ML20126K221
| ML20126K221 | |
| Person / Time | |
|---|---|
| Issue date: | 05/30/1985 |
| From: | Greeves J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Cobb L, Costanzi F, Gammill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| REF-WM-85 NUDOCS 8506100824 | |
| Download: ML20126K221 (1) | |
Text
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,_' NMSS MY 30 g REBrowning MJBell 40fcE/MT/2/7/85 JTGreeves 1- TCJohnson MTokar HJMiller J0 Bunting MEMORANDUM FOR: William P. Gammill, Chief LBHigginbotham Meteorology and Effluent PDR/tMMW(WYpp9)
Treatment Branch y yjy pg g { _ , Division of Systems Integration ;g y gg n , ,. . g_ _ Frank A. Costanzi, Chief P3 ; " - Waste Management Branch t h !L_- - -- Division of Health, Siting, DistribuSa: and Waste Management _ _._ _ _ . _ _ _ _ Leonard I. Cobb, Chief TiEtura to WM,623 2) ~ Safeguards and Materials Programs ~' Branch ~ Division of Quality Assurance, Safeguards and Inspection Programs Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety FROM: John T. Greeves, Chief Engineering Branch Division of Waste Management
SUBJECT:
SUPPLEMENT TO NUPAC ENVIRALLOY HIC REPORT Attached is a copy (non-proprietary) of a supplement to the topical report on the NUPAC Enviralloy Family of HICs. The supplement addresses the prototype drop testing of NuPac's EA_142 HIC. Inasmuch as your branch is assisting in the review of the topical report, your staff may have some coments on this report supplement. Please provide any coments by July 1,1985. E John . Greeves, Chief Engineering Branch Division of Waste Management
Attachment:
As stated 8506100824 850530 PDR WASTE WM-85 PDR OFC :WME N :WME : G : : : : 0____:____________:___4 _ ___: _ _ _____:____________:____________:____________: __________ NAME :MTokar:gh :TCM so - e es : : : : 0____:____________: _____ ____ I DATE :05/2'J/85 :05/b85 5/$d/85 : : : :
L 6 EA-Family /EA-142 s EA-142 PROTOTYPE TEST - W Supplement to NUCLEAR PACKAGING, INC. ENVIRALLOY HIGH INTEGRITY CONTAINERS February 1985 m M e y D f uj %v p e r # W fU
EA Family /EA-142 Enviralloy 190 Cubic Foot Prototype Drop Test 4 The Nuclear Packaging EA-142 High Integrity Container was tested in accordance with the requirements of the NRC branch position on high integrity containers and the State of Washington require-ments for high integrity containers for burial at the Hanford Burial Site. This prototype testing is done in accordance with Section 15 of Nuclear Packaging's Enviralloy High Integ.rity Con-tainers Topical Report dated June 29, 1984. The EA-142 High Integrity Container is a container approximately 64 inches in diameter by 70-1/4 inches high. The container is made out of Ferralium Alloy 255. The model that was. dropped was Nuclear Packaging series A container using a locki$g lug closure configuration. This container has four internal supports that come to bear beneath the closure ring. The container has approx-imately 24 inch diameter opening. The container is fabricated from 3/8 inch thick material except the closure ring and wedges which are 1/2 inch material. The gross weight the container is licensed for is 10,000 pounds. This weight corresponds to the license payload weight of Nuclear Packaging's 142 cubic foot Type B cask. The tare weight of the empty EA-190 container is approx-imately 2,575 pounds. The gross weight of the container that was dropped was approxi- . mately 10,200 pounds. The payload for the drop container con-sisted of moist sand. The sand approximates the consistency of dewatered resins which is the typical radioactive waste that j is shipped within these containers. In addition to the sand, 6 steel pipes (see picture) were placed in the container to simu-late worst case internals since normal dewatering internals are f abricated f rom plastic pipe. The container was closed in the normal way by placing a silicon rubber gasket top and placing the 3/8" thick lid on top of the gasket and driving in eight wedges i that sealed the container. It should be noted that during all i drop tests, these wedges were not resecured and no leakage did i occur. - The container was drop tested with the polyethylene and carbon optional seal as shown in Attachment 1. The seal was located in the center of the lid. The seal did not fail or cause any - release of contents. The container was dropped f rom both four foot orientations as required for a Type A package and from 25 foot orientations. 1 The four foot drops took place on an unyielding surface, a heavy duty drop pad that was designed for drop testing of casks. The 25 foot drops were done in a parking lot for heavy trucks that was basically a gravel bed over compacted soil. i e i i 1 L
y. u o a EA Family /EA-142 The container was dropped in five orientations f rom each drop height. These orientations were the bottom down, flat down, bottom corner down with center of gravity over struck corner, side drop, top straight down, and the top corner down with center of gravity over struck corner. One container was used for all ten drops. The container did not sustair. any significant damage f r.om any of the drops. The only damage that was sustained by the container was a slightly dented lif t lug on the top due to the four foot - drop on the top straight down, and some damage on the corners due to the four foot drop. The lifting lug was not bent or deformed sufficiently to prevent its use. The container was slightly bowed due to the corner drop on the four foot drop. K1so the ends, top and bottom were plastically deflected from the corner drop. None of these deformations were in the excess of 1/2 inch. The container did not sustain any loss of contents as a result of any
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of these drops. The container was not damaged either on the outside or on any of the inside supports, such that it would prevent its use. The container was cleaned up after the drop and all welds were magnetic particle tested to detect any damage to the welds. No damage was detected. In ' addition to the drop test the container under went a pressure test verifying the seal of the gasket. The container was pres- - surized to 57 psi before leakage was detected. This was per-formed as a soap bubble test with an air over water prior to the drop tests. Under this test no detectable deformation was noted. A successful lug load test was .also performed on this container. Each lug was load tested to 300% of its rated capacity. All three lugs were used to lif t the container by its f ull weight one lug at a time. The following pictures show the container during some of the drop tests and afterwards. o l i 2
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