) General (1) Except as otherwise authorized by the Commission, sym. (11) Equipped with a control device alarm signals shall be generated to bots prescribed by this section shall which shall energize a conspicuous make an individual attempting to use the conventional radiation caution visible or audible alarm signal in such enter the area aware of the hazard colors (magenta or purple on yellow a manner that the individual entering and the licensee or at least one other backs 70und). The symbol prescribed the high radiation area and the licens-individual, who is familiar with the ac-by this section is the conventional se or a supervisor of the activity are 2 tivity and prepared to render or three bladed design: made aware of the entry; or j summon aasistance, aware of such fail-(111) Maintained locked except during ure of the entry control devices. periods when access to the area is re E (iii) Be equipped with Control devices RA$tAnolf Smtot quired, with positive control over each : such that upon failure or removal of

1. Cross hatched area is to be magenta or purple.

individual entry. I physical radiation barriers other than the source's shielded storage container

. Background is to be ye!!ow.

(3) The controls required by para-the radiation level from the source graph (c)(2) of this section shall be es-shall be reduced below that at which it 0 8tablished in such a way that no indi-would be possible for an individual to [ 60 Evidual will be prevented from leaving a receive a dose in excess of 100 mrem in N ghigh radiation area, one hour; and visible and audible g (4) In the case of a high radiation alarm signals shall be generated to ares established for a period of 30 make potentially affected individuals N g0 N days or less direct surveillance to pre-aware of the hazard and the licensee vent unauthorized entry may be sub-or at least one other individual, who is 4 stituted for the controls required by familiar with the activity and pre-paragraph (c)(2) of this section. pared to render or summon assistance. l (5) Any licensee, or applicant for a 11 Aware of the failure or removal of the f cense, may apply to the Commission physical barrier. When the shield for O q\\ l the stored source is a liquid, means s for approval of methods not included shall be provided to monitor the intes-8 in paragraphs (c)(2) and (4) of this sec, rity of the shield and to signal. auto-I tion for controlling access to high ra. '} matica11y. loss of adequate shielding. A I distion areas.The Commission will ap-Physical radiation barriers that com-S g i prove the proposed alternatives if the l licensee, or applicant demonstrates 'e -r,. i that the alternative methods of con- ' A I i g trol will prevent unauthorized entry l AF~ 7 g Into a high radiation tres, and that .This paragraph (ex6) does not apply to

N.

the requirement of paragraph (c)(3) of radioacttre sources that are used in tele- .g ,this section is met. therapy, in radiography. or in completely self. shielded irradiators in which the source C) In addition to the contents of - is both stored and operated within the same signs and labels prescribed in this sec 2 (6) Each area in which there may shelding radiation barrier and. in the de-tion, licensees may provide on or near 4 exist radiation levels in excess of 500 signed configuration of the trradiator. is always physically inaccessible to any indi-such signs and labeb any additionalErems in one hour at one meter from g information which may be appropriate

• sealed radio-active source 8 that is used tfon in an a I

a that a ble in aiding individuals to minimize expo-D irradiate matenals shalt 8 dirtdual. This paragraph tex 6) also does not sure to radiation or to radioactive ma-apply to sources from which the radiation is terial. - (i) Have each entrance or access incidental te some other use nor to nuclear (b) Radiction creas. Each radiation point equipped with entry control de. reactor generated radiation other than radi-area shall be conspicuously posted vices which shall function automati. atton from byproduct, source, or special nu-cl.ar materials that are used in sealed with a sign or signs bearing the radi-cally to prevent any individual frors. in ish ed lato ation caution symbol and the words: inadvertently entering the area when so,u such radiation levels exist: permit de-1978. Each person !! censed to conduct actis ' CAUT!oN* $ liberate entry into the area only after ties to which this paragraph (ex6) applies

a control device is actuated that shall and who is not in compliance with the provt.

RADIATION AREA = cause the radiation level within the siens of this paragraph on Mar. 14. 1978.

• area. from the sealed source, to be re-ahall file with the Director. Office of Nucle-(c) Nigh radiction 2 recs. (1) Each at Matertal safety and Safeguards. U.S. Nu-high radiation area shall be conspicu 7 duced below that at which it would be j

possible for an individual to receive a clear Regulatory Commission. Washington. D.C. 20555. on or before June 14.1978, in-ously posted with a sign or signs bear-dose in excess of 100 mrem in one formticn cesertbing in detail the actions ing the radiation caution symbol and hour; and prevent operation of the the words: source if the source would produce ra- [t l4. IN8 an t s parag ph by diation levels in the area that could mar continue acttrttles in conformance with CAMM, result in a dose to an indhidual in present license conditions and the provt-O excess of 100 mrem in one hour. The sions of the previously effective i 20.20s4 Hrcx RADtATIoM AREA entry control devices required by this until such compliance is achieved. For such paragraph (c)(6) shall be established persons compliance must be achieved not l ' Or " Danger" in such a way that no individual will later than Dec. 14.1978. be prevented from leavine the area. i September 1,1982 20-7 l l l

PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION prise permenent structural compo. - (7, Licensees with, or applicants for. CAtmon i nents, such as walls, that have no licenses for radiation sources that are A Ac MAnarAds) credible probability of failure or re-within the purview of paragraph (cx6) moval in ordinary circumstances need of this section, and that must be used : (2) Each area or room in which natu. , not meet the requirements of this in a variety of positions or in peculiar ; ral uranium or thorium is used or , paragraph (cx5X111). locations such as open fields or for. - stored in any amount exceeding one (iv) Be equipped with devices that ests, that make it impracticabte to f hundred times the quantity specified g will automatically generate visible and comply with certain requirements of *,. in Appendix C of this part shall be g

• audible alarm signals to alert person-paragraph (c)(6) of this section, such conspicuously posted with a sign or 7 nel in the area before the source can as those for the automatic control of s!gns bearing the radiation caution symbol and the words:

be put into operation and in sufficient radiation levels, may apply to the Di. time for any indhidual in the area to rector. Office of Nuclear Material a operate a clearly identified control 2 device which shall be installed in the ; Safety and Safeguards. U.S. Nuclear Regulatory Commission. Washington, area and which can prevent the source

• D.C. 20555. for approval. prior to use I. rom being put into operation.

of safety measures that are alternative CACTIoM '

~ to those specified in paragraph (c)(6) of this section, and that will provide at RAntoACTIVE MATERIAL (s) (v) Be controlled by use of such ad-least an equivalent degree of person-(f) Co tetners. (1) Except as pro-ministrative procedure and such de-nel protection in the use of such gg

vices as are necessary to assure that sources. At least one of the alternative each container of licensed mate-

the area is cleared of personnel prior measures must include an entry pre-tion' hall bear a durable, clearly visible rial s s to each use of the source preceding venting interlock control based on a label identifying the radioactive con-t which use it might have been possible physical measurement of radiation tents.

• for an mdividual to have entered the ( that assures the absence of high radi-ca.

ation levels before an individual can parag aph (f)(1) of this section shall gain access to an area where such bear the radiation caution symbol and '(vi) Be checked by a physical radi. sources are used. the words " CAUTION, RADIOAC-TIVE MATERIAL" or " DANGER. ation measurement to assure that j prior to the first individual's entry RADIOACTIVE MATERIAL". It shall into the area after any use of the ._ (d) Airborne rcdioactivity crecs. (1) also provide sufficient information 8 to source. the radiation level from the As used in the regulations in this part permit individuals handling or using source in the area is below that at " airborne radioactivity area" means (1) the containers, or working in the vicin-which it would be possible for an indi-any room, enclosure, or operating area ity thereof, to take precautions to vidual to receive a dose in excess of in which airborne radioactive materi. avoid or minimize exposures. l 100 mrem in one hour. als composed wholly or partly of 11 G) Notwithstanding the provisions (vii) Have entry control devices re* censed material exist in concentra. ; of paragraph (f)(1) of this section la.

quired in paragraph (ex6)(1) of this fled in Appendix B. Table I. Column 1 $ eling is not required

tions in excess of the amounts spect. - b a section which have been tested for (i) For containers that do not con-8 proper functioning prior to initial op-of this part; or (11) any room, enclo, e tain licensed materials in quantitles y eration with such source of radiation sure, or operating area in which air. ! greater than the applicable quantities on any day that operations are not un-borne radioactive material composed " listed in Appendix C of this part. Interruptedly continued from the pre

• wholly or partly of licensed material (11) For containers containing only vious day or before resummg oper-exists in concentrations which, aver-natural uranium or thorium in quanti-ations after any unintended interrup*

aged over the number of hours in any ties no greater than 10 times the app 11-tion. and for which records are kept of 2 cable quantities listed in Appendix C the dates, times, and results of such Week during which individuals are in of this part. tests of function. No operations other, the area. exceed 25 percent of the (111) For containers that do not con-amounts specified in Appendix B than those necessary to place the

• Table I. Column 1 of this part.

tain licensed materials in concentra-source in safe condition or to effect re 0 (2) Each airborne radioactivity area tions greater than the applicable con-paris on controls shall be conducted shall be conspicuously posted with a centrations listed in Appendix B. with such source unless control de. Table I. Column 2. of this part. sign or signs bearing the radiation cau-vices are functioning properly. The li-(iv) For containers when they are at-tion symbol and the words.

• tended by an individual who takes the censee shall submit an ac:eptable schedule for more complete periodic CAUTION precautions necessary to prevent the tests of the entry control and warr.Mg expcwre o' any 'ndividval to radiation systems to be established and adhered AlatoRNE RADtoACTIVITY ARI.A or radin.,actiVL materials in excess of the limits established by the regula-( 11 a

i se tr xit par. (e) Adefiter"Il requirements. (1) tals that are used in transport ng ma. Each area or room in which licensed tions in this part. terials to and f rotn tlu irra(lation ma erial is used or stored and which P (v) For coetairers wner ttey are ir. area, and that are not interded fo. use co mains any radioactive material 2 transpcrt se packaged and labeled in by ir3dividuals controlled by sucn de-(otner than natural uranium or thor $ accordance with regulation!. of the De-vice:r and administrative procedares as lum)in an amount exceeding 10 times partment cf Transportation. are necessary to physically protect and the 'lutntity of such material specified,* fvi) For conta"ters which are accer.s!- warn against inadvertent entry 3y any in Appendix C of this cart shal; be individual through suc!" portil.t Exit conspicuously posted with a sa;n or ble 8 only to inde.iduals authorized to portals for processed materials shall sigt.s bearing the radiation caution handle or use them, or to work in the be equipped to detect and signal the symbol and the words: I vietnity thereof provided that the con-presence of loose radiation sources $ tents are identified to such individuals ' Or " Danger". E by a readily available written record. that are carried toward such all exit ],appQpr t t e n (if!) Fcr manufacturing er process and to automatically prevent such loose sources from being carried out of timate of acurity, date for shich activity is [s equipment. such as nuc e estimated. mass ennehment, etc. reactor components, piping, and tanks. the area. September 1,1982 20-8

PART 20 o STANDARDS FOR PROTECTION AGAINST RADIATION 1 f (4) Each licensee shall, prior to dis-0 20.205 Procedures for picking up. receit-Tasts or Exswv aseo Typs A Ouasemas

posal of an empty uncontaminated ing, and opening packages.

O { container to unrestricted areas. (a)(1) Each licensee who expects to M*"%, .] M a remove or deface the radioactive mate-receive a package containing quanti-

amew

sas*** g* rial label or otherwise clearly indicate ties of radioactive materialin excess of g 8' } O that the container no longer contains the Type A quantitles specified in i Lmd osctive materials. paragraph (b) of this section shall: "g 8' 3 (1) If tha package is to be delivered ao to the licensee's facility by the carrier. v i ao make arrangements to receive the vi am' package when it is offered for delivery vu 5 20.204 Same: exceptions. by the carrier; or ao Notwithstanding the provisions of (11) If the package is to be picked up .rn. e ,i yes.no es.sas isan-t 20.203, by the licensee at the carrier's termi-em sseemse e i tu a me sassier [ be posted with a caution sign because (a) A room or area is not required to nal, make arrangements to receive no-9 tification from the carrier of the arriv* > [ Footnote i removed 49 FR 19623] E cf the presence of a sealed source r.ro. al of the package, at the time of arriv-

• vided the radiation level twelve inches al.

'i N from the surface of the source con-(2) Each IIcensee who picks up a (cx1) Each licensee. upon receipt of carrier,e of radioactive material from a a package containing quantities of ra-packar tainer or housing does not exceed five s terminal shall pick up the dioactive material in excess of the millirem per hour. n package expeditiously upon receipt of g Type A quantities specified in para- $ notification from the carrier of its ar g graph (b) of this section, other than - rival. = those transported by exclusive use ve-(b) Rooms or other areas in hospi- ! (bx1) Each licensee. upon receipt of f hicle, shall monitor the radiation tals are not required to be posted with caution signs, and control of entrance ga package of radioactive material. I levels external to the package. The shall monitor the external surfaces of or access thereto pursuant to the package for radioactive contaml* package shall be monitored as soon as i 20.203(c) is not required, because of nation caused by leakage of the radio-practicable after receipt, but no later than three hours after the package is p the presence of patients containing by-active conterits, except: received at the licensee's facility if re-gproduct maternal provided that there (1) Packages containing no more ,are personnel in attendance who will than the exempt quantity specified in ceived during the licensee's normal working hours. or 18 hours if received a take the precautions necessary to pre-the table in this pare. graph; A vent the exposure of any indhidual to after normal working hours. (11) Packages containing no more (2) If radiation levels are found on 3 radiation or radioactive material in excess of the Ilmits established in the than 10 mdlicuries of radioactive ma-the external surface of the package in terial consisting solely of tritium. excess of 200 millirem per hour, or at Mgu a ons in this part. carbon 14. sulfur.35 or lodine 125; three feet from the external surface of ~ (iii) Packages containing only radio-the package in excess of 10 millirem j (c) Caution signs are not required to form "" 7

• • I'***"

be posted at areas or rooms containing the neensee shall immediate-radioactive materials for periods of (iv) Packages containing only radio-S ly notify by telephone and telegraph less than eight hours provided that (1) active material in other than liquid form (including Mo-99/Tc 99m gener-{ mailgrun, or facsimile the director of 4 the materials are constantly attended the appropriate NRC Regional Office ) during such periods by an indhidual stors) and not exceeding the Type Am, listed in Appendix D and the final de- + who shall take the precautions neces, quantity limit specified in the table in; livering carrier. g

• sary to prevent the exposure of any in.

this paragraph; and 6 f dividual to radiation or radioactive (v) Packages containing only radion-materials in excess of the limits estab-uc!! des with halflives of less than 30 (d) Each licensee shall establish and lished in the regulations in this part days and a total quantity of no more maintain procedures for safely open-and; (2) such area or room is subject to than 100 millicuries. R int packages in which IIcensed materi- ,the licensee's control. R al is received. and shall assure that tom call be perfumed as soon as practicable after receipt, buts such procedures are followed and that the due consideration is given to special m no later than three hours after.a faSA instructions for the type of package (d) A room or other area is not re-package is received at the licensee quireti to be posted with a caution sign. and control is not required for cility if received during the licensee s[ being opened. N each entrance or access point to a normal working hours, or eighteen E roem or other area which is a high ra. hours if received after normal workingp

• diation area solely because of the pres

hours, i 20.206 Instruction of personnel.

g 4 ence of radioactive materials prepared for transport and packaged and la-(2) If removable radioactive contami g Instructions required for individuals beled in sccordance with regulations working in or frequenting any portion of the Department of Transportation. nation in excess of 0.01 microcuriesf of a restricted area r,ra specified in (22.000 disintegrations per minute) perg i 19.12 of this chapter. 100 square centimeters of package sur.L

face is found on the external surfacts 3 of the package, the licensee shall im.

