Text

Application for Renewal of Certificate of Compliance 6400 for Super Tiger Shipping Package.Requested Info Re Leakage Test Requirements & Seal Replacement Schedules Is Presented in App C of Encl Matl
	ML19344A713
Person / Time
Site:	07000364, 07106400
Issue date:	07/28/1980
From:	Dipiazza R; WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	;
Shared Package
ML19344A715	List: ML19344A713; ML19344A716; ML19344A717;
References
	16936, NUDOCS 8008210613
	Download: ML19344A713 (61)
	v • d • e

{{#Wiki_filter:f ~ / ffY ].D S i Y/ j }/- 4 WD Westinghouse Water Reactor m 355 Electric Corporation Divisions Pittsburt1Pennsy!vania 15230 July 28, 1980 US Nuclear Regulatory Commission Office of Nuclear Material Safety & Safeguards Division of Fuel Cycle & Material Safety Washington, D.C. 20555 Attention: Mr. Charles E. MacDonald, Chief Transportation Branch

Subject:

Renewal of Super Tiger Shipping Package Certificate of Compliance No. 6400, Docket 71-6400 Gentlemen: The Westinghouse Electric Corporation hereby requests renewal of Certificate of Compliance No. 6400, Docket 71-6400 in accordance with the information attached to this letter. The package information referenced by the current NRC certification has been consolidated into a single application per your request. In addition, information requested by your letter regarding leakage test requirements and seal replacement schedules is presented in Appendix C of the attached material. A check in the amount of $150.00, payable to the U.S. Nuclear Regulatory Commission is attached as payment of the renewal fee. Please send the renewed certificate to me at the above address. If you have any ques tions regarding this matter, please write me at the above address or telephone me on 412/373-4652. Very truly yours Y / _/f b ,/ $$$?h(' f j kbh'tR_ 0C Ronald DiPiazza, N2 nager NES Lica c ' c'c, ni c i m t ion /dc 1Cd23 .8008o10 /O THIS DOCUMENT CONTAINS ~ P00R QUAUTY PAGES

{; .1.0 Super Tiger' Packaging Packag'nc Description 1.1 i Designation - Super Tiger. Shipping-Container Gross Weight - 45,000 pounds, maximum Fabrication - The package. consists of two, rectangular, essentially concentric, steel boxes. The space between the boxes is filled with a rigid, foamed plastic. The overall dimensions of the outside shell-is approximately.8' x 8' x 20'. The design and fabrication details for the Super Tiger Shipping Container are given in PPI Drawing 32106 which is-attached as Appendix A to our application, dated July 28, 1980, on Docket 71-6400. The contents will be further enclosed in a DOT Spec. 7A, or eg'uivalent, packaging. - The inner packaging is tied down or braced so as to withstand the forces specified in 10CFR71.31 (d). Coolants - Not required. 1.2 Contents Description Radioactivity - Not to exceed 2500 curies of recycle plutonium. Fissile constitusnt - Recycl'e plutonium possibly mixed with enriched uranium. Total Pu plus U will not exceed 300 grams. Form of 1NM 1 (. i) Radioactive material including fissile material as solids or liquids, in normal or special form packaged in secondary packaging which meets the requirements 'for Type A (49 CFR 5173.389 (j)) packaging. (ii) Radioactive-material including fissile material as solids, in normal or special form packaged in secondary packaging which meets DOT Specification 17C or.7H 55-gallon steel drums. Fissile material 1 ' concentration shall be no more than 5 grams fissile material in any liter. c Docket 7L-G400 D6te: '7-28 Revision No. Date: T } L

Q - -, a m. - a, y:, n,-,. _ e nw ~.. a u--u +~ (iii) Radioactive material including fissile material as solids in normal or special form packaged in an inner containment vessel which conforms to DOT Specification 2R and with a maximum usable inside dimension of 5.25 inches. The inner containment vessel shall be centered and positioned within a 55 gallon capacity DOT Specification 6J, 17H, 6C or 17C steel drum by solid industrial cane fiber-board having a density of at least 0.249/cc or by at least 4 steel rod radial spacers at 00 separation with bagged or tamped vermiculite having a density of at least 0.072 g/cc. (iv) Plutonium-bearing solid wastes packaged as follows, with no mixing of waste forms within a single drum: Soft waste (plastic sheeting, gloves, paper, profilter me'dia, polyethyl'ene bottles, shoe covers, etc.) Double-bagged in 12-mil thick PVC, with each bag heat-sealed (bag size not exceeding 22" x 16" x 10") and packaged within a DOT Specification 17H or 17C 55 gal steel drum with a sealed plastic liner and equipped with a standard drum closure. Hard waste (eauipment, metal cans, tools, etc. and HEPA filters Sharp edged and pointed items shall be rounded off and blunted: A. All items shall be strip coated (by painting, dipping, spraying, etc.) to fix containment prior to packagina. Glassware shall be sealed in metal containers. Zach item shall be double-bagged within 12-mil thick PVC, with each bag heat-sealed. Each item shall then be tightly packaged within 8'l ") I .,l 7

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.z mm m _.. _ m._ + x ' DOT Specifical ion 1711 or 17C 55 gal. steel drum. The 55 gal.timi shall be lined with a scaled plastic baq ttmsr and equipped with a standard drum clcsur.- .r B) All items shall be individually double bagged within 12-mit Ihick PVC bagging material, with each bag heat nealed, and these items shall be foamed rigidly in place within a DOT Specification 1711 or 17C SS gal steel drum, equipped with a standard drum closure, such that.a minimun annular thickness ol' 2 inches is maintained between the waste packaqon and inner drum wall. A minimum thickness ot'.1 inches of foam (foamed in place) will be maint ained between' the bottom of the drum and the lower most waste package, and between the lid of t'ho drum and the uppermost waste package. The foam shall have a nominal density of 0.029 g/cc. Solidified liquid waste Liquid waste shall be solidified in concrete in 30-gal drum which is sealed in a plastic bag and centered and supported in'a DOT Specification 17C or 17H 55-gal steel drum by vermiculite, absorbent, plastic or foam material. The SS gal drum shall be lined with a sealed P astic liner and equipped with a standard drum l closure; or Liquid waste shall be solidified in concrete in one or more containern which are lined with a polyethylene sealed bag. Each container-shall be double bagged in 12-mil PVC baqqina material, and each bag shall be heat scaled. These bagged containers shall be packaged. ltr in place foaming within a. DOT Specification 17H.or 17C steel drum, equipped with a standard drum closure, an outlined in itv' B) above. h$4 1 ' g-T Y D b 1_W O_ O #

