ML20206M145
| ML20206M145 | |
| Person / Time | |
|---|---|
| Issue date: | 08/04/1986 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-PROJ-M-44 NUDOCS 8608200488 | |
| Download: ML20206M145 (24) | |
Text
{{#Wiki_filter:.-- t O l AUG 04 W Project No M-44 MEMORANDUM FOR: Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety FROM: John P. Roberts Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety
SUBJECT:
MEETING WITH NUCLEAR PACKAGING, INC (NUPAC) Date and Time: August 1, 1986; 9:00 a.m. Location: 5th floor conference room, Willste Building, Silver Spring, Maryland. Attendees: See enclosure 1.
Purpose:
To discuss submittal by NUPAC of a dry concrete storage cask design topical report. Summary: NUPAC intends to submit a topical-report in late 1986 covering the design of a dry concrete storage cask which can store 9 containerized, unconsolidated, pressurized water reactor spent fuel assemblies. These can be loaded by use of a transfer machine (See enclosures 2 and 3). Major areas of discussion in the meeting centered on the temperature range for the concrete cask during storage and impact effects for a cask drop (See enclosures 4 and 5). NUPAC has previously been involved with concrete transportation casks for reactor resin wastes (See enclosure ;6). >4 9 8608200488 860804 PDR PROJ M-44 PDR
r t 8 AUG 0 41996 Leland C. Rouse 2 NUPAC is presently considering a concrete cask drop testing program of limited extent with a scale model cask to support its structural analyses. A future meeting is to be scheduled for early September 1986. ORIGINAL SIGNED BY; John P. Roberts Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosures:
1. Attendance List ^ 2. Brochure 3. Transfer Sequence ~. 4. Introduction 5. Impact Event 6. Cask Drop Testing 4 DISTRIBUTION: . Project No..M-44: PDR NMSS r/f FCAF r/f FBrown Beveridge/ Cornell JRoberts / m -___[_ f__I____________________________________[_________ ____b $_I__________________f.________ DATE:08/4 /86 :08/4/86: I 0FFICIAL RECORD COPY J
.i 4 ATTENDEES J John P. Roberts NRC/NMSS I Philip W. Birkeland ABAM Engineers J. F. Costello NRC/RES Hans Ashar NRC/RES Stephen Goetsch NUPAC r Jack D. Rollins NUPAC i Richard T. Haelsig NUPAC l Jim Schneider NRC/NMSS Gary C. Comfort NRC/NMSS j Philip A. Craig NUPAC 1 .. ~. - ~
2 s9 lNTrdoDUCTl0M TO CON' CRETE STUDY l GOALS GENE!2A,L BEHAVIOR OE CONCRETE AT ELEVATED TEMPGRATURES MIX DEStGM CONSIDERATlONS EXPECTED REMAVlOR OF COMCRETE lW TWE GFSC
SUMMARY
1 l l l
GOALS GXPOSURE 20-100 Y12 LIFE 4Go*Fe ID, 300 F e OD CNVIRONMENTAL a KEY PROPERTIES FoR A Goop l ENGINEERING MATERIAL AccEPTAeiLE. TklEEMAL CONDUCTlVITY (K > 0.8) REASONABLE STRENGTI-l o (f) > l.G KSI ) PRCDICTABLE SECONDARY o PROPERTIE5 C G, c<, SHRIN KAGE,,,,)
i l l l l GENERAL bel-(AVIOR AT ELEVATED TEMPERATURES j COMPOS lTE AGGREGATES (ccARSE 4 FINE) o j PASTE (CEMENT / WATER GEL) a INTERACTION o l BEHAY10R MODES i ABOVE 180 F PsDT ibELDW Goo F o / AUTOCLAVING, NUCLEAR APPL'f 7 LlVD2ATloN IF UN9EALED v INDRATloN lF SEALED A8oVE GOO *F o v AGGREGATE REACTIONS / PASTE REACTIONS 4 I I i e---,
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I EXPECTED P.3EWAVIOR OF CONC (2ETE IN TWG GFSC _ DEPENDENCG UPON GXCESS MolSTORG CONCRETE NEAR ID lNITIALLY MolsT eT > leo e THEN DRY e T4 460*F CONCRCTG IN MIDDLE MolST OVER LONG TERM, T ~ 300 F + CONCRETE NEAT 2 OD MolsT CORE G T < l&) F = TNGN DRICS P>EFoEE T > 2OO*F o CONSEQUGNCES To PRoPERTlGS NEAR ID l IN MIDDLG l NEAR OD o l
SUMMARY
