ML20125C311
| ML20125C311 | |
| Person / Time | |
|---|---|
| Issue date: | 07/26/1983 |
| From: | Singer B NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Nussbaumer D NRC OFFICE OF STATE PROGRAMS (OSP) |
| Shared Package | |
| ML20125B114 | List: |
| References | |
| FOIA-92-93 NUDOCS 9212110137 | |
| Download: ML20125C311 (7) | |
Text
{{#Wiki_filter:._ _ ._..~ _ _. . _ - _ - - _ _ _ _ _ _ . _ _ _ _ _ _ - . _ _ _ _ _ _ d
, UldlKibullON: ,
FC Central File
.! NMSS rf {
i
,l FCMC rf '
SLBaggett ! g 2 01983 i MEMORANDUM FOR: Donald A. Nessbasseer Assfstaet Directer for State Agreements Progres Office of State Programs ! FROM: Bernard 5foger, Chfef Material Certiffcatfesard Procedures Breech ; Divisfoe of Feel Cycle and Materfal 54fety,19455 SUEJECT: REQtrEST F0et TEDWIICAL ASSISTANCE Per year regnest dated Jose 28,1983, submitted to the State of Maryland by Neutree Products. Inc.se have review We ender-stand that Neutree Products, Inc. pr distrihete these Cebalt-ce searces. t;mses to ennefacture and cassercially not here adegente f aformattee to permit a seitable analy 1 We need Nostree ftems: Products. Inc. to provide additiemal tekreetIen en the felleetag
- 1. ,
A andsure detailed descriptfee of the searce, fuelede procedures standar'd searce. regetmd fir fabricatise and anaefeatfee of the 2. Descrfptfens ef the oporating condttiens 1stended hr the seerce \ focluding any itettattees'(envirassent, tempersters, cycles, etc.). i 3. L Masleenlihstres design levels esposted and at:1een soeber of cycles in of sdorse. l
. % does the enclosed O'Dessell 4 Associates, lac. report apply to the change? "
4. Are any ope n tfes restrictions betog receamended h r the assaded license by the applicent er befes considered by the state that should be coesfdared ie as analysfs? 5. Was r AltSI E538 or DOT 5pecial Pere-testies perferend en the . sea ce? If met, please seet these regef remmets.pievide data that shoes the searce will-eso, July 1983, DOT 5pecial- The searce Form testing sheeld be evaluated to the requirassets. 9212110137 920504
.PDR FDIA MOUTVIC92-93 PDR-2fgj37 O g -
UMNAM3 b .. onnu . i AC FORM. 318 (10 80) N RCM 0240 . . . . . . . . . . . , . . . < _ OFFICIAL RECORD COPY - I _
y Jl.t o M3
- , We will continee our review soon recafpt ..tJ}e,tabet'tyinformation. If you have any questions, pleasa contact Steve gtgget staff, Bernah . -- 1 Sin. M"$00$,;p e3 W~
ger, Thief Material Certiftcation and Procedures Branch Divisfon of Fuel Cycle and Material Safety, IMSS l < l l l-
\,
"'c' > . .F,C,MC, , g ,, ,,gij ,, ,, ,,, ,,,,, ,,,,,,,,,,,,, ,,,,,,,,,,,,, , ..
, S>a**>SLBaggetnt.41. U C ... ... St... ............. ............. ..
^"> ' 7./.26/,83 . . . . . . ;7/ /r.163. . ..72.3.fl07..
- nac ronn ais oasoi sscu o2.o OFFICIAL RECORD COPY
w a rr 2 [ [ - Qu [j - p . NEUTRON JRODUCTS inc ,
$301 Alt, Ephraim Road, P.O. Box 68 Dickerson, Afaryland20342 USA 301/349 3001 YWX: 710-823 0342 October 27, 1983
* *83 ~RN -2 A10158 hr. Charles E. Mcdonald, Chief' Transportation Cartification Branch Division of Fuel Cycle and Material Safety Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Mcdonald:
~
"~Please confirm that we are registered as a user of the Chem-Nuclear Systems, Inc. CHSI 1-13G radioactive materials shipping cask as stated in the attched correspondence. Package identification for this cask is USA /9044/B( )F.
We find that the certificate of Compliance for this package was not included with others-we received f rom your of fice on August 29, 1983. 4 Thank you. ,
- Sincerely, N NEUTRON PRODUCTS, INC.
- j. } 4. .
~
,2 0 N.00 '
, 1 .,
. Teresa L. Snyder .
s ,/.w.. > - ,.t.. q. . , ,
' Traffic Department
.:f.N4d.'
5,7(N*' 3 '- $$5@f 34: .'. . MJYM.s ,
'1 ' ' ' ' NN * "
N Enclosure
;4-.
J
.;... N',f',c.-
~
.'T(,TLS/kmw.,,Qh 5
* .* tM$;,,, , y'l.p . .
*' 7 '
(eq3;y 1,!;f3.. f
." ~ ?/*).' . .
y,3 g; , '.3.g,j . y
'f;12
- x. .
*f.if
. " a;:c,,;. Q,g', +C
" g ,,"[;, 7 D'qlir,.,,1d., 'v' .d
% frj N' CO
'i, ,-[ (/h.,'d [ , , g,j; s
4- , 4ges[: n.c
- w. e pocxmn s.
\'
W SW..
. ^4
,.. <WG; ; '
- D a W.e e p
& k.uW*,L,unUIC. wie 7.e s
. @i:W e =' .
. - I *.
m .
%g.; W.m, % '
u.:: ;;a-m MmLQ. xM,1;M T.NOVga 1983 y - . w
-s2
.;gg9,4? 0- ; wpp
, a- ~
y mAltssenos v
. . . w. .
9/ . *'.
~
.~S 'f 3*
~.'.:,n.'~. .
9, -
,7 1.g.
*;*;g 9 ,;
g; 7,p..,o .
- emt. . . . 47.g.,
' ^ -:.m
. , Jcg. a >. . ,, % - 490aBCLux Mg'. w ..g.gy 1 ~vti . ,% i:, ..
s.. . . 4go
- g y, y;p$pya. ., _ . 4;:y.;v;.g.
.. f ir,,1 m , .o , . f,.5 9...., s . .. .. t.
- y '.* '.' , ,.'.h,J,og.,, ), it", . ,
a
* , N' u .' a: y> .m_ n &.. f.. .,*.e ";:- *l .' ' . , *:
i.
,',. .,'f., ty, s, .=s. ... A .g-9 .s > -p
- h. l n .a . , ,n
>, . . . . s s, ,.,. .
3,
.e
.c .. -
-4 e
4.,,
-,- .r .
. . . . ..,n.-
October 23, 1980 .. . , n..,
~
~ Tr'a"nsp'ortatica Branch
- . . s ' V 'O ~+' '. .
Division of ruel Cycle-oud ... :" n..
- N..
- L ~ ,..:'M ,... W
* ? teria*1 Safety ,
.. .; 7.. .
Muc1 car ?mgulatory Ccmissicn .J...,',..,-.....
.y
=_h_..
. .h..ington_; D. r__C.=. . _20555 .
, .'..,.i.', . y . . ,
T--l1.
- g. ,.
. .: ... . . -.~. 4 c.>s . . t
_ . _ . _ . . - .- . . - . .., t. . .
\TTM: Pr. C. E.-UncDonald _ .
. V $ u t - -4._ '. '!,';i..'u s- ..
Citief, Transportation Brancli % . '
; M.,te - :,:
.b4e. w, .. ....
.p.:f.5/.F,%
~- ~:.
. .C. . m
;;entlemen: .. .
. e .. .
Pursuant to the requirc=ents of 10 C7a 73 *.2, Neutrou , Prod,uctsf,.( (.]..<(.,,
.n % c, . 2. .. ... .~:... .....% ~
Inc. , na holder _ of agree:eent stats licence nu=ber 1D-31-0'!5-01, "... -,.s' C.'..,"
- 4. .
, . . w.
2
.'9,4.%-
,%. m-s s- . . ,
,e.. .c s .. . . ...
vinhes to register as' a user of.the.Che:2-N.uclear, Systeme.. Inci. CU.SI. P
. .. . =....* ~?. W:
. :, . .a.; .-
4 ,
; g,
. , .....,r.,-r..
1-13G radioective,'t.sterials shippi=g cask. Pacha;;a identification'.4 A Of.,:.c,,d .
. ,t , . .-
. , ~.. . .- . . , . .,. ~...o..
nu=5er for this cask.is. USA /9044/3 ( )7, ITEC Dochet No. n :s w.s ,...... m-71-904.4..". .s... . . '. F_
- 2. m. , .
..r.. .w:.m...
.m L s ; 3..a ..i. 3;;. r.*F E ,g v..;;;.- -g g.
M-5 .j ..
. ;43 .w.y g- . >;,
s n , .. . .c+r, ,
,j .: . c.- .. - y
., . Sincerely, qs. .e.7,. , s.,.s' /xM.,
, , , . . , . . . - ,. a; ),;;y. ..
q .%,_'a ..i. w ~*w; - G'.+4. y.. - .c~v . 6
.e :...s ,
..,.s.
y
. bc ,;s:::!
m.. . , ,m.#
. , ,o
.g:%.o ::.,V.yd..
.. Q: ; . . *
~
L.5ECTWe PRODUCTS, ; T C..
. ,.. ; . ~ . . . . .].; c. %.
- D, . . , .
.:. . n. c. g;.,.;. . f;;2. . ,g. c, . g... ;. , _ .g, . .
, . 3. .g . , ,. _. q.. g;-:,yg.
.. . . _ ~ . _ ,- g . .c.,g,3.;.4 .r,..w, ,. , ,
, ., g . . ,,
, ..f -* . . j ,,, . . ,. f ..,.. , . . , . ,..
- . . . . , - , .,.. : . . . -:.- . . s.. ...s...,., . ,,..
, 4., . .
. .., ... . g.p, ,,.m; . , ,.:..
_s . p;.. .,,,-(p3
.._.....-oa . m..%..
.4, . m.. m,. .n t.. _ . . . .. .- .
g p .- . .J - - - - . , .i.qm:j. ,r., f ec %,2 ^ Carmina Ssedira .t-1 *~ .N ,3*p.m. s,..".s. J.bg;- F; .r,;.k.,s;r,,
, 4.i
. -; s . .,r s Qus11ty Assurance Manag;er
%.- .-<.... .n s , 2 i - p,. -:< ;;. .- ,
- s - .: .
;,,'?.i.,; m r.:- - e n g;;,;sy %.? s ,.
,., ,;.,,, ,,'4 U <y
, s
.. M.-,. .3 V,. D. :jJ.is ;* y q. ed-:e.W.
P r. ' .cc: .Mr. .IG Krasnar . .
.. .'..,,,,...p. ' ' . ? .A..
* , 1.
M W .
'#' ^ .
-* a-D N' *i' 7,
-. ;,C. E ? ~" W e, r ,S78 *.a.* :3
,.,* , , . . . . -.. w+ . .- .
' '.' .i>.,',~..'.*.,."...*.c.,'.r_*3.>.-e.a..,..s..,..,....
..,u... m. .- .. o
, , . , . 4 . s ,,.r..'r- ,3 ~ ..-.
...,,.m......#.,.y-..~ p p=
3
; . . , 3 ,,, --
' * - '~;; . '4 y
5.u
,x%r : %4-; ;
m -: . ..: .
.*,.,,.,g.~ O. '.:4 .' -
..y... 3
-cs/au . - , . . .. . .s .,...,,,q,,,.+
-e - -
..o.-t 4 .a, - ,a rc p g, . . . . c4 ,. .7 ,.
r. r s 3 .. . , * . , . , - 4 g.J. . .ap ,(. .
}.,,s) gy*. .g ..
- bec: J Corun' '- s. -..,
.- ;.. f,. c ,.. %. w .4 w.,g .:,
d- w t.-M.4. . %
. . . . 7 :: . mv. , w.-
3... .._. ,. ,. ,. ..v ..... ,* :c
' .. m, f . '. ..u .Eoger-Gerbig .-..
.. +
,. :s
. n. . . ^ * - - . t . +L.
&. . M. Q T , a .. . . s : :r
*- e :1.W. . ;: .'.'.'. *.RT. s. ,, .
~ :
.. "s ~ w~~ ; . Marvin-Turkania . .. ,&-
. ~- . .-;_.. ._,e...,.,m..-. . . s _., . ... .r.3.
. ,za M. .%,, , ;.w
- m. .. ; . s... a. .~ ~. .s... . .
. .. .v, ...
., .u. .; m._ c,.. .
.s
.,-.r.2c,.....,..,~,.',_ g~.,,,
.g c ., f_t .r . ,,,. .. . g
- . ., ,.-#. --..... ;.,. ._.3..
. , ., t.,,. . .- ,.n . e.2. . -
.r v . ,.,. . ,_.%,.......~e .. a s ,. ... .
_. . . ~a
. . ~ . -. ** .
m
* ' ~. *. ..
.u , . . .
.c Y G'T.* NT .(', ,,*ar e.Wa.g t hi&, , , '
, .. m.. * a fh 7 ' * "'* . 'Y?.?. 'O
'e m.
, h. .i (
^
3_ g 1 F-_ s-- ,w. M r'.w w....sa ; .a. . .. e s.
- v. w.. :. . . ~,. 4. .;,.a.x:.; 4.., m.,.e.w. ;<w,w c. .o.w,. .g.t. :
. ..>*,.,,.. ..... x. .
. .t . v a, , ..
- e. ~
.i. e . .,. ,
_ , .s. . + . ,.. sg . ..
.. g . .~
.g
.~. a ; .. .: .
s . -ng; -.
. s .-n
~~
~
- w. ~., . s . :*;.* ~ w;7 Je f* a* . .m.= .* . ..m.* .;4. .... ..t":-~. % .-% ,;
.n. . . e ;-: tW'e , %*3 %,mi,~*. . ** W ' -e '.:..: w" +
Q> - *. ".....a
,+>= . ll.~ 1 c.;, O s.4.~
- G2. ~~' *) . r = * - .
'e ,,
a, s i* r.T
@ *r , .,, ~ t Q . *.t . *. e{ , . O
' ... ?'c s.a':.t
- e. '
;. : '. ;,A4e,,.Jt. .
*in'*4 nag'*".
'../['.4 %:.,g;;; :A = '~ . * =;,,, .Q:
....-~,* m. 5,- ,:.
cm' . M.
~
. ,.q t-+.%; .
2.
- c ,es l.9 .%.'. -.-.3, :, A.. . <. .,a;, g'
- r. :'.1... A..*. .p ** T.-. .+. f**g. ,% w. .,.....-,.<.g-.
..r.... ' '. .n..
..~,..s.,.
- . %., : ..-- .--s c ~
rp .- f..... +
.. , ,,..,g...
.n 9p , ...
c . .: - . . .~
- y..
...e.,,...
r ,
....n.,-,.c... .; _ . ..:
m ,. . . _ . , , ,.;2.
.. v.a. .a.= ,4. .
, . , , . , . . . .-:;1,y.
4
- a g ,. f . . .i <..
* . . . - ,y. ,
a:Sc, i
.m %.. . ..
--'r*;.h*
. .,",5.0.
,w ..%.. J. r.l. *
. w.* 4 =W4.M. .eg.
.e
. , e .. -. . * .c *, '.g;,ma.
- a. e.s,,.24."eCW'0.,9r N .ett r '*' * *.... ? ~;i
. - : fe z.. . ; . ; _ .i .c t .-*.'.Y9 *= *'*
-. /'s.
