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Requests Renewal of Certificate of Compliance 6078 for 5-yr Period.Containers Currently Approved for Shipping Fuel Assemblies Enriched to 3.5% U-235.Requests Containers Be Approved for Fuel Assemblies Enriched to 4.1% U-235
	ML19290C060
Person / Time
Site:	07106078, 07109022
Issue date:	12/10/1979
From:	Lichtenberger; ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Macdonald C; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
	14977, NUDOCS 8001090107
	Download: ML19290C060 (73)
	v • d • e

{{#Wiki_filter:h l' b O T Y k,- C-E Power Systems Tet 203/688-1911 Comeustion Engineenng. Inc. Telex: 99297 ~ tcoO Proscect Hill Acad Wincscr. Connecticut C6095 H POWER SYSTEMS License SNM-1067 December 10, 1979 Docket 71-9022 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle & Material Safety Gentlemen: It is requested that Certificate of Compliance No. 6073 be renewed for a 5-year period. Enclosed are ten copies of our renewal application wnich is a consolida-tion of our original application dated July 3,1969 and all supolements to date. The CE Model 927Al and 927C1 containers are presently licensed for shipment of unirradiated U02 fuel assemblies enriched to a maximum of 3.5 wt i U 35 It is requested that these containers be approved for shipment of unieradiated UO9 fuel assemblies enriched to a maximum of 4.1 wt i U235 A comolete criticality safety analysis has been performed, the calculations and results of which are in-corporated into this renewal application. If you have any questions regarding the content of this application, please con-tact Mr. G. J. Bakevich of my staff on extension 3150. Very truly yours, H. V. Lichtenberger Vice President-Nuclear Fuel )[)3 l4[ Nuclear Power Systems-Manufacturing HVL/GJB/ssb Enclosure Ioq sooloM M

4 1 GENERAL INFORMATION 1.1 Introduction This renewal application is submitted for aporoval of Combustion Enqineering's fuel assembly shipping containers, identified as Model 927Al and Model 927Cl. The Model 927Al container is structurally identical to the Model 927C1 container with the exception of its reduced length. These containers meet the criteria of 10 CFR Part 71.40(a) for shipment as Fissile Class III, with a limit of 8 packages per shipment. 1.2 Package Descriotion 1.2.1 Packaaina The 927Al and 927C1 containers are fabricated of carbon steel and consist of a strongback and fuel bundle clamping asser:ly, shock mounted to the steel outer container. The fuel bundles are separated oy 1/d" thick, 5" x 6" x 3" high carbon steel spacer blocks bolted between the bundles to maintain a r,iinimum bundle to bun-die separation of 6 inches. The Model 927Al container is approximately 43" in dia-meter by 189" long with an approximate gross weight of 6,200 lbs. The Model 927C1 container is approximately 43" in diameter by 216" long with an approximate gross weight of 7,000 lbs. All safety-related features of both containers are described in CE Drawing NFM-E-4108, Rev. O, sheets 1 & 2 dated 11/27/79 which are included in Appendix 1.3 of this application. Drawings of pressure relief valves and lifting devices are also shown in Appendix 1.3 with material lists, dimensions, gaskets, and weld speci-fications included. 1.2.2 Ooeritional Features N/A (These containers are used for the shipment of unieradiated PWR fuel assem-blies, are of relatively simple design, and do not incorporate cooling systems, shield-ing,etc.) 1.2.3 Contents of Packagina Each shipping container shall contain two fuel assemblies. Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed, polyethylene sheath whicn will not extend beyond the ends of the fuel assembly. The ends of the sheath shall not be folded or taped in any manner that would prevent flow of liquids into or out of the sheathed fuel assembly. The CE Model 927Al oackage will contain two fuel assemblies consisting of 0.3765" diameter uranium dioxide pellets clad in.028" thick zircaloy-4 tubes in a 14 x la square array with a 0.58" pitch. Each fuel bundle consists of a maximum of 17c #uel rods enriched to a maximum of J.1", US. The maximum radicactivity for each fuel bundle is 0.30 curies. The maximum for each loaded fuel container is 1.60 curies, witn the maximum radioactivity for a shipment of eight containers or sixteen #uel bundles being 12.8 curi e. The CE v del 927C1 package will contain two fuel assemblies consisting of 0.325" o ciameter uranium dioxide pellets clad in.025" thick zircaloy tubes in a 16x16 square array with a.5C6" pitch. Each fuel bundle consists of a maximum of 236 fuel rods 1733 148 1-1

enriched to a maximum of 4.1% U235 The maximum radioactivity for each fuel bundle is 0.90 curies. The maximum for each loaded fuel container is 1.80 curies, with the maximum radioactivity for a shipment of eight containers or sixteen fuel bundles being 14.4 curies. For both the Model No. 927Al and 927C1 container, the upper bundle bracket may be secured to the strongback by either of the following hardwares: (i) Ten 3/4-16 UNF Hex Head bolts with associated washers and nuts, or (ii) Eight 3/4-inch diameter steel clevis pins with associated steel hair pin catters, and two 3/4-16 UNF Hex Head bolts with associated washers and nuts. The two bolts shall be placed in the uppermost position for that specified part. 1.3 Accendix Dimensional details of both containers are described in Drawing NFM-E-4108, Rev. O sheets 1 1 2 dated 11/27/79. 1733 149 l-2

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2. STRUCTURAL EVALUATI0ft 2.1 Structural Desian 2.1.1 Discussion The containment vessel for the two fuel assemblies consists of the 43" dia-meter carbon steel outer shell. The internal and external structures supporting and protecting the containment vessel for the two fuel bundles are shown in the referenced drawings (Appendix 1.3) as well as the internal structures for suppor-ting the fuel bundles within the containment vessel. The external shell is sup-ported by "L" shaped steel flanges,1/4 inch thick, welded transversely to each half of the shell. The structural design has not changed from the presently licensed container. The only recuested change from the presently licensed container is the option to use closure bolts which have a different shaped head tnan the bolts presently used. The " Bolt, Special" may be replaced by the "Round Head Square Neck Solt" as shown in Appendix 2.10. The proposed bolt is equal to or greater than tne present bolt in mechanical properties. A comparison of the two bolts to be used is provided in Appendix 2.10. 2.1.2 Desion Criteria The design test results described in Appendix 2.10 support the structural re-quirements specified in 10 CFR Part 71.35 and 71.36. 2.2 Weichts and Centers of Gravity The CE Model 927Al container weighs approximately 6,200 lbs. when loaded. The 14x14 bundles weigh approximately 1,300 lus. each with the container weighing approxi-mately 3,600 lbs. The CE Model 927Cl container weighs aporoximately 7000 lbs. when loaded. The 16x16 bundles weigh approximately 1400 lbs. each with the container weighing sporoxi-mately 4200 lbs. The containers are approximately symmetrical; the center of gravity being at the center of the container. Wnen the bundles are in the container, the center of gravity shifts vertically to a lower point because the bundles are vertically posi-tioned below the center of the container. 2.3 Mechanical Procerties of "aterials The container is fabricated of carbon steel. Material mechanical properties were verified by testing. (See Appendix 2.10, reference A & B). 2.4 General Standards for All Packacino 2.4.1 Chemical and Galvanic Reactions There are no significant chemical, galvanic or other reactions among the pack-aging components or between the packaging components and the package contents. The shipping container is fabricated of carbon steel and the contents are zircaloy-clad unirradiated fuel assemblies wrapped in polyethylene. 1733 152 2-1

2.4.2 Positive Closure The shipping container is equipped with positive closure bolts which will pre-vent inadvertent cpening. 2.a.3 Liftino Deiices (1) There are four lifting eyes on the lid, all of which are used to lift tne loaded container. Each of the lifting eyes is capable of lifting the loaded package. This was shown by lifting the loaded container free of the floor by each of its lifting eyes and holding to illustrate no yielding in the lif ting eyes. (2) It is not necessary to demonstrate that the lifting devices are capable of suoporting three times the weight of the loaded package withcut generating stress in any material of the container in excess of its yield strength be-cause no more than one loaded cackage will be lifted at one time. This is assured because this package will be part of a Fissile Class III ship-ment. As such, the containers shall be transoorted in a vehicle for the sole use of Combustion Engineering, with a specific restriction for sole use to be provided in the saecial arrangements. The special arrangements also include procedures for unloading the shipping containers one at a time. This will provide adequate administrative control to assure tnat lifting devices will never have to support more than the weight of one loaded con-tainer. The lifting eyes will not have to succort any compressive load, because loads placed on top of the shipping container will be supported by the stacking brackets.

2. 4.a Tiedown Devices (1) There is no system of tiedown devices which is a structural part of the con-tainer. The container is secured to the truck bed by a chain that is passed over the container and fastened to the truck bed.