GOALS i GENERAL f3ERAVlOR MIX DESIGM BEWAVIOR IM TWG SF5C CONCLUSIONS ACCEPTABLE CONDUCTNITY o REASONABLE STRENGTW o PREDICTAPsLE SECONDARY PROP'S o A GOOD ENGINEERIMG MATERIAL a i I l
t IMPACT EVENT: UNDER CERTAIN SCENARIOS, IT MAY BE REQUIRED TO MOV E THE LOADED CP-9 AROUND ON-SITE. THE MOST ECONOMICAL METHOD IS TO USE A HEAVY-HAUL FLAT-BED TRAILER. INTERFACING WITH SUCH A TRANSPORTER WOULD REQUIRE LIFTS OF SOMEWHAT LESS THAN 5 FEET. DUE TO GEOME-TRIC CONSTRAINTS, THE ONLY CONCEIVABLE ACCIDENTS WHICH COULD OCCUR WOULD RESULT IN INITIAL IMPACTS ON THE BOTTOM SURFACE OR
- CORNERS, AND IN THE WORST CASE, SLAP DOWN ONTO ITS SIDE.
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d IMPACT EVENT - ANALYSIS AND TESTING 1 1. SIMPLE DROP EVENTS CAN BE ANALYZED USING FIRST PRINCIPLE TO I DETERMINE G-LOADS AND INTERNAL FORCES. 2. SHEAR FRICTION ANALYSIS CAN BE USED TO DETERMINE THE ADEQUACY OF THE REBAR CAGE TO PREVENT GROSS REARRANGEMENT OF THE CONCRETE SHIELD. 3. REBAR PREVENTS GROSS PENETRATION OF MISSILES. 4. APPROACH IS TO ASSUME A CRACK, AND INSURE ADEQUATE REBAR CROSSES ALL POSSIBLE CRACKS. s 5. ANALYSIS METHOD GIVES REASONABLE RESULTS FOR THE DROP TESTS I WE HAVE PERFORMED TO DATE. 6. DUE TO THE UNVERIFIED NATURE OF THIS ANALYSIS METHOD, TESTING IS PROBABLY CALLED F OR. 7. . SIZE OF CASK DICTATES SCALE T.E S T I N G. 8. CELERITY EFFECTS (THE SPEED OF SOUND IN CONCRETE) GENERALLY WILL MAKE SCALED PERFORMANCE SOMEWHAT POORER THAN FULL SCALE PERFORMANCE, THUS SCALE TESTS ARE PROBABLY CONSERVATIVE. NUPAC SHEET 2
i IMPACT TESTING 0 TESTI NG MUST I NDI C ATE ADEQU ATE PERF ORM ANCE F OR AN ACCI DENT CONDIT10N O ADEQUATE PERFORMANCE IS CONSIDERED TO BE NO CRACKS UNDER-NEATH REBAR CAGE WIDE ENOUGH TO PRODUCE A SIGNIFICANT SHINE PATH, AND NO BREACH OF INNER CONFINEMENT O INTERNAL FORCES ARE MAXIMlZED AT HIGHEST F C O EXTERNAL DEFORMATION (IN IMPACT ZONE) ARE MAXIMlZED AT L OWE ST F C O SEVEREST RESULTS WHEN F IS LOW C 0 EXPERIENCE SHOWS THAT IMPACTS FROM UP TO 9 FT WI TH HI GH F C (~ 7,000 PSI) YlELDS VERY ACCEPTABL E RESUL TS (CONC. HIC IS (44%)3 0F CP-9, BY WEIGHT). O O
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___. _:.r _ _ :: ; $~ed C' 9a c., (.ptc. D6 COP TESTIN& Revision 1 September, 1982 A.12.4 SEAL INTEGRITY Sealing was accomplished as described and documented in Paragraph 5.2.4. The container cavity was pressurized to 10 psig and held in excess of one hour with no pressure drop. All sealing surfaces and areas were soap bubble checked per ANSI Standard U14.5 and no leakage detected. Both detection techniques demonstrated the container to be -3 3 leak tight to at least lx10 atm-cm jg, A.12.5 HANDLING ACCIDENT EVENTS (DROP PENETRATION) The test events described herein consist of: A corner impact on an unyielding surface from, o 3 foot height. A corner impact on an unyielding surface from 9' o height. A 40 inch penetration pin drap on the container o sidewall. The first and third events demonstrated the ability of the container to withstand Type "A" Normal Conditions por 10CFR71. The second sequential test involving a 9' drop was a develop-mental test to explore the ultimate capacity of.the container; this 9 foot drop exceeded design requirements of the container by a factor of three ( 3 ),, based on energy considerations. In summary, the package survived the first and third Type "A" tests with little damage and full retention of all functional capabilities. Thu ultimate capacity test at a 9 foot drop showed potential degredation of sealing features (for gaseous contents) but no loss of containment or ejection of contents for solids or particulate content forms. A.12-11