* ".l*.2.~
* . . .:A...~'.. .*. *3.r.
. .>=.*./.=, . . . :L.r":!r
- t g;;,,.a... a
M*'"*'g,.,.
% :.;pr .
m., s y
***r g . .. . . , . _ - . ;
- 4ff * ~f *.'* O,.J"* *.J. t .1, L .'#.* W.. p. rs'J.'"*' >1":".".!. O > ."; .".".". ..*?,.1.*, .". . y. . '.* "** .. 1 Mv.'.'.'.' *.. .* . J'. -,I. ,. 8,g*. W. m.J L.*
.+. *,. *d..g . I'l;'*1 i
.. -. s_ _______________x.,-_ __
-.. y tp UNITED STATES
((fC Q NUCLEAR REGULATORY COMMisslON
< .:- *o DEC 121980
. D. nA
- g y, ,,
7, WASHINGTON. C'. C. 2V555 m. Mr 7
' @ -t. #
%' 4 . . J DEC 101980 FCTC:ZDM .
71-9044 Heutron Products Inc. Attn: Mr. Marvin Turkanis 22301 Mt. Ephraim Road . Dir.kerson, MD 20753 Gentlemen: 1 As requested in your letter, we have registered you in accordance with the provisions of Paragraph 71.12(b) of 10 CFR Part 71 or 49 CFR sl73.393a as a user of the following: Model
~
Package-Identification Number
~~
GE-1600 USA /9044/B( )F
. i Sincerely, . .
4 #[ t# '
.. r::.2 ,
. ,.,3,*-*~
r .
, . .. Charles E. MacDonald, Chief i
. ' _ .;_ Transportation Certification Branch.
- Division of Fuel Cycle and ;
2~
/" '
. Material Safety .
cc: General Electric Co. Attn: Mr. G. E. Cunningham ='
. T- P.O. Box- 460 .
.m.- .Pleasanton, CA 94566 .
w.
.. 4e -
9
- A des ? . *
> .y at . ,; .. '3 O hl0 .f P
_I -a . ' _.. .p<. iN[, , *7 ( _M ,
.[ ."*b .. .'i lf b' '
d.y .:3h~y, * :qy'" a ; Q.s; - my ; ~yt ? '. : ~. ,.>. ' '; '
- y. 4_ . --, u.::. .z -. . . . .- . . .
g;y3 y ; . p .z ,- O.* . h'** .' O ( ' -
-/..'=~**., .# $N' .?' .'. .
SU'L b S b s ? % S hEr d E 0 h:S & 5 5 = 5 TU:5.h; ; - Hw.E !'
- S :~-5 0 5 L N:1.5:
- w. - . w=. . ..m
; w . . n.. u. wy:.:.;;w.u..:=,:,. . .
.a.
_ _ c0G :.%. . ,..*. : E:~~ . ..n - ,
- w. . n~ ww m,~. .. w. s.n' c ~t - . n c .7 n . ~.:c :..nr. n-
':- 6:? p. .. ',5
.u, ,Q;. &p .- w .- l~
h*G k: ,::.%d,l?.:
y%mlW.LkI'"
.\ Shp.D]s;i2:*: m"*.-
~
. :e -. .y *g:, ML. O. . . .
n.
- MM,,,
p, . .v.; -:.i,j , 7: d@
~
'W -
~-
j - 1.J a
'. '.L .~.A'f; ...~.:.~.. .= - - 7 A _
A E
- .6f=.Y:;'?.,. *
%~ ?W w..t i: ~.2 aq%qg .s. , . 4.5.. . . r ::=w:. y ~_ .= .n.. f
.. .AQ-.:
r .. w..,.ue
. . . . . .h. *4. W. .- .. .. . m.. js
r [ .. l I FCTC:EPE NC'l 16 1963 - 71-9081, 71-9044, 71-9152 Neutron Products, Inc. ATTN: Teresa L. Snyder 22301 Mt. Ephraim Road Dickerson, MD 20842 Gentlemen: As requested in your letter dated October 27, 1983, we have verified that you are registered in accordance with the provision of 49 CFR Part 173.471 as a user of the following certificates of compliance. Model Number Package Identification Numoer CNSI l-13C USA /9081/B( ) GE-1600 USA /9044/B( ) CNSI l-13CII USA /9152/B( ) Sincerely, Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and-Material Safety, NMSS cc: Chem-Nuclear Systems, Inc. ATTN: Ms. Robin Deal 240 Stoneridge Drive, Suite 100 Columbia, SC 29210
, 0 fc00Dhh
> o A { fSN y-536 kyK$ / k~g ' ~
. NEUTRON ORODUCTS inc 22301 Mt. Ephraim Road. P.O. Box 63 f
> Yf' s 'l l
Dickerson. Maryland 20342 USA
* / 301/34 73001 TWX: 710 823-0542 v
.K' N
.}
M April 8, 1985 g [- i Mr. Charles E. McDonalu Chief, Transportation and Certification Branch U.S. Nuclear Regulatory Comnission Washington, D.C. 20555 cd en
Subject:
Certificate of Compilance No. 5364 l
Dear Mr. M:
Donald: g During a discussion of several matters at NRC Transportation on March 297 1985, we described a failure of the drain / vent line il Section B of the ModelNo. NPI-67-0442 cask system and discussed our plans for effecting its repai d NRC representatives reconnended that we treat the Mtter as reportable under 10 CFR 71.95. This letter is in respinse to that recccmendation. it also addresses related experiences of drain line failures in Secticn C of the ca .k system. 2 though we are willing to file such reports, we have not considered drain line failures to be reportable under 10 CFR 71.95, because actions and precautions taken by Neutron Products have precluded significant reduction in the safety and effectiveness of the packaging. We have occasionally experienced failures of drain / vent ilnes, resulting in co:trnunication between the internal cavity (source chamber) and the internal volume containing lead shielding. In no case has the integrity of the boundary between the interior of the cask and the enviromnent been effected. The consequences of internal leakage are radioactive contamination of the shielding cavity and, in a hypothetical accident condition, possiule loss of some lead shleiding by migration of lead into the shipping chamber. The potential loss of lead shielding is limited by our practice of filling the unused volume of the shipping chamber with stainless steel rods and/or brass disks. Section C is the bottom section of cask Modes 11 and IV, as described Ir. the Certificate of Cccoliance. On several occasions the drain / vent lines have failed where they are welded to the stainless steel lining of the source chamber. The problem was first identified in 1974 and the weld w.u repaired. The problem recurred and repairs were made in 1980, 1983, 1984, arid 1985. The cause of the failures is thought to be differential thermal expansion between the lead shielding and the stainless steel lining and possibly also differential movement when the cask is set down, which events impose stresses on the drain line where it is welded to the lining of the source chamber. In the latest repair, recently completed, the old drain /sent tubes have been
' renoved and replaced with heavier wall tubing. In acdition, shims have been installed in the expansion vold at the bottom of Section C to restrain movement of the -lead. In our judgement, this repair is in accordance with the Certificate of Compliance and the basic design of the shipping container.
gggg w O g,
i Mr. Charles E. Mcdonald April 8, 1985 Page No. 2 Section B is the bottom section of cask Modes I and Ill, as described in the Certificate of Compilance, in 1980 Neutron Products identified an internal leak in a drain / vent line in a location not accessible for repair. An internal review of the safety significance was performed at that time and it was determined that the only potential concern was loss of some lead shielding, by migration into the source chamber, in a hypothetical accident condition. This possibility'!s mitigated by filling the unused volume of the source chamber as described above. Section B was removed from service in 1984 for the purpose of effecting repairs. The planned repair involves installing a stainless steel sleeve in the 4-1/2 inch diameter central hole and sealing the holes in the upper tube sheet, thereby isolating the source chamber from the cavity containing lead shielding, and providing for drainage through the top. Although we do not believe a structural review is required, our approach involves a change in the method of cask drainage and, prior to initiating these repairs, we will review with you the planned repairs and detailed drawings, with the hope that you will concur. Very truly yours. NEUTRON PRODUCTS, INC.
& L C.
Frank Schwoerer. Vice President F5a mbn NEUTRON PRODUCTS ine
} p , , - , .
n6UTROn 3RODUCTS inc t 2:301.\lt. Ephruim Road. P.O. Box 63 Dickerson. .\laryland 203J2 USA
.; g30pja)ft Tli'X: 710-328-0542 November 1, 1985 Mr. rharles E. MacDonald, Chief Transportation Branch Office of Nuclear Material Safety and Safeguards ~
U.S. Nuclear Regulatory Consnission Washington, D.C. 20555 Dear Mr. MacDonald . Please register Neutron Products as a user of the Model No. 700 shipping cask. The cask identification number is USA /5942/B( )F. Very truly yours, NEUTRON PRODUCTS, INC. . M Wayne J. Costley Quality Assurance Manager WJC:mbn
*s k N
rocxtTrn 6 usnac ,.
- -c
': NOV 41985 > Z!
9' ums t! 14AllSECTION C *' DOCKET CLERM ! b y/ Y ._ A
~
N anr9 M. 19dD@T ('n-
'. ,C_ w, e, l 2/-93 W
/
NEUTRON 3RODUCTS inc 22301 Aft. Ephraim Road, P.O. Box 68 Dwkerwn, Ataryland20342 USA
?nt1349.9n01 TliX: 7/O-825-0.<42 November 11, 1985 ,N
,y' a) d r, ~ . ,
Mr. Charles E. MacDonald, Chief
,- a
'
- G'd)
- h. .]
Transportation Branch ,, Ht Office of Nuclear Material Safety and Safeguards % v.s,fgp g m 3 :> Q l U.S. Nuclear Regulatory Conrnission Washington, D.C. 20555 Q. K ,-(c%.p,rcar fu u . C/ e/ Ref: Certificate of Compilance No. 5942
.lN.mQ v
- /Q/
Dear Mr. MacDonald:
This letter requests a modification to the subject Certificate of Compliance to allow Neutron Products to utilize the G.E. Model 700 shipping package to ship cobalt-60 from the Savannah River plant to Neutron Products' Olckerson, Maryland facility. Most of the irradiated cobalt material is nickel plated and all of the material is encas.ed in aluminum claddinJ. However, the material has been stored underwater for some time and the integrity of the nickel plating and aiuminum cladding can not be assured. Therefore, the material can.not be demonstrated to meet the requirements of "special form", stipulated in articles 5(b)(1) and 6 of the Certificate of Conpliance. Neutron Products proposes to ship this material in a sealed, vacuum-dried, end helium-filled liner in the G.E. Model 700 shipping package. The liner, in combination with the shipping package, will retain its integrity throughout the normal conditions of transport prescribed by 10 CFR 71.71 and the hypothetical accident conditions prescribed by 10 CFR 71.73. Enclosed.with this letter are (1) description of the liner, (2) a sumary of the procedures for loading and drying the liner, (3) analyses of the performance of the 1iner/ shipping package under normal conditions of transport and hypothetical aacident conditions, and (4) proposed wording of a modification to the Certificate of Compliance. A check for the $150.00 application fee is enclosed. Very truly yours, NIUTRON PRODUCTS, INC. C W Frank Schwoerer, Vice President FSemvc Enclosures . M qg. xo=e Q'Q999903gga
ENCLOSURE 1 DESCRIPTION OF SEALABLE LINER AND SLEEVE Liner Deslan The cask liner is shown in Neutron Products drawing 240139. The lower portion is a 10 IPS Schedule 10 stainless steel pipe, with a flanged opening at the top and a flat-plate bottom. The underside of the bottom is grooved to allow water to drain from the cask cavity, outside the liner. A small diameter pipe for purging water from within the liner runs from the flanged opening to the bottom of the liner. Savannah River. cobalt is in the form of aluminum rods of approximately 0.94 inch diameter and B inch length. These rods will be loaded into the liner, on basically a triangular pitch, with up to 64 rods per 8 inch high layer. Appropriate spacers / supports of stainless steel will be used to keep the rods in an upright position. There is room for four such layers. The actual number in any shipment will be established by the allowable curie loading or geometry, whichever is more limiting. The lid of the ilner contains a spiral-wound stainless steel and asbestos gasket, which seals the large opening in the liner. The mating flanges are machined with grooves that match the stainless steel chevrons of the seal. The Ild is held in place and the gasket compressed by twelve 3/4 inch bolts. This design is close to that of a standard flange for 10 IPS piping. The differences are in the outer diameter of the flange (14-7/8 vs. 16 inch) and in the bolt diameter (3/4 vs. 7/8 inch), which are limited by the 15 inch cavity diameter. one to introduce gas, the The lid of the liner is penetrated by two openings: other to purge water. Each opening has a stainless steel bellows _ valve, for sealing the opening, and a stainless steel hose connection. Enclosure 2 describes how these connections- are utilized to purge water from within the liner, vacuum dry the contents, and fill with an inert gas. The valves and hose connections are protected against impacts, which can result from the normal conditions of transport and hypothetical accident conditions of 10 CFR 71.71 and 71.73 by a section of 10 IPS Schedule 10 stainless steel piping and two transverse plates of stainless steel. The transverse plates also support a lifting pin. The liner will be assembled, sealed and leak-tested prior to use. The gap between the flanges (nominally 0.100 inch) w'.ll be measured after the lid bolts are fully torqued and the liner is demonstrated to be leak-tight. A shim ring will then be machined to the thickness of-the gap between flanges and will be used, with a new gasket, when the liner is used to transport normal form radioc tive material. This will ensure metal to metal contact at the flanges to transmit impact loads if-the shipping package is dropped. i neuxson anooucrs ,nc
i ENCLOSURE I Description of Scalable Liner and Sleeve Page No. 2 The weight of the liner is approximately 250 pounds. The maximum weight of the contents is 180 pounds. Thus, the loaded weight is a maximum of 430 pounds. Sleeve Desian The sleeve design is shown in Neutron Products drawing 240138. The sleeve is an annular cylinder of aluminum. that fills the space between the wall of the liner and wall of the cavity. Its purposes are to enhance radial heat transfer and to support the iiner against lateral Impacts. The weight of the sleeve is approximately 240 pounds. Total weloht of Cask Contents With a maximum weight of 430 pounds for the liner and its contents and a sleeve weight of 240 pounds, the maximum weight of the contents of the shipping package is 670 pounds, which conforms to the limit of 700 pounds specified in article 5(b)(2) of Certificate of Ccepliance No. 5942. neu,non anoouc1s inc
o ENCLOSURE 2
SUMMARY
PROCEDURE FOR LOADING, DRYING AND SEAllHG LINER Place the bottom portion of the liner in a holding fixture in a working l. platform, that is submerged at least ten (10) feet below the surface of the water in the storage pool (basin).
- 2. Transfer the cobalt-60 contali,1..g aluninum rods from storage buckets to the liner.
- 3. When the liner is filled, install the lid, with its integral seal and with boses attached to the two hose connections on the lid. One hose shall connect to a source of helium; the other shall run to a water container, install and tighten the lid bolts with a long-handled tool. -
- 4. Supply helium with sufficient pressur'e (approximately 25 psla) to displace water from within the liner. Collect the discharged water in a container and measure its vclume to ensure that essentially all of the water has been
--- removed. During this step, observe the top of the liner for indication of helium leakage, if such indication exists, retorque the lid bolts and/or replace the gasket and repeat this step.
- 5. Connect a vacuum pump to the cischarge line. Run the vacuum purto until a vacuum of at least 27" Hg can be maintained for 5 minutes with the pump turned off. (This is indicativn that all water has been removed from the liner.)