y-Large equipment waste (glove boxes, furnaces, blowers, ductwork, etc. HEPA filters excluded) Large equipment which will not fit in'to e 55-gal steel drum (see above contents) shall be enclosed in a strong, tight fitting box constructed of minimum 3/4" thick plywood. The equipment con- .taminated surfaces shall be strip coated (by paint-ing, dipping, spraying, etc.) or foamed to fix con-tamination or otherwise sealed by pipe caps or gasketed blind flanges prior to packaging. The space between the equipment and the box shall be filled with foam or vemiculite. Smaller strip coated (as outlined above) equipment items (which will not fit into a 55 gal drum) may be placed inside the larger piece of equipment (e.g., glove box) provided the space between the smaller and larger equipment is also filled with foam or vermiculite. All sharp or protruding objects from equipment shall be removed or blunted to eliminate the possibility of these objects damaging the packaging during normal or accident conditions of transit. Boxes shall not be comingled with 55-gal drums. The appropriate details regarding packaging of plutonium bearing solid wastes are provided in Appendix D to our application dated July 28, 1980. Neutron Absorbers, etc. - Not applicable Maximum Net Weight of Contents - The maximum net weight of the contents (including all DOT-7A or equivalent packagings and tie-downs or bracing) will not exceed 30,000 pounds. Maximum Decay Heat - Not to exceed 30 watts, total. Docket 71-6400D0fc 7-20-30 Revision ido. Dofc-PCGC

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.: +. ~ _. .u 2.1 General Standards for All Packages (Compliance with Subpart C of 10CFR71 General Standards - The material of the packaging is such that it will not react with the inner pack-agingts) or its tiedown or bracing. The inner DOT-7A, or equivalent packaging is constructed such that there will be no reaction with the plastic bagging material. 'The package is equipped with a pos.;tive closure device and scaling means. The specified system of lifting eyes will support 135,000 pounds without material yielding, as demon-strated on pages.21 and 22 of the Mechanics Research, Inc. (MRI) Report No. C2378, which is attached as Appendix B to our application, dated July 28, 1980 on Docket 71-6400. The same data demonstrates the adequacy of the tiedown arrangements. Standards for Large Quantity Packagings - The ability of the package to withstand a static, uniformly distributed load of 5 times the gross weight of the package is calculated on pages 13 and 14 of MRI Report C2378 attached as Appendix B. The resistance to a 25 psi external compressive force is computed on pages 19, 20 and 21 of MRI Report C2378 attached as Appendix B. 2.2 Normal Conditions of Transport Standards for Normal Conditions - The requirements specified for a package under normal conditions of operation will be met as a result of providing a DOT-7A or equivalent, inner packaging. The Super Tiger packaging will provide significant redundant containment.

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.... :- - m% g. _ - _ n R.m - __ : _ n :_ _ _ m.2 2.3 Hypothetical Accident Conditions Standards for' Accident' Conditions - The ability of the . Super Tiger packaging to provide superior protection to the DOT-7A or_ equivalent, inner packaging is -documented in MRI Report C2378 which is presented in Appendix B of this submittal. The report clearly demonstrates that there will be no mechanical or -thermal. event which would effect the inner steel box as a result of undergoing the hypothetical accident conditions. As a result, the containment effective-ness of the inner box would be unimpaired and the stresses imposed on the inner DOT-7A or equivalent, packaging would be significantly reduced. 3.0 -Criticality Evaluation 3.1 Package Array Evaluation The discussion which demonstrates that criticality will not occur as a consequence of damage to the inner containers is presented in Appendix E to our application date July 20, 1980. 3.2 Fissile Classification As a practical matter, each Super Tiger package will constitute a full' load shipment, due to its size. Each package will be assigned a Fissile Class as prescribed-in.10CFR71.6. When the quantity of SNM requires a Fissile Class III designation, the exclusive use of vehicle will be specified on the shipping papers. 4.0 Procedural Controls For each use, prior to closing the Super Tiger, the DOT-7A or equivalent package will be inspected for general quality and acceptability, the tiedowns or braces used to secure the DOT-7A or equivalent . package will be checked and the Super Tiger gasket will be inspected to assure that it is complete and . free from defects. ng4WL2A-phiM)Dofo: 7-28-80 . Revision No. Dofc:

e Following closure, the package.will be inspected to assure the presence of all closure bolts for which pro-vision ~is made in the-packaging. The lifting eyes and tiedown eyes also will be visually' inspected to assure that they do not display any cracks, thin sections, or 'other gross defects. The leakage test requirement for the package is pre-sented in Appendix C to our application dated July 28, '1980, on Docket 71-6400. The appropriate shipping personnel will be responsible to maintain the required records on each shipment. s t _ Docket 71-6400Date:7-28-80 Revision No. Dore:

APPENDIX A Super Tiger Construction. Drawings Protective Packaging Inc. Drawings 32106-1, Sheet 1 Revision F 32106 Sheet Dockct 71-64 00 Dato: 7-28-80 Revision No. Date:

APPENDIX B Mechani.cs Research Inc. (MRI) R,eport No. C2378 ) Dockct71-6400 Date: 7-28-80 Rcvision No. D o!c:

APPENDIX Q ".=.=. t ENGINEERING EVALUATION OF THE M SUPER TIGER OVERPACK DESIGNED TOR THE SFCPMENT OF LARGE QUANTITIES .OF HAZARDOUS MATERIALS m e c 8 O PH o $4 ci o G: C H o.4 e4 H 'd O.C C C Av o b

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1. O INTRODUCTION The purpose of this test report is to verify that the proposed Su'per Tiger shipping container is capabic of meeting the performance criteria set forth on 10 CFR.71 and 49 CFR 171, (Reference 1 and 2).

The Super Tiger overpack will be used to transport packages meeting criteria of Department of Transportation regulations enumerated in the Department of Transportation's Hazardous Ma'tcrials Regulations, (Titic 49 CFR, Part 171, Pa ra. 173. 3 96). In all cases the packages will be approved appropriate specification containers or U. S. A. E. C. approve,d containers for fissile radioactive material shipments by the AEC or one of its contractors or lic ens e c s. The Super Tiger. will be transported in a vehicic assigned sole use of the consignor, with a total transport index of 50 for fissile class 2 shipments I or the maximum number of packages in accordance with DOT regulations (Para.173.396 " Tabic of Authorized Contents") for fissile class 3 shipments. In all cases of fissile class 3 shirments, transport controls will be exercised [., t' protect against loading, transporang or storing of that shipment together o - e. 1 with other fissile material. This criteria was established to simulate hypothetical accidents in which any package containing hazardous materials ?- must be capabic of surviving. The proposed container will be used for hauling approved' specification containers of Type A, ' Type B and large quantitics of radioactive materials in solid, liquid and gas form. ' Maximum payload weight is approximately 28,700 lbs. with gross weight of 45,000 lbs. The DOT design discussed in this report is depicted on MRI- -Drawing No.-121350. (l'P E 3 2 / C6 ) h PR ')RIET Dit is d uten ontai prop eta in- \\ fo ation f Pr motivo acka.'ng, c.. Eor 1 Q2, h a, n uh. 9