In addition, the con-tainers on the truck bed are shored with wood blocks. (2) Since this package will be part of a Fissile Class III shipment, it will be transported in a venicle for the sole use of Corbustion Engineoring, with a specific restriction for sole use to be provided in the soecial arrange-ments. Combustion Engineering will supervise the loading of the vehicle to assure that the containers are fastened to the truck as described above. This will provide adequate administrative control to assure that no struc-tural part of the container is used as a tiedown device. 2.5 Standards for Tyoe B and Large Cuantity Packacing N/A (Type A quantity cer package). 2.6 Normal Conditions of Transoort The ability of the container to withstand conditions likely to occur in normal conditions of transport were assessed by subjecting the shipping container to the required tests and by other assessments described in this application. (? lease see references A, 3, and C of Appendix 2.10). 1733 153 2-2

2.6.1 & 2.6.2 Heat and Cold The heat and cold requirements are not applicable. Any pressure rise in the container above 8.5 psi gauge will be released by the automatic pressure relief valve. Materials of all structural ccmponents used in the manufacture of the con-tainer have physical and mechanical properties equivalent to or better than mild steel throughout a temperature range of -40 to 1500 F. 2.5.3 Pressure Pressure rise in the container in excess of 8.5 psi gauge will be released by the automatic pressure relief valve. The manual cressure relief valve is used for venting a cressure build-up of less than 8.5 psi gauge. It shculd be noted that the container is not pressurized for normal use. 2.5.4 Vibration Vibration normally incident to transoort was experienced by conducting a nor-mal shipping test with a simulated fuel bundle inside the container. No damage was incurred. 2.6.5 Water Soray The water spray test is not applicable since the container is safe from a criticality safety standooint for all degrees of internal and external water modera-tion and reflection. 2.6.6 Free Droo The free drop test was performed in accordance with the requirements of 10 CFR 71 and no significant damage occurred to the container or its contents. 2.5.7 Corner Droo The corner drop was performed in accordance with the requirements of 10 CFR 71 and no significant damage to the container or its contents occurred. 2.6.3 Penetration The penetration test was not performed because it is not credible that this test can result in the puncture of the shell and the puncture of the zirconium clad fuel rods to release radioactive material. 2.5.9 Comoression The requirement that the container succort, in comoression, five times its loaded weight without yielding is not applicable because it will never be loaded more than two high. The package will be cart of a Fissile Class III shipment; there-fore, it will be transoorted in a vehicle for the sole usc of Comcustion Engineering. Combustion Engineering will supervise the leading of the vehicle to assure that the containers are loaded only two high. 1733 154 2-3

2.7 Hyoothetical Accident Conditions This package was subjected to the hypothetical accident conditions as speci-fied in Appendix R to 10 CFR Part 71 and meets the standards specified in 71.36 of 10 CFR Part 71. 2.7.1 Free Drop a) Analysis The container was subjected to two 30-foot drops. The first drop was made with the longitudinal axis of the container at an angle of approximately 30* to the hori::ontal. The angle was such that the aft end of the container struck first, the container then rotating so that the bottom of the fore and skids hit the concrete slab. The container cover was removed at the test site after the 30* anole, 30-foot drop and the container visually inspected. The simulated fuel bundles were retained in the container cradle assembly and little relative movement of one fuel bundle with respect to the other was noted. The most notable deformation as a result of this test was in the skid brackets. See Appendix 2.10 Reference B. See photographs No. 6 through No.17 for various views of the container during and after this test. The second 30-foot drop was made with the container oriented such that the left side closure flange struck the concrete slab. The simulated load utilizing tubu-lar construction was nearest the ground. Upon impact tne container remained stable on its side without any rotation about its axis. After the 30-foot side drop, the container was inspected as above. Although the simulated fuel bundles had shifted sidewise from their original mounting cositions the fuel bundles did not come loose and were contained in the container shell after testing. The most notable deformation in the container shell is at the forward right closure flange. Refer to Appendix 2.10 reference 3, photographs No.18 through No. 30 for various views of the container during and after this test. It is concluded that the container satisfies the test retuirements by retainino the two fuel bundles within the strongback with complete separation of the two bun-dies. Further, the strongback with fuel bundles installed were contained witnin the container structure. b) Prototyce Testina The testing was performed on the CE Model 927Al container by Aoplied Design Co., in February 1969. The only major difference between the tested container and the existing container is the method of separating the fuel bundles. The boral plate in the original container has been replaced by carbon steel separator blocks. A struc-tural analysis was cerformed and completed in February 1971 to show that the modified container was covered by testing performed on the original container. This analysis was then submitted and aporoved by the Commission. (See Apcendix 2.10 reference C). As previously mentioned, the CE Model 927C1 container is structurally identical to the tested 927Al container except for its additional length. The Humidity Indicator and the Filling Valve are listed as optional on Drawing NFM-E-.11CS, Rev. O, dated 11/27/79, sheets 1 and 2 (Accendix 1.3). ~hese two features are not being utilized any longer and have been eliminated from some of the 927C1 containers. 1733 155 24

The Desiccant Access Hatch is also listed as optional. This hatch is part of all existing containers and was also on the tested container. This is no longer used and may be eliminated in the construction of any new containers. The only other item which is listed as optional is the "Special Design" closure bolt. This is the bolt that has been used in the past and was used in the testing of the container. However, it was found that the "Round Head Square Neck" bolt pro-vided a tighter fit and is made of the same low carbon steel with a minimum tensile strength of 70 KPSI. Therefore, these two bolts may be used interchangeably without compromising the safety of the container closure. (See Appendix 2.10). The material used as substitutes for the actual UO2 fuel bundles was solid stainless steel rods cut to length and assembled into dummy fuel bundles approximating the size and weight of the actual bundles. Accelercmeter readings and pnotograohs of the damaged package are included in Apcendix 2.10, reference S. c) Model Testing N/A (The full size centainer was tested) d) Comoarisen to Similar Packages Both the CE Model 927Al and 927Cl containers are presently aporoved. The only difference between the two is the greater overall length of the 927C1 container. 2.7.2 Pinnacle Test (Puncture) The container was subjected to the pinnacle test in accordance with 10 CR Part 71 Appendix B. The container was allowed to drop freely onto a steel cylinder, 6 inches in diameter by 8 inches high, fren a height of 42 inches. This distance is measured from the bottom of the shell to the top of the steel cylinder. The point of impact was approximately midway between the edge of the aft fork list guide and the edge of the aft container skid. The external birdcage structure of the container sustained no damage as a re-sult of this test. Examination of the inside of the container indicated no damage to the simulated loads, no relative movement of the simulated loads and no damace to tne suspension frame. 2.7.3 Thermal Materials of all structural components used in the manufacture of the container have physical and mechanical properties equivalent to or better than mild steel throughcut a temperature range of -40 to 1500 F. 2.7.a Water Immersion The package is so designed and constructed, and its contents are so limited that it would be subcritical if it is assumed that water leaks into the containment vessel, and (1) Water moderation of the contents occurs to the most reactive credible extent consistent with the chemical and physical form of One contents, and (2) The containment vessel is fully reflected on all sides by water. 1733 156 2-5

Therefore, since the criticality safety analysis was performed for all degrees of internal and external water moderation, the water immersion test was not performed. 2.7.5 Summary of Damage It is concluded that the container satisfies the test recuirements by retaining the two fuel bundles within the strongback and the separator blocks remain in place and continue to completely separate the two units. The strongback with the fuel bun-dies in place were contained within the package structure. 2.8 Soecial Form N/A (All radioactive material in the packages is in normal form) 2.9 Fuel Rods The CE Model 927Al and 927Cl containers will be used for unirradiated fuel rods only which are part of an overall fuel assembly. For both normal and accident con-ditions, the dummy fuel bundles were not affected during testing. This, coupled with the fact that these are unirradiated fuel rods designed to withstand the environment of a reactor core, assure cladding integrity. 2.10 Accendix (1) Applied Design tests and test results (References A & B), (2) Structural Analysis of containers with seoarator blocks (Reference C) and, (3) Comoarison of closure bolts (drawings and structural croperties) 1733 157 2-6

m APPENDIX 2.10 Test R. port No. 31 JA Qualificallon Test Pr.sedure for the Applied De s i n C.warriny.l.ide l 42 7A '1. t.il Slii pp i ne and S t..r ar. Con :.e i ne r f..e Ciwihuwsion Kn.incerin. Inc Fuel 1:und le Assembly 1733 158 pgB$ Ohb AP!'I.IED DESIGN COSIPAN'J, INf: Ton.awanda. N.w York i t. ! 30 Nove,hi e 2.",, 10/.8 Reference A

Te s t Report No. 2312A Qualification Tvst Procedure for the Applied Design Company Model 927A Metal Shipping and Storage Container for Corabustion Engineering, Inc. Fuel Bundle Assembly 9 ~T gg g 9 g g Mui 1.0 Purpose m It is the purpose of this Qualification Test Procedure to present a plan for testing Container, Applied Design Company's Part No. 927A for Combustion Engineering, Inc. for functional conformance to the applicable specification. 2.0 Applicable Documents Applied Design Company Drawing 027Al, Container Combustion Engineering, Inc. Spe c i ficat ion Code MFC-03-01 3.0 racilities ~ Holst for rough handling and hoisting tests. Quick release mechanism, mechanically actuated. Cables and connections as required to conduct impact test as described in a later section herein. Barrier as required to conduct impact tests. Wood blocking as required to conduct rotational drop test. Fork lift truck for lif.og and towing tests. Crane hoist for 30-foot drop test. 3.1 Test Equipmenc 15 psig. minimum range pressure measuring device. h Three acceleration sensing elements and recording equipment cap- .eble of measuring plus ur minus 25 vector g's with an accuracy of plus or minus ten per cent. 3.2 Utility' Requirements ,13 psig, mininum air supply Electrical power for instrumentarion. fbh O

mo m 9 9 Test Report No. 2312A Page 2 9 co o s n 4.0 Documentation A log will be kept of the test data. Photographs will be taken before and af ter the testing program. 5.0 Tests Tests shall be conducted in the order of listinn. 5.1 Install du1ny units. This will be acenmplished at Cod ustion Enr.inee r i ng, Inc. A log will be kept of this op< ati.a to es-tablish a procedure. 5.2 Unloading Test in accordance with Paragraph 4.4.10 vill be con-ducted at Conhustion Engineering, Inc. Hemove the dummy units from the strongback. The removal of the Fuel Bundle Assemblies will be observed and a log kept of this operation to be used in establishing a procedure. Rr!nstall dummy as accomplished in Paragraph 5.1 and ship container to Applied Design Company. 5.3 Pressurize container to 5 psig. and maintain this pressure for one hour. This test is performed upon return of the loaded con-tainer from Combustion F.ngineering, Inc. 5.4 Conduct the following Drop Tests: 5.4.1 Edgewise Drop Test per Paragraph 4.4.3.2 O f.<,_ <. Q 5. \\ QA. 56. n h 1\\7s7A-& b o ,t t G5 n This test is performed on each end of the container. 5.4.2 Cornervise Drop Test per Paragraph 4.4.3.3 O v i c. < R. E LE ASE. n N-.'