- 6. Close the discharge valve, using a long-handled tool.
- 7. Fill the liner with helium to 2 to 3 pst above the ambient hydrostatic pressure. (Minimum pressure in psia is given by: water depth in feet times ,
L 1/2 plus 17.)
- 8. Close the helium inlet valve with a long-handled tool. Observe tne liner for Indication of helium leakage. If leakage is indicated, make the necessary corrections and repeat steps as necessary to ensure that the liner is dry and filled with helium to the specified overpressure.
- 9. Pull the hoses off the hose connections.
- 10. Lower the GE 700 cask, with the sleeve inserted, into the pool,
- 11. Lift the sealed liner from the work platform and insert it into the GE 700 cask, neuTaon anooucrs ,,c
i \ . ENCLOSURE 3 EVALUATION OF PACKAGE PERFORMANCE UNDER NORMAL CONDITIONS OF TRANSPORT (10 CFR
'71.71) AND HYPOTHETICAL ACCIDENT CONDITIONS (10 CFR 71.73)
General General Electric Company has demonstrated (in a consolidated application for certification, submitted to the NRC by letter dated March 18, 1980) that the GE Hodel 700 shipping package will survive normal conditions of transport and hypothetical accident conditions, except that the lid gasket may fall. A way to prevent any dispersal of radioactive material under normal conditions of transport and hypothetical accident conditions, since irradiated cobalt from the Savannah River plant can not be demonstrated to meet the clad integrity requirements for special form material, is to seal the cobalt within a cask liner. This enclosure demonstrates that the cask liner and seal described in Enclosure 1, when loaded and dried as described in Enclosure and contained within the GE Model 700 shipping package, will remain intact through normal conditions of transport and hypothetical accident conditions; and thus ensure containment of radioactive material. The following evaluation builds upon General Electric's consolidated application for certification, referenced above. Normal Conditions of Transport Thermal: The liner components (stainless steel shell, and stainless steel, bellows-type shutoff valves, and stainless steel / asbestos gasket), the aluminum sleeve, and the contents of the liner are unaffected by ambient temperature extremes defined in 10 CFR 71.71. Calculated temperatures at an ambient temperature of 800F and a limiting heat load of 6500 watts are: Cask surface 3000F (ref: GE application) Sleeve I.D. 3390F Liner 0.D. 3800F Gasket & valves (4000F. Contents @ centerline 5050F. These temperatures are sufficiently above and below limiting temperatures for the materials that ambient temperature extremes will have no effect on liner or seal integrity. The pressure within the liner will be approximately 15 psig, which is well within the capability of the seal and liner. Pressure: The GE 700 package will withstand the range of external pressures defined in 10 CFR 71.71 (ref: GE application). The liner and its contents will therefore be unaffected by external pressure. Vibration: The GE 700 package will withstand vibration normally incident to transport (ref: GE application). The liner fits closely within neo,aon anooucrs ,nc .
c ENCt.050RE 3 Evaluation of Package Performance Page No. 2 the cask cavity and sleeve and will, therefore, be subjected to essentially no ampilfication of vibration. The close fits and the loose contents of the liner will tend to darro out vibration. The edge of the lid is of slightly smaller diameter than the flange on the liner, so there is no possibility of lateral inpacts on the lid that might loosen the gasketed closure. The valves and bolts are protected frort vibrational inpacts. Water spray: Water spray will not adversely affect the cask, including the lid gasket. Therefore the liner will be unaffected. Free drop: There is no dam ge to the GE 700 cask from dropping the distance prescribed by 10 CFR 71.71 f ref: GE application). It will be shown that, even when subjected to the higher loads resulting from a postulated 30 foot drop, the liner will retain its integrity. Toerefore, the liner, its seal, and its shut-off valves will retain their integrity for the one (1) foot free drop prescribed by 10 CFR 71.71. Corier drop: Not applicable. Ccmaression: Not applicable. Penetration: There is no damage to the GE 700 cask from the penetration impact prescribed by 10 CFR 71.71 (ref: GE application). Therefore the 1Iner wi11 be unaffected. Surrmary and
Conclusions:
The assessments set forth above provide assurance that the Neutron Products liner, transported within the GE Model 700 shipping package, will not be adversely affected by Normal Conditions of Transport and will retain its sealing function. Hypothetical Accident Conditions , Free drop: Based on analyses done by General Electric, damage to the GE 700 shipping package from a 30 foot drop would not exceed that suffered by the GE Model 100 package in a 30 foot drop test (ref: GE application). That damage consisted of local distortion of the steel overpack; the cask was not dam ged (ref: NRC Docket No. 71-5926, GE letter dated January 25, 1980). The question remaining to be addressed is whether the g-loadings, resulting from a 30 foot drop, would result in loss of integrity of the cask liner. NEUTRON JRODUCTS inc
l s -. . ENCLOSURE 3
' Evaluation of Package Performance Page No. 3 It appears, from damage suffered by the GE '100Lpackage, thatitha average deceleration of the caskLilner would be'in the. range of
- 50_to 100 g. However, Neutron Products has no quantitative dataL from which.to determine the maximum g-loading. Therefore,: to establish a conservatively high g-loading,-It is assumed that all' of the kinetic energy of the' shipping package (cask, contents, and overpack) Is absorbed by deformation of the lead shielding of the cask. The deformation and maximum g-loading are calculated using a " dynamic flow pressure" and theLgeometry of the cask. A conservatively high value of the.g-loading is_obtained by using a e
dynamic flow pressure of-10,000 psiL(reft ORNL-NSIC-68, A Guide for the Design, Fabrication, and Operation of. Shipping Casks for Nuclear Applications, February 1970). On this conservative basis, the energy to be absorbed by lead deformation is 35,500 lbs x 30 ft or 1.065x106 ft lbs. The worst case impact, with respect to liner _ integrity,Lis an upside. down impact. The cross-sectlonal area of lead is 988 in 2. Thus the force to deform the. lead is 9.88x106 lbs. As the lead cross-sectional area is uniform in the axial direction, the depth of lead deformation is 1.065/9.88 or .108_ft or 1.29 in. The corresponding g-loading, which is uniform with_deformetton.--iso 30/.108 or 278 g. All of the weight of-the liner,_lts contents-
- and the cavity sleeve (670rlbs; ref t Encicsure 1) is' carried in.
this postulated impact by the short section of.10 lPS Schedule 10 piping and the two transverse plates. That cross-sectional area is 11.7 in2. Therefore, the compressive stress at'278 g is 278
~
x 670/11.7 or 15,920 psi, which is well below the'yleid stress of. the material . Therefore, the shut-off. valves and other hardware on top of the lid 1will not be damaged. Tne total weight .of the bottom tection of the liner, and caskL sleeve (370-lbs) is carried-across the closure flange by the shim ring, which prevents further conpresslon of the seal ring,:that might-affect the Integrity of the seal ~. Other stresses in the liner are also well
- below the material yleid stress.
A bottom-down inpact results in lower stresses than those
- analyzed above because (1) the bottom of_the lead has a convex shape, which would result in a. lower g-loading and-(2) theLload carried by the liner wall is relatively low (230 lbs). A side-down impact, analyzed by the same conservative methodology' results In'a maximum g-loading of--270 g. Under-this condition, the wall of the-liner is subjected'to.an equivalent'pressureLof 90 psia, which results In a' hoop stress of'3,520 psis/well below-the material yield stress, neuTaon :>nooucrs inc
\
ENCLOSURE 3 Evaluation of Package Performance Page No. 4 From this conservative analysis, it is concluded that the liner will retain its integrity if the shipping container were . tubjected to a free drop of 30 feet. Puncture General Electric has analyzed the consequences of thlf' postulatea occurrence to be not greater than for the GE Model 100 package (ref: GE application). A test of the Model 100 package, consisting of a 40 inch droo onto a 6 inch diameter by 8 inch long steel bar, resulted in local yielding of the protective Jacket (overpack) but no penetration of the protective jacket and no damage to the cask (ref: Docket No. 71-5926, GE letter dated January 25, 1980). If the local deformation c? the protective Jacket is greater than .144_ inch for an impact in line with the center of gravity of the package, the 9-loading un the liner will be less than calculated for the 30 foot free drop. Analyses of the strength and stiffness of the liner Indicate that for such inpacts, the local deformation will exceed .144 Inch. Therefore, the cask liner and its seal would not be damaged. Thermal: General Electric has analyzed the GE 700 shipping package for exposure to the fire prescribed by 10 CFR 71.73. A coast up analysis indicated that a maximum temperature of 4640F could result at the innermost lead node-(ref: GE application). The materials of construction of the liner, bellows-type shut-off valves, and cask sleeve have acceptable mechanical properties at this temperature. The stainless steel and asbestos gasket will retain its function up to 10000F (ref: Parker Seals catalog). Furthery if the steady-state temperature difference of 1250F from the centerline of the liner to the liner surface is conservatively assumed to exist, the meximum centerline temperature would be approximately 5900F and the pressure within the liner would be approximately 18 psig..This is well below the capability of the seal and liner. Therefore, it is concluded that the cask liner will retain its sealing function throughout the postulated exposure fire. Water immersion: The seal on the cask liner is rated for a differential pressure of 250 psi (ref: Parker Seal-catalog). Therefore, the seal is capable of preventing in-leakage of water at an external pressure of 21 psig. Summary and
Conclusions:
The assessments set forth above provide assurance that the Neutron Products liner, transported within the GE Model 700 shipping package, will not be adversely affected by the Hypot"*'ical Accident Conditions and will retain its sealing funt;.On. neuTaon asoouc1s inc
ENCLOSURE 4 PROPOSED WORDING OF N00lflCATIONS TO CERTIFICATE OF COMPLIANCE NO. 5942 NOTE: Underlining designates proposed additions to existing wording.
- 5. (b) (1) Type and form of material Byproduct, source, and special nuclear material contained in solid ovide or metal form and in special form, or sealed within a liner constructed in accordance with Neutron Products" drawinos 240139 and 240138.
- 6. The radioactive material must be in the form of fuel rods, or plates, fuel assemblies, or meeting the requirements of special form radioactive material, or of normal form if sealed within a liner constructed in accordance with Neutron Products' drawinas 240139 and 240138,
- 8. Prior to each shipment the silicone rubber lid gasket (s) must be inspected.
This gasket (s) must be replaced if Inspection shows any defects or every twelve (12) months, whichever occurs first. Cavity drain line must be sealed with appropriate sealant applied to threads of pipe plug. Sealable 1Iner. If used, must be vacuum-dried, such that a vacuum of 27" Ho can be maintained for 5 minutes with the vacuum pump turned off, before sealino and pressurized with helium to 2 to 3 pst above ambient hydrostatic pressure, with no visible release of helium while the liner is underwater. i i neuTaon anooucrs ,oc 4
/D' t&v } 'I
. 2 . - 2 . . - .- - i. ,
. . . . . . . - . , . w ,, ,
.ru 6.>
~~
D Gi _. December 4, 1965 4 \ \ gI I, l 'a,/ . U r. Charles E. MacDonald, Chief [ E'y e'
%' Up*, V
. ~.J ~~s s w..
Transportation Certificaticr. Eranch j,- ! p 4 Jivision of Fuel Cycle and A -i c. I' [9.@..r M8 3 ,sE haterial Safety,!! MSS
!.S. Nuclear Regulatory Commission 7915 Eastern Avenue
' ~ .t ",' P"r,h A lh~/
i; - - - .md d-- .
'_ n
; ; q> = . t.; c- ,
L *. % a.- F,
><e- - O ".n _ CA O -
a M Q- --m. 3 O .O 5 'O ' 6=- E, l ~. e_ - .-g-
== :,; ,
j - _ f,* - ft - C
"*- '= - p- O.-.i,_1 %
m or* , _== >- y, - c- :.; 7; ,
- C - ~, C % -*= 2 = _~~
- v. n .;_ : : r~ a .
' e~ % ~ ..n' -C- ~
r
>- c =
=. 5 g>
.i_ .w, ..
,. :: i e 3- e;. m.
,=
n
.C = * !' O- -:- LA *: ., -M
- C. n ;-d. ' es : R n c- -C O 0 l q- Zc C v. --. N- - M._ i >C' -
O o= 0 to r* O 4
.r
- c. :.: m e- * - 0"J - :
- - h ==,=
- = . , u -. a .e -
mn C r=
**- ft & C. . P-o= r* W M D >=. *<
n <- m @ 'I C
= -I ,
a c l. t -
-T
-a
#w F-*~
y > < ** -E.,,o. r . N g - a l N =- -- _
. .- : l u w C 1 . - -r.. -
i t -
-f '- a y 9-E l 4 h I '
V: 1 + .i. (./". 4
"
- 1 (
i 1 .--- .
\
g - M I
.g i> M -
- w f - e'a -
Z= -'g _ 3-
'. = .N .N ;
N
.,9 N _N s 4 w,-
- W, -
.l... {L*- 3,- g j,2. .., W W - ~3 .. I ;
- n
- - "; i. .
C - - d.or LA o< e ca g_ p-+ ., =
.* ; . ll> "" N
',, l.2: >-
4 . .- w-
-W b-
}.>>- . -i g d - = = C. :: : ;.
.u W '. . . W ;
6 M=-
** > > . d. . 3 "*. - :"*..^
$ r > ^
e1 j. Z -- - , p:: . - *=: -: :. _ _ M -__ l_ u 4 _*4_
=
f y- .b: A'
=
g W
.b <_py'- . -
[.. .u .N - _w.
-: _ i ::
M _; --
; - .m -
w .. e
.d d -'
s.
> m.=
=-: <
w _ a } - - as .
- l'd
. *: ?
e - -
' m -_.__-
e
, ; r.
? +
t, , 6 $
.O: ** -
i 3 g ,. h. 8 - Z
'.A #as A .s%a A
-'vvvvv-
@ d W N "'"
[g'j[ . =* _
- , c-
.-** ** me,.,;<
d-. ~ W- .
$d C ,
n w > .e > cnc5- :l; '-
->. v- u t.a u u .-
& l-.