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Revision 1 September, 1982 Both bottom corner drop tests employed a lifting bar that rotated the container to 42 with respect to vertical. This angle was selected to cause the container to topple-over f following corner impact striking the lid closure region in a 1 " slap-down" impact. Analyses demonstrated this " slap-down" impact in conjunction with corner impact was the "most severe" orientation for the package. In both drop tests, the lifting bar produced modest local i distress in the concrete adjacent to the lift lug eye due to the introduction of lateral prying forces at the lightly reinforced top edge. In fact, modest cracking, due to these laterial prying forces, developed just as soon as the container was hoisted at an inclined angle. A.12.5.1 Three (3) Foot Corner Drop Figure A.12-7 illustrates the drop test setup just prior and at the instant of impact. The drop pad, or " unyielding" surface, shown consists of about 200,000 pounds of concrete topped with a 1-1/8" grouted steel plate..Tae container is supported by a " quick release" latch supported by a mobile crane. Resultant damago from the three (3) foot drop is illus-l trated in Figure A.12-8. The left hand photo indicates a crush, or crumble, zone at the point of initial impact, characterized by a'24" flat. Concrete on the sides and spalled away from the hoop reinforcing for a height of j about 12"; about as predicted. ) i e A.12-12 2 .r.--
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. ~... -. -. -. -. c r o. i Revision 1 September, 1982 i The top right photo shows very modest (insignificant) distress to the seal area. A small hairline crack is I seen at the center of the photo on the top edge of the l-concrete body sidewall. The epoxy sealant top surface j shows a circumferential hairline crack from the lug eye location to the body sidewall crack. l I The lower right photo shows distress around the lug eye i caused by lift fixture prying forces. None of these observed distress locations compromise functional performance of the container in any fashion. ? I i 1 j A.12.5.2 Nine (9) Foot Corner Drop i The container was initially rotated 180 about a vertical axis, with respect to the lifting bar, in order'to impact on the opposite, undamaged side. Prior to hoisting to a j the nine (9) foot drop height, the container accidently { dropped due to premature release of the " quick-release" i j latch. Damage was somewhat,more extensive than for the I i 'three (3) foot drop described previously. f i i j Figure A.12-9 shows the package immediately before and j l after impact. Figure A.12-10 shows resultant typical { damage. The left hand photos show that the initial impact zone is little chanced in character from that experienced l during the three (3) foot drop. The crush or crumble { zone increases up to about a 30" flat (versus 24" for l ) a three foot drop). i [ The right hand photos rhow significant damage to the j container closure region opposite the point of impact. - { A crack developed around the complete circumference of 4 the lid with width approximately 1/8 inch. Failure occurred in the lid concrete adjacent to the stronger 1 l L ~ mmm
i i i { Revision 1 September, 1982 i l l FIGURE A.12-9 ) MINE (9) FOOT COPNER DROP i Y I 4 l I l l 1 a l t I 1 L t t i ) i ..b _,. - e ? ad _f?+.4yg, 5 s i I l