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.g TestReportNo.23k2A Page 3 5.4.3 Flatwise Drop Test in accordance with Paragraph 4.4.3.1 Q V tCK R6. LEASE is" 4 Roll-over test in accordance with Paragraph 4.4.4 of the Specification. 5.a.4 Impact Test in accordance with Paragraph 4.4.5.2 r--- 1 1 1 g @== ', g \\ i Quick Release 5.5 Stacking Test in accordance with Paragraph 4.4.6 of the Specification. p g A wei:;ht equivalent to the gross weight of two containced, e A weight equivalent to twice the gross weigh't of a lo, d container is placed on'the stacking brackets of the test container and allowed to rest for two minutes, to illustrate there is no yielding 5.6 Hnisting test in accordance with Paragraph 4.4.7 of the Specification. The loaded container is lifted free of the flfor by each of its liftine eyes and held for two minutes. D"* 'T , 2. 1733 161 _oo o m

'D * * .a d d j L Test Report No.2[12A Pa"e 4 5.7 Lifting test in accordance wi th Para:;,raph 4.4.8 of the Specification. This test requires that the loaded container be transport ed 100- feet by a fork lift truck. This test requirement will be fulfilled many times in handling during the testing program. 5.8 Towing test in accordance with Paragraph 4.4.9 of the Specificatio; This test is conducted connecting the container en the towing eyes and towed for a Jistance of 30-feet in one direction and then the cow is passed on the other end of the container and enutainer is teved back to '.he original location. 5.9 Shipping Test This test is the return shipment from Combustion Ennineering. Clay will be placed between the suspension frame and the con-tainer shell to determine the maximum deflection experienced during the shipment. p[ 5.10 Pinnocie Test: ~ l If b Ayi g.. Contain,:r is droppec one t uac. 5.11 30-foor Drop re s t [+- - L o

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O Test Report No. 23123 on the Applied Design Company Model 927A Metal Shipping and Storage Container for Combustion Engineering, Inc. Fuel Bundle Assembly 1733 163 APPLIED DESIGN CCMPANY, INC. Tonawanda, New York 14150 February 7, 1969 Reference B

Test Report No. 2312B on the Applied Design Company Model 927A Metal Shipping and Storage Container for Combustion Engineering, Inc. Fuel Bundle Assembly The Applied Design Company Model 927A Container employs a special cradle assembly utilizing elastomeric shock mounts to isolate and protect the Combustion Engineering Inc. Fuel Bundle Assembly during conditions of normal shipping and handling as well as some likely abuse or accident. The container also protects the contents from possible damage due to the atmosphere. The work involved in the design, fabrication and testing of the container is covered by Combustion Engineering, Inc. Purchase Order No. 9801668. The qualification testing was accomplished in accordance with Test Report No. 2312A Qualification Test Procedure for the Applied Design Company Model 927A Metal Shipping and Storage Container for Combustion Engineer-ing. Inc. Fuel Bundle Assembly.. It is the C purpose of this report to summarize the results of the tests performed on the container with two simulated fuel bundle assemblies installed within. The simulated fuel bundles were furnished by Com-bustion Engineering, Inc. The actual fuel bundle assembles are iden-tified on Combustion Engineering, Inc. Drawing No. CND-SE-2813. I. Summary and Conclusions A. The dummy fuel bundle assemblies were installed in the strong-back and the strongback with assembled units satisfactorily lowered into the shipping position. B. The container satisfactorily protected the packaged items dur-ing the shipping test of the container under conditiona nor-mally encountered in shipments by common carrier. C. Prior to the rough handling tests the container successfully passed the lesk test. D. The container successfully passed the rough handling tests. The fuel bundles and suspension frame satisfactorily withstood these tests. The maximum accelerations imposed on the simulated 1733 164

Page 2 ~ Test Report No. 23123 fuel bundle during these tests are as fellows: Edgewise - Yore End Drop 50 s's Vertical Cornervise - Af t End Drop 40 g's Vertical 32 s's Vertical Flatvise Drop Roll-over (side to base) 14 g's Lateral Impact (Fore End) 20 g's Longitudinal 'E. The containet successfully passed the static load and handling tests. and two F. The container satisfactorily passed the pinnacle test of the 30-foot free fall drop tests as described in the United States Atomic Energy Commissionk Rules and Regulations, Title 10 - Atomic Energy Part 71. that the Model 927A Metal G. It is the conclusion of this report Shipping and Storage Container is capable of protecting the Combustion Engineering, Inc. Fuel Bundle Assemblies from it meets damage due to shipping and rough handling and that the test requirements of Combustion Engineering, Inc. Sppci-fication MFG-03-01. C It is further concluded that the container satisfies the te=* requirements of the United States Atomic Energy Commission's Rules and Regulations Title 10, Atomic Energy Part 71 by re-taining the two fuel bundles within the strongback, with the Boral Plate remaining in place and continuing to completely separate the two units. Further, the strongback, with fuel bundles installed, were contained within the container structure. II. Discussion The container was subjected to the tests of paragraph 5.0 of the Qual-ification Test Procedure as tabulated below: Test Test Procedure Date of Location No. Parstraoh No. Test Title of Test of Test 1 5.1 12-3 to Install Dummy Units Combustion Eng. Hartford, Conn. 12-4-68 2 5.2 12-3 to Leading Test Ship Combustion Eng. ~ 12-4-68 Container to Applied Hartford, Conn. Design 3 5.3 1-2-69 Leak Test Applied Design' N.Tonawanda, NY N, s wo mg g mg a n a A kb 1733 165

9 Page 3 Test Report No. 23128 Location Test Test Procedure Date of No. Paragraph No. Test Title of Test of Test 4 5.4.1 1-2-69 Edgewise Drop Test Applied Dc11xn N.Tonawanda, N.Y. 1-3-69 5 5.4.2 1-3-69 Cornerwise Drop Test Applied Design N.Tonawanda, N Y. 6 5.4.3 1-3-69 Flatwise Drop Test Applied Design N.Tonawanda, N.Y. 7 5.4.3 1-3-69 Roll-over Test Applied Design N.Tonawanda, N.Y. 8 5.4.4 1-3-69 Impact Test Applied Design N.Tonawandu, N.Y. 9 5.4.4 1-8-69 Impact Test Applied Design N.Tonawanda, N.Y. 10 5.5 1-4'-69 Stacking Test Applied Design N.Tonawanda, N.Y. ( 11 5.6 1-8-69 Hoisting Test Brace-Mueller-Huntley, Inc. Tonawanda, N. Y. 12 5.7 1-8-69 Lifting Test Brace-Mueller-Huntley, Inc. Tonawanda, N.Y. 13 5.8 1-6-69 Towing Test Brace-Mueller-Huntley, Inc. Tonawanda, N. Y. 14 5.9 12-5-68 Shipping Test Combustion Eng. to Applied Design 15 5.10 1-8-69 Pinnacle Test Applied Design N.Tonawanda, N. Y. 16 5.11 1-9-69 30 Foot Drop Tests Louis Levin & Co. Tonawanda, N. Y. The following personnel were in attendance for the listed tests: Mr. Edward Petras, Combustion Engineering, Inc., Hartford, Conn., all tests Mr. J. B. Aikman. Senior Project Engineer, Applied Design Company, Testa 1,2,4-8, 10 D** ]D *gTl@' s e Ju e Ju.1.k fru.m 1733 166

Test Report No. 23123 Page 4 Mr. W. F. Schreiber, Project Engineer, Applied Design Company. Tests 9-13, 15, 16 Mr. J. Kovacs, Project Engineer, Applied Design Company, Tes ts 4-10, 15, 16 Mr. H. Arsenault, Quality Control Msnager, Applied Design Company. Test 3 The discussion is divided as follews: A. Container Description and Wei ht s Employed; 8. Tes t Eq ui pmen t ; C. Installation Test; D. Shipping Test; E. Leak Test; F. Rough Handling Tests; G. Static Load and Handling Tests; and H. United States Atomic Energy Commission Prescribed Tests. A. Cont ainer Descriot ion and Weight s Emploved The container is of the horizontal circular style with a horizontal bolteu closure flang-and rubber 'O' ring gasket for sealing. The container is constructed of steel and is defined on Applied Design Company Drawing No. 927Al. The overall dimensions of the container 45-7/8 inches high, 43-1/4 inches wide and 188-1/4 inches long. are The forward end of the container is identified by the end contain-ing the nameplate. Left and right sides of the container are iden-tified as tnose sides to the viewers left and right when standing at the aft end of the container and looking forward. One simulated fuel bundle, located on the right side of the container, fabricated from steel plates. The other fuel bundle utili:ed was construction similar to an actual unit. The weights employed during the tests are summarized as follows: Container Weight 3285-pounds Two simulated Fuel Bundles and Boral Place 2835-pounds Total 6120-pounds The weight of the container was obtained by weishing on a certified scale. The weight of the simulated fuel bundles was obtained from Drawing Ne. CMD-SE-2813. The weight of the boral nlate is estimated. The condition of the container prior to the leak test is shown in photographs No. I through 5. The photographs and description are contained in Table I. 3. Test Eculpment 1. The test equipment employed during the performance of the 1733 167 g,l k e y3b g JL X e m;

Test Report No. 2312B Page 5 rough handling tests is listed as follows: a) Accelerometer The Statham Accelerometers employed have the follow-ing characteristics: Three non-bonded strain gauge type Range: Plus or minus 50 g's Natural Frequency: 550 cps Damping: 0.6 to 0.8

Response

Flac to approx. 440 eps. b) Recorder A Brush Development Company Recorder Model 8000-99 Ser. No. 125, was employed to record the accelera-tions. A calibrated resistor is utilized to check the equipment before each test to assure accuracy. The wiring is completely shielded and the system is gcounded to the chassis to eliminate pickup of stray voltages. The equipment empicyed in the testing is periodically calibrated in accordance with established procedures to insure its proper functioning. C. Installation Folleving a simple procedure, the strongback was prepared for the fuel bundles and raised to the vertical position. The two simulated fuel bundles were installed and clamped into place. The strongback with fuel bundles was lowered and bolted into its normal shipping post-tion. This test satisfactorily demonstrated that the stroneback provided adequate support to the fuel bundles during the operation of the strongback. 3. Shipping Test The container was subjected to the Shipping Test of Paragraph 5.9 of the Qualification Test procedure. Clay was placed between the suspension frame and the containar shell to determine the maximum deflections experienced during shipping.of the container from Combustion Engineering, Inc. to Applied Design Company. It is estimated that the distance travelled is in the range of 400-450 miles, thus considerably exceeding the specifica-tion requirements of not less than 200 miles. The deflections measured are tabulated in Table II. In addition, the calculated accelerations imposed as a result of these deflections are recorded in this table. wT 1733 168 oro