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SUMMARY

Since the Super Tiger is intended to act as a protective overpack for the shipment of large quantitics of hazardous materials, it was icit that the design should be substantiated not only by engineering evaluations but also by physical testing. The design philosophy was to use proven computer routines and analysis techniques to evaluate and size the prototy.pc design. Once this was complete, a full scale container was fabricated and subjected' to those tests critical to its acceptance. After all the testing had been completed, the following results were noted: 30 foot Drop Test - The container, loaded with a combination of liqbids o and solids, was dropped 30 feet onto the corner of its lid. The outside shell indented less than 14 inches with no deformation whatsoever to the inner container. o 40 inch Puncture Test - Side No. 3 sustained two - 40 inch drops onto " a 6 inch diameter pin resulting in no yielding or indentation of the inner container wr.11. Fire Test - Temperatures in excess of 1500 F for over 30 minutes werc," o sustained with a rise in contents temperature to a level of less than hI 150 F. , B'y combining these test results with additional analysis, it has been concluded that the Super Tiger possesses the ability to protect its liquid, gas or solid contents from exposure while meeting those AEC and DOT regulations stated in Reference 1 and 2. All cargo will be supported in a manner capabic of producing no more severe loading on the internal container than that of the tested prototype. Overall container dimensions and foam thickness can bc ecaled down as a function of impact pressures. 3.O CONFIGURATION / \\ The _overpack was designed as a general use container for the shipment of Type B hazardous materials. It was configured to possess the appearance and d

.x dimensions of a standard 8' x 8' x 20' modal cargo container, (see photo 1). Since it utilizes the universal I.S.O. corner fittings, it can be handled, stored and shipped in the same manner as any standardized shipping container. This provides obvious.cconomic advantages over any system implying a non-conventional container. l The overpack basically consists of two rectangular steel shells separated with rigid fire retardent polyurethane foam. Steel shells being fabricated from a low carbon steci are extremely ductile, thus allowing large distortions with no tearing. In addition to providing puncture and penetration resistance, the shell also acts as a durable flame shield. Since the thermal conductivity of polyurethanc foam is considerably lower than that of the best rockwool or fiberglass insulation, excclient thermal protection is provided. Due to its low cost and high energy absorbing capability, polyurethane foam als'o prevides P r~' i* 4,2 1 O G an ideal shock isolation media. MRI Drawing No. 51-?rlef>O-is attached to provide all construction details. p. ..._..y-7. e.7.. ,.y-c 7 y n f . Photo 1 JJ L/ .I: (q w *i-

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4. The f.ollowing is'an analysis of the Super Tiger's ability to resist the ~!oads of Paragraph' 71. 32 (a) of 10 CFR 4:. Part 71. ,1 = 956lb/m. hh h 'I '( l r r r Il x p.-. -{ -~ L- ~ A) Bending moment at bolt centerline: w = (5) (45,000) /240 = 938 lb. /in. x = 35 L = 240 Mt.= wx (L - x) /2 Mc = (938) (35) (240 - 35) /2 Mg = 3,365,000 in. -lb. . Conservatively assume only the bottom two bolts react this load: Pbolt = (3,365,000 in. -lb. ) /(2) (93) Pbolt = 18,100 lbs. Allowabic. Bolt I oad = 80,700 at 125 ksi Margin of Safety (Bolts) M. S., = 80,700 ~I 18,100-M. S. = + La rge / SS = PROTECTIVF.Iw"; @T o, me-

e m m,n y .~no p.... n.- .x +n- =- n w _a s B) Max. Shell Bending Moment: 2 wL ' Mma:: " g Mmax = (938) (240)2 /8 Mmex =- 6,753,600 in. -lb. Conservatively assume all loads are to be carried by the tri-l angular corner beams. Buckling stability of the corners is provided by the foam and face sheets. Area = 2 (111/2) ( 1875) + (16. 3) (,1046) Area = 4. 3 + 1. 7 Area = 6. 0 in. l fc = M/2hA - fc = (6,753,600) /4 (96 - 111/2) (6) i fc= 6,660 psi ~ Fg= 46,500 psi Margin of Safety: M. S. = 4 6, 5 00 ~I 6,660 i M. S. = +La rge ~

Conclusion:

.The proposed container is capabic of safely reacting

loads i,et forth in Paragraph 71. 32 (a) of 10 CFR Part 71.

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c~ o. ~~u ua. .=n- . ~ =. ~ =- ...... =. -. - - - * ~ =. =. - ~ ~ ~ ~ - = = Therefore, :he full scale pro:otype design utilized this technique. A difieren: wall configuration was used for cach of the four walls. They were: Side 1 - 3/16ths plus 3/16ths plus 3/16th o Side 2 - 3/16ths plus 3 /16ths plus 1/8th o Side 3 - 3/16th plus 1/Sth plus 1/Sth o Side 4 - 3/16th plus 3/16 o In cach case, the inner phtes were to be tack welded so as to release on impact. This was true with all but Side 4, since during fabrication a near accident resulted in a plate being solidly welded. The effects were shown in the actual testing of this side. Sec Scetion 5. 4 - 40 Inch Puncture Test. 4.3 Thermal Analysis Appendix 3 contains a thermal analysis on an 'overpack resembling the Super Tige r. The container was analytically subjected to the reciuired 1475 F fire test for a 30 minute period, using a transient electrical network analogy program, (Reference 3}. The results show that the content's temperature will at no time be raised more than 10. Since this analysis was for the urethane thickness of only 7", it was felt that the Super Tiger would have n'o troubic surviving the actual fire test. 4.4. Compression i i .Pa,ragraph 71. 32b, Reference 2, requires that packaging shall be adequate to -l 1 assure that ~the containment vessel will suffer no loss of contents if subjected 1 to an external pressure of 25 psig. Since the inner and outer skins are attached by means of the rigid polyurethane foam, a stress skin design of the following configuration is provided. /

_ _. =.. = .m.__ m _s .m [- L' outer Steel Shell N Inner Steci Therefore, the external pressure loads will be carried in the form of plate bending when the outside sheet is in compression and the inner sheet is in ~ tens ion. Foam compression strengths in excess of 100 psi are present at all points. The moments in a rectangular uniform load homogenous plate with clamp'ed edges is given in Timoshenko " Theory of Plates and Shells", page 228, Reference 4, as: b 192 l. - 2. 5 l a 76 q = 25 psi I d (M ) x=a/2, y=0 = . 085 qa2 = 12,300 in-2 ~ 1. x 2. (M )x=0, y=b /2 = . 057 qa = 8, 230 in-lb 7 The resultant are as follows: Load Component Outer Skin Inner Skin 1. M cdge -6600 +11750 x 2 .M edge -4410 +7850 y l t / Ib = 11750 psi < F = 63,000 psi TU E

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) A guaranteed minimum material yield strength of 46,500 psi assures high reliabt hy. Primary loads are reacted through Section X-X producing 2 a net cross section'arca of (1-1/8 x,1-9/16) or 1. 76 in, The allowabic load per casting will be: allow = (F ) (A ) = (46,500) (2) (1. 76) P 5 s 2 Pg, = 82,000 lbs/ fitting Assuming 'four fittings to be used for lifting, then ti.c net capacity is: G's = (82,000 lb/fittin2) (4 fitting) (45,000 lbs) G's' = 7. 2S g (vertical capability) Assuming cight fittings to be used for tic down, then the net capacity is: , G*s = (S2,000 lbs /fittine) (8 fittings) (45,000 lbs) G's = 14. 5 g (fore and aft) Therefore the standard I.S.O. fitting does possess the required stre,ngth to meet tie down requirements as set forth in Reference 2.