'e i.z
. * ' * ~. i*
-'O.& *1 "U >=- 1 I* :
- i oC M ' *1 - f . 4 '" **;
c = c ' c e-. ;:r.i1 >2 ~ . $ . et n m <;u 5 C f* I; ! c -- *
!_ +
t
.,-: 1 rn cs . ~, : i ' k,- ,-
sks ..s . ,. , . - ,
4 .' f
?4~
3.2 Ouality Assurance Procram _[ The quality assurance program elements described in this document-are , further delineated and implemented by quality assurance procedures and detailed operational procedures that cover all quality related transport operations at Neutron Products. A master list of these procecures-is' updated and maintained by the Quality Assurance Manager. These _
~
procedures. address the personnel, sequence of steps to be.followed, and the equipment to be used in safety related operations. The qualifications for personnel engaged in.these operations is established by Neutron Products' division management. Training which is primarily on the job, is required before persennel perform safety related activities. These training activities are documented. As stated throughout the secticns that follev, safety related activities are carried cut !y qualified personnel, in accordance with approved drawines and specifications, according to quality standards, in observance of recognized engineering practice, with appropriate equipment, and under quality controls. The quality related items t which this QA program-applies are documented. 3.3 Desien control For each quality related design activity forf a_ transportation package, specific organizational responsibilities shall be established; When such transportation package design-is required, existing specifications, procedures, oc instructions will be followed, or if necessary, new ones will be developed, to assure that all applicable design criteria willibe translated into the required drawings and specifications. To ensure that quality related design control is achieved, emphasis in the design process will be placed on' design' process planning to determine: quality related aspects of the design, subsequent periodic design reviews, maintenance of quality standards, and observance of recognized engineering-standards. The adequacy of quality related design and verification-that the reqaired design: criteria have been achieved,-shall be accomplished by a Quality Assurance audit of the design process and the final design. Results-ofL 4 the audit shall be documented. Control Copy Number 3_ '
,o ,~ ]7 ;,
3.4 Procurement Document Control Procurement documents for quality related items, are the products of the development of orawings and specifications. As such, the criteria established in Section 3.3 " Design Control" shall provide the necessary assurance that the procurement docucents meet the requirements of the Quality Assurance program. Further, purchase orders issued for the procurement of quality related items shall clearly show that the order is subject to the provisions of Neutron Product =' Quality Assurance program and that the materials, components, and equipment furnished by the vendor must meet the requ1 red specifications. Changes and revisions to procurement documents shall be subject to the same review and approval as the original documents as specified in Section 3.3. 3.5 Instructions. Procedures and Drawings Specific controls in the form of instructions, procedures .and applicable drawings shall be prepared, reviewed, approved, and put into use for the: e design of packages and components; e preparation of quality related transport packaging for use; e loading and unloading of radioactive caterial.s from quality related transport packaging; e transport of the package; and, e maintenance of the package. These shall include such activitics as. e development of criteria, specifications, etc.; e inspection and decontamination; e surveys for contamination and radiation; e procedures for loading, flushing and package closure; e rigging and hoisting; e overpack placement;
'. e securing the package for transport; Control Copy Number l
e cealing, marking and labeling the package: e transport vehicle radiation surveys; a package unloading; e recoval of the package radioactive contents; e package decontacination; and, e package caintenance. Reviews and approvals shall be accomplished in accordance with the requirements of Section 3.3 and Corporate approvals for radire. ion safety, adequacy for intented purpose, and quality assurance progrt- compliance. 3.6 Document Control The following documents shall be under the control of Neutron Products' Quality Assurance program: e Quality Assurance manual; e Operating Procedures; e Procedures for the Loading and Unloading of Radioactive Contents to Transport Packages; - e Procedures for Packaging for Transport; g e Inspection and Test Procedures; and, e Maintenance Procedures. Reviews and approvals of these documents shall be accomplished in accordance with Corporate approvals for radiation safety, adequacy for intended purpose, and Quality Assurance program compliance. The quality assurance manual shall be a controlled document and shall be issued accordingly. A master file of current procedures with appropriate revision t.urbers an? dates shall be maintained by the Manager, Quality Assurance. Copies of procedures shall be made available as required. Control Copy Number
.i Changes to these documents receive the same reviews and approvals as the original and are noted by revision number and date to be the current version.
3.7 Control of Purchased Material. Equipment and Services The Quality Assurance Manager, or his designee, shall be responsible for ensuring that an evaluation of suppliers of quality related items shall be done -to assess their capability to provide quality services and products. This evaluation can be based on a survey of the supplier's facility, a' review of the suppli .'s' quality assurance program, if appropriate, and a review of other records of the supplier. These surveys and reviews shall be documented and such documentation shall be maintained. Documentation accompanying the receipt of quality related items shall be reviewed for conformance with the purchase rcquest. 3.8 Identification and Control of Materials, Parts and Components The Quality Assurance Manager, or his designee, shall be responsible for assuring that materials, parts and components for quality related items are adequately identified and controlled in accordance with drawings, y specifications or procedures established for their use. A record of such evaluations shall be made. 3.9 Special Processes Loading.and unloading packages for radioactive shipments are special
~
processes. These shall be performed in accordance with Neutron Products' Quality Assurance procedures, QA 1003, Package Loading Procedure for= Radioactive Material, and QA 1004, Package Unloading. Procedure for-Radioactive Materials and Neutron Products' procedures applicable to the specific shipping container. For other.special processes, e.g. welding, radiography, etc..that require certification and conformance with standards, personnel and equipment qualifications shall be verified-and; documented.
- - 3.10 Inspection Control Quality related items shall be inspected upon receipt, receive periodic-inspections based on their .use, and maintained in satisf actory operating condition. The 1nspections and required maintenance shall be performed under the supervision of Neutron Products' management, or another qualified person = designated by-Neutron Products' management.
Modifications or repairs to quality related items shall be inspected in-accordance with the original design and inspection requirements, or acceptable alternatives. Control Copy Number ,
l d NEC approval shall be obtained prior to returning to service a container that requires maintenance work that would result in a safety related change in design, as depicted in drawings referenced in a Certificate of Compliance. l All inspections and codifications of shipping containers shall be recorded in the maintenance log for that contain 2r. . 3.11 Test Control Tests required on quality related items are to be conducted in accordance with the requirements of applicable regulations and those contained in the approvals of specific package or its components. Test results are to be reviewed, approved and documented. Prior to any special testing operation a technieni description of the test will be prepared, evaluated and documented. This shall include an evaluation of the prerequisites for the test, appropriate instrumentation and re,uired environmental conditions. 3.12 Centrol of Measuring and Test Equipment Measuring and test instrueents required for use on quality related items, shall be calibrated at specific intervals to assure its sufficient accutscy for the use intended. Calibration tert data for thess instrueencs shall be identifiable and traceable. Whenever such test equipment is found to be out of calibration, previous tests will be evaluated for validity and so documented. Where applicable, as in the case of radiation measuring instruments, the basis for calibration shall be traceable to nationally recognized standards. 3.13 Handling. Storace .. a shipping All operations concerning handling, storage and shipping of radioactive transport packages shall le in accordance with NPI QC Procedure 1005, Handling Storage, and Shipping Procedure for Shipment of Radioactive Faterials. In addition .'eutron Products' operational proced'tr6s govern such operatters with specific transport p2ckages. *he handling, preservation, storage, cleaning, packaging, as.d shipping requirements contained in these procedures are accomplished by specifically designated qualified individuale of Neutron Products under the supervisi< ' manag,'- All conditions of NRC package approval and U.S. DOT shipping requirements shall be satisfied prior to any shipments, and all necessary shipping papers chall be properly prepared. Control Copy Number
-o o
3.14 Inspection, Test and Operating Status Inspection, testing, and operating status of all shipping packages and components shall be in accordance with NPI QC Procedure 1006, Inspection. Testing, and Operating Status Procedure for shipping of _. c Radioactive Materials. Identification, test, and operating status of each package and ' component shall be known by the responsibl6 line manaders. Application-and removal of inspection tag markings, and shipping or other labels shall be controlled in accordance with QC Procedure 1006. The status of nonconforming, inoperativa, or malfunctioning packages or compenents shall be clearly identified to prevent inadvertent use. 3.15 Nonconforming Parts Nonconforming materials, parts, components, and services shall be _ ' controlled in accordance with NPI QC Procedures 1035 an'd 1006 which require the identification, documentation, segregation of tonconforming items and the notification of the respcnsible individual. Designations + of individuals responsible for the review and disposition of.the materials-are made in these procedures. Documentation.shall identify the nonconforming item, state its insraction requirements, describe the nonconformance, and identify final disposition. Approval of division management is required for final disposition. Acceptability of rework or repair shall be verified by reinspection and retesting, as-required, and as originally inspected, or by an equivalent I method. 3.16 Corrective Action The Quality Assurance Manager, or his designee, shall conduct an evaluation, in conjunction with the appropriate line manager, of any. conditions determined to be adverce to quality (such as nonconformances, failures, malfunctions, deficiencies,. deviations, and defective materials and equipment) to determine the need for corrective action. ; Repair or replacement of nonconforming parts or the correction of other- ~
-deficiencies'must be approved by division: management.
Follow-up reviews shall be conducted by the QA Manager to v- f the proper implementation of. corrective cctions and to clote or .e ' corrective action documentation.-
-i e
ncr Copr_ Number
o 3.17 Ouality Assurance Records Neutron Products shall maintain the following Quality Assurance records e Quality assurance procedures e Detailed operational procedures e NRC Certificates of Compliance e 1AEA Certificates of Competent Authority e Drawings, specifications and instructions e Procurement documents e Contract agreements e Inspection and test records e Transport package documents e Health physics records e Quality assurance audit reports These records shall contain sufficient information to describe or - document quality related activities or items. The distribution of these records shall be documented. 3.18 A,udits 7ne level of audits of the Quality Assurance Program will be dependent an the safety significance of the activity being audited. Audits of an; given activity shall-include an evaluation of the shipping and manufacturing practices and/or procedures, and shall be concerned with the safety and effectiveness of their implementation. Audits shall be planned and include the monitoring of operations and activities, review
- and pertinent documents and their control and maintenance. Audits shall be conducted in accordance with NPI Procedure QC 1007. Audits shall be performed at least once a year with spot checks as deemed necessary by the QA Manager. Audits shall ba performed by persons who do not have responsibility for the area being audited, and who possess the ability tc evaluate adequately the functions under inves'ig *. ion.
The results of these audits shall be documented and maintained by the QA Manager and reported to the Presidert along with any suggestions of recommendations for improvement. Su + sequently, the President shall direct line management to take appropriate corrective actions. Control Copy Nurber 3- S/VM p p. /8po., _
~
[ TEI $ NEUTRON )RODUCTS inc 22301 Mt. Ephraim Road. P.O. Box 68 Q
- Yg ~10 Ditkerson. Maryland 20842 USA pi y 101/349 3001 TWX: 710-828-0342 s tfP Q/
* January 8. 198 .i
, 4 Mr. Charles E. MacDonald. Chief Transportation Branch Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Contnission Washington, D.C. 20555 Reft Certificate of Concilsnce No. 5942 i t
Oear Mr. MacDonald: , This letter responds to your letter dated December 12. 1985: and supplements our application of-November 11. 1985. In which we requested a modification to ' the stbject Certificate of Compilance, to allow Neutron Products to utilize the G.E. Model 700 shipping package to ship cobalt-60 from the Savannah River plant to Neutron Products' Olckerson. Maryland facility. The following supplementary information is submitted with this letter.
- 1. Complete engineering drawings of the liner._which includest weld r symbols, welder Quallflection requirements, and a bill'of materials.
Demc.aration of the leak tightness of the liner under normal and i 2. accident conditions, by analyses described in Enclosures 3 and 3A.
- 3. Modified procedures to assure the dryness of the liner, described in Enclosure 2.
This additional Information is submitted in the form of-revised drawings and revised pages, in which the revisions are identified by vertical.llnes in the right hand margin. Very truly yours. NEUTRON PRODUCTS. int. r fJ Frank Schwoerer,-Vice Prestdent FSimvc-Enciasures sp: LV 6- i%l' 99.
/4/p-Woptsoece ;gCf6
r , e i ENCLOSURE 1. Rev. , i DESCRIPTION OF SEALABLE LINER AND SLEEVE Liner Deston The cask liner is shown in Neutron Products drawing 240l39. The lower portton is a 10 IPS Schedule 10 stainless steel pipe, with a flanged opening at the top and a flat-plate bottom. The u,,derside of the bottom is grooved to allow water to drain from the cask cavity, outside the liner. and tc provide rotational restraint when the Cover bolts are torqued. A small diameter pipe for purging water from within the liner runs from the flanged opening to - the bottom of the liner. Savannah River cobalt is in the form of aluminum rods i of approxlitately 0.94 inch diameter and 8 inch length. These rods will be loaded into the-liner on basically a triangular pitch, with up to 64 rods per 8 inch high layer. Appropriate spacers / supports of stainless steel will be usec , to keep the rods in an upright position. There is room for four such layers. The actual number in any shipment will be established by the allowable curie loading or geometry, whichever is more limiting. The lid of the liner contains a spiral-wound stainless steel and~ asbestos. ; gasket, which tenis the large opening in the liner. The mating flanges are machined with grooves that match the stainless steel chevrons of the seal. The lid is held in place and the gasket compressed by twelve 3/4 Inch bolts. This - design is close to that of a standard flange for 10 IPS piping. The differences ' are in the outer diameter of the flange (14-7/8 vs. 16 Inch) and in the bolt diameter (3/4 vs. 7/8 inch) which are limited by the 15 Inch cavity diameter. The closure meets the requirements of the ASME Boller and oressure Vessel Code. Section Vill. Div.-1, as described in Enclosure 3A. The lid of the liner is penetrated by two openings one to introduce gas, the : l other to purge water. Each opening has a stainless steel bellows valve. for sealing the opening, and a stainless steel hose connection. Enclosure 2 describes how these connections are utilized to pirge water from within the i liner, vacuum dry the contents and fill with an inert gas. The valves and hose ; connections are protected against impacts. which can result from the normal conditions of transport and hypothetical accident. conditions of 10 CFR 71.71 ; i and 71.73 by a section of 10 IPS Schedule 10 stainless steel piping and two transverse plates of stainless steel. The transverse plates also support a lifting pin, j The_ liner will be assemoted, sealed and leak-tested prior to use. The gap between the flanges (nominally 0.100 Inch)-will be measured after the Ild bolts =L are fully torqued and the liner is demonstrated to be leak-tight. A-Shim ring will then be machined to the thickness of the gap between flanges and_will he . [ used, with a new gasket, when the linee is used to transport normal form. j j ' J radioactive material. This will ensure-metal to metal contact at the fibnges t - transmit 11mpact loads if the shipping package is dropped. T L
. NEUTRON 3RODUCTS inc
. - - .w - . , .: . . - , , . - , . . . . , , . , . - - - - , . . , < _ , ., --:,-,,i-.---.-,--,..,--,+,
i i i ENCLOSURE I Description of Sealable Liner and Sleeve j Page No. 2 The weignt of the liner is approximately 250. pounds. The maximum weignt of the contents is 180 pounds. Thus, the loaded weight is a maximum of'430 pounds. [ i Sleeve Desfon . The sleeve design is shown in Neutron Procy ts drawing 240138. The sleeve is an annular cylinder of aluminum, that fills the space between the wall of the liner and wall of the cavity, its purposes are to enhance radial heat transfer and to support the liner against lateral Impacts. -l The weight of the sleeve is approximately 240 pounds. Total weicht of Cask Contents With a maximum weight of 430 pounds for the liner and its contents and a sleeve weight of 240 pounds, the neximum weight of the contents of the shipping-package is 670 pounds, which conforms _to the limit of 700 pounds speelffed Irr ; article 5(b)(2) of Certificate of Compilance No. 5942. l i; y
+
nelJTROnlRODUCTS inc -
F f
?
ENCLOSURE 2. Rev. i
SUMMARY
PROCEDURE FOR LOADING. DRYING AND SEALING LINER
- l. Place the bottom portion of the liner in a holding fixture in.a working platform, that is sutnerged at least ten (;0) feet below the surface of the ;
water it. the storage pool (basin). l
- 2. Transfer the cobalt-60 containing aluminum rods from storage buckets'to the f liner.
When the liner is filled. Install the lid, with its Integral seal and with ; 3. hoses attached to the two hose connections on the lid. One hose shall-connect to a source-of heliumt the other shall run to a water container.- - Install and tighten the lid bolts with a long-handled tool. t
- 4. Supply helium with sufficient pressure (approximately 25 psla) to displace :
water from within the liner Collect the discharged water in a container and measure its volume to ensure that essentially all of the water has been removed. During this step. observe the top of the liner for Indication of hellum leakage. If such Indication exists, retorque the lid bolts and/or ! replace the gasket and repeat this step. ,
- S. Connect a vacuum pum to the discharge line. Run the vacuum pum until a- ,
vacuum of 29.5" Hg can be maintained for 5 minutes with the pum turned -l , off. (This is indication that all water has been removed from the liner.) 4
- 6. Close the disenarge valve using a long-handled tool.