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Test Report No. 23125 Page 6 E. Leak Test The container was subjected to the leak test in accordance with Paragraph 5.3 of the Qualification Test Procedure, Test Report No. 2312A, prior to the rough handling tests. The container was pressurized to 5.55 psi gage. At the end of I hour there was no loss in gage pressure. It is concluded that the container satis-factorily passed. the requirements of this test. F. . Rough Handling Tests The container with two simulated fuel bundle assemblies installed was subjected to the following rough handling tests in accordance with Test Report No. 2312A Qualification Test Procedure: Para. 3.4.1 Edgewise Drop Test Para. 5.4.2 Cornervise Drop Test Para. 5.4.3 Flatwise Drop Test Para. 5.4.3 Roll-over Test Para. 5.4.4 Impact Test During these tests three accelerometers were employed to record the accelerations imposed on the simulated load. One acc e le rome te r was mounted at the top fore end, one at the tcp center and one at the top aft end of the simulated load which utilized steel plate cons t ruc t ion. In general, all accelerometers were mounted to .'easure acceleration in the directien of the drop or impact. De - tails of accelerometer orientation for each test are given in Table III. The maximum accelerations imposed on the simulated fuel bundle during each of the above rough handling tests are as follows: Edgewise - Fore End Drop - 50 g's Vertical Cornervise - Aft End Drop-40 g's Vertical Flatwise Drop - 32 g's Vertical Rollover (side to base) - 14 a's Lateral Impact (Fore end) 20 g's Longitudinal Accelerations recorded during these rough handling tests are lis ted in Table III. Prints of accelerations-vs-time traces representative of the various tests conducted are attached to this r*wict as Figures No. I through No. 7. These figures are labeled to imitcare the type of test and calibration of the coordinates. Examination of the dummy fuel bs2dlet t.sd container upon completion of the tests showed that they were in good condition.

Test Report No. 23123 Page 7 C Stetic Load anc' yandling Tests In order to assure the structural strength of the contai.aer under normal usage, the following performance tests were conducted: 1. Stacking Test The container was subjected to the stacking test in accor-dance with Paragraph 5.5 of the Qualification Test Pro-cedure. A weight of 12,000 pounds simulating the stacking of two containers, was placed on the stacking brackets of the container and allowed to rest for over 2 minutes. No yielding was observed. It is concluded that the con-tainer satisfactorily passed the requirements of this test. 2. Hoisting Test The container was subjected to the hoisting test, Para-graph 5.6 of the Qualification Test Procedure. The con-tainer was lifted free of the floor by each of its lift-ing eyes, individually, and held for at least 2 minutes. No yielding sas observed and it is concluded that the con-tainer satisfactorily passed the requirements of this test. 3. Lifting Test The container was subjected to the lifting test, Para-graph 5.7 of the Qualification Test Procedure. The container was transported a minimum of 100 feet by a fork lift truck. No problems with stability of the container on the forks nor evidence of the forks causing any defor-mation of the container were noted. It is cencluded that tne container satisf actorily passed the requirements of this test. a. Towing Test The container was subjected to the tewing test of Paragraph 5.8 of the Qualification Test Procedure. The container was towed a minimum of 50 feet by means of each set of towing eyes. No proble=s were encountered in towing the container and no evidence of deformation of the container was noted. It is concluded that the container satisfactor-ily passed the requirements of the test. H. United States Atomic Enerty Cenmission Prescribed Tests In order to assure the structv... strength and reliability of the 1733 170

Test Report No. 23128 Page 3 container under extreme accident conditions, the following tests of the United States Atomic Energy Commissions Rules and Regulations Title 10 - Atomic Energy Part 71 were conducted: 1. Pinnacle Test The container was subjected to the pinnacle test in accor-dance with Paragraph 5.10 of the Qualificacion Test Pro-cedure. The container was allowed to drop freely onto a steel cylinder, 6 inches in diameter by 3 inches high. from a neight of 42 inches. This distance is measured from the bottom of the shell to the top of the steel cylinder. The point of impact was approximately midway between the edge of the aft fork lift guide and the edge of the aft container skid. The external birdcage structure of the container sustained no damage as a result of this test. Examination of the inside of the container indicated no damage to the simu-laced loads, no relative movement of the simulated loads and no damage to the suspension frame. It is, therefore, concluded that the container satisfactorily passed the pinnacle test. 2. 30-Foot Drop Tests The container was subjected to two 30-foot drops. The first drop was made with the lengitudinal axis of the container at an agle of approximately 30' to the hort-zontal. The angle was such that the aft end of the centainer struck first, the container then rotating so that the bottom of the fore and skids hit the concrete slab. The container cover was removed at the test site 3 af ter the 30' angle, 30-foot drop and the container vi3-ually inspected. The simulated fuel bundles were retained ir. the container eradle assembly and little relative move-ment of one fuel bundle with respect to the other.as noted. The most notable deformation as a result of tnis test was in the skid brackets. See photographs No. 6 through No. 17 for various views of the container during and after this test. The second 30-foot drop was made with the container oriented such that the left side closure flange struck the concrete slab. The simulated load utilizing tubular construction was nearest the ground. Upon impact the container re-mained stable on its side without any rotation about its axis. ada ]M = gem +o 1733 171 o

Test Report No. 23123 Page 9 After the 30-foot side drop, the centainer was inspected as above. Although the simulated fuel bundles had shifted sidewise from their original mounting positions the fuel bundles did not come loose and were contained in ene con-tainer shell after testing. The most notable deformation in the container shell is at the forward right closure flange. Refer to photographs No. 18 through No. 30 for various views of the container during and af ter this test. It is soncluded that the container satisfies the test requirements by retaining the two fuel bundles within the strongback with the Soral Plate rema in ir - in place and continuing to completely separate the two vaits. Fort.ie r, ene stronaback with fuel bundles installed were cen-tained within the enntainer st ructure. a Conducted by c

3. Ai k: nan Senior Project Engineer Written by J. Kovacs Project Engineer Approved by d

A-# H..E. Jonnson General M.anager Applied Design Company, Inc. Tenawanda, New York 14150 February 7, 1969 1733 172 o e m an no n n3 m e M M JL h

TAB 12 I Photographs of the Applied De91en Company Model 927A Container at Various Stages of the Test Program A. Photographs Subsequent to Shipping Test and Prior to Rough Handling Tests. Photograph No. Degeriotion 1 Cover Removed Fuel Bundles, Aft End 2 Cover R moved Fue1 Bundles, Fore End 3 Cover Removed Aft End, Strongback N 4 Cover Removed

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Aft End, Partial Side View of Stronaback 5 Complete Assembly Aft End, 3/4 Side View B. Photographs Illustrating the 30-Foot Free Fall Drop Test and Result 30 Degrees to Horizontal. Photograph No. Descriotion 6 Container Underside, Af t End Down Container Being Raised for 30' Angle, 30-Foot Drop. 7 ' Container Raised 30-Feet at 30 Just Prior to Release. 8 Container at Instant of Impact after 30, 30-Foot Drop. 9 Container After 30', 30-Foot Drop Fore End View 1733 173 g g qg M o M MIAL

TABLE I - Continued Page 2 Photograph No. Description 10 Container After 30, 30-Foot Drop Aft End View, 11 Container Af ter 30', 30-Foot Drop Fore End View. 12 Container After 30, 30-Foot Drop Bottom View. 13 Container After 30, 30-Foot Drop Cover Removed Fuel Bundles, Fore End. 14 Container Af ter 30, 30-Foot Drop ~ Cover Removed Fuel Bundles, Fore End. C L5 Container after 30', 30-Foot Drop Cover Removed Fuel Eundles, Aft End. 16 Container Af ter 30 ', 30-Foot Drop Cover Removed Left Side View 17 Container After 30, 30-Foot Drop Cover Removed Fore, Left Side View. C. Photographs Illustrating the 30-Foot Free Fall Drop Test and Results - To Left Side Closure Flange. Photograph No. Description 18 Container Raised 30-Feet Just Prior to Release Left Side Down. Container at Instant of Impact after 30-Foot 19 Side Drop. 20 Container after 30-Foot Side Drop Fore End View U 1,/ ;,;, 1 7 4 nn n L m _me m

TABLE I - Contained ' Page 3 Photograph No. Desertation 21 Container After 30-Foot Side Drop Aft End View. 22 Container After 30-Foot Side Drop Fore Right Side View. e 23 Container After 30-Foot Side Drop Aft Left Side View. 24 Container Af ter 30-Foot Side Drop Cover Removed Aft Left Side View. 25 Container After 30-Foot Side Drop Cover Removed Aft End View. 26 Container After 30-Foot Side Drop C Cover Removed Right Side View. 27 Container After 30-Foot Side Drop Cover Removed Fuel Bundles, Fore End View. 28 Container Af ter 30-Foot Side Droo Cover Removed Fuci Bundles, Aft End View, 29 Container After 30-Foot Side Drop Cover Removed Fuel Bundles, Aft End view. 30 Container After 30-Foot Side Drop Cover Removed Fuel Bundles, Fore End view. C o**m

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( TABLE II Test Data and Results Obtained During Shipping Test of Applied Design _ Company Model 927A Container Maximum Deflection Calculated of Suspension Frame Ac ce le ra t i cn Point of Megaurcewne Inches g's 1. Fore End Shock Mount 0.165 2.05 2. Center Shock Mount 0.L16 1.28 3. Aft End Shock Mount 0.164 2.05 The calculated g's represent the loads imposed on the dummy units in the same relative locations as the indicated shock mounts. m = O e O