5. O FULL SCALE TESTING

. A full scale prototype container was fabricated by Star Iron and Steel Company, Tacoma,' Washington and subjected to the required testing as outlined in Reference 1 and 2. Mr. A. O. Dodd, Nuclear Safety Branch. H LS Division, ' Richland, Washington, acted as official test witness for the AEC. e W

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3gg 4 r, F i 8 2, r. ~. p' x gh Q c,* ~ } 'l;.' ', ' '. /;*..J. N. ..L.- - Y./k:.] ppgp*' s,- .+ / ~ s. D..:4 Q.: g;y.h.g~'N;: M g c, y / \\ w{t., -Qi r,f -? ? IM.,, C.G[.., i<;r..: :, ~ < %.q. . z. ~~q,<;g.; y: ^ ., e. :- G ~. .A a-n m.._ 1. mum _ =- 4 The inner and outer container covers were secrued making the container ready for drop testing.

5. 3 30 Foot Drop Test Super Tiger was trucked from the fabrication and loading site at Star Iron to the Port of Tacoma faciiity for the drop sequence. On route the truck trailer rig was weighed at a registered truck scale which determined the gross Super Tiger weight to be 45,260 lbs.

After a considerabic amount of design review it was concluded that the most critical drop orientation would be a diagonal drop onto the corner of the cover. I / MECHANICS RESEARCH TNO..

..; y. ._ : am : : m : -- .- _ :n =-.- ,. x a, r. . A quick release device was rigged between the cranc and container to provide The drop height was measured by a 30' length of rope instaneous relea se. The container was then raised to a point where . attach'ed to the lower corne r. the lower corner was over the target area. Upon release the container was allowed to free fall 30' onto the steel plates, (See photos 10 through 14). Photo 1b <r;/ N .. c,f. .h f. !s ' *) [" 4' } u a

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...sw - O . _;.k a _ _, _.. ..n... MECITA NICS RESEARCH INC. o j 1 On impact the ext ernal s}cin' buckled in the region between the corner fitting e and the interface clorure area (see photo 15 through 18). The ductility of the plate is evidenced in the 180 degree bends or wrinkles ' f the external o s kin. An external seani weld at the edge tore for approximately 10". This introduced'no problem since the full area was backed with the diagonal-gusset plate. Maximum corner identation was less than 14". .J..W M ';;.-:'yx :.p.7 (W m. 7 7 d p nm' Photo 15 Fr'4 3, Qm..,i.' Q, VE sg)gt w

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.m m,au a. m.._,, a_ 2,,; _.. . v yw.g___. _.. _.,. M ate rial yielding appeared restricted to this area. Lat e r, on removal of the cove r, it was appa rent that deformation war wholly restricted to the cap. (see photos 19 and 20). It was felt that if the cap were to be replaced the net effect of the 30' drop would have been undetectable to the remainder of the container. The inner cavity saw no deformation whatsoever. -,1..Pho to 19 h, 4 -- - m.- - -, ' m9 Photo 20 j /&~- _,s j t, t .4, h ,,. Q, h: jM ~ "; 4 N' '1 b, i.' W -~ w .. m':.:~ e '-l -} - s, 'd ~? j y - : ;c.+3,~,___ _ :' t. : a, J .e

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_40" Puncture Test Four separate 40" drop tests were conducted. As explained in Section 4. 2, each of the four sides represented a slightly different configuration. The' purpose of the drop test was not only to qualify the container but also to provide a design evaluation of the different types of construction. The test went as follows: Test 1 - a 40" drop onto the center of Side No. 3 This side contained three layers of steel plate (3/16+1/8+1/8). On irnpact, (photo 21 and 22) the pin produced a local indentation approximately 2-1/2" deep. As can be seen from photo 23 and 24 the external skin was not cut or torn in any way. Post test inspection of the inner container failed to show any evidence of the puncture test. No indentation or deflections were detectable on the inner container. This was true for the first three tests. There was also no evidence that the 8" tall pin had bottomed ~out.

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Test No. 3 - Test No. 2 wa s duplicate.-' on Side No. 2. In this case the .maxirnu:n indentation of les s than 4" was observed, (see photos 27 and 23). 7]. I f [ J j f p -.P. h. o t o 2 7 j l r t i i j I i f i' l r s } h L- _..i ,r - i "p% a+ , ~* i f s'i e==.,

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9 y s ) 1 represent a conservat,ive test arrangement since in practicality the container would remain on top of the puncturing device during an accidential fire.

5. 5. 2 Fire All twelve burners.were ignited and the furnace door closed. Surface temperatures of the ' steel shell exceeded 500 within the first five minutes of testing. On reaching approximately 600 the virgin urethane foam begins to locally decompose creating a very dense pungent gas. Since sufficient oxygen to support combustion was not present within the shell, the gases must exhaust through the pressure port and burn external to the container.

In theory the velocity of the excaping gases is higher than the rate of flame propogation making sure that the combustion reaction is always exothermic, therefore taking heat away from the container rather than adding heat to it. Inspection ports in the furnace wall verified this to be the case. Large quantities of smoke and flame were apparent.. (see photos 37 and 38). Photo 33 ' kamw.-f.g mwX.dj P .s,..; :==.,--:-e s 1 P'% ' * ' l.' b M.,.j 2,;.C W T' n. . Q.,;.,7 .G. <.., ~ *'? ;' wn * ' v a - :(,~ - 7.s.w. : ".' '. .[1

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o g-, o. APPENDIX C Leakage Test Requirements I 1 l 10 ' D o c in- > 71- 0 10 0.O r :!:1 3 0 Revisico No. D af :- ' P.c.vre.. - - -

.1 LEAKAGE TEST REQUIREf4ENTS FOR Tile T40 DEL #6400 OVERpACK L I. SCOPE As a part of the consolidated application for the renewal of the Certificate of Compliance for the f4odel No. 6400 overpack[1,2] leakage test requir'- e ments for this package were defined per methods described by Regulatory Guide 7.4[3] and ANSI N14.5E43. Requirements were def.ined for an annual leakage test for the containment closure and its. body, and for the assembly verification prior to each shipment. In addition, a seal replacement schedule is established. II. LEAKAGE TEST REQUIREf4ENTS Leakage test requirements for'this package were determined per Section 4 of the ANSI StandardE43. This evaluation followed the steps.n that procedure. 1. Since it satisfies all requirements of Type B packaging, the package is a Type B(U) as described in Section 3.19. 1 NOTE: Unless otherwise specified, sections, tables, and appendixes-referenced in this text apply to the ANSI StandardE43, 2. The containment requirements fe both nonnal (R ) and accident (R ) N A conditions of transport are (from Table 1): x 2.78 x 10-10 per second RN=A2 -9 RA=A2 x 1.65 x 10 per second. The A values ~ for plutonium a're[5]; 2 Pu-238 0.003 Ci Pu-239 0.002 Ci Pu-240-0.002 Ci pu-241 10.1 Ci pu-242 0.003 Ci. y 1.,_. ?cvision Th. 'Dhtc &!E _ _

e l l

For this evaluation, a conservative A value of 0.002 Ci was used.