I 20.207 Storage and control of licensed I

mediately notify the final delivering

interieb in unrestricted areas. carrier and, by telephone and tele g a g (a) Licensed materials stored in an

graph, mailtram or facsimile, the sp M unrestricted area shall be secured propriate Nuclear Regulatory Com e from unauthorned removal from the Tor example. containers m locations such ster.nlled canals. storsse vaults, or hot mission Inspection and Enforcement' p* ace of storage I

Regional Office shown in Appendix Dl(b) Licensed hnaterials in an unres-of this part. trfeted area and not in storage shall be. I 20 4 May 3t 1984 t i a ,cr.c .---_n--- -,, - - ~- .---c. -,---n,-.--, ,+w--

PART 20 o STANDARDS FOR SROTECTION AGAINST RADIATION f (b)The Commission will not approve (a) 0.05 microcuries or less of hidro-tended under the constant survell-

• any application for a license for dis-gen-3 or carbon 14 per gram of lance and immediate control of the 11-i posal of licensed material at set unless medium, used for liquid scintillation censee.
• the applicant shows that sea disposal counting; and f offers less harm to man or the envi-(b) 0.05 microcuries or less of hydro-

- ronment than other practical alterna-gen.3 or carbon.14. per gram of animal % sTE DISPOSAL tive methods of disposal. tissue averaged over the weight of the I 20.301 General requirement. entire animal. provided however, tissue may not be disposed of under No licensee shall dispose of licensed

• this section in a manner that would material except:

2 permit its use either as food for (a) By transfer to an authorized re. humans or as animal feed. cipient as provided in the regulations 5 20.303 Disposal by release nto sanitary a

• in Parts 30,40.60. 61. 70 or 72 of this sewerage systems.

0 of M E& chapter, whichever may be applicable: No licensee shall discharge licensed cords showing the receipt, transfer 7 Of material into a sanitary sewerage and disposal of such byproduct materi-system unless; al as specified in j 30.51 of this chapter; O (a) It is readily soluble or dispersible and (d) Nothing in this section relieves ( e 4 antity of any licensed or the licensee from complying with (b) As authorized under i 20.302 or other radioactive material released other appucable Federal. State and Part 61 of this chaoten or into the yste b) e

e. ee ee } )ar er o local regulations governing any other paragraphs (b)(1) or (2) of this section.

toxic or hazardous property of these (1) The quantity which. if diluted by ,, materials. I(c) As provided in 120.303, applica. s the average daily.;uantity of sewage I ble to the disposal of licensed material $ released into the sewer by the licensee.

• by release into sanitary seserage sys-e will result in an average concentration

$ 20.311 Transfer for disposal and "" tems, or in i 20.306 for disposal of spe, a equal to the limits specified in Appen-manifesta. I cific wastes, or in i 20.106 (Radioactiv g dix B. Table I. Column 2 of this part: (a) Purpose. The requirements of this

• lty in effluent.s to unrestricted areas).

or section are designed to control transfers ( (2) Ten times the quantity of such of radioactive waste intended for material specified in Appendix C of disposal at a land disposal facility and this part; and establish a manifest tracking system and 9 20.30: Method for obtaining approval of (c) The quantity of any licensed or supplement existing requirements proposed disposal procedures. other radioactive material released in conceming transfers and recordkeeping any ne month, if dHuted by the aur-for such wastes.%e reporting and (a) Any licensee or applicant for a 11-c;nse may apply to the Commission ",8 recordkeeping requirements contained ed b 1 cense w not res for approval of proposed procedures to in this section have been approved by in an average concentration exceeding dispose of licensed material in a the limits specified in Appendix B. the Office of Management and Budget: manner not otherwise authorized in Table I. Column 2 of this part; and OMB approval No. 3150-0014. the regulations in this chapter. Each (b] Each shipment of radioactive application should include a descrip-waste to a licensed land disposal facility tion of the licensed material and any must be accompanied by a shipment

other radioactive material involved, in.

(d) The gross quantity of licensed manifest that contains the name. ~ cluding the quantities and kinds of and other radioactive material, exclud-address and telephone number of the i such material and the levels of radio-ing hydrogen 3 and carbon-14, relea. sed ; person g,enerating the waste.%e . activity intolved, and the proposcd into the sewerage system by the licens : manifest shall also include the name. " manner and conditions of disposal. ee does not exceed one curie per year.$ address.and telephonenumberorthe The application should also include an The quantities of hydrogen 3 and u name and EPA hazardous waste analysis and evaluation of pertinent information as to the nature of the en* carbon-14 released into the sanitary 0 identification number of the person sewerage system may not exceed 5 transporting the waste to the land vironment. including topographical. curies per year for hydrogen 3 and 1 disposal facility. %e manifest must also geological, meteorological, and hydro-curie per year for carbon-14. Excreta indicate as completely as practica e: a logical characteristics: usage of ground from individuals undergoing medical and surface waters in the general area; diagnosis or therapy with radioactive physical description of the waste; the the nature and location of other po-Z material shall be exempt from any volume: redionuclide ldentity and tentially affected facilities: and proce* 2 limitations contained in this section. quantity: the total radioactivity and the dures to be observed to minimize the principal chemical form.he e risk of unexpected or hazardous expo-solidification agent must be specified. sures. 3 f 20.305 Treatment or disposal by inciner* Waste containing more than 0.1% chelatfag sgents by weight must be

• • k"*

identified and the weight percentage of No licensee shall treat or dispose of the chelating agent estimated. Wastes licensed material by incineration classifitt as Clu;s A. Chas B, oc Class except for materials listed under C in i 61.55 of this chapter must be i 20.306 or as specifically approved by clearlyidentifieel as such to the the Commission pursuant to n anifast.Le totalquantity of the il 20.106(b) and 20.302. radic nuclides H-3. 0-14. To-99 and I-129 must be shown.The manifest 6 20.306 Disposal of specific wastes. required by this paragraph may be Any licensee may dispose of the fol* shipping papers used to meet lo ving licensed material without Department of Transportation or regard to its radioactivity: O February 28,1983(reset) 2M (next page is 201can l

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION Environmental Protecdon Agency (1) Acknowledge receipt of the waste equivalent documentation by the i

regulations or requirements of the from the generator within one week of collector: receiver,provided aD the required receipt by returning a signed copy of the (7) Include the new manifat with the information is included. Copies of manifest or equivalent documentation: sh:pment: manifests required by this section may (2) Prepare a new manifest to redect (a) Retain copies of original manifests belegible carbon copies orlegible consolidated shipments: the new and new manifests and documentation manifest shall serve as a listing or index of acknowledgement of receipt as the "-~ (c) Each manifest mustinclude a for the detailed generator mamfests. record of transfer oflicensed material certi8 cation by the waste generator that Copies of the generator manifests shall required by Parts 30,40, and 70 of this the transported materials are properly be a part of the new manifest.De waste chapter; and classineo, described. packaged, marked. collector may prepe s a new manifest (9) For any shipment or part of a and labeled and are la proper condition without attaching the generefor shipment for which acknowledgement is for transportation according to the manifests, provided the new manifest not received within the times set forth in applicable regulations of the contains for each package the this actim caduct an lam 4adon in Department of Transportation and the information specified in paragraph (b) of accadance wah paragraph (b) d &is r a==laaton. An authorised this section.no collector licensee shall secu m i reptuentative of the waste ter certify that nothing has been done to the sh{ne land Apaa=I facility operator shan sign and date the==ai waste which wouldinvalidate the (d) Any generatinglicenses who generator's cert 1Rcation: I ACh**" mce g t transfers radioactive weste to a land (3) Forward a copy of the new d f b m udem w facility or a Bcensed weste manifest to the land disposal facility

• '[g'$Qeuum h h or sha!! comply with the operator at the time of shipment; y

.Ib shippw to b nd8d is se requirements in paragraphs (d)(1) (4) Include the new manifest with the BC* *' e tan md h mu through (8) of this section. Any shipment to the disposal site: generating licensee who transfers waste (5) Retain a copy of the manifest and , d huf.urd & uab

• peg,#Ikstured d &e to s licensed we ste processor who treats documentation of acknowl ment of g or equivalent tation or speckaps wsste shad comply with receipt as the record of trans er of the 3::e s of paregraphs (dX4) licensed material as required by Parts between materiabusempedu shan h u u m a Hoted on the manifest (s) c 2s section. A licensee

,. 30,40, and 70 of this chapter. and retain

haB

j information from generator manifests

g g,,g

s j ma(2WalMain copies d au compted 7,[N*

E E ndests or equivalent documentation ' wa(1) Prepare all wastes so that the

• unta se Cauninsa aMm &eir ste is classified according to I e1.55 (e)For any shipments or any part of a

- and meets the waste characteristics

shipmentforwhichacknowledgementof ; espoeldon;and I3 * "I requimments in i 31.50 of this chapter.

receipt is not received within the times E ctor. # p'm' muw) (2) Label each package of weste to "' forth in thi' "Cti "*

• nduct **

genW.

• c O

and the Director of the nearest identify whetheritis Class A waste innstigationin accadance wie Commission Regional OfBcelisted in Class B waste, or Class C weste,in p8r88Faph (h) of this sectim Appendix D of this part when any accordance with l 61.55 of this chapter; (f) Any hcen wasu proc rw o (3) Conduct a quality contml program shipment or part of a shipment has not "*'$o$ ledge """#.ed wh 60 days ak se adunce '"5' to assure compliance with Il St.55 and )A i of the weste """""**I" e1.56 of this chapter. the program must from the generator within one week of [h) Any shipment or'part of a include management evaluation of receipt by returning a signed copy o.'the shipment for which acknowledgement is g (4) Prepare shipping manifests to meet ( ) Pmpam a new manifat e"st muts not received within the times set forth in this section. must: the requirements cf Il 20.311 (b) and (c) the requirements of parsgraphs (b) and (1) Be investigated by the shipperif g gg (c) this wetim Puparation of the the shipper has not received notiAcation (5) Forward a copy of the manifest to i the intended recipient. at the time of N, 'w,* pmcas" of mceipt within 20 days after transfer: shipment: or, dehver to a collector at the (3) Prepare all wastes so that the es u enje weste is classified according to I 61.55 (2) Be traced and reported no o ta of a siped copy of the manifest or and muts the was.s charactoriencs invutigation shad include tradag the "luivalent documentadon fmm de requirements in i 61.36 of this chapter: shipment and Bling a report with the (4) Label each package of waste to nearest Ceaunission Regional OfRce couecton identify whether it is Class A waste. listed in Appendix D of this part. Each (6) Include one copy of the manifest Ctes: B waste. or Class C waste,in licemees who conducts a trees wis hiPm accordance with il 81.55 and 81J7 of investigettort shau S!e a witten report (?) n PY this chapter: with h semed t'wadon's Regional documentation of acknowled ement of (5) Conduct 's quality control prog *am WRce wt&ta g weeks d compInnes d mceipt as the record of trans er of to assure compliance with Il 8135 and b licensed material as required by Parts 61.5s of this chapter. The program shah 30,40, and 70 of this chapter; and, include management evaluation of (8) For ariy shipments or say part of a audits: shipment for which acknowledgement of (6) Forward a copyof the new receipt has not been rece!ved within the manifesi to b disposal sita operator or times set forth in this section, conduct waste collector at the time of shipment. an investigation in accordance with or deliver to a collector at the time the paragraph (h)of this section. weste is collected, obtaining (e) Any waste collectorlicensee who acknowledgement of receipt in the form handles only prepackaged weste sha!!: of a signed copy of the manifest or 2010a December 30,1982 tnext page is :010 b)

s PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION

.l I 20.401 Records of surveys, radiation monitoring, and disposal (a) Each licensee sh&Il maintain re-cords showing the radiation exposures of all individuals for whom personnel monitoring is required under i 20.202 g of the regulations in this part. Such records shall be kept on Form NRC-5, ) g in accordance with the instructions m IQ contained in that form or on clear and legible records containing all the in-formation required by Form NRC-5. The doses entered on the forms or re-cords shall be for periods of time not exceeding one calendar quarter.' (b) Each licensee shall maintain ,. records in the same units used in this

• part, showing the results of surveys O required by i 20.201(b). monitoring f required by Il 20.205(b) and 20.J)6(c),

and disposals made under il 20L302. 20.303, removed i 20.304,8 and Part et of this chapter. O (c)(1) Records of individual exposure to radiation and to radioactive materi-al which must be maintained pursuant to the provisions of paragraph (a) of this section and records of bioassays. Including results of whole body count-ing examinations, made pursuant to i 20.108, shall be preserved until the g Commission authorizes disposition. (2) Records of the results of starveys E and monitoring which must be main- - tained pursuant to paragraph (b) of

• this section shall be preserved for two years after completion of the survey except that the following records shall be maintained until the Commission authorizes their disposition: (i) Re-cords of the results of surveys to de-termine compliance with 120.103(a);

(11) indhe atsence of per:orgiel moni-tortyg data, records of the results of sutTeys to determine external radi-ation dose; and (iii) records of the re-sults of surveys used to evaluate the release of radioactive effluents to the j er.vironment. 01 December 30,1982 2010b 1 (next page is 201 t) )