TABI.E III Acceleration Test Data Obtained in the Test of Applied Design Company Model 927A Container Drop Acecleration - c's Height Acceleromet.r Title of Test Inches No. I No. 2 No. 3 Remarks Paragraph 5.4.1 12 5 15 23 All Readines Edgewise Drop 24 7 23 35 vertical Force End 30 11 30 50 Paragraph 5.4.1 12 20 10 6 Accel, Mounted Edgewise Drop 24 33 20 11 Top of Steel Aft End 30 43 25 13 Plate Dummy as Fo l le.vs : No. I Aft No. 2 Center No. 3 Fore ( Paragraph 5.4.2 12 18 10 5 Same as 5.4.1 Cornervise Drop 24 35 20 5 Aft End 30 40 20 6 P.iragraph 5.4.2 12 7 4 12 Same as 5.'+.1 Corner Wisc 24 10 10 18 Fore End 30 11 22 38 Paragraph 5.4.3 18 22 32 32 Same as 5.4.1 Flatwise Drop Paragraph.5.4.3 No. 2 Changed Roll-Over (Base to Side) 3 7 3 to Read Lateral Roll-Over (Side to Top) 7 3 8 Otherwise Same Roll-Over (Top to Side) 3 6 3 as 5.4.1 Roll-Over (Side to Base) 6 14 8 Paragraph 5.4.4 Impact (Aft) 18 10 14 6 Same as 5.a.1 Impact (Fore) 18 10 20 2 Except: No. 1 Long No. 2 Lenu No. 3 vert O. D**D " l0 TlM ..I e n MbL 1733 180

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Il ' l ' ' DATC DY l ' 'l rui?. i. A.. /.1/ i, ; <- ' h-IC f'~ oY ' CnCCn DArc .Z' ZMM:7 VKz o c/?~r a rys/? cy /~0 N A .30 ' pacP 7//f /M.J.4 C 7 yrt o c/7y /J 1/ = V. p 4 Vzx3fsx3cxi2 = F2 7 '$c : c. = fV/L.411is*'/PL,Y W 7~ % /200 /$1 E 00 f 4 E l. A. J rn',.".U' kJT $,y : /.3 G 7 070 kN y [MA1C7 EVfA'5,V = $"' W= j('f?.')e(G7) = 43/, 700 i n -/61 .LT. I.4'?R G}' A B.l0E.?.r.6' E>' Bf.4 CiPf/ c'fDEL ~ (//'GiV / ' /7~/AL //4'A4 ?7 7//E //./ER7/A L CA D i/ f?GAf7~RE / i /TCf.<- 6'EL siJJENEl7 /J A.fAC71"D E,V THf /pos/7~/c V///G ~ BAA C KE73 40 S.A 7 ff A 7 EA CA/.rs?4 C/R GR/f(/Gm. rbc/.U;) BRA cnE? P y x /G EoL 7~ 18 8 ~ g Vj i .<---F f / u.rl Ais,f ~ ) 3 4f d - x. fx * '.? teh f 7977 9 8 .1 C ~. 'L T > %- t 7).y ut.: v, /

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lo " lo v FA 1733 190 E.eeM eM A XIL

COMDUSTION ENGINEERING, INC. CAL.CULATION NO. NUCLEAR DIVISION DWG.NO CONTrtACT NO. '7 A I SHCCi' 2 OF ?!I! !^ h-~ 9 -.' r p.'~rsf f. /) f ff / '._*// Y DATE ~ ? GY f'

9/ {/70

'l[1T f yp poji)4 l' t's, t '7,A / t '/~.<' A '/'s / Y f/ f CHCCK DATC DY s s /W,v y/~,4 c Toft ///G WA1 t/NA54s 70 l'A'G V/s'E AA/}' /-VEC'f'N' A A 7/0// OA/ THE X/6 8/?A.C Kf7 BG4 7 M} 7ER/dl- 07%'fR 7//A.4/ 7~//, t 7 7//E V ARE C Oh'/;'CA/ C4/? EON J Tff4 J700/C s 'SO 4 71 /]//J J'y / f C/* C/~/ 7/// * ///M/ EGA 7 //AJ 4 C/71 0f ~ d:/,7 GCO /21/. AJJ OMMG A V V 4 r//f/ 7Z JHf'!A !72f/dCE's ' C X c)TJ.=.y.9, dGC,pi/. /~ c// /?s/* / p. ff.9 7h's /N u?OJE = ,$ / T iM :/: .? 7,e.c // G.5 +'.9 0 E TC.9)WA,-WC L 04.0/HG /J ~ ?dl0-

/ # L P f / C E ! / 7.'y'/.& 4.

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m.- NUCLCAR DIVISION owo. No. CONTRACT NO. -~' A S H Cr"' OF SUUJCCT A" ' f' 'I ~ ?' ' ' * / A'ff U Y ll#!l Y$ GY/ I' Y DATC' j)//f'/'/ './ ' f.- rs 7's is/r s' 4.s s,n / kof f. 7 l 5 lk gy 5h t cyggggggg i 5^/ DETE'TM/MJUG 7~HE ENER GY ABJCABED OF VE.8.<CdCKE7 /7 /J A.11UNED 7kA 7 7/ s BJ'A CA E7 4 C71 A J A L /A,.sg A V J l'R /A G-O P 7 0 7~H E Z G,1 ; iff f 9/4fp ~70 J//2A* /T THL' /30271. / I/'f EMEAC)',1BJ,?sES B 7 [//4~ 8C4 7f /_f /f/Npig stA/D /f /VfG//d!"L'D. '~ Ifx2 X h* 5 .c G.S,, /u a c,,.-h. r,== 3 i J; : u.n,, +-: u l !: .w ., ^' $.= n l, s i r e mu..m ','{i. ! .#v :.. J o r i~' t !a " ),h L j, = a. 7s E.7 J = s,, 2x/jsky k: 7.13

a. : foc h.h ~ 5('if Yl)

A F: 4 + <3 t g = (l'I d ,e:P a i.- b a-K Ly n, 445: F e

=

c< 19 c/ 8 4B : el r = r 2 gy,3 R?=N+A%*,f="ff+ffg-g'-y)p,.j o D-y m JL 1733 192 _m e m

COMDUGTION ENGINEERING, INC. CALOULADCN No. NUCLEAR DIVISION CWG. NO CONTitACT No. S H CC'. OF ' ?'Y S b'/*? A]5 Y I/ ! O GY ? " N CUS1CCT DATC YN I f////',) //.' e'r * *7"A /A/f f ,*1,//, ff Vf/ f cugcg pric By .i l /f~: j f -f sly l' A MG c2i f' _4 u;, p y <+t3 a rva /2 fZi b f '{i ') k., y- /6(.k) l. F i 2. ~f6 '# (; '0' -- 4.]2,y/O '/dh /2 25'[j-.'c9) ,T - I R, =.6L 5, = x.u.- ? 2x/i>.f y = 5/n 'i 4 = 's"

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COMGUSTION ENGINEERING, INC. CALCUL.ATION NO._ NUCLEAR DIV:GION DWG.NO '7 00 SHCCT b CONTTIACT NO. OF O M # ' ' '~~/i lII? ' / ! ( n'~ ' = 5 Y 'Y?/ <~ ' i DATC DY M /l SUWCCT D s 7') I )" A /*I /A f V r/ ( (>/ / P/'/.d 4 J A CHCCK DATC DY J/A CE f=2000/6: [ f u C /s. 7.) F F. f A Easts >'.' asons.cs ey 8/?a c /cr 7, 2; = } A*5 ' = f N@

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l/33 }94 9999

COMBUSTION ENGINEERING, !NC. CALCULATION NO. NUCLEAR O! VISION DWO. NO. CONTrt ACT NO. -~' ' ' < I-sytty 7 og su ulcCT. O *' * " ? " P /7 rt A *. j,ips v > /3 / /'O aY F W A' OATE S/// Dl'i'l f- /*/~ /7"/ / Vf/7 ),*/,J,r f, V'f,)] CHCCK DATE OY ./ L NN !d

l

,Af JR Ez rz (q -m + w,As x. sugt,in gy)[-z) y .n' L o y 2 I = ~/ EQ z.- M p A' 3 W d.-x WL A t e -o o /! x3 3 /?f - ( :. Wa L '{-' -f,) L AN lX / c lk _ ]

J-r f/f - AZ + %h%

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J oe /0 ~ /49 1733 195 9' h D D .[1 x y s

COMOUSTION ENGINEERING, INC. CALCULATION NO. NUCLCAR DIVISION DWG. NO. CONTRACT NO. /" O SHC{ OF SUDJCCT / ' ' "70 / * ' ' NM M 7 ' Y >/E'!'i DY / /' '" t DATE 1/// t* R' /./ D.o,* ? A s.U/* l' A,'/,Jf Vr/_ c lT)% gy cugggog3g a i* E-f c 2 o o o >j_fS_ y+ N o g.- ~ mex ~ y .ir ' ~ /9GCOfJ/ <f.J FCP /*3 2 Mc-F fvrt 4J!rn;/)/ /J Eggs 7/C EN' A C)' 4 8JCA SE.O 8,Y FVEd A11f = f, Z L '? 'N JM, L '_ v/. L ',,,,,) 1g o .2fj .1 u,i g 3 a -A F */ ' 1J _/ z009l./S , j_ _ _f ,,,,.,3 arz .g ge im >>c 5 '? ' V /~og 8 rics/;f E,y: En/ = c ix -/l., 6/ri: G.,V A'r';'.','./' /w4 A/7ER BRA c,t: 7~ E:4 7 i" A'A c 7:).P A +.?i, 7 co - 3 3 0 - e = 9 3i, 3 g o m -/h . h: = . '. BRK/.-l' 7.5 W ff)E 4.95 C42 yEPy A/77' E L*Nr/?Gy / M I/w.sc 7 oi Fun scsEA'B.!Y o/v'.fEPwTo/? mmL IN 7/// hMFL'/C VS JEC7/0iV /7 WAJ S//OWA/ THA T 7<<<E ~ BA/) Cit:7s d'ftli 4 A Sion's A Att $ 4/cig ' [ A//cy,V/ of 77/.f <4 t/A/l 454! /*.!*fN C Y L)l'.?/A/G /~P 4 c'? O R f Cf TN.E R/M CAZ7 SGL 7r-lH' & C 7//f ~VE 4 A JJ [.*/5/>' H/.'ll /t//'^ a 7 1733 196 ~~

COMOUSTION ENGINEERING, INC. CALCULATION HO. NUCLEAR DIVISION DWC. NO. CONTrtACT NO. J## SHECT OF CU DJ CCi f'''''"~? I*'=Y N#l'# A DATC ! *'l UY ' ' ' '! / ej

ff*A i ss ? !?