2 The containment requirements-are: l R = (0.002)(2.78)(10-10) C1/s = 5.56 x 10-13 Ci/s g A.= (0.002)(1.65)(10- ) Ci/s = 3.30 x 10-12 Ci/s. R 3. These package containment requirements were converted to maximum permissible leakage rates per Section 5.3 and Appendix B. I a. Activity of the Medium Per Section 5(b)(2) of the Certificate of Compliance for this package, plutonium in excess of 20 curies must be in the. form of metal, metal alloy, or reactor elements except for solid waste packaged in, nonr'espirable form. Therefore, 20 Ci would be the maximum activity contained in the package. Leakage from this package would be by airborne transportation of powders. Assuming that it is uniformly distributed within the package, the activity of the medium that could escape from the containment system dur-ing normal and accident conditions is: 20 Ci 20 Ci C ~- C = N A 3 3 6 3 76 in x 76 in x 172 in x 16.387 cm /in 16.28 ic 10 cm -6 3 = 1.23 x 10 Ci/cm b. Permissible Leakage Rates for the Medium Permissible leakage rates for the medium during normal (L ) and g accident;(L ) conditions are: A -7 3 L = R /C = 4.52 x 10 cm /s g = 1.23 x 10-6 N N 3 Ci/cm 3 Lg = R /CA " 1.23 x 10 = 2.68 x 10 cn jg 'g 3 Ci/cm Dato: Revision No. Date: -D onket -

c. Pressure and Temperature of the Medium The pressures and temperatures under normal conditions will be due to ambient variations encountered during transport. Assuming the altitude varies between 0 m (sea level) and 2,000 m, the pres-sure inside the package would range between 1 atm and s 0.8 atmE03 Further, assuming a temperature range between 0 and 35 C, and the worst combination of these pressures and temperatures, i.e., load the package at sea level at O'C and transport it to 2,000 m at 35 C, the pressure inside the package would be: P2=P) ([T) = (1 atm) (308 ) = 1.13 atm 1 For accident conditions, results of a thermal test as described in 49 CFR 173.398(c)(2)(iii)E73 will be used. The results of the fire test [8] at 1,500"C for over 30 minutes showed a rise in the package contents temperature to a level less than 150 F (65 C). The pressure would be: P2 = 1 atm (29 ) = 1.13 atm 4 If, however, the accident also assumes the worst condition during normal transport, the pressure inside the package could become: P2 = (1.13 atm)( )=1.28atm d. Establishing Maximum permissible Leakage Rates

From Section 3.6, " Note

It is considered conservative to assume that slurries and powders leak as water. (The predicted leakage rate will be greater than the actual leakage rate.)" Therefore, from Section B.7: I' l Dockc( Daa: Rcvidon (!c. Date: Ponc l

2L Ny (Pu-Pd)X y 2 2 Ny (Pu -Pd )y 3 3 Where: L = Fluid leakage rate (atm cm /s for. gases; cm /s for liquids) N = Fluid viscosity (cp) Pu = Fluid upstream pressure (atm) Pd'= Fluid downstream pressure (atm_) For this analysis: X = Water Y = Dry air = 0.8904 cp[6] NX b63 N = 0.0183 cp y (Pu)y=1.0atm (Pd)y = 0.01 atm Rearranging the equation and inserting these values: 2 2 X (Pu -Pd )y

LX (0.8904 cp)(1.0-0.0001) atm L N y

'Y

2Ny (Pu-Pd)y 2 (0.0183 cp)(Pu-Pd)X 2

24.33 atm L L = y (Pu-Pd)y For normal conditions: -7 3 LX " 'N = 4.52 x 10 cm /s (Pu)y = 1.13 atm (Pd)y = 0.8 atm 2 -7 3 = (24.33 atm )(4.52 x 10 cm /s) = 3.33 x 10-5 3 L atm cm /s [ y (1.13 - 0.8)(atm) Docket Date: Revi:icn No. Date: I'

7 9 0 For accident conditions: 3 Ly =-LA = 2.68 x 10 cm /s (Pu)X = 1.28 atm (Pd)X = 0.0 atm = (24.33 atm )(2.68 x 10-6 cm /s) = 1.36 x 10~43 2 3 atm cm 73 -L Y (1.28 - 0.8)(atm) -5 Therefore, the maximum acceptable leak rate is 3.33 x 10 atm 3 cm /s for dry air at 25 C and a' pressure diff.erential of 1 atm against a vacuum of 10-2 atm or less. However, for assembly verification, a maximum leak rate of a Type A quantity in 10 days 'is allowed [2] Although a leak test -3 3 sensitivity greater than 1 x 10 atm cm /s would not be required, a minimum sensitivity of 1 x 10~I atm cm /s should be 3 met. Per 49 CFR 173.389(t)E73, a Type A quantity for plutonium is 0.001-C1. The allowed leak rate is: 0.001 Ci -9 R = (10 days)(24 hr/ day)(60 min /hr)(60 s/ min) 1.16 x 10 Ci/s-The activity is: C = 1.23 x 10-6 Ci/cm 3 The ' permissible leakage rate.for the medium is: 1.16 x 10~ ~4 3 ~6 3 = 9.43 x 10 cm /s L = R/C = 1.23 x 10 Ci/cm e _ pocpet. Di:te: Rcvhion No. D ale.- .Pjyi!L,_._, _