PART 20 o STANDARDS FOR PROTECTION AGAINST RADIATION exposures occurred, and the extent of [ 1 (3) Records of disposal of ficensed uals, circumstances under which the (b) 7kenty.fourhour notification. Each licensee shall within 24 hours of

• materials made persuant to il 30.302, O

1 2 30.303. removed i 20.304.8 and Part et of possible hazard to persons in unres* 2 discovery of the event. report any event tricted areas; e involving licensed material possessed = this chapter are to be maintained until &e Conunission authorizes heir by the licensee that may have caused or j or all ta en. r of r em e 'g, disposition. al; and I,., threatens to cause: (6) Procedures or measures which ~ Records which must be main-have been or will be adopted to pre r- (1) Exposure of the whole body of (4) tained pursuant to this part may be a i any individual to 5 rems or more of ra-the original or a reproduced copy or m yt a re urrence of the loss or theft d h 2 of h microform if such reproduced copy or (c) Subsequent to' filing the written whole body of any individual to 30 microform is duly authenticated by report the licensee shall also report res or more of radiation; or exposure authorized personnel and the micro-any substantive additional informa. N of the feet ankles, hands, or forearms I , form is capable of producing a clear tion on the loss or theft which be. y to 75 rems or more of radiation; or g and legible copy after storage for the comes available to the licensee, within m. (2) The release of radioacti.e materi-period specified by Commission regu-30 days after he learns of such infor. R alin concentrations which. If averaged a lations. mation. over a period of 24 hours, would

• (5) If there is a conflict between the (d) Any report filed with the Com-exceed 500 times the limits specified

,= Commission's regulations in this part. mission pursuant to this section shall for such materials in Appendix B. license condition, or technical specifi-be so prepared that names of individ. Table II of this part; or cation, or other written Committion uals who may have received exposure (3) A loss of one day or more of the approval or authorization pertaining to radiation are stated in a separate operation of any facilities affected; or to the retention period for the same part of the report. type of record, the retention period " (e) For holders of an operating license ; J-specified in the regulations in this (4) Damage to property in excess of part for such records shall apply for a nuclear power plant, the events

32.000.

unless the Commission pursuant to included in paragraph (b) of this section g l 20.501. has granted a specific exemp-must be reported in accordance with the tion from the record retention require-pir,sa.4 described in i 50.73 (b), (c). L ments specified in the regulations in (d). (e) and (g) of this chapter and must l- (c) Any report filed with the Com- .this part. include the information required in 2 mission pursuant to this section shall 120.402 Reports of twt or lose W Paragraph (b) of this section. Events 3 be prepared so that names of individ-noensed metertat. reported in accordance with 150.73 of - a uals who have* received exposure to ra. (a)(1) Each licensee shall report to the this chapter need not be reported by a

• distion will be stated in a separate Commission. by telephone. immediately g duplicate report under paragraph (b) of

{ part of the report. this action. afterit determines that a loss or theft of 2 . (d) Reports made by licensees in licensed material has occurred in such

• Isaaes asessesseneWincidenen, response to the requirements of this i

quantities and under such circumstances section must be made as follows: (a)Imad/We nWi#cW/on. Each that it appears to the licenses that a = Ucensee shan immediately report any (1)IJcensees that have an installed pans events involving byproduct. source, or Emergency Notification System shall et area make the reports required by paragraphs (2) Reports must be made as follows: special nuclear material possessed by a g the ucensee that may have caused or 2 (a) and (b) of this section to the NRC (i)1.!censees having an installed , Emergency Noti 8 cation System shall

• threatens to cause:

2 Operatior, Centerin accordance with (1) Exposure of the whole body of z i 50J2 of this chapter. u. = make the reports to the NRC Operations any individual to 25 rems or more of I (2) All other licensees shall make the Center in accordance with 150.72 of this radiation; exposure of the skin of the ' reports required by paragraphs (a) and

chapter, whole body of any individual of 150 (b) of this section by telephone and by (ii) All other licensees shall make rems or more or radiation; or exposure telegram, mailgram, or facsimile to the reports to the Administrator of the of the feet, ankles, hands or forearms Administrator of the appropriate NRC appropriate NRC Regional Office listed of any individual to 375 rems or more Regional Office listed in Appendix D of in Appendix D of this part.

, af radiation: or e. (2)The release of radioactive materi- -this part. (b) Each licensee who makes a report under paragraph (a) of this section shall. 3 alin concentrations which. If averaged l 5 20.404 (Reserved) i 1 within 30 days afterleaming of the loos over a period of 24 hours, would or theft, make a re rt in writing to the exceed 5.000 times the limits specified I so.40s Reports of everespesures and t U.S. Nuclear R tory Commission, for such materials in Appendix B. escesolve leveis and oeneeneremone. Documert Control Desk. Waehington. Table II of this part: or (a)(1) !n addition to any notification D.r120555. with a copy to the (3) A loss of one working week or required by 120.403 of this part, each appropriate NRC Regional Office listed more of the operation of any facilities licensee shall make a report in writing in Appendix D of this part.The report . affected; or o concoming any one of the following ,st allinclude the following information: g-g types ofincidents within 30 days of its occurrence [ (1) A description of the licersed ma* b (4) Damage to property in exce;.s of f (i) Each exposure of an individual to g A 00 m.

• radiation in excess of the applicable I

I y c emi 1. ph a 1 f rm: f (2) A description of the circum ; limits in il 20.101 or 20.104(a) of this E part, or the licence: $ stances under which the loss or theft occurred: (ii) Each exposure of an individual to a (3) A statement of disposition or radioactive materialln excess of the probable disposition of the licensed applicable limits in ii 20.103(a)(1). O materialinvolved: 20.103(a)(2), or 20.104(b) of t'us part, or (4) Radiation exposures to indhid-in the license: 2081 May 31,1984 (reset)

1 i PART 20 o STANDARDS FOR_ PROTECTION AGAl.NST RADIATION (iii) Levels of radiation or with the procedures described in year was in each of the following esti-concentrations of radioactive material in paragraphs 50.73 (b). (c) (d). (e), and (g) mated exposut e ranges: a restricted area in excess of any other of this chapter and must also include the cpplicable limit in the license: g Information required by paragrapha (a) we.,, (iv) Any incident for which and (c) of this section. Incidents v.-se

• 0;*lll',,*

notification is required by 120.403 of reported in accordance with I 5053 of a this part; or [ this chapter need not be reported by a no,anw.o. noow. i. (v) Levels of radiation or . duplicate report under paragraphs (a) or

• • waa* "powe ***
• o i ---- +

concentrations of radioactive material

• (c) of this section.

Us's oI 1 (whither or not involving excessive (e) All otherlicensees who make o s e a rs i exposure of any individual)in an reports under paragraphs (a) or (c) of

o rs = i

__a

• J unrestricted area in excess of ten times this section shall, within 30 days after j M'_

2 any applicable limit set forth in this part tearning of the overexposure or a s to a I cr in the license, excessive level or concentration make a ', Q s 4 a E (2) Each report required under report in writing to the U.S. Nuclear "s.7 _ _ 4 3 p;ragraph (a)(1) of this section must Regulatory Commission. Document r to e - - - disenbe the extent of exposure of Control Desk. Washington. D.C. 20555. individuals to radiation or to radioactive with a copy to the appropriate NRC ,o io,i m.tirial. Inclu: ling. Regional Office listed in Appendix D of si to ir (i) Estimates of each individual's _ this part. cxposure as required by paragraph (b) ++ew.===== as=ewawswaarsuas a "8'w'*a'"**********'**S'*'*a9* of this section: [ii) Levels of radiation and j I 20.406 [ Reserved) concentrations of radioactive material f (,uired in order to obtain better infor-inv:lved: rnation about the exposures actually a (iii)The cause of the exposure levels recorded. This section does not require or c ncentrations: and % 20.407 Personnel moMoring reporta. improved measurements. (iv) Corrective steps taken or planned Each person desenbed in i 20.408 of 2 20.408 Reports of personnel momtonnt _ts prevent a recurrence. this part shall, within the first quarter of o on termination of employment or (c) Any report filed with the Com ;; each calendar year, submit to the

• g mission pursuant to paragraph (a) of ;$ Director. Office of Nuclear Regulatory (a) This section applies to each

, this section shallinclude for each indi 2 Research.U.S. Nuclear Regulatory person licensed by the Commisnon to:

vidual exposed the name, social secu ; Commission. Washington.DC 20555.the (1) Operate a nuclear reactor de-i rity number, and date of birth, and an r po pecifie, d in paragraphs (a) and z estimate of the individual's exposure.

(} . s section, covermg e preceding calendar year. ', The report shall be prepared so that cility as defined in i 50.2(r) of this this information is stated in a separate { part of the report. ~ (a) A report of either (1) the total 2 ssess or use byproduct materi-(c)(1)!n addition to anY notificat number of individuals for whom per-required by 120.403 of this part each sonnel monitoring was required under al for purposes of radiography pursu-ant to Parts 30 and 34 of this chapter, i 20.202(a) or i 34.33(a) of this chapter _- licinsee shall make a report in writing of during the calendar year; or (2) the (3) Possess or use at any one time, 12v11s of radiation or releases of t tal number of individuals for whom for purposes of fuel processing fabri-radioactive material in excess of limits pe nnel monitoring was provided cating, or reprocessing, special nuclear ecified by 40 CFR Part 190 " Environmental Radiation Protection C**** tcr h su h to in I d s at Sttndards for Nuclear Power least the number of individuals re E II**' nium- .w nMm a any mmW Operations." or in excess of license quired to be reported under paragraph e na n merd pumant 2 M M of conditions related to compliance with 40 (a)(1) of this section. The report shall 6 indicate whether it is submitted in ac- ; this chapter. CFR Part 190. (4) Possess high level radioactive (2) Each report submitted under 3 cordance with paragraph (a)(1) or of this section. If personnel waste at a geologic repository oper-o p r: graph (c)(1) of this section must E (a)(2) O d:scnbe: monitoring was not required to be pro, ations area pursuant to Part 60 of this (i) The extent of exposure of

vided to any mdividual by the !!censee _ chepter, or a

• individuals to radiation or to radioactive under il 20.202(a) or 34.33(a) of this

- (5) Possess spent fuel in an inde. e mitirial: chapter during the calenda' year, the pendent spent fuel storage installation (ii) Levels of radiation and licensee shall subrait a negative report (ISFSI) pursuant to Part 72 of this I co 1Mntations ef tadicadive materni indicating that such personnel moni- ; chapter.or involved; toring was not requaed. 2 (6) Possess or use at any one time. (iii) The cause of the exposure. levels, fw pessm w hMW M the perso el n toring in a 10 recorded by the licensee for individ,. distribution pursuant to Parts 30, 32 or cnneentrations; and uals for whom personnel monitoring l or 33 of this Charter, byproduct mate-(iv) Corrective steps taken or planned rial in quantit es exceeding any one of t3 cssure against a recurrence, including was either required or provided, as de-t! e schedule for achieving conformance scribed la parahrapti (a) of this sec I the following quantitles: with 40 CFR Part 190 and with tion. indicating the number of indNid-associated license conditions. uals whose total whole body exposure ' A !!censee whose license expires or termi. (d) For holders of an operating license recorded during the previous calendar nates prior to, or on the last day of the cal-f;r a nuclear power plant, the incidents encar year, sbau submt reporta at the expi. no h o included in paragraphs (a) or (c) of this ' A hcenne whon hcense expires or tennmetes y ',*g". thp, d'Y 'I th' C*j"d*'((,w secti:n must be reported in accordance license was in effect. of the hcense covenns that part of the year dur.ng which the bcense was in effect. June 29,1984 2N2

[ PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION I 20.409 Notifications and reports to indi-viduals.

(a) Requirements for notifications , g and reports to individuals of exposure ,37 c so , g to radiation or radioactive material are

hise ico a specified in i 19.13 of this chapter.

e ** '3' (b) When a licensee is requirtd pur- "; fM ,y " suant to il 20.405 or 20.408 to report w w ur io to the Commission any exposure of an Tem '.000 individual to radiation or radioactive material, the !!censee shall also notify em e.eman or ame un mano e ao sca. sim e.,a the individual. Such notice shall be yg*jg=g gg transmitted at a time not later than the transmittal to the Commission. and shall comply with the provisions of i 19.13(a) of this chapter. ExczrrIONs ann AnorrioNAL Rzeernenmers 3 (y) Receive radioact ve waste frees ' other persona for disposal under Part 81 8 20.501 Applications for exemptions. ! of this hotar. The Commission may, upon applica. tion by any licensee or upon its own ~ [ . initiative, grant such exemptions from

the requirements of the regulations in

• this part as it determines are author-E ised by law and will not result in

>(b) When an individual terminates '. undue hazard to life or property. employment with a licensee dese.ribed in a paragraph (a) of this section, or an 5 20.502 Additional requirements. individual assigned to work in such a The Comrntazion may, by rule, regu-licensee's facility, but not employed by lation, or order, impose upon any 11-the licensee, completes the work censee such requirements, in addition / assignment in the licensee's facility, the to those established in the regulations \\ licensee shall furnish to the Director. in this part, as it deems appropriate or Office of Nuclear Regulatory Research. necessary to protect health or to mini-g U.S. Nuclear Regulatory Commission. mize danger to life or property.

Washington, DC 20555. a report of the a individual's exposures to radiation and EwroncruzNT E radioactive material, incurred during the g period of employment or work 1 20.601 Violations.

assignment in the licensee s facility, ~ containing information recorded by the An injunction or other court order h:ensee pursuant to il 20.401(a) and may be obtained prohibiting any viola. 20.10s. Such report shall be furnished tion of any provision of the Atomic within 30 days after the exposure of the Energy Act of N. as amended, or individualhas been determined b the Title II of the Energy Reorganization Y Act of 1974. or any regulation or order Ikensee or 90 days after the date of issued thereunder. A court order may termination of employm,ent or work . be obtained for the payment cf a civil assignment, whichever is earlier. O penalty imposed pursuant to section a 234 of the Act for violation of section 6 53.57.6L 63.81.82.101.103.104.107

• or 109 of the Act, or section 206 of the Energy Reorganization Act of 1974. or any rule re'gulation, or order tasued thereunder, or any term, condition, or limitation of any license issued there.