,A * / ; ' V '/, 0l/J CHECK DATC DY ' a THE J f A Ji?4 7C R 3 4 0C E S h.// 7H A 4. a 7 c-! 4 '<*Gts/9 7 C/~ /('/MC7/C .f/JEi('if..bMCE 7af.rr/M,U IcuT E.i C CM ARE RE 4 / 7/ ;/El.V /f/ (/ D 7/'//J EA/ZR Gf kV/L L BE <9 BJC<RZD /^/ 17~/ A/'U-THZ EUJl ASSE/YsLP f/!/MAM/d/ /d'>' / 44'S7/* C ? THE //W' 'S 7 t'f4 C C/7,7 /.S Y'E,$l* = \\ [2 6 7 'f e c '/ = fo.'? /H,% '7~ A/~ 7///.5 t/Ed C Cs 7*iv /7/J 6/A/LMZ4,V 7~A'/* I~ "/H E.1f/ c!<? G,?//f OU/4 4 /,7C.WJE J/.:/Wa"/Cd. '/7 Zd7ff, if., f// /A /? Ail /.i7.U./CE., & ' U.>' / 7 : /a's /- Ad A.,'? W;'s D 7/V4 7 i~"f ~ ~ A C 7' /, */J'/ V './a 4L,Y / l "?. * ' ? C f s J A c c/*//...~/.7,. / 6/E4 / O J'J i 17/? t. ' i'OR [.

N/E 4,1 ?l ' !J /~ [ZdA'? A' Y. **' ' L'. f EE7k ffA/ J /~f A

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4. / jr. p ' a a sec 1733 197 me m Ao w W. J. mao o A COMDUSTION ENGINEERING, INC. cat.CULATION NO. NUCLEAR DIVIC,10N Dwo.NO_ CONTRACT NO. SHCCT /O OF S U DJ E CT ;).., < '..,, / ,*1 * ? s' /:.. '

g y D ' /*/

., /, DATC rp; y p.~. ; * ?- ~* A *s a. *)r . g' g ,[ go CHCcK DATC DY , fuel /M D b 0 e ~- 9_ ,9,; --ve g .v-A L.,-

u. ti, L

I '-% (f a tA ~C C E!0C 't .,_ _. _2 9 :4 s.) c 1 A:J u n t./ C 714.'7/c N///:is /~c/?/7' s? 7 L c C A 7/C v'1, /?, is ? C O /./ /K'M //,*,&,A C7/A'G,Js.f 4 /?C &? I~Pi /W?f.t Vd L H/ cd /r /5 fl'), 9 w/// ni /fy /J THE FGJ. )'. % / C,/-? cNf'.& 7~ A 7 /M/) //M' ?!. h**.R / # E' fciff f'C D c troiJ .t E C 7/C' './ /'fp = G $ ' G '- Ref/,-7 ?.? 5* .v.+'E ? i C') : J'I( t. L' r 7 (11: 7 .. _ _ _{lo. : h. - a 2 l..:.g i .y ,AL 7/i: c/ f/. TA'/! f.\\'/','/?J/Cs' /J A c 7iv !ly 0//4J',4h'1/C. '.is "G N ,P,' R H C 7 f f,h,4 1 7,'C ,< Y d 7 N A L.;'.s).O p 2 /.<Pc - 9' Z r#/?.'? ' 4 i S 7,e A uf // '..w(A//9'(< ) 7* / J C c,y.i/.9 t.c? p.v. u / p-w 7)/sa c/ '/, s' V t'// lc/ c /* 7i"?, I,"I'.rc r '/4.!: i' / V.4 7 Ci/? E C f 7/?A~ /c.'ayC2.4' C,.,4 CV!p 7/cA/. ?c.(C. vf /WIA 7 C.c ^',r,'.s:.4?f /cB 7'/Z.'.%: % , w.+.y..v/,us , w. : 7 e; w <.:.c ?.u..v .r.s.r.e c n e. p,w ::wB 7ueD w)8is >w a ?c.w v,7z s?.e/.: .= O.L .tr J..a 1733 198 s CCMCUSTION ENGINEERING, INC. CAL.CULATION NO. NUCLEAR DIVISION DWo. NO. C // CONTRACT NO. DHECT OF S U DJECT /''''* O ' f * ' " " ' 7_ _ DATE ~ ' I '1 DY # N ' jf1/ r t's r > o" ( t o ~f.!

or r s's

/ tsjp y fse ,S?1 NG c9y.gg pggg gy Z/.('c - 9 Aitt i?cs.D. f/? cN ift/ 3 /^/r 'sc .//d// -7C' ~ 2.ff fu /,'y 7.i /.970 /~C'/t E/,? C y'. ~~Of/.'/G- /.p~,c, c c / D /G C <*/r ED I*//d' / Vf. w s w.i /s.2 x ; f o ?! s.et ?.?, c c c r 9 C, cccm.u nr.rnc?/.w, 7: 72' C e c a ') cCC 7 g g/ ccc up y_ r .i...-r7 y - ~ (p..: 2 py y - v 3, '^v (:r 's S yrie -/6.z e 3 7Xi/: x/

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s. M A / # /.s

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10. t 17 s 7.'c '. /. ;.' /.5 - ) /4 2.T.,0 D**D T)

}733 }99 T w u.. 2 eesa COMGUSTION ENGINEERING. INC. CAL.CULATION No. NUCLCAR DIVISION DWO. NO.

2 CONTR ACT NO.

S H CCT OF l /?T ' / ' Y S U DJ CCT Of* T/" DATC DY ' 'l .r'9 foo) f Y f/ f .1 ' l,'7 0 lll$ f)/ r tr.9/ ' ?**'t** cygggog3g gy / / b/C /W',Y /M C/// flsif 7/C d?Jfff C.7 c,A/ C; 7HE.fVf6 '/?C/.).'. / /C $: $~h ; .7j~5d

[l[//7

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i. / n v = a = 3rr4 x4

.2 n i o. & z /.p.,,,. 357 g s e,o o v 3 ng 1733 200 e uMe _ L% s SHCCT O f' CON 18t ACT NO y s s ..y) ...o,, = a. UY .e..,g.,...

'3

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/

SUDJCCT CHCCK DATC DY v.* 'f,1~f w&.-. L w :., - s'-- - L' s' uC 1 _ rto e'_

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c.

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d 4

w W b u y S - r~u R 7 Y^ r Eum:..qJ' 4 es cano r. n ,n _n m i n.- L.3 l'I Il fi II t Ii (( l'l I ~il -- ~ ~ i l - - g j l~"] I g I l I ll i g h Ii I l' gi u iq .s J < -+- C -+= S h,7j M&'[. -G)fq . j.. -- t' ' ~.: n... q - r ~ n' g, ' n,' t. f~( i

i;-

7 L ~ ..::..- l I / It j< l h, _. [ = ij / It l l

h. l j

l ! g i i,, ) d ~' J ,. m,_., e ;; e 2 7,., ,w y men emma 7 yn.:;~ R.MfS 'C' ff- -g-1733 201 i' ( " 2D T }U@L D**2D 2. e n APPENDIX 2.10 Comoarison of Closure Bolts Bolt-Special (SAE C-1010) - This bolt presently being used has a minimum tensile streng:n of 60 KPSI ana a minimum core hardness (Rockwell B) of 70. Round head Souare Neck Bolt (A307) This bolt is constructed in accordance with specification A307, with a minimum tensile strength of 70 KPSI and a minimum core hardness (Rockwell B) of 69 assured by the vendor. The closure bolts to be used will have a tensile strength of 10,000 psi greater than the bolts presently being used. (See Applied Design Drawing d98425 dated 2/22/57 redrawn 9/25/67 and Combustion Engineering Drawing dY0885 dated 6/22/79, Rev. 0) 1733 202 3,q g nEviS:ONS fj1 ~, svu ocscarrTiou oAre A r.wae v a t I: op.c n.: jj!=l,* D 1)REDRA'/iN g,gs 47 v' - '!iiii NOTE. l 3 Eni IO ff [~!i j

l. PROTECTIVE FINISH PER SPIOO7A.

I-~ s2 i 'iii ! i 2.SOLTS SHALL SE IN ACCORDANCE. Nl'/ 4 r!!!!! WITH SAE-STANDARD FOR PHYSICAL l -h0 0'.~. i ji!cwEll A.EQUIREMENTS FOR SOLTS, v q'33 f a ji!'jE CAPSCRE.W5, STUDS, AND NUTS /,\\ f.015

i519i C,RADE 1.M 3

s>z1: 30./ fzR. MAX ON l i,-+.500.O K ,I5:*- e + EEEe;i A ALL CORNERS ON - m.., 00 _ /' TOP PORTION OF I']% 4 'i* j_ HEAD [!\\ 1 +16 l 1 f~ ic"- O 4 A 2 / i T7 'j" + j 1 77;, 3' i S:(E. AK '/ l g4 R M AX. l ED GE. snbR

5?h I

~ I.r. I - = 2 "c-1 MIN. PE.RFE.CT -ia M i THREAD. ~N l v =, 1 7=~ -l 'l +1-13 UNC -2 A i 1 2 M ATERI AL. l UNLESS OTHERWISE SPECIFIED DIMENSIONS ARE IN INCHES. l ST EL SEE C-lO!O c TOLERANCES ON NOTE.2. NEXT ASSY l USED ON rnac tems et swats Anotes 2'

n

,,ge:c,7,os m?'I APPLIED DESIGN o.rc S g.3. 7 ,h<J, (.Y CO M P A N Y. iNC. I OR4WN R. s=, *. ? i 4 ccs Css. H.A. 2.-22..h? ~ 7ey,,,yo,,yg,ycyg i ST R ES S PUNCTfCM 3 %~ O uATEplAL 1733 203 AP*ROVEC jcc c _r COC E s DC..r NC. 5474 ~ AppsOvAt oESicN ACTIVITY 98425 A SP2G2.J \\ '{ [ l$ MEET APFRCV AL OTHE9 g g.g R f C No. 1 AR ~1 1 - 13 UNC