Converting the leakage rate to that for dry air and assuming noral conditions of transport: 2 -4_ cn 3/s) = 6.95 x 10-2 3 = -(24.33 atm )(9.43 x 10 atm cm /s L Y (1.13 - 0.8)(atm) Therefore, the maximum acceptable leakage rate for the package -2 3 assembly vbrification is 6.95 x 10 atm cm /s for dry air at 25 C and a pressure differential of I atm against a vacuum of 10-2 atm or less. 4. Leakage tests are required for fabrication verification, for assembly verification, and for periodic verification. 5. Par Section B12, the se'nsitivities required for the leakage tests are: -5 3 -5 3 S <1/2 L = (0.5)(3.33 x 10 atm cm /s) = 1.66 x 10 atm cm /s for the fabrication and periodic verifications and S <1/2 L = (0.5)(6.95 x 10-2 atm cm /s) = 3.48 x 10-2 atm cm 73 3 3 for the assembly verifications. Both sensitivities are for dry air. 6. A review of the leakage tests described in Appendix A shows that a halogen detector test can exceed the sensitivity requiremen.t for. each test. III. HALOGEN LEAK TEST EVALUATION To verify that a halogen leak test satisfies the sensitivity requirement for these particular tests, the leakage rates have to be converted from dry - to the test atmosphere. From Section B4.1: Docicet Dato: I?avisi n No. Dato: Ih

2 L fly (Pu -Pd )y y tiX (Pu -Pd )y Where: X = Freon 12 (CCl F ) 22 Y = Dry air. 0, ~ 11 = 0.013 cp[6] fi = 0.01827[6] (Pu)y = 1 atm (Pd)y = 0.01 atm Inserting these values: 2 2 Ly (0.01827 cp)(Pu -Pd ) = (1.405)(L )(Pu -Pd )y (atm~2) 2 L = y X (0.013cp)(1-0.0001)atm From Section A3.7.2, the test item must contain a minimum of 0.3 kg of Freon per cubic meter of air space. For the Freon: 3 Package volume = 16.28 m Molecular weight of Freon =.1.20.91 gr/gr moles 3 3 =J(300gr/m)(16.28m)=40.4grmoles n 120.91 gr/gr moles) Freon 3 For the air: Since 1 gram moles of gas occupies 22,414 cm at standard conditions: 0 3 16.28 x 10 cm = 726.3 gr moles n '.NI 3 = 22,414 cm /gr moles The test pressure becomes: n P2 = P) (2) 1 Dock 1 D II"I' inn 11a D o '. M

Where: Pj = 1 atm n) = 726.3 'gr moles n = (726.3 + 40.4) gr moles = 766.7 gr moles 2 Therefore: 2 = 1 atm (-k7 ) = 1.056 atm = 15.5 psia = 0.8 psig P 3 ol and % Freon = nF con (100) = (

4 9"

,7 gr m les) 100 = 5.3% Calculating the leakage rate for the fabrication and periodic verification

tests, Where:

L = 3.33 x 10-5 atm cm /s 3 y (Pu)y=1.056atm (Pd)y = 1 atm L = (1 406)(3.33 x 10-5 3 2 2 atm cm /s)([1.056]2,gjg )(atm )(atm-2) y = 5.39 x 10-6 atm cm /s 3 flowever, since the Freon is only 5.3% of the gas, the leakage rate becomes: L = (5.39 x 10-6)(0.053) atm cm /s = 2.86 x 10 atm cm /s 3 -7 3 and the sensitivity is: S = 1/2 L = (0.5(2.86 x 10-7 atm cm /s) = 1.43 x 10 atm cm /s 3 -7 3 Docket Date: Rcvision No. Dato: Pnm

For the assembly verification tests: -2 3 L = 6.95 x 10 atm cm /s y L = 1.13 x 10-2 atm cm /s 3 y L = 5.99 x 10~4 atm cn.3/s S = 3.00 x 10-4 atm cm j3 3 Per ASTA L-427I93, this method can satisfy the requirements for both tests. The sensitivity of the test can be increased by increasing the quantity of Freon. For example, if the package was pressurized with Freon to 2 psig: 2 psi + 14.7 psi = 16.7 psi = 1.136 atm P 2"(1 ) "1 " ( 'l at tm) 726.3 gr moles = 825.1 gr moles n Freon " "2 - "I = (825.1 - 726.3) gr moles = 98.8 gr moles n " Freon (100) % Freon = " 98.8 gr-moles (100) = 12.0y Total 825.1 gr moles n Calculating the leakage rate for the fabrication and periodic verification tests: -5 3 Where: L = 3.33 x 10 atm cm /s y (Pu)x = 1.136 atm (Pd)y = 1 atm L = (1.406)(3.33 x 10-5)(atm cm /s)([1.136]2 _ g)3 )(atm )(atm-2) 3 2 2 X -5 3 = 1.36 x 10 atm cm /s Docket Date: Revision No. Dnic: ~r

~ Since the gas is'12.0% Freon, the leakage rate becomes: 3 -6 3 L = (1.36.x 10-5' atm cm /s)(0.12) = 1.63 x 10 atm.cm /s and the sensitivity is: 3 -7 3 S = 1/2 L - (0.5)(1.63 x 10-6 atm cm /s) = 8.15 x 10 atm cm /s i or s 5.5 times more sensitive than the previous test. Sensitivities will have to be determined for' the actual condition during each test. Based on this evaluation, a halogen leakage test using Freon 12 can be used to demonstrate the leakage requirements of the Model #6400 overpack. IV. SEAL REPLACEMENT SCllED'ULE The se?ls for the package should be replaced annually. In addition, they should be inspected prior to each shipment and replaced if necessary. The period verification leakage test should be performed in the area of the seal after each replacement. V. RECOMMENDATIONS The following requirements should be included in the consolidated applica- . tion.for renewal of Certificate of Compliance No. 6400: -5 1. A' test capable of detecting a leak greater than 3.33 x 10 atm 3 cm /s of-dry air at 25 C and a pressure differential of 1 atm against a vacuum of 10-2 a,tm or less shall be performed on the - containment system within the 12-month period preceding actual use for shipment. In addition, this test shall be performed (in the area of.the ' seal)'after each seal replacement. A halogen leakage test may be used to satisfy these requirements. { Docket - Date: Revision No. Dato:

_ 1. ,~ -2 3 2. A test capable of detecting a leak. greater than 6.95 x 10 atm cm /s of dry air at 25 C and a pressure' differential of 1 atm against a vacuum of 10-2 atm or less shall be performed tb verify the assembly .of the package prior to each shipment. A halogen leakage test may be used to satisfy these requirements. 3. The seals shall be ' inspected prior to each shipment and replaced.if required. In addition, each seal shall have been replaced within the 12-month period preceding actual use for shipment'. The leakage test i requirements described-in Paragraph 1, above, shall be used after each replacement. VI. REFERENCES l 1. .USNRC Certificate of Compliance No. 6400, Revision 8. 2. Letter, USNRC to Westinghouse, December 31, 1979. 3. Regulatory Guide 7.4, " Leakage Tests on Packages for Shipment of l Radioactive Materials," June, 1975. 4. ANSI N14.5, "American National Standard for Leakage Tests on Packages fo'r Shipnent of Radioactive Materials," October,1977. 5; ' International Atomic Energy Agency (IAEA) Regulations for the Safe i Transport of Radioactive Materials, Safety Series No. 6, 1973 Revised l . Edition. 6. CRC Handbook of Chemistry and Physics,1976. 7. Code of Federal Regulations, Title 49, Transportation. 8. Mechanics Research, Inc., Report C2378, " Engineering Evaluation of the' Super Tiger Overpack Designed for the Shipment of Large Quantities of Hazardous Materials," (A Supporting Document for Reference 1). 9. ASTM E 427-71, " Standard Recommended Practice for Testing for Leaks Using the Halogen Leak Detector (Alkali-Ion Diode)," Reapproved 1976. t m nedVD _ IDatei !?cvision t!o. Date: a