) under, or for any violation for which a i license may be revoked under section 186 of the Act. Any person who will-fully violates any provision of the Act or any regulation or order issued thereunder may be guilty of a crime and, upon conviction, may be punished by fine or imprisonment or both, as 8The Commission will evaluate the data provided by law. obtamed for 1978 and 1979 pursuant to this '- O% paragraph and the benefits derived there-from and may take action, includir.g publi. [ Note removed 49 FR 19623] cation of notice of proposed rulemaking, to extend or otherwise modify this reporting requirement. 20 13 June 29,198

e PART 20 o STANDARDS FOR PROTECTION AGAINST RADIATION e e Apposoot A4.mem FActons Pon Maareutons e piumme amusse Dessenst

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• N ans

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==e magm sa a e se m m = ew m e m assin amo.r.,s emeen.e sde on eeM cese== Eme e.s .em.e= un. essa e. en se _ _ _ _ _ _. =essrenne a messess er sus to peesus e me emmy es emner manes e emmenans em amonw hsa em a ssi en en sus se. mas en emme esseumat e s. pume es. erw seyesiwwe su e=== m amesasa e meneena emmes se ease ames asynensee, se a,us a se eens amese or, eswamme se sms e eues asuu e see t en a een ew a e espumum we __, __ __ a pen.co em,e. e enma i e. = amese ami suensa esw e se sw messen use = ease amm o emes i t. sw =.sy=====as se ee e s me emeca suoces es== es e=s= ese e mas e e as saaneese== ao easme e peamm esse eman amma see ame esse e g ass== e nam 6 u' cowne..e spenses sus== es. mas _ anam 7mme t. w enamnee emmes e ese any m = nu ivue e veerums a ime =ne emawww .emas Y.s si e w = em senemme ees se amme I"'*=*e er ime wwe a nenes en osemann e e masse e a==ye, see o eman er en ene== eses e _ _ __ om se ones su t e asse=sm e amo ese ou e a esem ses Tras syse e eussenes e as mamme er & sown saarea. e es.a. ammes,===.e.,.a.s.s.,e ese e e mes aus as

====s ew ye re y=mma se e==w a remes.es co a mesmaw w en es=<een e enga.e.=e,m a e se awe men seso me, es ines er - =.e see e m =m - a mamme wea me e es. e awares ou em.enes eroe summa

==emseg es ess se imme a pe e ens e mm.s e e. es =m menww a se. wase, ore _ _ me e een m eses e4 emerenes erwe rammaeManes e amam e ese e an, ese me was sum s.e u.ne.a % emm 1 smusaw== e.n e e= ness ae e e== W asi as, merou an e er ew essee ayer arm as esmeros es== nwg e amme a amen, ens mesens, es ou emess emme oms e

== aseme=+ema ?>= mesume eu se - _ e e enen essee erwena en en mme. e

==== or===amme wee a mammpases een en se sempi su o se=sene, een,e som. e se e unwwe e== esenee e em no e'esime e.s.em.a.n.n ausse su.s to eswaeus emme sesaama eseg een enum,e ou may e me na s.e amm o s.e.e.senwee eine asianse e uma thee sus sepomm e e masas e emovenaeus==ews answuma ewww eesamen man .a omesse eneasseseacwe,messe=enamen=samar=sw = _____as. = sus ne =am ) se es e m.e.e a.amme-mee oes.u.s, ease womesa su se =em se me'=een>a=m,=emme me er eseg e e ee amas e a m

== en a= e y e eurow enameneemme = pm cme eenne senseen messes asen w.memass amusen i e es eue a uma emeew mae a meme en emme.=.e.m.eann.e em,permares messes semens a _ses en sewa=s e ese eenmas we as an e sw a nase se.eemes emin %.=es.e e i amass e ens as es non e eserna _ es e is, e aseme e==4 m sw en a me irse e so.m.een sus e, l emance apes se se .e ees== = sies ne yeen e

• *=macem enes = sine se som er eseemen a amme emme Nees L-440tecten facture for respirators.

as may be approved by the U18erves af Enes/NanomalInsutets foe Occupathanal Setery and Health (MOSH) according to apphcable approvals for respitators nor type and mode of use to protect against airborne radionmettdee, may be used to the extent that they de not exceed t.be protecnon factore listed in this table. The protect 1aa facture listed am time table may not be appropriate ne circumaammens e4ere cheencal or other respiratory hasards aust in add tion to radiological hazards. The selection and use of respirators for these circurretances should take into account appucabo approvels of the UA Bureas of Mines /NMS.L Neen.3 Jtachoecove conimminmats for which the coecenirsuos values in Table t column 1. Appendus 8 of this part are based on internal dose due to inhalation may, in addinon. present external exposure hazards at lusher concantre tions. Under these circumstances. liautat ons on occupancy immy have to be governed by external dose hauts. December 30,1982(reset) 2044

e PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION i ~ APP 80001I B Comessouslene he Air and Weser Abese lesserol Sesegreemd (See notes at and of accenes] tabas I t.mse a esme.s (esemie seem.ori lease,. 8 c one i celeme 2 cei c.le 2 Air Weser Air Weser t (u i/ml)(uci/ml)(u t/ml>(pci/ml) c c A.sa a m (09)... Ae 227 3 2 x10"8 e x10*s 8 x10*'* 2 x10** e 8 3 x 10-" 9 x10-s 9 x10 -is 3 x 10-* Ae 220 8x10-e 3 x10-8 3 x10-' 9 x10-s 1 2 x t0** 3 x10-s 4 x10~ " 9 x10-8 Amarteleen (99)....... Am 241 5 6 x 10*'8 1 x10-8 2 x10-es 4 x101 e1 1x10** 8 x10** 4 x10'en 3 x10 s ,2 x IO*is ,e x30-8 Ami 242m 5 6 x 10*'8 1 x 10-* 4 3x10-8 3 x10-s x ig-is xig-s Am 242 S 4 x 10** 4 x 10-8 1 x10-' 1 x10-8 1 1 3 x 10-' 4 x10-8 2 x10-' 1 x10*s Am 243 e x10-'8 l x 10-* 2 xlo os 4 x yg-e i Ixl0-* 8 x 10** 4 x tens 3 x10-s Am 344 5 4 x 10** f x 10-' l x t0*F 3 xl0*8 1 2 x10*8 1 x 10-8 8x10*F 5 x 10-s ensomeeev (31).. Sb 122 5 2 x 10-7 8 x10-8 4 x 10-' 2 x10-8 1 1 xlO-' 8 x10-8 3 x t0-' 3 xlC-s f h Sb 124 5 2 x10*F 7 x10** 3 x 10 2x10-s g i 2 x 10** 7 x 10** 7x10-* 2 x10-a 58-Sh123 5 5 x10-' 3 x10-8 2 x 10-' I x 10-* 1 3 x10-8 3 x10-s 9 x 10-* I x10-8 i A 37 Seb8 e x10*8 1 x10** l Areen (18)... A 41 Sob 2 x 10-* 7 x 10-' S x 10** Areenie (32)..... As 13 2 x 10** . 1 x10-8... 4 x10-e I 4 x 10-7 1 x10-8 I x10-e 3 x 10 ** As74 8 3 x 10 2 x10-s 1 x10-8 3x10-s i i ix10*' 2 xIO-s 4 x 10-' 3 x10*8 As 74 S 1x10*' e x 10** 4 x 10 2 x10's i 1xIO*F ex10-8 3 x IO*' 2 x 10-s As 77 5x10*' 2x10-s 2 x 10-8 4 x10-s l I 4x10-F 2 x 10-s 1 x10-8 8x10-s Assesene (SS).. At211 5 7 x 10-' 3 x10-s 2 x 10** 2 x le** I 3 x 10** 2 x 10*8 1 x 10*' 7 x 10-s Seriom (54)... Se 131 S l x 10** 3 xte-s 4 x10-' 2 x 10** 1 4 x 10-' 3 xle-8 1 x 10-8 2 x10-8 Se 140 5 1x10-7 8 x10** 4 x 10 3 x10*8 1 4 x10-e 7 x 10** 1 x10-' 2 x10-s Bertielleen (97)....... Oh249 8 9 x10-" 2 x10-s 3 x 10-" 4 x 10** 1 1x10** 2 x10-8 4 xIO*' 4 x IO-* Ek 250 3 1x10-7 4 x10*8 5 x10-' 2 x10** 1 1 x10-8 e x 10-8 4 x10-8 2 x10-* SoryNican (4).. Se 7 5 6x10-8 3 x10-8 2 x10-' 2 x10-s 1 1 x to

• 5x10-8 4 x10-'

2 x 10-s Biesmash (83)..... El 20e 5 2 x10*' Ix10-3 4 x 10-' 4 x10-s i 1x10*' 1x10-8 5 x10** 4 x10*8 Bl 207 3 2x10-' 2 x 10-8 4 x 10-' % x10*8 9 1 x10-' 2 x 10-s 5X10-* 4x10-s Of210 4 x10*' 1x10-s 2x10** 4 x10-8 1 4 x 10-' I X10-s 2 x10** 4 x10-s 81 212 S Ix10*F 1x10-s 3 x10-' 4 x 10-* t 2x10-' 1 x10-* 7 x 10* 4 x10-* l l 2015 December 30,1982(reset)

s e PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION O

C-e re e.. a.e.4wese,abesef.e.,relsea., o e (See notes at and of sopenen) Tebbs i Tebte a Elemene (seemee member) leese,e8 Cenome I Ceaume 2 Column 1 Ceaome 2 Ab Air Weser t.(u i/miXuc'%eer l/miXu i/mly(u t/mi) c c c Bremise (33) er 82 5 Ix10-* 8 x10 8 4 x10. e 3 x10-* I 2 x 10-' I x10-s 4 x10" 4 yte 8 Cadmeeme (48) C4109 S x10-e 3, ge"s 3 x g0-' 2 x 10

• I F x t0-8 8 x 10- 8 3 x 10-'

2xto* F x 10** I x 10-' 3 x10 s C4 IISm 5 4 u t0~8 1 4 x 10- s F x 10 -* I x10-' 3xto8 C4 IIS S 2 x te' ' 8 x te-8 8 x 10-' 3 x 10- s a 2 x10*' I x 10- 8 4 x t0 4 xt0 8 Csistem (20) Ce 43 S 3 x10-e 3 x10

• 1 x 10

9 x10'8 I t x 10 ' S xte'8 4 x 10-' 2 x10-8 Ce 47 5 2 x 10-' I x10 8 4 x 10 ' S x 108 8 2 x to F 1 x 10- a 6 x t04 3 x10 8 Celeferneome (98) 0 249 5 1 x 10*'8 l xt0-8 3 x 10-. e x 10 I 1 x 10-* ; F x 10-* 3 x 10"8 2 x10-8 O 250 5 3 x 10-'8 ; 4 x,10-* 2 x 10-'s 1 x 10 -s I e I x 10** F x 10-8 3 x 10"8 3 x 10- s O 251 8 2 x 10-'8 1 x 10-

• 4 x 10"*

4 w IO"' g I t x to-*. 8 x t0 -* 3 x t0-'8 3 x10-s O 232 sS e v 10 '8. ' 2 x 10-* 2 x10"8 7 3 to

• i g
• I 3 x 10-u. 2 x t0*

g x10":. y age

• O 253 5

e x 10 -'I 4 x10-8 3 x10*" l x 10

• I Sx10'*. 4 x 10 ' 8 3x10""

l x 10

• O 234 3 x10 -'8 i 4 x t0-'

2 x 10ns. 1 x t0-' i S x10-'8 4 x10-* 2 x10-'8 1 x 10-8 Corben (4) C 14 5 4 x 10-* 2 x 10-8 1 x 10-' 8 x 10" (Cor) Sob 3 x10-s I x 10-* Carlem (38).. Ce 141 8 4 x10-F 3 x10*s 3 x 30-e ..9 x10- s 1 2 x 10-'

• 3 x 10*8 3 xIO" 9 x10-s Ce 143 S

3 x 10-' 1 x10-8 9 x 10" 4 x10-s 1 2x10-' 1 x10-s F x IO*' 4 x10*8 Ce144 5 1 x10-' l 3 x10** 3 x 10-4 1 x10-8 8 4 x lO-' 3 xle-* 2 x10-8 ; 1 x10-s Caelsen (SS). Ca 131 S 1 x 10-s. F x10-8 4 x to-F 2x10-s i 3 x 10-* 3 x 10-8 1 x10*' 9 x 10-* Cs134m 5 4 x 10-8 2 x 10-8 1 x 10-8 6 x 10-8 1 4x10-*, 3 x 10-8 2 x 10-'. I x10-s Cs134 5 4 x t0-e 1 3 x10-* l x10-' 9 s to** 4 x10-8 ; a x10-s I I x IO-e e t x10-8 Ca138 8 x 10-', 3 x10-8 2 x 10-' 1 x 10" 8 9 x 10-' F x10-8 3 xle" 2 x 10" Ca 114 S 4 x to-' ' 2x10-s I x10-8 9 x10-8 1 2 x 10-' 2 x10-s 4x10-' I e x10*8 Cs 137 5 6 x 10-8 4 x 10-* 2 x IO*. 2 x 10-s i 1 x10-8 1 x10-8 5x10-* 4 x 108 Chierene (17). Q 34 4 x 10-' 2 x10-8 1 x10-' s ex10-8 1 2 x IG-' s 2 x10-8 8x10-* 4 x10-8 0 88 5 3 x 80-*. I x10-s 9 x10-e 4 x10-8 1 2 x 101 0 1 x 10-8 7 x10-' ! 4 x 10-* C-(24).. C# S1 S I x10-8 8x10-e 4 x10-' 2 x 80*8 1 2 x 10-* 8 x10-8 e x10-* 2 x 10-8 O December 30,1982(reset) 20-16

9 8 e PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION O APP 9HetX 0 Cemeesmuseese la Air end Weser Above Mesuret testgreend-Consesumed f$es noems et and of aseeneul Toble i Tense N Sleanese (esamte. leesese I Ceesme I lCelessa2 Coseen f Ceeman 2 Air I Weser Air Weser t (u i/ml)(uct/mi)(u t/al)(a i/si) c c c t-* 2 x iG-' ixie-' s xie"- 3 i,0-Co e0(2n.. C. s1 s 2xiG-' .i x iG-> 2x 6 xiG-4 xiG-* i 9 xiO4 4 x iG-. I 3 xiG-' I 3 xiG-8 x iG-. 4xiG-8 C. no 2 xie-. e x to-4 xio-8 3x0-* i x iG-* s x ie-.' C. se s 3 xiG > 2 xiO4 9 x ie-. i i x it-> i niO4

x ie-.