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L: - ' ~~ 3 Revision 1 l September, 1982 i 4 epoxy grout. The bulk of radial crack damage was con'- i centrated in the vicinity of the lift lug eyes. Certainly l a portion of this was due to prying forces induced by the test lift bar, j It appears that the majority of damage was due to the rigid i body lid accelerating into the top edge of the body lip. ) The body lip resists these forces by hoop tension in the l reinforcing steel. This reinforcing steel yielded and l ruptured within the top 6-8" of the container lip region; " necked" bars can be seen in the lower right photo. Upon yield of the steel the lip region of the body increased in diameter producing a tensile circumferential ) crack around the lid. I i Despite this complete circumferential crack, the lid l l remained firmly attached to the body. This is because the h i lower plate of the lid is held captive beneath the 1 intact apoxy grout attached to the body lips see joint detail, Zone C6, Drawing EP-20-101D, Appendix A.l. Lid attachment was further explored by destructive exam-ination of the joint, see Figure A.12-11. In the photos shown in this figure, the lip is broken away to the body l lid flange. These photos show the captive lower plate of the lid and also indicate the primary gel seal remains substantially intact. Subsequent to these photos, a j bulldozer fitted with a ripper bar failed to remove the lid from the body. I i Thus, under nine (9) foot drop conditions, containment j for solids and particulate contents is conclusively i demonstrated. J A.12 -18
f 1, l Revision 1 ~ i September, 1982 1 FIGURE A.12-11 DESTRUCTIVE EXId4INATION OF LID JOINT i FOLLOWING NINE (9) FOOT DROP ,e j l l ~~ ..; 7..y., y. mf C ..'y. J.' * ,. ' *
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j , The removable inner containment system / fuel basket can bo modified to fit specific user requirements and a variety of j nuclear or radioactive payloads. Available now for transshipping operations at utility sites, . casks such as the NuPac 125 0 will also be used at either a monitored retrievable stomgo facility or in repository oporations in the 1990's. Those casks are designed for "well aged" fuel. I Principal design features includo: O Lowcost Nuclear Packaging's T 3 an'd NuPac 125 O cat,ks are the only 0 Licensability new spent fueltransportation packages to belicensed in the O'Capablo ofIntermodaltrantport U S. sinco 1976. Both are licensed to " current}' requirements O Convenient,self contained uprighting systom and as such bear the "D(M)F" designation. j OCg elm M Wsus i I The NuPac 125 0. rail cask is used for transpcrting canisteis of The T 3 cask was designed. licensed and tabncated by l damaged fuel from the Unit 2 reactor at Three Milo Island to Nuclear Packaging for the U S. Departmont of Eno.gy's Fast the Idaho National Enginconng Laboratory at Idaho Falls. Flux Tor,t Facility, Tho technical stafI at Nuclear Packaging can i I idaho. The NLPaa rail cask' employs'n unique " double ' do' ign'and hconso shipping containers and handl.ng systems { s .containttionti system which safofy encapsulalas the damaged, for any nuclear application. Nucloat Packaging has the onpor.. i 4 1 fuel canistors and represents a prototype of a now generation tise and roscurces to produco containers for all forms of ' of irradiated fuel shrpping casks for this decado arwl the nort. nuclear material-on timo and within budget. + j I i i Ntit1Ulft 4 t l '/ I t.~ K.,./ I t '.Il l t e t u.,y j 1010 South 336th Street
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