.E ~ APPEhBIX D Packaging Evaluation for Plutonium Bearing Solid Waste Dockef71-6400 Octe: 7-20-80 Revision No. Date: T. . _1 1

.. _ - - - -. ~... -. - - - _ - -... - 6 9 INFORfMTIOri FOR PLUT0NIUM WASTE DRUM SHIPMENTS WESTINGHOUSE NUCLEAR FUEL DIVISION PLUT0NIUM FUELS DEVELOPMENT LABORATORY s \\ i i Docket No. 7.1-6400 Certificate of Compliance No. 6400 . April 3,1979 ~. \\ e .m. -y,,, _ _... -

TABLE OF C0:lTENTS Section Ti tle Pace,. 1 INTRODUCTION - l-l 2 WASTE CHARACTERIZATION AND HANDLING TECHNIQUES 2-1 2-1 2.1 Soft Wastes 2.1.1 Waste Description , 2-1 ~ 2.1. 2 Current Packaging Methods 2-1 2.1.3 Packaging Procedures 2-2 2.2 Hard Wastes 2-3 2.L1 Waste Description 2-3 2.2.2 ' Current Packaging Methods 2-3 2.2.3 Packaging Procedures 2-4 31 3 OVERPACK PACKAGING PROCEDURE g e 5 9 e 9 e G e ! 6 t 4 11 M

.I SECTION 1 INTRODUCTION Plutonium-bearing solid wastes,. gen.erated within the Westinghouse Plutonium Fuels D:velopment Laboratoty (PFDL), are packaged in DOT Specification 17H 55-gallen drurs and transported to a disposal ' site in a Super Tiger package. Specific restrictions, however, have been placed on shipment of these wastes un'less it is shown that the inner 55-gallon drums containing plutonium in excess of twenty curies will not release the plutonium when the entire shipping package is subjected to the normal and accident conditions of transport. s Waste descriptions, packaging methods, and other significant areas of infonmtion are described in the following sections, in support of a request for exemption per 10 CFR 71.42(b3). s rd e S l 'i 1-1 O

~ - ~ - - - - .._n--_,---~,----,- _.m: -..,. .n SECTION 2 WASTE CHARACTEP,IZATION AND HANDLING TECHNIQUES 2.1 SOFT WASTES 2.1.1 Waste Description -) This material includes plastic sheeting, glove box gloves, paper, cardboard,. ~ prefilter media, empty polyethylene bottles, canner's gloves, shoe covers, etc. These wastes account for the largest percentage of all.the waste generated. The soft wastes generated within glove boxes contain a plutonium contamination which is "smearable" but not visually detectable. Supportive ' measurement data show-that an individual waste package, removed from a glove box, norpally contains loJ" level quantities of plutonium contamination. Non-glove box soft wastes are handled as potentially contaminated because they are in the laboratory area. The activity levels from these wastes are ~ less than detectable. s 2.1.2 Current Packaging Pethods Soft wastes generated within glove boxes are removed in 12-mil thick PVC bags using specialized bag-out procedures and heat-sealing techniques. Each scaled bag of waste is placed into another 12-mil PVC bag which is also scaled. This doubic-bagged package is then placed into a large 4-mil thick . hen the drum is filled, the liner is PVC bag which lines the 17H drum. W sea' led with plastic tape. 2-1 1 j

Potentially contaminated non-glove box soft wastes are packaged in the same manner as the glove box wastes regardless of their nondetectable. levels of con tamination. Soft wastes are compacted when required as part of a volume reduction pm gram.- Soft packages, described above, are transferred to a specific ~ glove box, opened, placed inta the compactor bag, and subsequently compacted. After a specific quantity of soft packages are compacted, the package is removed, double bagged as previously described, and placed into the lined 17H drum. A typical compacted package with double bag has a . dimension of 22" high x 16" length x 10" width. Each sealed soft package, whether noncompacted or compacted, is nondestruc-tively assayed to determid6 the plutonium content. If a package cuntains a quantity cf plutonium contamination greater than 15 grams as specified by a PFDL operational procedure, it will' be returned to the glove box area of origin for investigation, redistribution, and repackaging. ' ~ 2.1. 3 Packaging Procedures A. Current packagir g trethods for noncompacted and compacted soft wastes will remain the same. ..B. Procedures will be revised to imp 1ement the following segregation requirements during packaging into 17H drums: 2-2 ~

, - n.m..

._.....w-- i 1. Soft wastes will not be comingled with hard wastes within the same 17H drum. 4 2. Compacted soft wastes will not be comingled with noncompacted 4 soft wastes within the same 17H drum. p 2.2 HARD WASTES 2.2.1 Waste Description This material includes failed equipment, empty metal cans, tools, defective glassware, solidified liquid waste, etc. These wastes currently account for a small percentage of the PFDL waste generated. This waste is closely examined and precondi3oned prior to renoval from the glove box. Precondi-tioning includes brushing and wiping these waste items to collect any ~ residual raterial that may be present. Non-glove box hard wastes are handled as potentially contaminated because they are in the laboratory area. I l t' ' 2.2.2 Current Packaging Methods Hard wastes generated within glove boxes are packaged using the double-bag l-procedure and heat-scaling techniques described in Section 2.1.2 All sharp. edges and pointed itens are rounded off and blunted prior to packaging to prevent ' tearing and rupture.of t'he bag material. Potentially contaminated non-glove box wastes are packaged in the same manner. \\ 2-3 O