,3 x iG-* C. 40 x ie-* i xiG-. 3xiG-* 2 xiG-s i Cooper (29) Ce 44 5 2 x to-* 1x10-8 7 x 10-8 3 x 80-* 1 1 x gg-s 4 x10-s 4 x10-8 2x10" Casese (96).. Cm 242 5 1x10** F x 10 ** 4 x 10"8 2 xIg-s el 2 x10-4 F x10-* 6 x 10"8 2 xto-8 Cm 243 4x10-* 1 x10" 2 x 10-'8 8 x 10-* 1 1x10-* 7 x10

• 3 x10-'8 2 x10-s T

Cm 244 s 9 x to-'s 2 x 10-* 3 x 10** 7 x IO-* g I Ixt0-* 8 x10 ; 3 x 10-4 3 x10*s Cm 348 8 xte-'8 1 x to-* l 2 x to-'s 4 u te-* g 5 . M iO~ > 4xio-. 3 x iG-. ,i n,ie-" x 0-- i nio-* 2 x 10-8 4 iO4 Cm s.6 O Ix10-* 8 x10-* 4 x10-'8 3 x IO*s Cm 247 3 5 x10-'8 1 x10-* 2 x 10-'s 4 xgg-e i 1xt0-* 6 x t0-8 4x10-* 2 xte-8 Cm 240 6 x 10-'8 f x10-s 2 x 10"* 4 x10-8 8. lx10*H 4x10-e 4 x10-'8 1 x10-* Cm 349 s t x10-8 6x10- ; 4 x 10-' 2 x10-8 e x te-s 4 x ie-s 4 xto-* 2 xiG-8 Ovepressee (tel Dy 168 8 3 M 10-* Ix10-8 9 x10-' 4 x10** I 2 x 10-* 1 x10-8 7 xte-a 4 x gg-e Dy 144 S 2 x10-' 1 x10-8 e x 10-* 4 x10-s i 2xIO-' 1x10-8 F w IO-* 4 x10-s Olnesele#we (99) Es 283 5 8x10-* 7 x 10 ** 3 x 10'" 2 x10' 8 1 4 x 10'" 7 x 10- 8 ; 2 x 10' " - 2 x10*s le 284= 5 3 wt0*. S wie

• 2 x 10
• 1 x te-8 1

6 xte I 3 x te'

• 2x10
• 2 x t0*8 Se SS4 2 x 10 " - 4 xt0'*

4 x 10 *, I x ig-s S x10

• l 4 xie
• 2 x 10 " l iMiG-*

w iG -* i xio-. e 4 x10" e 3 ule-8 Se 255 3 8 4 w it-* 8 x 10** 1 xlO " ! 8 ,3 x 10 Irttem (44) 3r 169 8 4 x le-' 3 wie 8 2 ute e ! ugg s I I 4 x It 3 x t0-8 i I w ie'* 9 x 10' 8 Br 171 8 Fx10-' 3 x10 s ! 2 wie e l 1 ute a I e x t0*' 3 x 10-8 I 2 x 10 -* t ul0** i Sereptem (43) to 152 3 4 u te ' 2 xte'8 l t uto

• 1 e uit 8 (T/2 9.2 0ws) B 3xte-'

2 M10 a ; g x 30 e, 4 x10 8 2 x to' 8 4 x 10 * ' 8 u to-s Se 152 8 t x te-* f 2 x10*s ; 4ute

• 5 Nie 8 (T/2 =I3 yrs) I 2 xgg-e i Se IS4 S

4xle". 6 x 10 * ' t u te'

• 2 F 10 8 i

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s PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATl8N O

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4 ,.8 PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION r APP 89004X 0 e " : la Air and Weeer Ahee, lessered See6 posed-Consemoed (See noies al ens of aspemm] Tehee l Teh4e e pseems 'esende eventer) leasepe8 Ceaween 1 Coleone 2 Celene I Ceeosee 3 Air Weser i Air Weser t (u i/ml)(uci/al)(u i/ml)(u i/ml) c c c i Iiu i 3xir* 2 xir8 t i xis-> . x ie-* io se (33)..... I ISS S 1 xl0-' F x10** I x 10-' 4 x 10"' I 4 x10-' 2 x 10-e g u l0*' F x10-8 b6dises (77).. Ir 190 S I x 10-' 6 x 10 *8 4 x 10-8 2 xle-* I 4ule-' S x te-s 1 x t01 3 x10-* Ir 193 S 1 x50-' 1 x10-s 4 x 10" 4 x10-s 1 3 x 10** 1 x10-8 9 xIO-* 4 x10-s Ir194 2 x10*' I x10-8 8 x104 3 x10-8 4 2x10*P 9 x 10-* 3 x104 3 x1g-s bee (36)... Pe SS S 9 x 10*' 2 x10-8 3 x10-* 8 x10-* 4 1 x10** F x10-8 3 x10-* 3 x te-8 Pe 39 5 1 x10*' 3 x10-8 3 x10-' 4 x10-s 1 5 x 10-' 3 x10-s 2 x104 3 x10-8 Kryssee (M)... Er SSm Set 4x10-8 I x10-' l Set 3 x10 + l. 3 Mr S,S ,I x 10*s 2 x10-. r8 m xtr. mLeeshonom (SF). Le 140 5 3x!O-P . F x le**. 2 x 10 e l.... Kr 80 Sub 1 x 10** $ x104 O g 2 x10*s I Ix10*' F x10-8 4 x IO *' I 2 x10*8 (83).. Pb 203 8 3 x10-8 9 xle-8 9 x10-e ! e x gg-e 1 2 x10*e 1 x10*8 4 x10-e 4 x10** Pb 210 8 1x10** 4 x 10-8 4 x10"s x10*' I 2 x10** 3x10-8 8 x 10*'8 2 x10

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s PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION O

APf98404X 5 Ceaseasterlens la Air end Weser Above Neeured Seshyeend-Consemoed (See notes at and et apperem] l r e1 .. e. I asemene (seemse n.mber) onesePo8 C+8v== I C+4*ma a Cea ma i : Ce4=ma 2 l Ak Weeer l Air Weser t.(pci/al)(uct/ml)(a i/ml)(u i/ml) c c i l No 237 5 4 x10"8 ! 9 x 108 I x109a I 3 x 10-* Newsw=ve (93) i I x 10"' i 9 x 10-* i 4 x108 ! 3 x10-8 Mp 229 3 0x10-8 1 4 x10-s l 3 x10-e 1 x 10-* i I F x IO*' 4 x 10-8 l 2 x10-s 1 x 10** Niehoa (20) N4 39 S Sx10-' 4 x 10-8 2 x10-e 2 x 10'

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f PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION OU APP 8880tX B C.ne.apest le Air end Weser Ab.ve peeser.4 8.sh ; f (s . e., e,i i t.mi i tems. e i !c ic -2 i c i ; c e2 si te is.e-ori I. i i i i Aar I Wes.r Air i Weser t,(u i/ml)(uci/ml/(u i/mi)(u t/mi) l c c c P. =s S 3xiG-= i xir* i. ira s xir.. ,,,,,n,.e, (,.), - - - i 4 xir" 9 xiO~ l i xira 3 xie-. P. =3 5 2 xiO4 i xire i exir. 3 xi0~ i 2 xiO4 i xive i 8 x iv. 3 xiO~ P. 344 5 3 xie-a t i xiG-* t e xie-- I 4xir' 3 x t0* 1 xic** l 1 x t0-s 2 xie I I 3 x te-" l 3 xira F xir' e 4 (u). P. Sie 5

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s e PART 20

• STANDARDS FOR PROTECTION AGAINST RADIAT18N e

~S 2_ e la Ak and Weser Above Nasered Roshposed-.Ceestseed F-(See noese et one of aseenent fable i Tetle E I i elemens (seemse evenber): esmope ' Ceeema I t Celessa 3 Celease t l Ceemana 2 l Weser Air Weser Air t,(u i/ml)(uci/ml)(u i/ml? (u t/si) j c c c e_. (44) to 97 5 2 x 10** 1 x go-s s x10** 4 x10** I 2 x 10-* I x191 4 m ie-' 3 x t0** Re t03 5 8x10*' 2 xte-s 2 x to-* e xig-s 1 8 x 109 2 x10*s 3 x t0-' 8 Mgg-s te les S 7 x10-8 3 x t0-8 2 x10-e 3 x te' I $ x10-8 3 x10-s 2 x10-8 9 x10' Re 106 8 8 x10-s 4 x IO** 3 x10"* I x 50*s i e x t0-' 3 x t0-* 2x10** 1 x10-8 Somertem (42) Sm 14F S F x t0*" 2 xig-s 2 x t0*'8 4 x10-8 1 3 x 10** 2 x10-s 9 x te-* F xle-s So III S 4 xle I x10-8 2 x10-' 4 x10-* I 1x10*' 8 x10-s 8 x10" 4 x10-* Se 153 S SxIO*' 2 x10*8 2 x10-8 8 x10*s 1 4 u t0** 2 x10-s 1 x10** 8 x10-8 T $esedlem (21) Se 44 8 3 x te-' I x t0-s .e x ge" 4 xte-s 3 i 2 xie i xiG-s xiG-* 4 xiG-s le 47 5 4x10*' 3 x10-s 2 x10-e 9 xig-s [ t.

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4 ,e PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION i

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s a o PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION ~ e ~G APPSN0lX $ Coneensressoas la Air and heeer Above Meeerei tech a f (See noses at and of appenom] ' re i t e. i t i

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8xlO-' 4 x10-s 3 x t0-' 1 x t0-8 I Ix10-' 3 x10*8 4 x 10 -' 8 x IS' I 4 x 10-', 2 x l0-s 2 x 10-8 Fxt0-8 W 187 5 I 3 x 10*' - 2 x t0-s,A g Urenauen (92) I x10-e 6 x 10-s 1 x10-" l U 2A S 3 x 10**

• I x10-8 l i 3 x 10**

I [ t Ix10-*! t x 10** 4 x 10** - 8 x IO-* l U 232 5 IxIO-* 8 x IG** i 3 x 10-'8 3x10-N 8 3x10-" ' 8 x 10-8 9 x 10-es. 3 x 10-s i l U 233 3 x 10* * ! 9 x10** 2 x 10-" ' 3 x 10-s i 1 1 x 10** ; 9 x10** 4 x t0*'8

• 3 x10-s 4

so U 234 3 4 x 10**. 9 xIO-* 2 x 10-". 3 x IO* 8 8 I x 10**

• 9 x 10**

4 x 10-'s 3x10-s U 233 s' SxIO** 8x10-* 2 x 10-" - 3 x 10-s I I XIO-* 3 8 x 10** 4 x 10-es ' 3 x 30-8 U 234 5 6 x 10-* l I x10-8 2x10*" e x 10-8 1xt0-* I x t0-8 4 x to-'8 3 x 10- 8 e 7 x10*H l i es W 238 , $ 8 O x t0-e 3x10-4 4 xte-8 8 8x10** I x lo-s 3x10-* 4 x IO-' U 240 5 2 x t0-' l x10-s e x t0** 3 x te's 1 2 x 10*' x 10-8 4 x10" l 3 x te-8 4 U eeeeral IxIO-* I x10-8 8 x 10** ' 3 x 10-8 I Ix10** 1 x109 3x10-* 3 x10-s V- - (23) V 48 5 2xt0-8 9 x10-* 4 x 10-' 3 x10-s i a 4 x 10"' 8 x t0** 2 x 10* 3 x te-s Xeeen (34). Xe I3tes Seh 2 x t0-s 4xgg-r Xe 133 Set t xto s l 3 x10*' Xe 133m Set t xIO-s 3 x10-' Xe 333 Set 4 x10-' Ix10-' Yleerbiene (70) Yb ITS S 7 x10-8 3 x10-s.. 2 x 10-8 8 x 80'.. l ex10*' 3 x 50-s 2 x 10-8 Ix10' Yurtene (39) Y 90 S Ix10-' 6 x 10-* 4 xIO* 2 x10-s 1 I x 10*' 4 x t0** 3 x t0-' 2 x10-8 Y 9tm S 2 x10 8 I x10-' 8xt0-P 3 x t0-' I 2 x10-s 1 x 10-' 4 x10-' 3 x t0-8 I Y 91 S 4 x 10-s 8 x10-* 1 x IO-* 3 x10-s 1 3 x IO** 8 x10-8 1 x10-' 3 x10-s Y 92 3 4 x 10-' 2 x10-8 3 xIO*' 4 x10-s I 3 x 10-' 2 x 10*8 8 x10-8 4 x10*8 l Y 93 2x10-7 8 x IO-* 4 x10* 3 x IO*' I x IO -' 8 x te-* s x10-* 3 x 10-8 O D8cember 30,1982(reset) 20-24

o e e PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION APPt8804X 6

\\ I Cene - - an Ab end wese, Aheve feeswel techoreend.-Come6need e. rowei rowe n i !, ca o e i. I ! ca.o.e 3 - ce3 cose.. i no-o 1=e-is here ie.cos. ' [ Ah we, Aw www e (u i/ml)(uci/ml)(u t/ mil (u i/ni) c c c 3xw.I g i 4. i x w* j 4 xiO m ,0, 2.

i i xiG-,

i 4 3 x10-8 8 6 x l01 8 x t0-8 3 x10 In etsi 8 4 x10-' 3 x10-e f g x 10-' F x10-s 3 3 x 10-'. 3 x 10-8 l 1 x10-8 4 x10-8 j ] 2a 49 8 7 x 10-8 5 x10-8 3 xle-' ' 3 ute-s I 9 x 10 -* 5 x te-s 3 wig-' 3 x10-8* Zweemium (40) Ze 93 3 1x10-' 3 x10-s 4 xig-e g x 30-8 1 3 x 10-' 3 x10-8 1 x 10-8 8 x 10-8 e 3r 95 3 1x10-8 3 x 10-' 4 x10-* e x10-8 g 1 3 x10-8 3 x10-s t x804 4 x10-8 E 2, 97 3 l u te-' 3 x10-8 4 x 10*' 3 x10-s 1 l 3 xt0-s I 9 x194 8 x10