9 L'E d

geh\\ 9 / 'h '} 'llf j!!$ t? 'I'k \\ \\ fittwm'n n9 / _ _. r - c l i t - 4 2 EE l - m-- d I 3 f $hb & $Yk!, l $C l0N &$ BON $/ wim gje 7 ; viny & M/N. rins/LF JrRENGrH of 70 KPJZ. 2, pro 77cnvf F/N/2 S&LL Bf C 1MfRC/AL [*C 1733 204 UNLESS OTMERWISE SPECIPIED CE CIM AL TCL.. P R ACTION AL TOL.: 1 1i64 = ANGLES: tQ 3ce PINISHt PILLE TS: l APP R O V. DATE TITLE Orsas asi snero ecces ti64 man. g.y gg This Orow+ng es the Property of WA COVSUSTION ENGINEERING,INC. Ob N.P.M. h WIN CSO R. CON N E CTICUT REv. and s not to me reproovced or useo to furni.h a*ty information / C for masing of crewmen oc aoosette escoot wnere prow +oso for / O O foe av ogreement wetn sa.o comoan. l SMEET / OF # PixTURE CE 0393132 (2/72) m, m 3-D 6 2. . n e ou a 3.0 THERMAL EVALUATION Materials of all structural components used in the manufacture of the con-tainer tave physical and mechanical properties equivalent to or better than mild steel throughout a temperature range of -40'F to 1500 F. 1733 205 3-1 4.0 CONTAINMENT 4.1 Containment Boundary The primary containment of the CE Model 927Al packages is the 11 gauge steel shell. The unirradiated UO2 fuel pellets are placed within zircaloy fuel rods of approximately.025 inch thick walls. These fuel rods are then assembled into bun-dies. a.l.1 Containment Vessel The outer shell is composed of 11 gauge steel. 4.1.2 Containment Penetrations There are a total of 5 penetrations into the primary containment. Of these, only 2 are presently needed. The remaining three are listed as optional and may be eliminated upon construction of any new containers. Those which are no longer used are the Desiccant Access Hatch, Humidity Indicator, and the Filling Valve. The Humidity Indicator has been eliminated on the longer con-tainers because of its lack of reliability. The filling valve has also been removed because the containers are no longer pressurized. The desiccant access hatch is still on all containers; however, the desiccant bags are presently placed in the container before tne container is closed. 4.1.3 Seals and Welds All seals and welds are soecified on Drawings NFM-E-4108, Rev. O, dated 11/27/79, sheets 1 and 2. 4.1.a Closure The "T" Head Special-Bolt is presently being used for closure of the containers. It is requested that the Round Head Square Neck bolt shown in Appendix 2.10 be app-roved for closure of the containers also. The replacement bolt is equal to or greater than the "T" Head Special Bolt in mechanical properties. 4.? Recuirements for Normal Conditions of Transport It is concluded that under normal conditions of transport (as specified in 10 CFR part 71, Appendix A) the tests results described in Section 2.6 of this applica-tion indicate the following results: (1) There will be no release of radioactive material from the containment vessel. (2) The effectiveness of the packaging will not be reduced. (3) There will be no mixture of gases or vapors in the container whicn could, through any credible increase of pressure or an explosion, significantly reduce the effectiveness of the package. (a) The ::ackage is so designed and constructed, and its contents so limited, tnat unoer the normal conditions of transport specified in Appendix A of 10 CFR Part 71: 1733 206 (a) The package will be subcritical. Criticality safety calculations are presented in Section 6 of this appli-cation. (b) The geometric form of the package contents will not be substantially altered. (c) There will be no substantial reduction in the effective-ness of the packaging, including: (i) Reduction by more than 5 per cent in the total effective volume of the packaging on which nuclear safety is assessed; (ii) Reduction by more than 5 per cent in the effec-tive spacing on which nuclear safety is assessed, between the center of the containment vessel and the outer surface of the packaging, or; (iii) Occurrence of any aperture in the outer surface of the packaging large enough to permit the entry of a 4" cube. A3 Containment Recuirements for the Hycothetical Accident Conditions s TFe effect en the loaded container of conditions likely to occur in an accident was assessed by subjecting a container with simulated fuel bundles to two 30-foot free deep tests and puncture tests as specified in Appendix B of 10 CFR Part 71. These tests demonstrated that no radioactive material would be released. The thermal test was not performed because all structural materials in the shipping container, the fuel bundles, and the stainless steel absorber plate can withstanc 1475 F for thirty (30) minutes. The water immersion test was not performed because full flooding was assumed in the nuclear safety calculations. It was evident from the test that the package would be subcritical, because the two (2) fuel bundles remained in the same position with respect to each other, the simulated fuel bundle was relatively undamaged, and the seaarator blocks re-mained intact between the bundles. Therefore, the nuclear safety calculations for the undamaged package apply, since optimun moderation and reflection by water were assumed in those calculations. 1733 207 4-2 5.0 SHIELDING EVALUATION N/A (The packages are used for shipment of unirradiated UO2 fuel bundles which have maximum external dose rates of 7.5 mr/hr penetrating radiation prior to loading into the containers). 1733 208 s 5-1 6.0 CRITICALITY SAFETY EVALUATION The Model 927Al and 927C1 shioping containers are approximately 43 inches in diameter and up to 217 inches long and contain two fuel assemblies of the types previously described in this application. The two fuel assemblies are separated by six inches minimum. 6.1 Calculational Model The calculational model used in the criticality analysis closely approximates the actual container dimensions. The fuel assemblies were assumed to be comprised of 4.1 wt % U235 enriched UO7 with no poison shims. The most reactive assemblies (the 16x16 design) were modeTed. A three high double infinite array of shipping containers was assumed to be reflected by 4 inches of concrete above and 16 inches of concrete directly underneath, with a 25 foot separation distance between the two reflectors. (This simulates the floor and ceiling of CE's fuel fabrication plant and is necessary to demonstrate safe storage of the containers both inside and out-side of Diant areas). Variable density water mist was introduced to determine the peak reactivity of the system. The density of water within and external to the con-tainers was made identical. Four grouo cross sections were generated at the various mist densities using the CEPAK Code for the following regions of the model: fuel cell, water holes, steel strongback which holds the bundles, the mist region exterior to the assemblies and container, the outer steel shell of the container, and the concrete reflectors. 6.2 Results and Conclusions The above cross sections were used in KENO-IV to determine peak reactivity of the system under the conditions noted. The highest keff of 0.8601 : 0.0082 was obtained for the full flood case while a secondary peak of 0.6206 : 0.0051 was ob-tained at a water mist condition of 0.035 gm/cc H 0. Details of the calculational 2 model and results obtained are presented in Figures 6.1 and 6.2. Since hypothetical accident conditions indicate no movement of the bundles within the container and no significant deformation of the container, the criticality analysis applies to both normal and accident conditions of transport. Although the containers are stacked two-high only (weight limit restriction of truck on highways), the analysis demonstrates that a 3 high double infinite array of containers remain suberitical for all degrees of water moderation as well as for full flood with full water reflection. Each fuel assembly snall be unsheathed or shall be enclosed in an unsealed, polyethylene sheath which will not extend beyond the ends of the fuel assembly. The ends of the sheath shall not be fcided or taped in any manner that would prevent flow of liquids inco or out of the sheathed fuel assembly. All con-tainers will be shipped as Fissile Class III with a maximum of 8 packages per ship-ment. 1733 209 61 6.3 Validation of Calculational Methods for Nuclear Criticality Safety To validate the methods used in the criticality analysis, the 2.5 w/o U23s U09 critical separation experiments by Battelle (Reference 1) were analyzed in three dimensions. The mean keff value of these nineteen experiments was 1.00157 with a standard deviation of.00419. The experiments are concerned with the critical separation between water-flooded subcritical clusters of fuel rods in the presence of various fixed neutron poisons. The experiments were carried out in a 1.8m x 3m x 2.lm deep tank pro-vided with features specifically designed and built for these experiments. These experiments involved aluminum-clad 2.35% U235 enriched U02 rods about 12mm in dia-meter by 914mm in length. The critical separation between three subcritical clus-ters of these rods aligned in a row was determined and analyzed with and without the following neutron absorber materials (neutron ooisons) located between the clusters: 304L Steel with 0,1.1, and 1.6 wt% baron; and boral. 6.3.1 Descriotion of Exceriments The experiments analyzed each consisted of three assembly-like configurations separated by water and/or coison olates with the spacing adjusted to criticality. Figure 63 illustrates typical top and end view of the arrangements. The 914mm length fuel rods 11.176mm in diameter of 2.35 w/o U225 in UO2 were clad with 6061 aluminum having an 0.D. of 62.7mm and 0.762mm thick with different alloys of aluminum for top and bottom plugs. A fixed square center-to-center pin pitch of 20.32mm was main-tained. The number of pins in the width of the cluster varied (in different experi-ments) between 14 and 17 and the length from 20 to 24 pins. The experimental data on exoeriments analyzed are given in Tables 1, 2 and 3. 6.3.2 Method of Calculation The calculation methods which are essentially those used to determine reactivity for fuel rack storage, fuel shipping containers clus other fuel configurations found in fuel manufacturing areas are based on CEpAK (Reference 2) cross sections. Using an appropriate buckling value and takinc proper account of resonance absorption, three fast groups are collapsed from 55 fine energy mesh groups in E0RM and the one thermal group is collapsed from 29 thermal energy groups in THERM 0S. Fast cross-sections for certain trace elements such as sodium and zine were obtained from GGC-3 (Reference 3). In addition, each component such as water gap, end plug, or poison plate has its thermal cross section determined by a slab THERMOS calculation employing the procer fuel environment. Normally, for two dimensional representations, the transport Code DCT-IIW (Ref-erence 4) is used. Since, however, the short fuel length made necessary a three di-mensional treatment, the Monte Carlo Code KENO-IV (Reference 5) was used with six axial levels. Batches of one hundred neutron histories were used with the first four discarded. Calculated keff values are shown in Table 4 For economy, about 150 batches were run for most cases, however, because of their greater use in fuel stor-age analyses, about 500 batches were employed for plain stainless steel and boral. The mean value of the calculated keffs is 1.00157 with a standard deviation of .00419; thus at a 95/95 confidence level using a o multiplier of 2.423, the keff values are between 1.012 and 0.991 1733 210 6-2 6.3.3 References 1. S. R. Bierman, E. D. Clayton and B. M. Durst, " Critical Separation Between Subcritical Clusters of 2.35 w/o V:3s Enriched UO2 Rods in Water with Fixed Neutron Poisons", PNL-2438, October 1977 2. CEPAK -- A Snythesis of the following computer codes: FORM - A Fourier Transform Fast Spectrum Code for the IBM-7090, McGoff, D. J., NAA-SR-Memo 5766 (September 1960) THERMOS - A Thermalization Transport Theory Code for P,eactor Lattice Calculations, Honeck, H., BNL-5816 (July 1961) CINDER - A One-Point Depletion and Fission Product Program, England, T. R., WAPD-TM-334 (Revised June 1964) 3. J. Adir, S. Clarke, R. Forelich, and L. Tody, " Users and Programers Manual for the GGC-3 Multigroup Cross Section Code", GA-7157, July 25, 1967 4 R. G. Sottesy, R. K. Disney, A. Collier, " User's Manual for the DOT-IIW Discrete Ordinates Transport Computer Code", WANL-TME-1982, December 1969 5. L. M. Petrie and N. F. Cross, " KEN 0 IV, An Imoroved Monte Carlo Criticality Program", ORNL-4938, November 1975 1733 211 6-3 O 5 e J a: - : e (*) w6u { l .jp w a,d,,l?.t r j e d . l',4 1 ,11