- 7. Fill the liner witn helium to 2 to 3 ost above the emblent hydrostatic 4 pressure. (Pressure in psia is given by: water depth in feet times 0.43 plus 14.7.)
- 8. Close the hellum inlet valve with a long-handled tool. Observe the liner '
for indication of helium leakage. If leakage is Indicated, make the.' necessary corrections and repeat steps as necessary to ensure that the liner is dry and filled with helium to the specified overpressure. ,
- 9. Pull the hoses off the hose connections. [
- 10. Lower the GE 700 cask. with the sleeve' inserted, into the pool.
- 11. Lift the sealed liner from the work platform and Insert it into the_GE 700 '
cask. i NEUTRON )RODUCTS inc . , y r- -9 - y r -- - . -,
..r-- -,4.-v... ,,rd',',. y - .- - -sm---r-.-.-c,,.,,,,e,- +- . ~ , - ---c ,,-.--e4.--% --
ENCLOSURE 3. Rev.1 EVALUATION OF PACKAGE PERFORMANCE UNDER N09FAL CON 0lT10NS OF TRANSPORT (10 71.71) AND HYP07HETICAL ACCIDENT CONDITIONS (10 CFR 71.73) General General Electric Company has demonstrated (in a consolidated application for certification, submitted to the NRC by letter cated March 18. 1980) that the GE Model 700 shipping package will survive nornal conditions of transport and hypothetical accident conditions, except that the lid gasket may fall. A way te prevent any dispersal of radioactive neterial under normal conditions of transport and hypothetical accident conditions, since irradlated cobalt from the Savannah River plant can not be demonstrated to meet the clad integrity requirements fcr special form material. 15 to seal the cobalt within a cask liner. This enclosure demonstrates that the cask liner and seal described in l_ Enclosure 1. when loaded and dried as described in Enclosure 2 and contained within the GE Model 700 shipping package, will remain intact through normal conditions of transport and hypothetical accident conditionst and thus ensure containment of radioactive material. The following evaluation supplements General Electric's consolidated application for certification, referenced above. Normal Conditions of Transport Thermal: The liner components (stainless steel shell. and stainless steel. bellows-type shutoff valves, and stainless steel / asbestos gasket), the aluminum sleeve and the contents of the liner are unaffected by amolent temperature extremes defined in 10 CFR 71.71. Calculated temper'stures at an ambient temperature of 800F and a limiting heat load of C500 watts are: Cask surface 3000F (ref: GE appitcation) R Sleeve 1.0. 339eF Liner 0.0. 3800F l Gasket & valves (4000F Contents @ centerline 5050F, These temperatures are suffic'ently above and below limiting temperatures for the materiais that amolent temperature extremes will have no effect on liner or seal _ integrity. The pressure within the liner will be approximately 15 psig, which is well within the capability of the. seal and liner. The bolted closure of the liner and the isolation valves are designed for these conditions, as described in Enclosurs 3A. Pressure: The GE 700 package will withstand tne' range of external pr essures . , defined-in 10 CFR 71.71 (ref: GE application).JThe liner and its contents will therefore be unaffected by external pressure. DOUTROn JRODUCTS1nc
ENCLOSURE 3 Evaluation of Package Performance Page No. 2 Vibration: The GE 700 package will withstand vibration normally incident to transport (ref: GE appilcation). The effects of vibration on the liner are discussed in Enclosure 3A. Item A.9. It is shown that tt'.e Integrity of the liner will be maintained when the package is subjected to vibration under normal conditions of transport. Water spray: Water spray will not adversely affect the cask, including the lic gasket. Therefore the liner will be unaffected. Free drop: There is no damage to the GE 700 cask from dropping the discence prescribed by 10 CFR 71.71 (ref: GE application). It will be shown that, even when subjected to the higher loads resulting from a postulated 30 font drop, the liner will retain its integrity. Therefore, the liner, its seal, and its shut-off valves will retain their integrity for the one (1) foot free droo prescribed by 10 CFR 71.71. Corner crop: Not appilcable. Compres s ion: Not applicable. Penetration: There is no damage to the GE 700 cask from the penetration imoact prescribed by 10 CFR 71.71 (ref: GE application). Therefore the liner will be unaffected. Summary and
Conclusions:
The assessments set forth above provide assurance that the Neutron prooucts liner. transported within the GE Model 700 shipping package, will not be adversely affected by Normal Conditions of Transport and will retain its sealing function. Hypothetical Accicent Conditions Free crop Based on analyses done by General Electric, damage to the GE 700 shipping package from a 30 foot drop would not exceed that suffered by the GE Model 100 package in a 30 foot drop test (ref: GE application). That damage consisted of' local distortion of the steel overpacks the cask was not damaged (ref: NRC Docket No. 71-5926. GE letter dated January 25 1980). The question remaining to be addressed is whetner the g-loadings, resulting from a 30 foot drop, would result in loss of Integrity of the cask liner. neuTaon asooucis inc i
6 ENCLOSURE 3 Evaluation of Package Performance ; Page No. 3 Damage sustained by the GE 100 package in a test 30 ft, drop, anc its general similarity to the GE 700 package. Indicates that the i average deceleration of the cask Ilner upon impact from a 30 ft. drop would be in the range of 50 to 100 g. However. Neutron Products has no quantitative data from which to determine the maximum g-loading. To establish a_ conservatively high g-loading, it is assumed that all of the kinetic energy of the shipping package-(cask, contents. and overpack) is absorbed by deformation of the lead shleiding of the cask. The deformation and maximum-g-loading are calculated using a " dynamic flow pressure" and the geometry of the cask. A conservatively high value of the , g-loading is obtained by using a dynamic flow pressure of 10.000 psi (ref ORNL-NSIC-68. A Guide for the Design. Fabrication, and Operation of Shipping Casks for Nuclear Applications. February 1970). On this conservative basis, the energy to be abset oed by lead defo*mation is 35.500 lbs x 30 ft or 1.065x106 ft lbs. The worst case Impact, with respect to liner integrity, is an upside down impact. The cross-sectional area of lead is 988 in2. Thus l the force to deform the lead Is 9.88x106 lbs. As the lead' cross-sectional area is uniform in the axial direction, the depth of lead deformation is 1.065/9.88 or .108 ft or 1.29 in. The corresponding g-loading, which is uniform with deformaticn. Is i 30/.108 or 278 g. The Integrity of the liner, the bolted cPaure and gasket,_ and the shutoff valves and tubing have been analyzed for these conditions as described in Enclosure 3A. It is concluded that resultant bolt and gasket loads and stresses are ! acceptable and, therefore. the Integrity of the liner will be maintained. A bottom-down impact is less severe than a top-down impact because (1) the bottom of the lead has a convex shape, which would result in a lower g-loading and (2)-the loads on the closure of the liner are relatively low. A side-down impact.' analyzed by the same conservative methodology results in a maximum g-loading of 270 g. The integrity of the liner under these conditions is also discussed in Enclosure 3A and it is ,
-demonstrated that the integrity of the liner will be maintained.-
From this conservative analysis, it is concluded that the liner will retain its integrity if the shipping package is subjected te' L a free drop of 30 feet. g l' NEUTRON 3RODUCTS inc : { . _ - _ _ . _ ;_ ; _. ~.
4 ENCLOSURE 3 Evaluation of Package Performance Page No. 4 Punctures General Electric has analyzed _the consecuences of this postulated occurrence to be not greater than for the GE Mo196 100 package (reft GE application). A test of the Model 100 package, consisting of a 40 inch drop onto a 6 Inch diameter by 8 inch long steel bar, resulted in local yleiding of_ the protective 1 Jacket (overpack) but no penetration of the protective jacket and no camage to the cask (ref: Docket No. 71-5926. GE letter dated January 25. 1980). If the local defornetton of the protective Jacket is greater than .14d inch for an impact in line with the center of gravity of the package, the g-loading on the liner will be less than calculated for the 30 foot free drop. Analyses of the strength and stiffness of the protective jacket Indicate that l for such Impacts. the local deformation will exceed .144 inch. Therefore, the cask liner and its seal would not be damaged. Thermal General Electric has analyzed the GE 700 shipping package for exposure to the fire prescribed by-10 CFR-71.73. A coast up analysis _ indicated that a maximum temperature of '4640F could result at the Innermost lead node (reft GE appilcation). The materials of construction of the liner, bellows-type shut-off valves, and cask sleeve have acceptabte mechanical properties at this temperature. The stainless steel and asbestos gasket will retain its function up to 10000F (reft-Parker Seals catalog). Further, if the steady-state temperature difference of 1250F from the centerline of the liner to the liner surface is conservatively assumed.to exist, the maximum centerline temperature would be approximately 5900F and the pressure within the liner would be approximately 1B psig. This is well below the capability of the seal and liner. Therefore, it is concluded that the cask liner will retain its sealing function throughout_the postulated exposure _ffre. _ Water immersion: The closure of the cask liner has been analyzed for a_ differential pressure of 150 pst as described in Enclosure 3A. l_ Therefore, the seal is capable of preventing in-leakage of water at an external pressure of 21 psig. Summary and
Conclusions:
The assessments set forth above provide assurance that the Neutron Products liner, transported within the GE Model 700 shipoing package, will not be adversely affected by the Hypothetical Accident Conditions and wl'l retain its sealing-function. DOUTROD 3RODUCTS1nc' u
s ENCLOSURE 3A. Rev 0 ANALYSIS OF LINER INTEGRITY This enclosure discusses the Integrity of the liner, including the bolted ; closure and tha valves and fittings on the top plate, for normal conditions of transport and hypothetical accident conditions. This enclosure supplements the analyses described In Enclosure 3. i A. Normal Conditions - Bolted Closure ; The analyses in this section follow the methodolcgy of Appendix II (Rules for Bolted Flange Connections) to Section Vill. Olvision 1 of the ASME Boller and Pressure Vessel Code. The calculations are done in accordance with the procedures for flanges with ring type gaskets. because that is the type of gasket used. The Shlm in the liner closure is designed to carry essentially no load during bolt up and normal 'oerating conditions. These analyses are - applicable to initial boltup and conditions seen by the liner under normal conditions of transport. Potential free drops under normal conditions of transport are enveloped by the free drops analyzed as hypothetical accident conditions in the next section. , d
- 1. Material properties Liner and flange material (304 SS plate, reft Subsection C of ASME Vill) '
(1000F <5000F Tensile strength 75.000 pst i Yleid strength 30.000 Working allowable strength 18.800 (Sa) 12.100 (Sb ) Bolt material-(Unbrako 1960 Series alloy steel, or equivalent) Tenslie strength 180.000 psi Yleid strength 155,000 l Working allowable strength 50.000 (Sa). >40.000 (Sb) In order to limit the torque that must De applied by a.long-handled tool. , the bott-up stresse will be limited to: Bolt-up stress 30.000 (Sa ')
- 5. Bolt Loads (ref: UA-49. ASME Section Vill)
It is necessary to examine two separate and independent conditions. as follows: Operating conditions: Wml = 0.78S'G 2 P + (20 x'3.14 G m P) = 24,788 lbs. where P = design pressure ='150 psi b = effective seating width of gasket = .293 In. G = dia at gasket load reaction = 11.413 in, m = gasket factor = 3.0 NEUTRON JRODUCTS inc.-
t > ENCLOSURE 3A , Analysis of Liner Integrity Page No. 2 Gasket seating: Wm2
- 3.14 b G y = 105.002 lbs wheres y = gasket seating load = 10.000 psi (reft *.a~ ble UA-49.1)
$-) 3. Reovired Bolt Area (reft UA-49)
The recuired total bolt area is the larger of the following:
't Amt
- Wml/Sb Am2 " Wm2/Sa' where Sa' is the bolt-up stress, used instead of Sa as-specified by ASME Section Vllt, and Se and Sb are the allowable workfng stresses. '
Thus: i Am g = 24.798/12.100 = 2.05 In2- , Am2 = 105.002/30.000 = 3.50 in2 The latter case (gasket seating) governs. The bolt area at the base of the threeds is .785 (.620)2 = .302 in2, The total bolt area (A b) = 12 x .302 = 3.62 in2. which exceeds the required bolt area.
- 4. Flance Oeston Bolt load (ref UA-49)
Operating conditions: =Wml = 24.788 lbs Gasket seating: = 1/2 (Am2 + Ab) Sa .= 106.800 lbs
- 5. Flanop Moments (ref UA-50)
Operating conditions: M=MO+MT+MG = 48.096 in Ib Gasket seating:
-M = 103.007 in Ib
- 6. Flance Stresses (ref: UA-51)
Operating conditions:- -(Allowable Stress) longitudinal hub stress = 8.785 psi (18.100 ps!) , Radial flange stress'= 220 (12.100)' Tangential flange stress = 5.977 -(12.100) Gasket seating: Longitudinal hub stress = 18.850 (28.200) D Radial flange stress = 472 (18.800)- Tangential flange stress = 12.794 (18.800)-
~
NEUTRON )RODUCTS inc
4 ENCLOSURE 3A Analysis of Liner integrity Page No. 3
- 7. Stresses in Top Plate (ref: Roark, Formulas for Stress and Strain, Table X)
The boltuo loads impose a bending moment on the top plate and, as a result, a maximum bending stress of 6,705 psi, which is well within the allowable working stress of the material.
- 8. Bolt Toroue The required bolt torque is established by the gasket seating condition. A tentative value, based on data provided by Unbrako, is 1320 In.lb. The actual value will be established in the course of pressure testing the first liner, prior to the first shipment, by measuring the torque required to compress the gasket to its nominal seated thickness of 0.100 in, or whatever is reoutred to prevent leakage of helium at the design pressure of 150 psig. That experimentally determined torque will be used when sealing the liner for shipments.