• 3 x104

) $ Amy slaste red 6eawehde Set 1 x101 3 x10-8 l m ed ehe.e wah j l desev =ede wh* *ea eache _ er __ : seeaea l l end orth ree6eese6,e helf-life toes thee 3 Amy elaste - - - - -- 3 x10-' 9 x10-s 1 x 10-" 3 x 10-* noe Neced eheve wth desey mode seher them g 6 l etche - or g _.. n.e6.e sad ween redteesse,e t l hem. awe w me. 3 i h . 4 x10 8 3 x le '* ! 3 x 10' 8 e Amy e6egee. _ _ _ _lede 4 x 10 * ' f e.es Desed she.o,he e eh

e. wed i

ee.re b,. e-i esse w _ i M

• Amended 37 M 233m

)Y ah p ea are ter em a e

14. Fee estubie satittures of U-3*0, U-334 88d U*384 to air shoutlean testsity assy be take

" Amended 39 > R 23990; fontnote re. einano class of weer's meiosist_ Itatelag fester. lf me percent by weight (es. deugnated 40 > N 50704. rishment) et U-385 to less thea 8. the esa*

• • • Asnended 40 bit 50704 esamen m for a 40-hour warouseh t Amended 34 PM 29314' shoes rades concentrattoes are approprt*

Table 2. to 0.3 mattingroans urastums per eutto' t Amended 39 F M 2$463; redesignated sto for protection from redes-333 essahtaad masser of att average. Per any a ' t, with its short-lived daughters. Alternatively. tage product of the average : and 40 >R 5f1704, the value la Tabne I rnay be Reynamed by one= . time of espleure during a N wortweek e third t%) "worttag level." iA 'Nserblag lshall act esemed OX1tP* OA ACE-kr/mt. where R level"le deSaed as any eesabinasseen of short* re SA to tae spectae actietty of take ureatunt to. g lived reden-133 daughtere.. -- 310. g beled. he someostrattoa value for Tante E le lead-314, blesluth-314 and potonause-314. La 6 0.00f skullgreams uraniums per eutta meter et [ one liter of air, without regard to the degree $ sir. N speette activity for esturet urmaines S "ma[U.ao"rg,.,o*f !.3N,NY In[,Ea* se em tgimte per areas U. ne speesse ,a, e no m e a vaiue ma, he ne=itr - e=or mi-en er U-=. U-= replaced by one-thirtieth (%s) of a "worslag and U-234,1f not known, shee he t level" The limit on redoa 333 concentratione 34 g.g x gg4 curtes/ gram U U4selated in restricted eroaa snay be tussed on an sa* sam (0.4+0JO E+0.0004 F) 104 52m anat *=nes. ,,g,,, g i,,3,,,,,,,,,,, g,,,,,,,,, g.,3 3, {esproceed as percent. ) 20-25 Decembef 30,1982(rmt)

e 6 PART 20 o GTANDARD3 FOR PROTECTION AGAINST RADIATICN ( e O NOTE TO APPFNDIX B ~

3. If any of the conditione spec 18ed below uors at a., en.e w-.e,e. a mm.e i. m, e,

= =et. the arr=90nd1=======1eed water of faere thaa one redienesetide. the tiradane value, below n1&y be laced in 11eu of those spect$ed for pearfoes of t&ls Appendis should be determaned ao la paragraph 2 abo,TO. we~

a. If ihe idanut of.ach raionneud. in de" %f*

ae=== aa== wt

• a===tr===

neu d,,e de,I,3'.,'e."a,e"F,ne""."*tet",F,,n,'"*a"; .e .ed e .,os. note,m.ne.

e. u,s.

of on. or more of the raionucudos in the T esseuclide is tae mistiare. the rstm heeween the quentit y 4o n11Iture la not known, the concentration a tDe misture and the hmit otherwtie esteh. -timit for the suisture to the limit spec 18ed .e. m1 ^3%" M','n':F,a",'"""tt'*aJ rh,= =ta ^ Pre =at= -= ra' tha raa2a===22ae $= th' unny,endes a t.e am.e mar.et e e,re roe,Sumat:

= u t

= x--t a===irmu-rausnu u. or E s asPta: If radleeuctides A B a sneenettspons ca. Ce, and dc.. and C are present $

b. If tPe identity of each radionucilde.WR la and d the appiacaNe the al1Iture la not knoorn. but 18 le kn MPC's, are MPC and MPCs. and MPCc reatwe-tirelv. then the concentratens shall be heated *se that that certain redlonuclides spec 18ed la Ap-the senem ens retiensnip easts:

pend 13 "s* are not present in the mixture, the eencontration unit for the mixture le Ca. Ca. Ce the lowest coneantratlon 11mit epoc18ed in N PCa ' MPCa 'Ep Appendiz "s* for any radionuclide which to not known to be absent front the n112ture. - tr e.th e tsw t see ** e $ re llan: ierte a a w. r * 'v cu ce.ntre'& af enr O or .re

n. u.e iunisme 4:4we..i. a. antts P *nal! be:

ev = *e puri..

a. For purposes of Table 1. col 1-6 x 10-8 6

b. For purpocos of Table 1. Col 2-4 x 10d g

e. For purposes of Table !!. col 1-2 x 10-u

d. For purposes of Table II. col 2-3 x 10d Table I Table II e, Eisenes (asemie number) and isotope Catama 1 Colume 2 Cohana 1 Colana 2 Air (, Clin 11 m eser Air (,C1/ sal)

Water (, Cunni) (eC4 Mal) Dtt is known that $r so, t125.112L I 129. I 121. (1123, taiste 11 enly). PD 21o. Pe 110 At :sti,25. Th 422. Th. ka 2:2, Ra 2;e. Ra 220. As 227. Rs 228. Th 23a Pa 2 not. Ca 2ea Cr 2*. and Fm na are wet presens.... eXIO4 8X10 e j A 5 Ifit

• known test se so.1123. : i2s, a 62s. ta tal, i 122, e

tatHe !! oeur). Pt 210, Pe 2HL Ra 223, Rs 228. Ra 23, i g Pa 221. Tlwins. Cm sea, Ci 234, and Fm 2a6 are not Dft".'7n'i;sigs;WT sirig, iyii,17 di me are e " giti ia enly). Pt 21% Ra 2:8. Ra 24 Ca 2es. er R DYmMtGiiiiiiiiiiWiiWnikii".siK)is l 22n are not present.................................. 8X11P* IX19* D 65 is known tuna alpe4mitters and er so, I 129. Pt 21tL As 227. Ra 22B, ra 220,Pu 341, and Da Je8 are net EUits't'E*' e'Einittifi~a' ail'Nid'1's"25' pd D Re 23. and Pu 241 are not preseas.................. 3XIe.e IX10 e D 45 m known taas alptedantsers and At 227 are est I Il fM'iEe't" i'$$flbNRYaEYU"25,N Zse. Pu 2eo. Fu 2e2. Fu 244. Ce tea. Ci see and C12sn are met present 8x194 1X11Pe [ura. If a alzture of radionuclidae constets of 4 nium and its daughtere in ere dust prior i g to chemscal separauen of the armatusa froma the ore, the values spec 18ed below niay be [ used for uranium and its daugttlers througth S radium.226.instead of those from paragraphe

1. 2. or 3 above.

a

a. For purposee of Table I. Col.1-1x10-an j

act/mi groes alpha activitP: or 5X1cra act/ i m1 nature vanirm: or 're mscrograma per f* euble metu J air atural 1trantusa. C

b. For purposes os Table II. col 1-.8 x 10-u l

$ pC1/mi groes alpha settvity; or SX10-semol/ ( al natur-2 uranluna; or S salsregrame pee i g,,, cuble meter of air naturns uranium. l l

8. For puryceae of thte eote, a radio.

~ nuclide maf be conendered as not present in ) a mixture if (a) the raue of the concentra. l l tion of that radionuclide in the misture u (Can. io the concentrauon unit for that g redsonuende spect8ed in Table II of Ap- - pendir n (arFCap does hot esosed he "e (i.e. g ) and (b) the siant of such f* stlos for su the radlonuclides considered me { i not preent ta the mixture den not exceed 1 I Ca Ce I (La ggr; + upc, +.... 5%). O December 30,1982(reset) 20 26

t 9 e e PART 20 e STANDARDhi FOR PROTECTION AGAINST RADIATION m*==*= g e.r,ma.a= emaalas me===sume -e es memos nome ameos = minume w u-ma e les mmen w==hme asom. onmium.eim.. 3,miuns.................. .el ,,0,,,,, l.es osa m m.iei.................. .el a,mium.in...._......._ 4mentium.34:................

u..,,,,,,,ue e ne, i.e et, m

e. ,e m. e. 4.umony 133.................. m ,,,,,,,m..,, _. _,... _ Anumoar.13e............... le g m,e,e, a.l tu,ee w mei.n e.ma. g ,em,ium.i, _.__.. _, i. e.ees Anumoer.las................. le

u..e ese,m ne...

.1 i ,e,, e,ue Areente.73....................... ISO Flauaum.191 _--__ 100 Areente.74 le rmunum.leem ---._-- les 4 7e....................... Puunum.1se.........-.... les Mw e W m wbmo ymunum 1e7m.........-.... les b h W e hM N h 188 1.......... - - - - Piaunum le?........... el g baown enousteJ.he limit let the combinauen itinum.t.o lo peuuntum See................ pene nue :to................. eI g ebeuid be derhaal as follows. Determine. for as num 140................. se Petaantum-43............. 10 tech lestepe la Ibe combinaties. Ibe relio Blamuun.310.................... I g le scomsne.e3..................... ,,eeeesymau.las... _.. les e. between the geantity present in Ibe Cadmium.10e................. le pressosymium.14e..-._._.. Ice * @ den @ be M h Cadantu nt. I ism..............* Promeublum.147 le ' establiebed Ier the speciflC lectops when not Cadmium. I I S..................* Promethiumn.440....... le is egebinettee.The som of such rettee for all Ca lciunt.48.................... It

• gg

"*88"s"um*ggg ".*.".."*".". ~.. Rhen 180 ISO the lectopes in Ibo aa-ha-aaa= may not Caletum.47...................... le les enesed "1"(L4.

• unity").

Carton.14................

• 100 Rhensum.les _. _ _-.

ISS Certum.141................. Rhodium.100m._ lee

==

100 Certum.143................... Rhostum.108 _. 100 Certum. I 44.................. I g,ggggg.gg___,_- gg Cesnum.131.................. 1.See g,g,gg,,.gy,,,,,,,,,,,,,,_ ISS gg Cesium.134sa................. 100 Ruthenium.97. Cesium.134.................... I Ruthenium. LGS --.- IG 10 Rutheniusa.108. le Cesaum.138................... Cest u m.136.................... le Ruthentuun.100..-- 1 Ceslum.137.................... le Santerlum.let --- 14 Chlori ne.34.................... SS Samarium.188 100 Chlorine.38.................... 10 acaadium.48.. IS Chromnum41.. .. 1.000 Scandiumn.47 _ ISO Cobalt 48m............. le Scandiumn.48...... le Cobalt 40.............. 14 Seleatum.?S... le i Ootalt 00............... I auteen at......... les l Copper.44....... ............ 100 siteer.106........ 10 Desprostum.I64......... 10 sateer.1less...... 1 Dysprostum.lte................. 100 siteer.ll!... 100 Erbium. l et..................... 100 Sott um.34................ It 100 istronuum.88..._.. 10 Erttum.171................... 100 Stronuuan.as............ I h, Europium.lSS 9 3 h.............. j Eieroptum IS3 13 y7............ I b, Strontiusas9..... 0.1 $ Europiu m l S4................... I I stronuuna.el...... 10 Europsum l SS................... le g Strontium.03.... le g u. Fluorine.18.................... 1.000 u. sulphur.34.......... It' le 10 g Oedolmaum.153................. g Tmatalumn.183................ Ondohm um l Se................. 100 Technetium 06........... 13 04 l h ima.72.................... 10 Technetium.97en........... ISO 100 Technettum.97.............. 100 Germantum.71.................. O u td. i t*8........................ 100 Technettum Spea.............. ISO Ould. I PO........................ 100 Techneuum.00................ le Ma tha um.181.................... 10 Tellurtum.13Sm............... le Holmanm.186.................... 100 '1411urtum.137m........... 10 Hydrogen.3....................

3. 000 Tellurium.137...............

100 Indium. l l3m.................... 100 Tellurium.130m............... 10 1:adiu m.1 t em.................... 10 Tellurium. lN................. 100 Indt um.11 Sm.................... 100 Tellurlum laiIn............... le Indium I I S..................... 10 Tellurtum.133................... le le lodine.133...................... 1 Terntum.800.............,.. lut m e.126...................... I Tlhalit um.300................... 100 J Iveme.'39 O.1 Tha!!i u m 301.................. 100 tc, dine.131 1 Thallium.302.................. 100 104tue.I33 le Tha t!!u m.304.................... 10 I

• • !hortum (natural)8.

100 fodine.133...................... todme.134 10 Thu tt um.170.................... 10 10 Th ullum-ITI.................. 10 Iodine.135...................... tridi um.193..................... 10 Ti n. I l 3....................... 10 Iridi u m.194..................... 100 Tt n. t 25....................... 10 f ron 45......................... les Tungst en. n e t.................... 10 trot. 59 le Tu rcten. l te................... le 100

• • Tunesten.187 100 Kr3pton.85 Ursalue (asterstle.....