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[!JD VI(W UI ! v~ a PLA'dVICW 1733 214 nsun s.3 D*"]D D)0301 @ oJuu2UAlfdo o e Ju TABLE 1 EXPERill.E:.:TAL DATA C.N CLU5ERS CF 2.35 wr. U Et;R! HED UO NcDS IN WA R 2 FUIL CLUSTERS LENGTH x WIDT4 CRITICAL SEP ARATION 20.32mm 50. PITCH SE1V,'EEN FUEL CLUSERS (1) (FUEL RODS) (Xc, mm) EXPERilJ.ENT l'U.;EER 20 x 17 119.2 0.4 015 20 x 16 T,3. 9 0.5 035 20 x 16 FA.4 0.5 (X9 (2.) 22 x 16 (3) 103.5 0.5 018 20 x 14 44.6 1.0 021 (1) FERPENDiCULAR DISTA'.'CE EET/iEEt1 THE CELL COUNDARIES OF THE TUEL CLUSERS Lli.ilTS ARE CGE STANCARD DEVI ATICU (2) RERUN OF EXPERil.iENT 0:3 (3) CENER FUEL CLUSER AT 20 x 16 RODS. Ti/0 CUTER FUEL CLUSTERS AT22

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W1T 'T le 1733 215 m m M e MUMhL

4 T. ELE 2 MA U ENRICitED 00 RODS lilWAER WITH 304L STEEL PLATES O EXPERIMENTAL DATA ON CLUSERS OF 2.35 win 2 g BEIV/EEN FUEL CLUSTERS (1) C ust 301L STEEL PLAIES (2) FUEL CLUSTERS fer@ h LENGTH x WIDill DISTANCE TO CRITICAL SEPARATION 20.32mm 5Q. PIICil BORON CONENT TillCKNESS FUEL CLUSTER (3) BERVEEN FUEL CLUSERS (4) g g m (FUEL RODS) wtr. Op. mm) (G, mm) (Xc. mm) EXPERIMENT fjUMBER 20 x 16 0 4.SS 0.15 6.45 0.06 63.3 0.2 02S 20 x 16 0 4.3510.15 27.32 0.50 76.410.4 00h 20 x 16 0 4.85 1 0.15 40.42 0.70 75.1 0.3 027 20 x 16 0 3.0210.13 6.45 0.06 74.2 i 0.2 0?7 20 x 16 0 3.02 0.13 40.42 0.70 71.6 i 0.3 026 20 x 17 0 3.02 0.13 6.45 0.06 101.4 : 0.3 C* 20 x 17 0 3.0210.13 40.42 1 0.70 114.7 0.3 033 20 x 17 1.05 -2.93 0.06 6.4510.06 75.6 i 0.2 032 ] 20 x 17 1.05 2.93 0.06 40.42 0.70 96.2 0.3 033 U 20 x 11 1.62 2.93 t 0.05 6.45 0.LY; 73.6 0.3 038 20 x 17 1.62 2.98 i 0.05 40.42 i 0.70 95.2 0.3 037 os (1) ERROR LIMITS Si10WN ARE ONE STANDARD DEVIATION (2) PLATES ARE 356mm WICE BY 915mm LONG. (3) PERPT':0!CULAR DISTANCE f ERVEffl f!IE CELL BOUNDARY OF THE CErlER FUEL CLUSER AND THE NEAR SURFACE OF THE SEEL PLAE (4) PERPit:DICULAR DISTANCE BEBVEEN IllE CELL BOUNDARIES OF THE FUEL CLUSTERS

To di,' i enish f: on 9):perimnt !!OCS of T.Qlc i.

TABLE 3 Eyr EPI.',iE iiAL CATA CN CLUSTERS CF 2.35 4 U El.'RICf9.'C RODS IN '/!ATER WlIH BORAL PLATES 3 BEP//EEt; FUEt CLUSTERS (1) FUEL CLUSTERS BORAL PLAES LE :0TH x 'lii. iH OI S T A.*:CE TO CHlilCAL SEP ARAilCN 23.3 n 50. NICH TH!CKNE55(2) FUEL CLUS EF. (3) BET /.EE:: FUEL CL'J5iER5(4) (FUEL P.C;5) ip, rc.m) (G. mm) (Xc. n el EXPERI,'.1ENT ::Ut.'.EER 73> 17 7.13 0.11 6.45x0.06 63.4 : 0.2 OM 20 x 1, t.13 0.11 44..:2 0.60 90.3 0.5 016 22 x 16 (5) 7.13 : 0.11 6.45 : 0.C0 50.5 0.3 0 17 (1) ECT;GR Lllf.II5 SH0'llN ARE ONE SlANDARD DEVI AilCN (2) It:CLUDE5 ' 02 mm THICK CLAODl!:G CF '.r'E !!00 At 0 : ElIHER 5101 Of THE scc-Al CCRE MAERt AL. PLATES 355mn 'lllDE SY 915 mm LCNC. (3) PER E'.DiC'ULAR DISTANCE FET/.EE:J THE CELL SOU::DARY CF THE CEnri R FUEL CLUSTER A OF THE SCRAL PLATE (4) PERPE';DICULA?. DISTA';CE EETl.EEN THE CELL SOUNDARIES OF TFE tut 1. CLUSTERS (5):ENER fuit CLUSTER At 20 x 16 RODS. rii0 OuiER FUEL CLUSTE?.5 At 22 x 16 ROSS EACH 1733 217 D**D D 'T Y f 2.u wo e h 7.0 OPERATING PROCEDURES 7.1 Procedures for Loading the Packaae Manufacturing Specification MFG-03-02 contains detailed procedures for the packaging and preparation for shipment of fuel bundles. In compliance with Sub-part D to 10 CFR Part 71, the following are inspections, tests, and special pre-parations which are included in these procedures: a) External Inspection of Shipping Containers b) Preliminary Preparation of Shipping Containers for Loading c) Final Preparation of Shipping Containers d) Loading of Fuel Bundles e) Security of Strongback f) Security of Accelerometers g) Final Closure of Shipping Containers 1) "0" Ring Inspection

2) Fastening of Closure Bolts h) Loading of Desiccant i) Label Preparation j) Loading and Fastening of Containers to the Conveyance Vehicle 7.2 Procedures for Unicadino Package Manufacturing Specification MFG-03-04, "Unpackaging and Insoection of Fuel Bundles" provides procedures for the following:

a) Inspection of Conveyance Vehicle Prior to Unloading b) Unfastening and Off-Loading of Containers c) External Inspection of Shipping Container d) Preliminary Preparation of Shipping Containers for Unloading e) Final Preparation of Shipping Containers for Unloading f) Unloading of Fuel Bundles 7.3 Procedures for Preparation of an Emoty Packace for Transoort Manufactu*ing Specification MFG-03-04, "Unpackaging and Inspection of Fuel Bundles" provides procedures for tne following: a) General Securing of Strongback b) Securing of Strongback c) Procedure for Loading and Fastening Containers on the Conveyance Vehicle d) Label Preparation of Empty Containers and Venicle for Transport l[}} }}g 7-1 In addition to the above procedures perfomed by Manufacturing, the Quality Assurance Depart:nent perfoms a thorough inspection of the container and bundles both during and after the loading operation. These procedures are in accordance witn 10 CFR Part 71.62 & 63 and are available for inspection. 1733 219 7-2 8. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.1 Acceptance Tests All containers to be fabricated will be constructed in accordance with drawings NFM-E-4108, Rev. O, dated 11/1/79, sheets 1 and 2 and shall be source inspected prior to leaving the vendor's facility. Changes to the design of the container which fall outside of the safety envelope specified in this application will be submitted to NRC for approval. This may include retesting of the container if analytical results are not capable of demonstrating that the test sequence pre-viously performed would be applicable to the changes made. 8.2 Maintenance Program The maintenance program uses the Quality Assurance inspection procedures to determine when any repair or replacement of material is required. These inspections include: a) Visual Inspection

1) Container External Condition

2) Container Internal Condition

3) Cover Gaskets b) Tests Performed 1)

Impact Records Tested

2) Test of Manual Pressure Relief Valves 1733 220 O

1C M 8-1}}

ML19290C060

Text

Response

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