~ ~~ -- w [ Defective and broken glassware, e.g., beakers, pipets, etc., is crushed in Liquid waste quart cans, covered by a lid, taped closed, and double bagged. The 30-gallon drum, sur-is solgified in concrete in 30-gallon' drums. rounded by a plastic bag drum liner,.is located inside a 17H 55-gallon drum. The void space between the 30-gallon drum and the 55-gallon drum is filled After the concrete-liquid mixture hardens, the 30-gallon with an absorbent. drum is sealed, the bag i's taped closed, and the lid of the 17H drum is sealed. Liquid waste 'is assayed prior to solidification to ensure that the package does not exceed 15 grams of plutonium contamination. 2.2.3 Packaging ProceTures All contaminated hard waste items will be treated for fixation of A. the contamination prior to packaging. Dependent on the specific. hard item, the method of treatment would include the use of a plastic strip ' coat, a plastic dip process, concrete solidification, As an example, crushed glassware would be solidified in etc. concrete,' tools could be dipped, weigh balanges could be sprayed, I etc. Procedures will be revised to implement the following waste B. ~

segregation requirements during packaging into 17H drums

} i i I - \\. 2-4 1 i

v. 'l. lHard wastes will not be comingled with noncompacted and compacted soft wastes within the same 17H drum. 2. Plastic packing material will be added in the 1711 drum to fill voids surrounding the double-bagged packaged hard item. U C. In the case of a solidified drum, the void space between the 30-gallon and the 55-gallon drums will be filled with an absorbent or plastic packing mterial.. The drum liner will be heat-sealed closed instead of taped closed. s O O* e W e k% i i i a 1 4 e e l' i \\ \\ 2-5 w, w~ .-n.

e SECTION 3 '0VERPACK PACKAGING PROCEDURE A full load of 42 drums placed in the. Super Tiger will be requimd. In the event a full load of contaminated waste is not available at the time of shipment, additional drums, whether full or empty, will be added to ensure the full complement of 42 drums. 4 e O mueWD .6 o O G 9 6 e m t

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s \\/ 12uclear Fuel Services, Inc. ERWIN. TENNESSEE 37G50 - e (G15; ~ w) A Subsidiary of Getty Oil Company j a. s Distribution 7/6/79 liRC FILE No. 71--6400 11RC File (Corp.) C. W. Taylor W. C. Manser, Jr. July 6,1979 C. J. iiichel f A. M. Maxi v K. D. Hensley J. E. Kirkpatrick Mr. Chdries E. MacDonald, Chief ' Transportatien Branch Division of Fuel Cycle and Material Safety ~ U. S. lluclear Regulatory Comnission Washin'gton, D..C. 20555

Reference:

(1) Docket 70-143; ST:M l24 (2) Letter _ dated 12/22/78, C. J. liichel to C. E. MacDonald (3) Letter dated 2/26/79, C. E. MacDonald to C. J. Michel (4) Letter dated 4/26/79, C. J. Michel to C. E. MacDonald (5) Letter dated 5/30/79, C. E. ItacDonald to C. J. Michel (6) llFS-NRC Meeting, Silver Springs, Md., 6/7/79

Dear !!r. MacDonald:

The information requested in referbnce'5 regarding our request for an

amendment to Certificate of Compliance' USA /6400/B()F is submitted in the attached. safety analysis in accoidance with. agreements and discus-sions made at the meeting listed in reference'6.

3~ s ~ ~ - Your.carliest action on this iequest is appreciated. Very truly yours, .3 b ] Adminisltrative Manager C. J. tichel s. 'Y .~ CJM:kj Attachment / \\ PD $d8 ?0f

m r, age or e ( s + - ATTACll:ENT To Letter Dated July 6,1979 ' C. J. Michel to C. E. MacDonald SAFETY Af!ALYSIS REPORT FOR PLUTO:1I0:1 PACKAGIf!G I.- -INTRODUCTIOt Nuclear Fuel Services proposes to utilize the Super Tiger packaging presently liconsed.by the Nuclear Regulatory Comnission as Certificate of Compliance USA /6400/,8()F to transport contaminated waste generated - in the deconnissioning of its plutonium facility (see NFS Plan for De-commissioning of Plutonium and Uranium-233 Facilities, dated October 9, 1978). Although the Plan specifies decontamination of equipment prior to packaging, it is anticipated that some packaged objects will contain residual quantities of plutonium in excess of 20 curies. Since the Super Tiger was not licensed to transport more than 20 curies of plutonium in oxide for ', NFS requested, in a letter dated December 22, 1978, an amandment to tr.2 Certificate to permit the Commission to specifically authorize ' shipments in excess of 20 curies of plutonium. In response to that request for amendment, the NP,C requested additional information in letters dated February 26, 1979 and May 30, 1979. This report consolidates all information required for our amendment request relative to the transport of pieces of large equipment contain-ing in excess of 20 curies of plutonium. II. SCOPE This report is written to demonstrate that the form of the plutonium 4 to be scaled and packaged in plywood containers within the Super Tiger package is 'nondispersable and therefore nonrespirable. III. WASTE DESCRIPTION ANb PREPARATION ' ~ In the course of decomnissioning the NFS plutonium facility, large picces of equipment such as glove boxes, furnaces, blowers, ductwork, etc., which will not fit into a 55-gallon drum, will be prepared for dispos al. All such equipment will be decontaminated of any gross j . quantities of plutonium prior to packaging. NFS will immobilize any residual contamination and provide the first containment barrier by applying a strippable coating on all exposed contaminated surfaces of equipment and metal scrap. This coating has clastic properties which ninimize cracking and chipping during impcct. It will easily withstand the 150" F temperatures that were experienced within the Super Tiger during the fire test. It can be applied by brushing, dipping, or spraying, It also has the property of retaining contamination if the coating is removed from the surface. r m EpaHn

. uu-*-- g - Page 2 of 2 All sharp or potentially dangerous objects that protrude ~ from equip-ment will be reroved or blunted to eliminate the possibility of these -objects piercing their containment. In order to effect economies in packaging / shipping and in total land commitment at the burial site, NFS may elect to place smaller metallic scrap, piping, etc., that will not fit into a 55-gallon drum, inside of the. larger glovebox and equipment items being packaged for' transport. In this case these smaller-objects will be subject to the strippable coating requirements outlined above. In addition, such objects shall be firmly supported inside the larger pie'ces by filling the surrounding void spaces inside the larger pieces with packing materials such as foam or vermiculite. The intent of this procedure is to minimize the chance for penetration 6f the containment barriers under accident con-ditions. Combustibles, cleanup materials, and similar items will not be included or shipped in this packaging system. In no case will objects small enough to. fit into a 55-gallon drum be packaged in wooden boxes. IV. PLYWOOD COMTAINER' DESCRIPTION Plywood boxes will be sized specifically for the gloveboxes and large pieces of equipment to provide for a tight fit, thus minimizing in-ternal movement during transport. All boxes will be rectangular and constructed with 3/4" exterior grade plywood. Packing materials such - as foam or vermiculite will be placed between the contained glovebox and the plywood box for additional protection and support. Also, if the plywood boxes contain large equipment items other than gloveboxes, packaging _ materials such as foam or vermiculite will be used to fill the void spaces between the equipment and the box. The plywood containers will be shored with wood within the Super Tiger to minimize movement. Where space permits, dunnage bags will be utilized. Plutonium content of each box will be limited to 60 grams. The volume of each' box will be greater than that of a 55-gallon drum. 9. rp s. e U 6 / g O g a p . s. k

APPENDIX E Criticality Evaluation i 1 Dodt>f !1-64 00D0fe: 7-28-80 ~ Revision No. Dofe: e ~- 12 J}}

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