100 10 Krypton.47 Lan t hanu m.140................. 10 IJ ra nium.333.................. .01 Lutetsum.lT7 100 !!ranturn.334 Uranium.338...... .01 af antanese43 ...m...m..m.. 10 Va n.ad hun.48.................... 10 . St a ng anese S4................... Ig Xenan-t3im................... 1.000 100 kra nys nese-Se................... IO Xenon.133..................... af erc u ry. lS7m................... 100 Xenon.136...m.m.m...m.. 100 S terc ury. I 97..................... 100 Yt t erht um.175.................. 100 Stercury.303..................... 10 Ytt rium.00...................... le 11oly bden um.90................. 100 Yttrium.91...................... 10 M eodymiu m.147................. 100 Yttrium 93.................... 100 N eod vmau m.140................. 100 t 93............ ~...... ! 8 Based on alpha distalegration rate of N a c k e l.50........................ 100 .-~~~~~~~ .gg,ggg,.3%.330 had tholt daughter Prodh 2 i nc.80m.......................,,100, .mased on alpha ensintegrasson rate oc N ac k el -G3....................... 10 g ..-~~~~~ N ac k el48........................ 100 Zlreon t um.~93.................... 10 g,ggg, g.ggg,,g g,gg. Ninemm.93m.................... 30 Ninnium.WS 30 Zircont um.95.................... 10 AmenJed 36 F M 16A98. O*maum.148 10 Zircontum 97.................... 10 ,, Amended 39 F M 2J990. Naoua u m.97..................... 10 20-27 December 30,1982(reset)

s< e PART 20 e STANDARDS FOH PROTECTION AGAINS'T RADIATION e O APPenoix D.-UmTED STATES NUCLEAA REGULATORY ComHSSON REGIONAL OrriCEs Asemen Taewww e4 nres Regen k Cemocteut, Ossemera Oseict of Conwnem unne. Maryter4L h M 431 Pet Ave IGng of Pruest PA 19408 atS 337-8000 773 des-100tL y emelt New Mengenea New Jeesy, Pese YetL Pennoyerena Rnoen enemiqL and ~ venn.E y Regan a Alenema Flensk Gange, Karmel$y he Morei Caroest Puote USNRC, tot Menene Sweet, Sune 3100, Aempet GA 30303_ Hoei 221-4603, FTS 243-4903. moa see Comas Tennessom wens won marea, one was m a megen = me== insens e.a nacneen, menneens u.eem one== weconen, usNRC,798 RooW44 Ro04 Glen EM L 00137 (Stri N-$ A Repen le assannes concreen teena mensen Leveneae, Moneene. Neerneh4 New M St1 Ayen Pleen Onve, Sete 1000, Artiggest TI T6011 1817) ee0 4,$00 FTS 348-8500. 00, FTm ras.etoa Mosca Peerm Dahoto, cuenoma Sam Deeces. Tense, Uters one W e '? Repen N 7isac h UspelC, Repon N t.kamme Recovery Fiend Orflee, 730 Smens (303 234-7232, FTS 2se-723a. Seest P CL Bee 25325. Denver. CO a0271 Sepen w Aaesee, Annone. CeNorma Mewet, Nevoet Qegorg Wearwgest and U$NRC,1450 Mene Lane, Sune 210. Wesea Crees, CA 94006_ MtS 943-3700, FTSI 446 UA sumenes and - a me Pacet O O September 30,1983 20 28

UNITED STATES NUCLEAR REGULATOR / COMMISSION RULES and REGULATIONS TITLE 10. CHAPTER 1. CODE OF FEDERAL REGUI.ATIONS-ENERGY PART REPORTING OF DEFECTS AND NONCOMPLIANCE 21 O'"P'""*"* I 21.3 Se*Pe. l 21,3 De8 minions. Ses. The regulations in this part apply, ex-Asaned in this part (a) " Basic conspo,- 31.1 Purpos'- cept as spec 1Scally provided otherwise in e nen when applied to nuclear power re. acopduoms. Parts 31,34,35,40, or 70 of this chapter,3 actors means a plant structure, system. Dea 21.4 Interpretauons. to each individual, partnernhlp, corpora-E component or part thereof necessary to. au comununtentions. tion, or other entity Heensed pursuant to h-assure (1) the integrity of the reactor ,the reltlations in this chapter to possess, a (2) the caps-ces.e Pomung requirements. ,use, and/or transfer within'the United

• coolant pressure boundary, tor ~and main; 31.1 asempuons bihty to shut down the reac States source, byproduct and/or special 4ain it in a safe shutdown condition, or nuclear materials, or to construct, man-et entlure to comp 1T 8' ufacture, possess, own, operate and or "ia=**"'

r a eefect. sts transfer within the United States,'any (3) the capsbutty to psugnt or miti-essensees o yeosssessur Docesses produccon or utilisation facility, and to : to the consequences of aceldents which M each director (see i 21J(f)) and respon. p rpsult in potential chite expo-sible otDeer (see i 213(3)) of such.a 11. g 'sures comparable to those refersed to IR zussacrease, ameomme eensee.The regulauons in this part apply a il 100.11'of tids chapter, 11.41 Inspacesoms, also to each individual, corporation, L sist Mainesonnes ot eoeores. partnership or other enuty doing bust. " Basic compo ' Enra-=====,r nees within the United States, and each nent," when applied to other facGitles director and responsible ofBeer of such and when. applied to other activities H. 31.01 Fanure to notity, organtsation, that constructs (see 121.3 annand pursuant to Parts 30, 40, 50, 10 Aormonsrve sec.1st, Pub. L eS-70s. es (C)) a production or utilisation facility or gg of thjs chapter, manna a conspD-sens. see: see. See, Pub. L el-lel, es Stat. E ess; eso. see, Pub. L eS-4es, se Stat late

• Meensed for manufacture, construccon nent, structure, system,- or part thereof or operation (see i 21J(h)) pursuant to that is diracGy_ procured by the lleensee tin gs.c.seet.ssee, sees),

4 Part 50 of this chapter or supplies (see.- of a facility or activlsy sutdect to the l GaNaast, Paovssions i 21J(1)) basic components (see i 21.3 for a facility or activity Heartaed.: segulauens.Ist this part and in which (a)) SIld F#'9"'** other than for export, under Parts 30,: a defect (see 1313(d)) or faDure to a casophy with any *PP anMa regg]stigst H 'line regulations in this part establish 40,.00, 70, or Tr. ' in this ehapter, order, or license issued precedums and requirements for imple-. ; O by ttse Cnemianton could create a sub-smentation of section 306 of the Erdrgy IEsthhis in these regulations stantial safety hasard (see i21J(k)), moorymisation Act of 1914.*ntat secuan should be deemead to preshede alther Irt au cases *' basic cosoponent" includes requires any individual director or re-sponsible eScer of a firm coastsucting,- 6 as indisidual de a manufacturer /sup, design, inspection, testing, or consulting, owning, operating or supplying the com. 3 p.gg.a===W g servloes. Important to safety that are Penanta 'of any facDity or acuvity which ; T2f3(a-1)) nM dul> Ject.rade item (see associated with the cosaponent hard-to the regula-warm whether these servlees are per. lis lisensed or otherwise regulated pur a tions in this part from reporting to the formed by the==panant supplier os' suant tothe Atoude Energy Act of 1954,' r%-meanian a known or. suspected others. " as amanded or the Energy Reorgantus-O defect or failure to cosaply and, as au-tassa Act of Im,whominkmathn thortmed by law, the klentity of anyone A mnmarcial grade itent is " ggggy 30 reporting 1ptil be.withbald frosa dis. not a part of a basic component until a I pIIed to such faculty or se5,ity fans $3 elosure. after dadia=tian (see 8 31 a(e-1)). domply with the Atonde Energy'Act of (a-1) "fTmmaeels! grade itdInt" 1984, as amended or any applicable rule, meansi en itest thar is (1) hot subject ~ regulation, order, or lleense of the Com-

te, design orspecifloation requiramanta" matselsen

• • 'P**" ** ""U P****" *o9e*rning a{ thatfan W k,MW W. W-ie~topa ne caus sma ine u

ho hasards or tha thefde t activlt defeckoch fa' umhere (N n Ues Hosased starsuant to part 30,40, to .on.s re iar toum are ii.a.nd I E'ed= appH=um= om, man rau. N#U # which or activi coin create a==sianuai-rety ha-rd. uon.m,d. tot ta .e = e to inanedsately notify the Commission of .below: ties or activities licensed pursuant to' such faBure to comply or such defect, Region: part 30,40,80,70, or 71 of this chapter unless he has actual knowledge that 1 (Phundolphia)...... [3_37 5000* W (3) to kor.dered fdthi nnahu-the '%==8==8an has been adequately in. % III (chicaso).......

1. sal-4eos.

facture' r/ supplier on me hemis of spect. II ( Atlants)........ formand of such defect or failure to (31 932 2500 *

auspir, IV (nanas).........

(81 55U floations set forth in the usanufactur- % V (san Francisco).. (415) 943 3700 " -* Amended 43 FR 52201. tAmended 44 FR 2568. " Amended 44 FR AHO 21-1 November 9,1979

PART 21 o REPORTING OF DEFECTS AND NONCOMPLIANCE y er's published product description (for who is vested with executive authority j~ -pample a catalog), over activities subject to this part. Suppliers of commercial grade (k) "Substantialsafety hazard

• means ; items are exempt from the provisions

~ (b) " Commission" means the Nuclear a loss of safety function to the extent u: of this part to the extent that they Regulatory Commission or its duly au-that there is a mafor reduction in the de ',, supply commercial grade items. gree of protection provided to public, thorized representatives. 2 fc) " Constructing" or " construction" health and safety for any facility or ac. % means the design, manufacture, fabrica-tivity licensed, other than for export, NoT!rICATION tion, placement, erection, installation, pursuant to Parts 30, 40, 50, 70_and 71. 21.21 Notification of failure to comply (D Supplying" or " supplies means g g g, gg a modification, inspection, or testing of a facility or activity which is subject to the. contractually responsible for a basic ' regulations in this part and consulting component used or to be used in a facil-(a) Each individual, corporation, part-a services related to the facility or activity-ity er activity which is subject to the nership or other entity subject to the regulations in this part. regulations in this part shall adopt ap- _that are important to safety. propriate pmcedures to (1) provide for g 21,4 Inierpretaisons. (1) evaluating deviations or (in inform-2.- (c-1) " Dedication" of a commercial Except as specifically authorized by ing the licensee or purchaser of the de-a

grade item occurs after receipt when the Commission in writing. no interpre-viation in order that the licensee or pur-E that item is deaWted for use as a tation of the meaning of the regulations chaser may cause the deviation to be in this part by any omeer or employee evaluated unless the deviation has been

basic component.

of the Commission other than a written corrected; and (2) assure that a director interpretation by the General Counsel or responsible omcer is informed if the (d) " Defect" means: will be recognized to be binding upon construction or operation of a facility. or [ (1) A deviation (see 121.3 (e)) in a the Commission. activity, cr a basic component supplied for such facility or activity: g basic component delivered to a purchaser 6 21.5 Communleations. = for use in a facility or an activity subject (1) Falls to comply with the Atomic 2 to the regulations in this part it. on the Except where otherwise specified in Energy Act of 1954, as amended, or any L basis of an evaluation (see i 21.3(g)), this part, all communications and re-applicable rule, regulation, order or !!- ports concerning the regulations in this cense of the Commission nlating to a {the deviation could create a substantial a safety hazard; or part should be addressed to the Director, 'substantial safety hazard, or Omce of Inspection And Enforcement, (1D Contains a defect. The effective - (2) The installation, use, or operation U.S. Nuclear Regulatory Commission, (Mte of this paragraph has been deferred of a basic component containing a defect Washington, D.C. 20555, or to the Direc* until January 6,1978. as defined in paragraph (d)(1) of this, tor of a Regional Omce at the address (b)(1) A director or responsible omeer specified in Appendix D of Part 20 of subject to the regulations of this part section; or (3) A deviation in a portion of a fa. this chapter. Communications and re-or a designated person shall notify the cility subject to the construction permit ;' ports also may be delivered in person at Commiulon when he obtains information or manufacturing licensing reqtitrements ; the Commission's omees at 1717 H 8treet reasonably indicat!ng a f ailure to compig of Part 50 of this chapter provided the p NW Washington, D.C.; at 7920 Norfolk or a defect affecting (D the construction devtation could, on the basis of an eval-w Avenue. Bethesda, Md.; or at a Regional or operation of a facihty or an activity untion. create a substantial safety haz- ~ Omce at the location specified in Ap-within the United States that is subject ard and the portion of the facility con.

• pendix D of,Part 20 of this chapter.

to the licensing requirements under Parts taining the deviation has been offered to 6 21.6 Posting requirements. O 30,40,50,70 or 71 and that is within his

• organization's responsibility or (11) a the purchaser for acceptance; or Each individual partnership, corpora-tion or other entity subject to the regu E basic component that is within his or-(4) A condition or circumstance in-ganization's responsibility and is sup-tNs pad, M pst curmnt '0 plied for a facility or an activity within volving a basic component that could la a

contribute to the exceeding of a safety copies of the following documents in a the United States that is subject to the limit, as defined in the technical specif1- """#""8 M*I " OU ""# #"*I8 cations of a license for operation issued licensing requirements under Parts 30, within the United States where the ac-40, 50, 70 or 71. The above notification pursuant t Part 50 of this chapter, tivities subject to this part are conducted is not required if such todividual has (e) " Deviation" means a departure from the technical requirements included actual knowledge that the Commission tion 6 e En rgy rg has been adequately informed of such de- , in a procurement document (see i 21.3 Act of 1974, and (3) procedures adopted to th au his k f5 " Director" means an individual. W[ 2) t I n tifi a on r quired by this g g .ggukuom in paragraph shall be made within two appointed or elected according to law, a par ad p f who is authorized to manage and d!?ect go hor thproce days following receipt of the information. y m ,p rac , the affairs of a corporation, partnership ticable, the licensee or firm subject to Notification shall be made to the Direc. tor. Omce of Inspection and Enforce-or other entity. In the esse of an indi-the regulations in this part may, in ad-vidual proprietorship, " director" means ment, or to the Director of a Regional e ind,fdual dition to posting section 206, post a no. Omce. If initial notification is by means tice which describes the regulations / (g) Evaluation" means the process other than written communication, a procedures, including the name of the in-accomplished by or for a licensee to de-written report shall be submitted to the dividual to whom mports may be made termine whethen a particular deviation and states wh th be ined appropriate Omce within 5 days atter.the could create a substantial safety hazard.' information is obtained. Three copies of The effective date o this a tiorr has (h) ' Operating or operation" means each nport s, hall be submitted to the been deferred until January 6,1978-the operation of a facility or the conduct Director, Of!'ce of InspectMri and En-of a licensed activity which is subject to 9 21,7 Exemptions, forcement. the regulations in this part and consult-The Commission may, upon application (3) The written report required by this ing services related to operations that are of any interested person or upon its own paragraph shall include, but need not be IMD0', tant to safety. initiative, grant such exemptions from limited to, the following information, to (D Procurement document means a the requirements of the regulations in the extent known: contract that defines the requirements this part as it determines are authorized (1) Name and address of the individ. which iacilities or basic components must by law and will not endanger life or ual or individuals informing the meet in order to be considered accepta-property or the common defense and Commtulon. ble by the purchaser. security and are otherwise in the public (ID Identification of the facility, the (j) Responsible omcer,, means the activity, or the basic component supplied president, vice-president or other in

interest, for such facility or such activity within dividual in the organization of a cor-the United States which fails to comply p) ration, partnership, or other entity or contains a defect.