- 9. Vibration The GE 700 cask and the liner are shipped in an uortght position. The only '
type of vibration that potentially threatens the integrity of the liner and bolted closure is a lateral, rocking motion in which the edge of the top-plate impacts the Inside of the cask cavity. This would impose a shear loading between the top plate and flange of the liner, which would be resisted by friction between the heads of the bolts and~ top plate and by-shear and bending loads in the bolts. Any vibration that may. occur will be damped by friction between the liner and sleeve and by relative motions of the contents of the liner, it is estimated that the maximum lateral vibrational impact loading will be no greater-than 19, which is a factor of approxinately 500 below the loading that could cause relative motion ' between the top plate and flange. Therefore, the integrity of the liner is not threatened by vibration incident to normal conditions of transport. B. Liner Integrity - Hypothetical Accident Conditions
=
l I 1. Free Drop l Upside-Down impact I in an upside-down impact, the contents of the liner (180 lbs) transfer their load directly-to the central portion of the top plate. The load'Is essentially uniformly distributed. The top plate itself and its appurtenances weigh 115 lbs. The loads from the bottom of the liner (250 lbs) and the sleeve (240.Ibs) are transmitted to the top plate through the shim ring. The maximuni compressive stress in the shlm ring for a 278g impact is 4,100 psi. The maximum compressive stress in the liner wall is 3750 psi. Both of these values are within acceptable limits for 304 SS. NEUTRON )RODUCTSinc
I t ENCLOSURE 3A Analysis of Liner Integrity Page No. 4 These impact loads impose a bending moment on the top plate opposite in direction from the boltup loads. The maximum combined bending stress In the top plate is approximately 5000 psi. which is well below the allowable working stress. The deflections at the bolt circle and at the gasket are less than .001 in. The bolt loading and gasket compression are essentially unaffected. One of the isolation valves on the top of the liner and its attached tubing weigh less than 0.75 lb. If all of the load from a top-down impact of 278g 15 carried by the two #10-32 screws in *.he bottom of the valve body, the tenstle stress in the screws is only 7.840 psi. The stresses in other portions of the valves and fittings are even lower. Therefore. the valves and fittings will remain in place. The valves and fittings are surrounded and protected from impact by the short section of 10 IPS piping and two cross plates, which extend above the tops of the valves. The total cross-sectional area of the pipe and cross plates is 11.7 in2. The cocoressive stress in these parts from a 2789 top-down impact is 15,920 psi, which is below the yleid stress of 304 SS. No significant deformations of these structural members will occur and the valves and fittings will not be contact the interior of the cask cavity. In surnery the liner, including the bolted closure and pressure boundary fittings on the top plate; will retain its integrity in case of a 30 ft. free drop with a top-down impact. Bottom-Gown impact in a bottom-down impact, the mass of the top plate is supported by shim ring and the wall of the bottom section of the liner. The contents, bottom plate of the liner, and sleeve do not impose loads on the closure or liner wall. The maximum compressive stress in the shim for a 278g Impact is only 1000 psl. The maximum compressive stress in the liner wall is 10.790 psi. Both of these values are within acceptable limits for compressive stress. The moment on the top plate is opposite in direction and smaller than the moment from the boltup loads. The resultant stresses and the deflections at the bolt circle and gasket are negligibly small. The bolt loading and gasket compression are essentially unaffected. A bottom-down drop subjects the valves and fittings on the top plate to lower loadings than described above for a top-side down impact and will not violate the pressure bounoary, in summary, the liner, including the boltec closure and fittings on the tco plate, will retain its integrity in a 30 ft free drop with a bottom-down impact. neurnon anooucis inc
t ENCLOSURE 3A Analysis of liner Integrity Page No. 5 Side-Down impact in a side-down impact. the assembly clearances are such that the edges of the flange and top plate could Irpact the wall of the cask cavity before the body of the liner obtains lateral support from the sleeve. In this case, there is a potential shear loading in the liner wall just below the flange, from the mass of the liner and its contents. The resultant stress from a 270g impact is 12.300 lbs. which is an acceptable shear stress. A $1de-down impact would impose a moment on the supports of the valves on the top plate. The moment is resisted by the two screws in the base of the valve body and by the tubing attached to the valve body. If it is conservatively assumed that the moment is resisted by the screws only, the tensile stress In the screws is 35.350 psl. As this is less than the ultimate tensile strength of the screw material (about 48.000 psl at 5000F). It is concluded that the valve will remain in place. In summary, the liner will retain its integrity in a 30 ft. free drop with side-down impact. Oblique Irpacts An obilque, e.g., corner, impact of the shipping package will result in larger distortions and hence lower g loads than postulated for the other impacts discussed above. The loadings on the liner and its appurtenances can be regarded as superpositions of fractions of the loadings described aoove and the total loads will be lower. Therefore, the liner will retain its integrity.
- 2. Hypothetical Fire As described in Enclosure 3. the maximum temperature of the lead in the cask is 4640f. which Indicates that the liner, bolted closure and gasket.
and valves and fittings on the top plate will have a maximum temperature of no more than 5000F, All of the materials, except the asbestos filler in the gasket and the heao bolts have the same coefficient of thermal expansion. All parts of the bolted closure will be at essentially the same temperature. because the heat flux through the top Of the liner is negligible and stainless steel has a relatively high thermal conductivity. The differential thermal expansion between the neck of a bolt and thickness of the too plate is approximately .0018 in. and is in the direction of increasing the gasf<et seating force. The bolts have ample margin to assume the additional load. The maximum internal pressure in the liner will be 18 psig (ref t Enclosure 3), which is well celow the design pressure of 150 psi and the rated pressure of the gasket (250 psi). Based on data from the gasket manufacturer, the gasket will retain its function up to 10000F, I nGUTROn JRODUCTS inc
.,.,.7 . . - . - . . . _ - - . -- -- -_ .. r e 4 CNCLOSURE 3A Analysis of Liner Integrity Page No. 6 All of the parts of the valves and fittings on the top plate, that cotrorise- j r the prussure boundary, are stainless steel and will retain their integelty ,- and sealing function to a terrcerature of at least 5000F. In surrmary, the liner will retain its entegrity during exposure of the shipping package to a hypothetical fire as prescribed by 10 CFR 71. b 6 4 nOUTRODORODUCTS.inc
, ,,4-. - ~ , , - , .J-, ,-+'., . - - - . . ,
% - - . _ , , . , . . ~ , , . .
nGUTROn JRODUCTS inc
- 230! 311. Ernraim RoJd. P.0, B<.'r c3 Dickerwn, .\larvtand cs t; !. 5 J ;
T;1'L 710-?:M!J:
'86 p _4 jrf;. 9 !001
)
February 6. 1986
** . Cterles E. MacDonald, Chief Transportation Branch Cffice of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission hashington, D.C. 20555
- Refs: 1. Certificate of Cor.pliance No. 5942
- 2. Neutron Products Letter dated January 8. 1986
Dear Mr. MacDonald:
Confirming a telephone conversation of today between Mr. Odegaarden and myself, heutron Products has no ob.lection to your filing drawings, submitted by reference 2. In the Public Document Room. Very truly yours. -! NEUTRON PRODUCTS INC. I t.cWY_444, F. Schwoerer. Vice President F5 mvc
& h somen B f~ -
~
& FEB 4 seg; $
l num mu % l t Doaneg l: d' g
,gycogfeasWF m
y .-
/
p_ 7pgdf s - 3 o; a.v
;;;u; .< _. ;v, w :: 3 ., ,
= . . -
- .: ,: . L.
- r n ll ~~ i; * ).y 8..)f.d; February 28, 1986 Mr. Charles E. MacDonald, Chief ~ .h
@ RECEiVD n Transportation Branch Office of Nuclear Matertal Safety and Safeguards g- C u.S. Nuclear Regulatory Commission E~ IDE 3 566 > -j Washington, D.C. 20555 -
'Zi U.s.NuctuR cattm N '.U J Rn'.uT331 Ref: Certificate of Compilance No. 5942 u sa. a ,
s -
Dear Mr. MacDonald:
N .. r-This letter supplemerits our application of November 11. 1985, in which we requested a modification to the subject Certificate of Comollance, to allow Neutron Products to utilize the G.E. Model 700 shipping package to ship cobalt-60 from the Savannah River plant to Neutron Products' Dickerson, Maryland facility. The following supplementary information is submitted with this letter.
- 1. Complete engineering drawings of the liner, Revision D dated 2/27/86, which suoerst:de drawings submittad by our 19tter dated January 8, 1986.
- 2. Demonstration of the leak tightness of the liner under normal and accident conditions, by engineering analyses that are (a) summarlzed in Enclosures 3 and 3A, wntch supersede earlier versions submitted by our letter dated January 8, 1986, and (b) detailed in Enclosures 38, 3C, and 3D, which contain information not previously submitted.
- 3. Modified procedures to assure the dryne' of the liner, described in Enclosure 2 Rev. 2, which supersedes tne version submitted by our letter dated January 8, 1986.
We believe that, with this submittal. our application is fully responsive to your requests for additional information. Very truly yours,
<D I N1 NEUTRON PRODUCTS, INC.
P CDCXEIO us:c 1
!21 ,,,,,,,,
-- Frank Schwoerer, Vice President
~
~~,
F5:mvc Enclosures
. W3 C CCC Q
., ,,e
/
'% w p[/
R i. & pg
@g6WQ Lf6 (g .
- i t
Et4 CLOSURE ?. Rev. 2
SUMMARY
PROCEDURE TOR LOADl!JG. DRYING AND SEAlltlG Lit 1ER >
- l. Place the bottom portion of the liner in a holding Fixture in a working platform, that is submerged at least ten (10) feet below the surface of t.~.e water in the storage pool (basin).
- 2. Transfer the cobalt-60 target rods from storage buckets.to the liner.
- 3. When the liner is filled, install the lid, with its integral seal and wit 9 transparent hoses attached to the two hose connections on the lid. One h:$e connects to a source of heliums the other loops above the surface of the pool but ends in the pool. Install and tighten the lid bolts with a long-handled tool.
- 4. Supply helium with sufficient pressure (approximately 25 psla) to disple:e water from within the liner. Observe the discharge hose.to ensure that essentially all'of the water has been removed. Also observe the top of tre liner for Indication of helium leakage. If such Indication exists, retorcJe the lid bolts and/or replace the gasket and repeat this step.
S. Close the discharge valve, using a long-handled tool.
- 6. Connect a vacuum pump to the inlet line. Run the pump until a vacuum of 29.5" Hg (0.5" Hg absolute pressure) can be maintained for 5 minutes with the pump turned off. (This vacuum corresponds to a saturation temperature of 58.80F, which is lower than the pool temperature and is, therefore, Indication that all water has been removed fro.= the liner.) .
- 7. Fill the liner with helium to 2 to 3 psi above the ambient hydrostatic pressure. (Pressure in psia is given by: water depth in feet times 0.43 plus 14.7.)
- 8. Close the inlet valve with a long-handled tool. Observe the liner for.
Indication of helium leakage. If leakage Is Indicated,'make the necessary corrections and repeat steps as necessary to ensure that the liner is dry and filled with helium to the speelffed overpressure.
- 9. Pull the hoses off the hose connections.
- 10. Lower the GE 700 cask,-with the sleeve inserted.-into the pool. .
- 11. Lift the sealed liner from the work platform and insert it into the GE 700 cask.
4 k 6
., ,-. .- g.--. - . . , , . - -,. w. , - - , . - , ,4- . , - ,, ,-,,.,,,-._,,n,, ,,,..-..,,,en...,
6 ENCLOSURE 3. Rev.i EVALUATION OF PACKAGE PERFORMANCE bNDER NORMAL CONDITIONS OF TRANSPORT (10 CFR 71.71) AND HYPOTHETICAL ACCIDENT CONDITIONS (10 CFR 71.73) General General Electric Company has demonstrated (in a consolidated application for certification. submitted to the NRC by letter dated March 18. 1980) that the GE Model 700 shipping package will survive normal conditions of transport and hypothetical accident conditions, except that the lid gasket may fall. A way to prevent any dispersal of radioactive material under normal conditions of transport and hypothetical accident conditions, since Irradiated cobalt from the Savannah River plant can not be demonstrated to meet the clad integrity requirements for special form material, is to seal the cobalt within a cask liner. This enclosure demonstrates that the cask liner and seal described in Enclosure 1. when loaded and dried as described in Enclosure 2 and containeo within the CE Model 700 shipping package, will remain intact through normal conditions of transport and hypothetical accident conditions; and thus ensure containment of radioactive noterial . The following evaluation supplements General Electric's consolidated appilCation for certification, referenced above. Normal Conditions of Transport Thermal: The liner components (stainless steel shell, and stainless steel, bellows-type shutoff valves, and stainless steel / asbestos gasket) the aluminum sleeve, and the contents of the liner ee unaffected by ambient temperature extremes defined in 10 CFR 71.71. Calculated temperatures at en ambient temperature of 800F and a limiting heat load of 6500 watts are: Cask surface 3000F (ref: GE application) Sleeve I.D. 3390F Liner 0.D. 3800F Gasket & valves (4000F Contents O centerline 4910F. l These temperatures are sufficiently above and below limiting temperatures for the materials that ambient temperature extrenes will have no effect on liner or seal integrity. The pressure within the liner wlli be approximately 26 psig, which is well l within the capability of the seal and liner. The bolted closure of the liner and the isolation valves are designed for these conditions, as described in Enclosure 3A. The heat transfer calculations are detailed in Enclosure 3B. Pressure: -The GE 700 package will withstand the range of external pressures defined in 10 CFR 71.71 (ref: GE application). The liner and-Its contents will therefore be unaffected by external pressure.
_ _ - _ _ _ _ - m -- I e s , E'4CLO5URE 3. Rev.2 Evaluation of Package Performance Page No. 2 Vibration: The GE 700 package will withstand vibration normally incident to transport (reft GE application). The effects of vibration on the liner are discussed in Enclosure 3A. Item A.9. It is shown that the Integrity of the liner will be maintained when the package is , subjected to vibration under normal conditions of transport. Water spray: Water spray will not advers91y affect the cask, including the lid gasket. Therefore the liner will be unaffected. Free drop: There is no damage to the GE 700 cask from dropping the distance prescribed by 10 CFR 71.71 (ref GE application). It will be shown that, even when subjected to the higher loads resulting from a postulated 30 foot droo, the liner will retain Its Integrity. Therefore, the liner, Its seal, and Its shut-off valves will retain their Integrity for the one (1) foot free drop prescribed by 10 CFR 71.71. Corner drop Not applicable. Compression: Not applicable. Penetration: There is no damage to the GE 700 cask from the penetration inpact prescribed by 10 CFR 71.71 (ref: GE application). Therefore the liner will be unaffected. Summary and
Conclusions:
The assessments set forth above provide assurance that the Neutron Products liner, transported within the GE Hodel 700 shipolog package, will not be adversely affected by Normal Conditions of Transport and will retain its sealing function. Hypothetical Accident Conditions
?