November 10,1978 21 2

e i m PART 21 o REPORTING OF DEFECTS AND NONCOMPLIANCE +9 c d (till Identification of the firm con-component supplied for any licensed fa-1 structing the facility or supplying the cility or to be used in any licensed ac-basic component which fails to comply tivity sufficient to assure compliance with e' or contains a defect, the regulations in this part. After de-livery of the facility or component and (iv) Nature of the defect or failure to pri r to the destruction of the records comply and the safety hazard which is relating to waluations (see i 21.Ugn w created or could be created by such de-notifications to the Commission (see fect or failure to comply. I 21.21), such records shall be offered (v) The date on which the information to the purchaser of the facility or com-of such defect or failure to comply was ponent.If such purchaser determines any obtained. such records: (vi) In the case of a basic component (1) Are not related to the creation of which contains a defect or fails to com* a substantial safety hazard, he may au-i ply, the number and location of all such thorize such records to be destroyed. or components in use at, supplied for. or (2) Are related to the creation of a being supplied for one or more facilities substantial safety hazard, he shall cause or activities subject to the regulations such records to be offered to the organi-l in this part. ration to which he supplies basic com-(v11) The corrective action which has ponents or for which he constructs a fa. .' been, is being, or will be taken; the name cility or activity, If such purchaser is unable to make the sib for e a tion an e th of determination as required above then the time that has been or will be taken to responsibility for making the determi. complete the action

• nation shall be transferred to the indi-

+ 1 (viii) Any advice related to the defect vidual, corporation, partnership, or other or failure to comply about the facility, entity subject to the regulations in this i activity, or basic component that has part that issued the procurement docu. I been is being, or will be given to pur-ment to the purchaser. In the event that chasers or licensees' the determination cannot be made at (4) The director or responsible officer that level then the responsibility shall may authorize an individual to provide be transferred in a similar manner to s the notincation required by this para

• another individual, corporation, partner-'

graph, provided that, this shall not re-ship, or other entity subject to.the reg-lieve the director or responsible officer ulations in this part, until, if necessary. of his or her responsibility under this the licensee shall make the determina. ) paragraph-tion. (c) Individuals subject to paragraph tc) Records that are prepared only g abi may be required by the Commission @ for the purpose of assuring compliance g to supply additional information related R with the regulations in this part and are i to the dafect or iallure to comply, not related to evaluAttons or notifications t g e PaoccarstENT DocusttNis ' to the Commission may be destroyed "I d' 'I DI " * * ~ l R 21.31 Procurement documente. ponent. a Each individual, corporation, partner-(d) The effective date of the section ship or other entity subject to the reg-has been deferred until January 6, I?i8. ulations in this part shall assure that ENroRCEMENT each procurement document for a fa-cility, or a basic component issued by $21.61 Failure ta notify. him, her or it on or af ter January 6,1978 Any director or responsible officer sub-specifies. when applicable, that the pro-ject to the regulations in this part who visions of 10 CFR Part 21 apply. knowingly and consciously falls to pro-INSPECT!oNs. Rtconos vide the notice required by 6 21.21 shall J be subject to a civil penalty in an amount g 21.11 In pect. not to exceed $5.000 for each failure to ion,. j Each individual, corporation, partner-provide such notice and a total amount ship or other entity subject to the regua not to exceed $25,000 for all failures to lations in this part shall permit duly provide such notice occurring within any { authorized representatives of the Com-period of thirty consecutive days. Each mission, to inspect its records, premises, day of failure to provide the notice re-l activities, and basic components as nec-quired by 121.21 shall constitute a sepa-essary to effectuate the purposes of this rate failure for the purpose of computing part. ,the applicable civil penalty, 9 21.31 %intenance of records. tal Each licensee of a facility or ac-tivity subject to the regulations in this I part shall maintain such records in l connection with the licensed facility or activity as may be required to assure j compliance with the regulations in this part. j (bi Each individual. corporation, part-nership. or other entity subject to the regulations in this part shall prepare } records in connection with the design, j manufacture, fabrice.tlon. placement. Nott.-The reporting and record keeping i erection, installation, modification. in-requirements contained in this part have i spection, or testing of any facility. basic been approved by the General Accounting Office under B-180225 t RO 446). 21 3 November 10,1978 (reset) t .~

e e The Pennsylvania State University SNM-95 Renewal SUPPLEMENT C 28 May 86 University Isotopes Committee and University Health Physicist I. UNIVERSITY ISOTOPES COMMITTEE The current membership of the University Isotopes Committee is listed below, followed by a brief summary of the experience and training of each member. W. W.

Pratt, Ph.D.,

Chairman W. A. Jester, Ph.D. E. S. Kenney, Ph.D. R. L. McCarl, Ph.D. R. D. McCarthy, Ph.D. F. P.

Naugle, M.D.

A. T. Phillips, Ph.D. W. W. Pratt, Ph.D. Chairman, University Isotopes Committee Professor of Physics Training: Four years of graduate work in experimental nuclear spectroscopy at Iowa State University. Experience: Two years of research in nuclear reactor shielding at Brookhaven National Laboratory. Two years of research in nuclear reactor studies with a Van de Graaff generator at State' University of Iowa. Thirty years of research in nuclear spectroscopy at The Pennsylvania State University. Has worked with radioactive material in all physical forms l at activity levels from tracer quantities to 100 mci. W. A

Jester, Ph.D.,

Associate Professor of Nuclear Engineering Training: M.S. and Ph.D. thesis on use of neutron activation for analysis of trace elements. Experience: Over 20 years of research in neutron activation analysis and industrial use of radioisotopes. Instructor for health physics course in Nuclear Engineering Department. Designed airborne radio-nuclide assay equipment. Has used radioactive material in microcurie to curie levels.

SUPPLEMENT C Page 2 E. S.

Kenney, Ph.D.,

Professor of Nuclear Engineering Training: Oak Ridge Institute of Nuclear Studies Radiological Physics Fellowship; University of Rochester and Brookhaven National Laboratory 1953-54. Experience: Served as Radiation Surveyor at Westinghouse Bettis Field Plant, Pittsburgh, PA. Served as University Health Physicist, The Pennsylvania State University 1955-59. Taught courses in radiological safety in the Department of Nuclear Engineering 1963-present and while serving as University Health Physicist. Has handled a variety of radioisotopes from tracer to multicurie levels in sealed and unsealed form as health physicist, reactor super-visor, during graduate research in nuclear physics and as a faculty member, 1955-present. Has designed ion chamber survey meters, irradiators, air monitors and other health physics instruments. Has patents on-Dynamic Radiography and Neutron Bottle for diagnostic radiology R. L.

McCarl, Ph.D.,

Professor of Biochemistry, Associate Dean of the Graduate School, Director of Intercollege Research Programs. Training: Radio chemistry course (approximately 30 classroom hours) while completing graduate work. Experience: Member of Pennsylvania State University Faculty since 1957. Performed activation analysis experiments 1960-61. Extensive use of P-32 to 50 mci activity levels in early 1960's. Use of C-14, H-3, P-32, and I-125 in millicurie quantities in various research projects involving metabolic studies with tissue culture cells and other biochemistry research 1960-85. R. D.

McCarthy, Ph.D.,

Professor of Food Science Training: Completed courses in radioisotope methodology at Pennsylvania State University and University of Maryland. Experience: Actively engaged in research on metabolism in animals using radioisotopes from 1956 to present. Instructor for course on experimental methods including use of radioisotopes.

SUPPLEMENT C Page 3 F. P.

Naugle, M.D.,

University Physician Training: Instruction in biological effects of radiation as a U.S. Navy flight surgeon. Attended REACT /TC conference on "The Medical Basis for Radiation j Accident Preparedness", 18-20 Oct 79. A. T.

Phillips,

/h.D., Professor of Biochemistry Training: Course in radioisotope use. Experience: Research using H-3, C-14, S-35, P-32, and radioiodine to 1 Ci amounts 1961 to present. Item 7. R. W. Granlund, University Health Physicist Training: AEC Radiological Physics Fellowship, Vanderbilt University and Oak Ridge National Laboratory, 1958-60. Certified in health physics by American Board of Health Physics, 1967. Recertified 1982, 1986 (in review). Experience: University Health Physicist at The Pennsylvania State University 1960-present. Responsible for University radiation safety program including 1 megawatt research reactor, over 200 radioisotope laboratories, a 76,000 curie cobalt-60 irradiation facility, numerous X-ray machine, and a neutron generator. Has worked with unsealed byproduct material in curie activity levels, alpha sources to 500 millicuries, neutron sources of various types, and kilocurie quantities of material as sealed sources i i including cobalt-GO and irradiated reactor fuel, i Private health physics consulting experience in diagnostic X-ray, nuclear medicine, industrial and University research, waste disposal, shielding and

training, j

K%34 i a )

f Pennsylvania State Univerai+- SNM-95 Renewal 30 May 86 Supplement D 1. Facilities for Handling Special Nuclear Material. With over 200 radioisotope laboratories in operation, a complete list of facilities would be too lengthy and repetitive. The suitability of a particular laboratory is determined in the review by the University Isotopes committee and the health physics staff. The University has shielded containers ranging in size from portable units for microcuries of activity to multi-ton units for kilocuries of activity. Most laboratories are equipped with fume hoods. Several hoods are equipped with absolute filters and two hoods, used for almost all radioiodine labeling are equipped with activated carbon filters. Two hot cells are available at the Brenzeale Nuclear Reactor (see Appendix C). Glove boxes for radioactive material are also available in several laboratories. Tongs of various type and size are used according to need. Lead bricks and concrete blocks are used extensively for gamma-ray shielding and plastic shields are used for beta radiation shielding. 2. Radiation Detection and Measuring Instruments. The instruments listed below are those routinely used by the health physics staff. Numerous other instruments are available in the many radioisotope laboratories. These include GMSM's, liquid scintillation counters, gamma scintillation counters, low-background alpha-beta counters, multichannel analyzers, sodium iodide and germanium detectors, tritium air monitors, velometers, and various air sampling devices.

Pennsylvania State University Page 2 SNM-95 Renewal 30 May 86 Type-Manufacturer Model Number Radiation Range GMSM Various Various 8 a, 8, Y 50,000 cpm and higher 50-2000 mL/hr Ion chamber Victoreen 440 2 6,Y 300 mR/hr Ion chamber Victoreen 471 1 8,Y 300 R/hr Ion chamber Eberline RO-2 2 6,Y 5 R/hr Frisker Eberline RM-12 3 a, 8, Y 50,000 cpm Frisker Ludlum 177 1 a,B,Y 50,000 cpm Rem-meter Eberline NRD-4 1 neutron 10 rem /hr Emergency Eberline GADORA 1 Y 1000 R/hr LSC Beckman LSC-100 1 a,6 106 cpm LSC Beckman 1 a,8 106 cpm Low Background Canberra 2001 1 a,6 106 cpm counter t Ion chamber Cary 31 1 a,8,y 10-14 for gas samples NaI detectors Various Various 3 gamma 106 cpm Si surface Harshaw I a los epm barrier Multichannel Canberra 30 1 a,8,Y 106 cpm Analyzer Multichannel Nucleus 1 a,8,y los cpm Analyzer TLD reader Harshaw 2000 2 Y,6 105 rad Condenser Victoreen 570 1 Y 250 rad R-meter l

Pennsylvania State University Page 3 SNM-95 Renewal 30 May 86 3. Instrument Calibration The University has a J. L. Shepherd model 72M tracktype gamma calibration facility with 130 mci and 84 Ci Cesium-13h7 sources, with an exposure rate range of 1 mR/hr to about 400 R/hr. Several Cobalt-60 sources in the activity range of several microcuries to about 100 millicuries are available for field calibration. A one millicurie radium-226 source mounted in a shield with a sample slide is available for calibration of TL dosimeters. Calibrated condenser R-meters are available for calibration of sources and cross-calibration of other instruments. Plutonium-beryllium sources with a known emission are used for calibration of neutron dose equivalent meters. The calibration frequency for instruments used for routine radiation measurements by the health physics staff is annually. Instruments such as lab monitors or GMSM's used for contamination detection are not calibrated routinely but are checked for proper operation with check sources mounted on the instruments. Special instruments such as ion chambers for gas samples are not routinely used and are calibrated as needed. Counting equipment is calibrated with standard counting sources such as Eberline SD-1 plutonium-239 alpha sources, SD-2 strontium-90 sources, SD-4 technetium sources, or sources prepared from solutions obtained from the National Bureau of Standards or traceable to it, including tritium, carbon-14, chlorine-36, iodine-125, iodine-129, cobalt-60, and sodium-22. A set of IAEA gamma standards is also used for calibration gamma spectroscopy equipment. Routinely used counting equipment is checked against standard sources on a weekly frequency. A calibration curve is produced for each batch of TL dosimeters. Pocket dosimeters are calibrated annually. 4. Personnel Monitoring Film badges, thermoluminescent dosimeters and pocket dosimeters are used for personnel monitoring. Thermoluminescent dosimeters are used for most of the personnel monitoring. The change frequency is quarterly and the current supplier is R. S. Landauer Jr. and Co. Extremity monitoring using TLD finger badges is used to supplement body dosimeters for some personnel. These are supplied and read by the Health Physics Office of the University with a monthly or quarterly change frequency. Pocket dosimeters are used for monitoring of visitors and for special purposes where immediate read out is desired. TLD body badges are supplied and read by the Health Physics Office for short term issue (1 semester or less), such as persons enrolled in a course or training program. The University reserves the right to use commercial suppliers other than R. S. Landauer Jr. & Co. to supply either film badges or TLD personnel monitoring devices or to perform TLD service internally without notice or approval j of the NRC.

The Pennsylvania State University Page 4 SNM-95 Renewal 30 May 86 5. Waste Disposal Radioactive waste disposal is handled by the Health Physics Office, including distribution of waste containers to the laboratories, collection of waste, compaction, solidification of liquids, incineration, shipping to a disposal site, and/or disposal on site. Facilities for storage and processing of waste include two large rooms in the Academic Projects Building and a 20'x20' building about 2.3 miles from the center of campus. This building houses the compactor and is inside a chain link fence. Solid waste is collected in the laboratories in fiber drums, fiber boxes, or steel drums. Separate containers are used for short half 4ife waste. Waste to be shipped to a commercial disposal site is compacted into steel drums. Typical volume of this waste before compaction is about 1000 ft3 per year. Short half-life waste is stored for decay. Solid waste with a concentration in uCi/g less than the values in Appendix B Table 2, Column 2 of 10CFR20 may be released for disposal by the county solid waste authority. Liquid waste is collected in the laboratories and transferred to the Health Physics office for disposal. Liquid waste to be shipped offsite is combined in steel drums and solidi-fied. Liquid waste may also be released to the sewer as provided for in 10CFR20.106 and 10CFH20.303. Heleases to the sewer from individual laboratories requires approval of the Health Physics Office. M ~ -}}