Free drop: Based On analyses done by General Electric, damage to the GE 700- ' shipping package from a 30 foot drop would not exceed that suffered by the GE Model 100 package in a 30 foot drop test (ref: GE application). That damage consisted of local distortion of the steel overpack; the cask was not damaged (ref: NRC Docket No. 71-5926. GE letter dated January 25, 1980). The question remaining to be addressed 15 whether the-g-loadings, resulting from a 30 foot drop, would result in loss of integrity of the cask liner. I
)
L 4-
-r- , - --- -
-i ENCLOSURE 3. Rev.2 Evaluation of Package Performance Page No. 3 Damage sustained by the GE 100 package in a test 30 ft. drop, and its general similarity to the GE 700 package. Indicates that the '
average deceleration of the cask liner upon impact from a 30 ft. d op would be in the range of 50 to 100 g. However, Neutron Products has no quantitative data from which to determine the maximum g-loading. To establish a conservatively high g-loadi..g. It is assumed that all of the kinetic energy of the shipping package (cask, contents, and overpack) is absorbed by deformation i of the lead shleiding of the cask. The deformation and maximum g-Ivading are calculated using a " dynamic flow pressure" and the geometry of the cask. A conservatively high value of the 9-loading is obtained by using a dynamic flow pressure of 10,000 psi (reft ORNL-NSIC-68, A JGuide for the Design. Fabrication, and . Operation of Shipping Casks for Nuclear Applications. February 1970). On this conservative basis, the energy to be absorbed by lead deformation is 35,500 lbs x 30 ft or 1.065x10 6 ft lbs. The worst case impact, with respect to liner-Integrity, is an upsice down impact. The cross-sectional area of lead 1s 988 in2. Thus the force to deform the lead is 9.88x106 lbs. As the lead cross-sectional area is uniform In the axial direction,'the depth of lead deformation is 1.065/9.88 or .108 ft or 1.29 in. The corresponding g-loading, which is uniform with deformation, is 30/.108 or 278 g. The Integrity of the liner, the bolted closure and gasket, and the shutoff valves and tubing have been analyzed . for these conditions, at described in Enclosure 3A. It is ' concluded that resultant bolt and gasket loads'and stresses are acceptable and, therefore, the integrity of the liner will be maintained. A bottom-down impact is less severe than a top-down impact because (1) the bottom of the lead has a convex shape, which & would result in a lower g-loading and '(2)~ the loads on the closure of the liner J relatively low. A side-dcwn Impact, i analyzed by the same ovoservative methodology results in a maximum _ g-loading of 270 g. The integrity of the liner under these conditions is also discussed in Enclosure 3A and It-Is demonstrated that the integrity of the liner will be maintained. From this conservative analysis, it is concluded that.the liner. will retain-its integrity if'the shipping package is subjected to L a free drop of 30 feet. 1 L -
~ .. .- _
ENCLO5URE 3. Rev.2 Evaluation of Package Performance Page No. 4 Punctures General Electric has analyzed the consequences of this postulated occurrence to be not greater than for the GE Nodel 100 package ( ef: GE appilcation). A test of the Model 100 package. , consisting of a 40 inch drop onto a 6 Inch diameter by 8 inch long steel bar, resulted in local yleiding of the protective Jacket (overpack) but no penetration of the protective Jacket and ; no damage to the cask (reft Docket No. 71-5926. GE letter dated January 25. 1980). As shown by detailed analyses in Enclosure 3C. the 9-loading on the liner will be less than calculated for the 30 foot free drop. Therefore, the cask liner and-Its .eal would not be damaged. > Thermal General Electric has analyzed the GE 700 shipping package for exposure to the fire prescribed by 10 CFR 71.73. A' coast Up analysis indicated that a maximum temperature of 4640F could result at the innermost lead node (ref: GE application). The materials of construction of the liner, bellows-type shut-off valves, and cask sleeve have-acceptable mechanical properties at this temperature. The stainless steel and asbestos gasket will retain its function up to 10000F (ref: Parker Seals catalog). Further, if the steady-state temperature difference of Il00F l from the centerline of the liner to the liner surface is conservatively assumed to exist, the maximum centerline temperature would be approximately 5750F and the pressure within the liner would be approximately 30 psig. This is well below the capability of the seal and liner. Therefore, it is concluded that the cask liner will retain its sealing function throughout the postulated ~ exposure fire. Water immersion: The closure of the cask liner has been analyzed for a differential pressure of 150 psi as described in Enclosure 3A. Therefore, the seal is capable of preventing in-leakage of water at an external pressure of 21 psig. Summary and
Conclusions:
The assessments set forth above provide _ assurance that the-Neutron Products liner, transported within the GE Model.700 shipping-package, will not be adversely affected by the Hypothetical Accident Conditions and will retain its sealing
- function.
9
a ENCLOSURE 3A Rev.1 ANALYSIS OF LINER INTEGRITY This enclosure discusses the integrity of the liner (including the bolted closure and the valves and fittings on the top plate), 'or normal conditions of transport and hypothetical accident conditions. This enclosure supplements the analyses described in Enclosure 3. A. Normal Conditions - Bolted Closure The analyses described in this section follow the methodology of Appendix !! (Rules for Bolted Flange Connections) to Section Vill, Olvision 1 of the ASME Boller and Pressure Vessel Code. The calculations are dcne in accordance with the procedures for flanges with ring type gaskets, because that is the type of gasket used. The shim in the liner closure is designed to carry essentially no load during bolt up and normal operating conditions. These analyses are applicable to initial boltup and conditions seen by the liner under normal conditions of transport. Potential free drops under normal conditions of transport are enveloped by the free drops analyzed as hypothetical accident conditions in the next section. The development of these results is detailed in Enclosure 3D.
- 1. Material Properties Liner and flange material (304 SS plate, ref: Subsection C of ASME Vill)
(1000f (S000F Tensile strength 75,000 ps! Yleid strength 30,000 Working allowable strength 18,800 (Sa) 12,100 (5 3) Bolt material (Unbrako 1960 Series alloy steel, or equivalent) Tenslie strength 180,000 ps! Yleid strength 155,000 Working allowable strength 50,000 (S al >40,000 (S b) In order to limit the torque that must be applied by a long-handled tool, the bolt-up stresse will be limited to: Bolt-up stress 30,000 (S a')
- 2. Bolt loads (reft UA-49, ASME Section Vill)
It is necessary to examine two separate and independent conditions, as follows: Operating conditions: Wml = 0.78S 2G P + (2b x 3.14 G m P) = 24,791 lbs. wheret P = design pressure = 150 psi b = effective seating wid,th of gasket = .293 in. G = dia at gasket load reaction = 11.414 in. m = gasket factor = 3.0
\
l
O EtJCLO5URE 3A, Rev.1 Ar.alysis of Liner integrity Page flo. 2 Gasket seating: Wm2 = 3.14 b G y = 105,011 lbs . where: y - gasket seating load = 10,000 psi (reft Table UA-49.1)
- 3. Required Bolt Area (ref: UA-49)
The required total bolt area is the larger of the following Amt = Wml/Sb Am2 = Wm2/Sa ' where Sa, is the bolt-up stress, used Instead of Sa as specified by ' A5ME Section Vill, and Sa and Sb are the allowable working stresses. Thus: Amt = 24,791/12,100 = 2.05 in 2 2 Am2 = 105.011/30,000 = 3.50 in The latter case (gasket seating) governs. The bolt area at the base of the threads is .785 (.620)2 = .302 In2, The total bolt area (Ab) = 12 x .302 = 3.62 in2 , which exceeds the required bolt area.
- 4. Flanne Desinn Bolt load (ref: UA-49)
Operating conditions: =Wml = 24,791 lbs Gasket seating = 1/2 (A m2 + Ab ) Sa = 106,000 lbs
- 5. Flanne Homents (ref UA-50) .
Operating conditions: H=HD+HT+MG = 29.060 in Ib Gasket seating: H,= 104.717 in Ib
- 6. F1ance Stresses (reft UA-51)
Operating conditions: Stress Allowable Sfty Fetr* Longitudinal hub stress = 5,202 ps! 18.100 pst 3.5 Radial flange stress = 131 12,100 92. Tangential flange stress = 3,662 12,100 3.3 (Sn+Sp)/2 = 2,667 12,100 4.5 (SH+S 4,432 12.100 2.7 T )/2 =
- Acceptable value = 1.0 or: greater G
t h.
e ENCLOSURE 3A Rev.! Analysis of Liner Integrity Page No. 3 Gasket seating: Stress Allowable Sfty Fctr' Longitudinal hub stress = 18,744 28,200 1.5 Radial flange stress = 471 !8,800 40. Tangential flange stress = 13,194 18,800 1.4 (Sg+Sp)/2 = 9,608 18,800 2.0 (SH+5T )/2 = 15,969 18.800 1.2
' Acceptable value is 1.0 or greater
- 7. Stresses in Top Plate The boltup loads impose a bending moment on the top plate and, as a result -
a maximum bending stress of 6.383 psi. The allowable working stress of the material is 18,800 psi and the Safety Factor to the allowable working stress is 2.9.
- 8. 8olt Torque The required bolt torque is established by the gasket seating condition. A tentative value, based on data provided by Unbrako, is 1320 in.lb. The actual value will be established in the course of pressure testing the first ;lner, prior to the first shipment, by measuring the torque required to comp ess the gasket to its nominal seated thickness of 0.100 in or whatever is required to prevent leakage of helium at the design pressure of 150 psig. That experimentally determined torque will be used when sealing -
the liner for shipments.
- 9. Vibration The GE 700 cask and the Ilner are shipped in an upright position. The only type of vibration that potentially threatens the Integrity of the liner and bolted closure is a lateral, rocking motion in which the edge of the top plate impacts the inside of the cask cavity. This would impose a shear loading between the top plate and flange of the liner, which would be resisted by friction between the heads of the bolts and top plate and by shear and bending loads in the bolts. Any vibration that may occur will be damped by friction between the Ilner and sleeve and by relative motions of
< the contents of the liner. It is estimated that the maximum lateral vibrational Impact loading will be no greater than 1g, which is a factor of approximately 50 below the loading that could cause relative motion between the top plate and flange. Therefore, the integrity of the liner is not threatened by vibration incident to normal conditions of transport.
- 8. Liner integrity - Hypothetical Accident Conditions
- 1. Free Drop Upside-Down impact l
In an upside-down impact, the contents of the liner (180 lbs) transfer their load directly to the central portion of-the top plate. The load is essentially uniformly distributed. The top plate itself and its ,
- r-
ENCLOSURE 3A, Rev.1 Analysis of Liner integrity Page No. 4 appurtenances weigh 115 lbs. The loads from the bottom of the liner (135 lbs) and the sleeva (240 lbs) are transmitted to the top plate through the shim ring. The maxln(n compressive stress in the snim ring for a 2789 impact is 3,363 psi. The maximum compressive stress in the liner wall is 3950 psi. The yleid stress at 4000f is 20,700 pst and the Safety factors to yleid are 6.2 ond 5.2, respectively. These impact loads inpose a bending noment on the top plate opposite in direction from the boltup loads. The maximum conbined bending stre?;s in tne top plate is approximately 14,000 psi, which is below the yield stress of 20,700 psl. The Safety Factor to yleid is 1.5. The deflections at the bolt circle and at the gaskot are approximately .001 in, which means that the bolt loading and gasket compression are essentially unaffected. One of the isolation valves on the top of the liner and its attached tubing weigh less than 0.75 lb. The load from a top-down impact of 2789 1s carried by two #10-32 screws in the bottom of the valve body and four welds at the base of the hold-down channel. The tensile stress is 2.840 psi, which_gives a Safety Factor to yleid of 7.3 As the stresses in other portions of the valves and fittings are even lower, it can be concluded that the valves and fittings will remain in place. The valves and fittings are surrounded and protected from impact by the short section of 10 IPS piping and two cross plates, which extend above the tops of the valves. The total cross-sectional area of the pipe and cross plates is 12.8 in2. The compressive stress in these parts from a 2789 top-down impact is 14.563 psi. As the yield stress at 4000F is 20,700 psi, the Safety factor to yleid is 1.4. No inelastic deformation of these structural members will occur and the valves and fittings will not be contact the Interior of the cask cavity. In summary, the liner, including the bolted closure and pressure boundary fittings on the top plate, will retain its integrity in case of a 30 ft. free drop with a top-down impact. Bottom-Down impact in a bottom-down impact, the mass of the top plate is supported by shim ring and the wall of the bottom section of the liner. The contents, bottom plate of the liner, and sleeve oo not impose loads on the closure or liner wall. The maximum compressive stress in the shim for a 2789 Impact is only about 1000 psl. The maximum compressive stress in the liner wall is 10.179 psi. Both of these values are within the yleid stress at 4000F (20,700 psi) and the Safety factors to yleid are 20 and 2.0, respectively. The moment on the top plate is opposite in direction and smaller than the~ moment from the boltup loads. The resultant stresses and the deflections at the bolt circle and gasket are n,gligibly e small. The bolt loading and gasket compression are essentially unaffected. A bottom-down drop subjects the valves and fittings on the top plate.to lower loadings than described above for a top-side down impact and will not violate the pressure boundary. ,
4 I ENCLOSURE 3A, Rev.1 Analysis of Liner Integrity Pcge No. 5 In summary, the liner, including the bolted closure and fittings on the top plate, will retain its integrity in a 30 ft. free drop with a bottom-down impact. Side-Down impact in a side-cown impact, the assembly clearances are such that the edges of the flange and top plate could impa ;t the wall of the cask cavity before h the body of the liner obtains laterci support from the sleeve. In this y case, there is a potential sheer loading in the liner wall just below the j{ flange, from the muss of the liner and its contents. The resultant stress from a 270] impact is 13,770 lbs, which is less than the ultinate shear strength of the material at 4000F (35,400 psi). The corresponding Safety Factor is 2.6. A side-down impact would impose a moment on the supports of the valves on - the top plate. The accent is resisted by tne two screws in the base of the valve body and by the hold-dowri channel over the valve bocy. The neximum tensile stress in the screws is 12,156 psi. t,s the yield stress at 4000F is 20,700 psi, the Safety Factor to yleid is 1.7. The load on the hold-oown channel loads the welds in shear and gives a stress of 5,250 psi. As the yleid stress in shear is 11.385 psi, the Safety Factor tc yleid is 2.2. This demonstrates that the valve will remala in place. In summary, the liner will retain its integrity in a 30 ft. free drop with side-down impact. Oblique Impacts An obilque, e 9., corner, impact of the shipping package will result in larger distortions and hence lower q loads than postulated for the other impacts discussed above. The loadings on the ilner and its appurtenances can be regarded as superpcsitions of fractions of the loadings described above and the total loads will be lower. Therefore, the liner will retain its integr.ty.
- 2. Hypothetica! Fire a
As described in Enclost.re 3, the maximum temperature of the lead in the cask is 4640F, which Indicates that the liner, bolted closure and ga'sket. and valves and fittings on the top plate will have a maximum temperature of no more than 5000F. All of the materials, except 'che asbestos filler in the gasket and the head bolts. have the same coefficient of thermal expansion.-All parts of the bolted closure will be at cssent:lally the same temperature, because the heat flux through the top of the liner is negligible and stainless steel has a relatively high thermal conductivity. The differential thermal expansion between thi! neck of a bolt and thickness of the top plate is app-oximate'y .0016 in, and is in the direction of increasing the gagket seating force. The bolts.have ample margin to assume the additional load -
'er
! E14C 05URE 3A. Rev.1 Analysis of Liner integrity Page flo. 6 The maximum Internal pressure in the liner will be 30 psig (ref Enclosure 3), which is well below the design pressure of 150 pst and the rated pressure of the gasket (250 pst). Based on data from the gasket manufacturer, the gasket will retain its function up to 10000F. All of the Wrts of the valves and fittings on the top plate, that; comprise the pressure boundary, are stainless steel and will retain their integrity and sealing function to a temperature of at least 5000F. In summary, the liner will retain its Imtegrity during exposure of the shipping package to a hypothetical fle c - orescribed by 10 CFR 71. e i 1 4 s
EtJCLOSURE 3A Rev.1 Analysis of Liner Integrity Page flo. 7 Table i Sumaary of Minimum Safety Factors Safety Factor To Stress Condition Liner Flange Stress 2.7 Allowable Working Stress Operating Conditions
-Gasket Seating 1.2 Allowable Working Stress Liner Lid Bending Stress Gasket Seating 2.9 Allraable Working Stress 30 ft Upside Down Drop 1.S Yleid Stress at 4000F Protective Pipe and Plates on Ltd 30 ft Upside Down Drop 1.4 Yleid Stress at 4000F Liner Wall Shear Strength at 4000F 30 ft Side Down Drop 2.6 Valve Supports on Ltd 30 ft Side Down Drop 1.7 Yleid Stress at 4000F a O e
J ENCLOSURE 33,-Rev.Cf Page:1 of:13. NE6I_IBo82[E8.6H6ky!!!_:_gQB6(I:@9gB12dEUI!_EB95.!aV6ENbH_BIYsB 3 6gsu!2110B81-
- 1. Use GE 700 shipping container, which consists 'f'a' cask and protective Jacket, with an aluminum inner sleeve and liner, per Neutron Products, +
drawings nos. 240138 and 240139.
- 2. The maximum allowable heat load per shipment is 6500 watta.
T
- 3. Target slugs are positioned in the liner by egg-crate spacers approximately as shown in Figure 1. There are 4 layers of.8" long slugs,- .
for a maximum loading of 240 slugs per shipment.'This results in 50% of the liner. volume occupied by slugs and150% by fill gas.
- 4. The target slugs are loaded into the liner at random. Actually our personnel will be instructed to load higher _ activity alugs adjacent to the liner wall.
- 5. The fill gas in the liner is He at 2 atmospheres absolute (after reaching thermal equilibrium).
- 6. The fill gas in the cask is air at 1 atmosphere absolute.
- 7. 854 of the thermal energy is deposited in the slugs; 7% in the Al sleeve; and 84 in the lead._ shielding of the cask.
- 8. All heat transferred from the liner is in the radial direction, i.e., heat transfer from the endsnia neglected.
- 9. Ambient temperature is 800F.
- 10. At a heat load of 6566 watts, the cask surface temperature is 3000FL(GE calcalation, ref: GE letter to NRC dated 3/18/80). At other heat. loads,
~
the temperature difference.between the' cask'aurface and ambient:is-directly proportional to heat +1oad. Ugthgg_gf_6dglygig A BASIC language program (RADXFR), written for an IBM-PC-computer,-was-used'to
. calculate temperatures inside the cask-and liner.:A listing of'the_ program is ,
given in Appendix A. The program. utilizes:a.very simple;nodelito calculate h'est-- transfer within the liner.5 Supplementary hand calculationsiwere-then performedL to refine the' analysis of heat transfer-inside theiliner.
~
\
t 9 e
b ,-. I ENCLOSURE 3B, Rev.C
-Page 2 of-15 1
2I [The- shipping container, aluminua sleeve, and liner are represented in'RADXFR es concentric cylinders, as illustrated in Figure 2. The temperature _at node:1, the cask surface, is obtained as described in Assumption #10. For a-heat-load-of-6500 watts, the temperature is-2980F, 1l
. -. G The temperature difference across the wall of the cask la giveniby: L T2 -Ti = ( Q / 2 (k1 L) In rg/r2 ,
Heat deposited in the cask wall is conservatively assumed to be deposited - at the inner surface (node 2). The thermal conductivity used is that of lead, as given by-Table 28, Chapter 2 of-HandbgoB_g{_ Heat _ Transfer, , Rohsenow and Hartnett, McGraw-Hill,1973. The carbon steel inner shell anc - stainlesa steel inner ahells have been neglected. The temperature difference across the annular gap between the inner shell of < the cask and the aluminum sleeve is given by: T3 -T2 " (f1'f 2) ( Q / 2Trk2 L) In rg/r3 where: .k 2*N,v+krad c k e ,y =k g f(NGr). Per data of Mull & Reiher.for heat transfer through vertical air layers by free convection kg:= thermal conductivity of air at 1 atmosphere;(from Handbook of Heat Transfer . 4 k red = r$diationIc~oA~p~o~nent = ( T3 ~ .T2) t/(T 3-T2 ) f t.= fraction of thernal energy deposited within liner-f2 = fraction of thermal energy deposited in sleeve The temperature difference across the aluminum sleeve is given by: T4 -T3 = (fi +f 2 ) ( 0 / 2trk3 L> in r3 r4
/
Heat deposited in the sleeve is conservatively assumed.to be deposited at the inner surface. Thefthermal-conductivity is that~of' aluminum, from-Haggbggh_gf_Hgat_Itsgsigg, as cited above. -. The temperature difference across the annular gap between the aluminus sleeve-and the liner (T S-T4 ) is calculated in the- same way, outlined above, as for [ L -the gap between the sleeve and the cask inner shell, except that f2 is. omitted. i I j-y w y ,-w 'l-<.e - w- . + . - , , . - , - - _
ENCLOSURE 3B, Rev.0 Page 3 of 15 The temperature difference from the centerline of the liner to the liner outer surface is given by: T6-T5 = q r3 2 /4k5 where: q r5 L*fl 0 L = height,of source k5 is based on series heat conduction through layers of metal (aluminum) and gas (helium), such that: 1/k$= (vim /k,+ vi g/kg ) vi,, vig = volume fractions of metal and gas k,k m g = thermal conductivities of metal and gas, where the letter is conservatively evaluated at 1 atmosphere In supplementary calculations, the heat transfer within the liner uas slightly refined by assuming that the slugs are in four concentric rings, with an everage gap of C.35" between each ring. Temperature difference across these gaps were calculated by: T=Qt/kA where: Q varies from ring to ring, based on uniform heat deposition k = thermal conductivity of heliua (2 times the value at 1 ata. from Handboek_9 f _Usst_Itanefst) A = 1ID L D = average diameter of gap . The resulting temperature differences are conservatively high because both convection and radiation, within the liner, have been neglected. E!!Mita The printouts from two computer runs of RADXFR are given in Appendix B. The first is for the heat load of 6566. watts (QR) used by General Electric in its calculations. The second is for 6500 watts. From the second run, the maximum temperature in the liner is 5600F and the liner surface temperature is
~
3800F. The supplementary hand calculations resulted in temperature differences across the gas-filled gaps and target slug temperatures _as follows: Ring No. Gap T Slug Temperature 1 470F 4270F 2 31 458 3 22 480 4 11 491 i These values conservatively neglect both convection and radiation. 8.
9 CNCLOSURE 3B, Rev.0 page 4 of 13
-The internal pressure at these conditiens is obtained as follows. The fill-pressure (per Enclosure 2) la 14.7 + 10' x .43 + 3 = 22 psia at oOOF (5400R). The absolute pressure is directly proportional to the absolute temperature. At an average temperature of 4600F (10000R) in the liner, the pressure'is 41 psia, or'26 psig.
\
e 0 e
ENCLOSURE-3B, Rev.C Page 5 of IT' F_ _19 .u. r e.1
, em., e9 4e 9& 9 8841 ' WB'le >
4 4 4weee
.m . b
& ..HW9 9 0
- 4 M M.6
+ ee w
~
s
\
+-- e
.8 Ow 3
i m 9
- es 1 9
)
W4 E e
.' /
[N T
-. ., ..~.
es.,
, s . . . .. . --
, . . .. . . .. ) ,
- 3. .
. e , , , ,, . e e * * * .
- e -. we e e..m
, ,. =**= . . g e...e , ,
5e 4 O. .._ .. . . . . . . . .-- ...
- q
. t
, ,. . , , -e + + iw .e a e+. a.-.s e+* en e e
# 4
...........-...,_...._J
..:! CLOSURE 3B, Rev.0 Page 6 of 15 E19Fre_2 A ( ) (H c Mt.
g.i get
" EMF Wat.
4 coureurs - L (s) 9 @ G G . 1 l l 1 I i , 6 1 54 5 L I rodd( Wodes 5 9 e % G
- 9 s
. . _ _ _ _ _ _ _ _ _ . _ _ _______ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ ___ ___.__ _ _ . _ _ _ . __ 'I
4 r..: CLOSURE 33 Rev.; Page 7 of 1$ 6EEEgIK_6 100 REM PROGRAM RADXFR 110 REM CALCULATES STEADY STATE TEMPS IN CYLINDRICAL SOURCE & SHIELDING 120 CLEAR 130 DCFINT I,J,M,N 140 DIM M (6) , R (5) , T (6) , A (6) , B (6) , C (6) , AV (2) , a :/ (2) , CV (2) , WM (2) , F (2) 150 REM READ CONSTANTS FOR THERMAL CONDUCTIVITY FITS 160 REM 1= AIR; 2= HELIUM; 3= LEAD; 4= ALUMINUM; 5= BRASS; 6=STLSS STEEL 170 FOR I=1 TO 6 180 READ A (I) , B ( I) , C (I) 190 DATA .0043 0036,0. 0274,.020,0,20.3, .903, .017 200 DATA 117.. 5,1.5,58.87,18.2,-3.067,9.4,.368, 022 d10 NEXT I 220 REM READ CONSTANTS FOR VISCCSITY FITS 230-FOR I=1 TO 2 240 READ AV (I) , BV (I) , CV (I) 250 DATA 27.9,59.0,-2.2,51.0,54.2.-1.6 260 NEXT I 270 WM(1)=28.96 : WM(2)=4!
- 280 PRINT " INPUT TITLE AND DATE" 296 INPUT TITDAT$
300 PRINT " INPUT RADII (5 VALUES), INCHES" 310 INPUT R (1), R (2), R (3), R (4), R (5) 320 PRINT " INPUT SOURCE HEIGHT, INCHES" 330 INPUT H - 340 PRINT " INPUT MATERIAL INDEX FOR CASK" 350 PRINT "1= AIR, 2=HE, 3=PB, 4=AL, 5= BRASS, 6=SS" 360 INPUT M(1) 37C PRINT " INPUT MATERIAL INDEX FOR OUTER GAP" 360 INPUT M(2) 390 IF R(4)=R(3) THEN 440 400 PRINT " INPUT MATERIAL INDEX FOR SHIELD RING" 410 INDUT M(3) 420 PRINT " INPUT. MATERIAL INDEX FOR INNER GAP" 430 INPUT M(4) 440 PRINT " INPUT MATERIAL-INDICES FOR SOURCE: METAL, GAS" A50 INPUT M(5),M(6) 460 PRINT " INPUT VOLUME FRACTIONS OF SOURCE MTLS: METAL, GAS" a70 INPUT VF1,VF2 480 PRINT " INPUT TAMB,DTR" 490 INPUT TAMB,DTR 500 PRINT "INOUT O,GR" Sim INPUT Q,OR 520 PRINT " INPUT HEAT DEPOSITION DISTR; FACTORS: SOURCE - F (1) , RING - F(2)" 530 INPUT F ( 1) , F (2) .
+
ENCLOSURE 3B, Rev.; Page 8 of ~3
' 540 LPRINT TITDAT$
. 559 LPRINT ~
560 LPRINT " RADII & SOURCE HEIGHT (INC-ES)" 570 LPRINT R (1), R (2), R (3), R (4), R (5) , H SGS LPRINT 590 LPRINT " MATERIAL INDICES" 600 LPRINT M (1), M (2) , M (3) , M (4) , M (5) , M (6) 610 LPRINT GEO LPRINT " VOLUME FRACTIONS OF SOURCE MTLS: METAL, GAS" . 630 LPRINT VF1.VF2 _~ 640 LPRINT 650 LPRINT 'D","F(1)","F(2)" 660 LPRINT Q, F (1) , F (2) 670 LPRINT 680 LPRINT "TAMB=" TAMB 690 L=L/12! 700 FOR I=1 TO 5 710 R ( I) =R ( I) /12 ! 720 NEXT I 730 PI=3.1416 740 REM CALCULATE DT FOR OVERPACK 750 DT=DTR*0/QR 760 T(1)=TAMB+DT 770 LPRINT "T(1)=" T(1) 780 REM CALCULATE DT ACROSS CASK 790 J=M(1) 800 N=0 ~ 810 TAV= (T ( 1 )-32 ! ) /1. 8 _ 820 N=N+1 830 K=A (J) +B (J) * (TAV/100 ! ) +C (J) * (TAV/100 ! ) ^2 840 DT=(Q/H)* LOG (R(1)/R(2))/(2!*PI*K) 650 TAV=(T(1)+.5*DT-32!)/1.S . 860 IF N (3 THEN 820 870 T (2) =T (1) +DT 880 LPRINT "T(2)=" T(2) 890 REM CALCULATE-DT ACROSS OUTF.R GAP 900 J=M(2) 910 N=0 920 T (3) =T (2) +100 !
-930 N=N+1 940 TAV= (T (2) +T (3)-G4 ! ) / 2. 6+273 !
950 TABS = (T (2) +T (3) ) /2 ! +460 ! 960 KC=A ( J) +B (J ) * (TAV/100 ! ) 970 V=AV (J) +SV (J ) * (TAV/100 ! ) +CV (J) * (T AV/100 ! ) ^2 ! 980 VN=V*6.72E-08*1545!* TABS /(14.7*144!*WM(J)) i 4 0 9 L____ . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ _ _ . _ _ _ _ _
ENCLOSURE 3B,-Rev.0 Page 9 of il 3 950 L=R(2)-R(3)- 1000 GR=32.2*L^3*(T(3)-T(2))~/(VN^2* TABS) 1010 IF GR(20000! THEN 1070 1020 IF GR)200000! -THEN 1050 1030 KCV=KC*.18*GR^.25/(H/L)^.11 1040 GOTO 1110 1050 hCV=KC*.065*GR^.333/(H/L)^.11 1060 GOTO 1110 1070 Y= LOG (GR) *. 4343 1080 X=.04+.05*(Y-3.3)^2/ LOG (H/L) : IF Y(3.3 THEN X=.04 A100 KCV=KC+10!^X a 110 SUMT= (T ( 2) +460 ! ) ^3+ (T (2) +460 ! ) ^2* (T (3) +460 ! ) + (T (2) +460 ! ) * (T ( 3) +460 ! ) ^2 1120 SUMT=SUMT+(T(3)+460!)^3 1130 KR=1.714E-10*SUMT*(R(2)-R(3)) 1140 K=KCV+KR 1130 DT= (F (1) +F (2) ) * (Q/H)
- LOG (R (2) / R (3) ) / (2 ! *PI *K) 1160 T (3) = (T (3) +T (2) +DT) /2 !
-117c IF N(5 THEN 930 1180 T (3) =T (2) +DT -1190 LPRINT "T(3)=" T(3) 1200 REM CALCULATE DT ACROSS SHIELD RING 1210 TEMP =R(4)-R(5) '1220 IF TEMP) . 001 THEN 1250 1230 T(4)=T(3) : T (5) =T (4) ,
1240 GOTO 1660-1250 J=M(3) 1260 N=0 1870-TAV=(T(3)-32!)/1.8 1280 N=N+1 1290 K=A (J) +B ( J ) * (TAV /100 ! ) +C (J ) * (TAV/100 ! ) ^2 ' 1300 DT= (F (1) +F (2) ) * (Q/H)
- LOG (R (3) / R (4) ) / (2! *PI+K) 1310 TAV=(T(3)+.5*DT-32!)/1,8 ,
1320 IF N(3 THEN 1280 1330 T(4)=T(3)+DT 1340 LPRINT "T(4).=" T(4) 1350 REM CALCULATE DT ACROSS INNER GAD 1360 J=M(4) 1370 N=0 1380 T(5)=T(4)+100! 1390 N=N+1 1400 TAV=(T(4)+T(5)-64!)/3.6+273! 1410 TABS = (T (4 ) +T (5) ) /2 ! +460 ! 1420 KC=A(J)+B(J)*TAV/100! 1430 V=AV (J) +BV (J) + (TAV/100 ? ) +CV (J) + (TAV/100 ! ) ^2 1440 VN=V*6. 72E-08*1545 !
- TABS / (14. 7* 144 ! *WM ('J ) )
14501L=P(4)-R(5) _ t t
ENCLOSURE 3B, Rev.0 Page 10 of 3 1469 GR=32.2*L^3*(T(5)-T(4))/(VN^2* TABS) - 1470 IF.GR(20000!-THEN-1530 1480 IF GR) 200000! THEN 1510 1490.KCV=KC*.18*GR^.25/(H/L)^.11 1500 GOTO 1560 1310 KCV=KC*.065*3R^.333/(H PRINT L)^.11 1520 GOTO 1560 1530 Y= LOG (GR)*.4343 1540 X=. 04+. 05* ( Y-3. 3) ^2/ LOG (H/L) : IF Y (3. 3 THEN X=. 04 1550 KCV=KC*10!^X 1560 SUMT= (T (4) +460 ! ) ^3+ (T (4) +460 ! ) ^2* (T (5) +460 ! ) + (T (4) +460 ! ) * (T (5) +460 ! ) ^2 1570 SUMT=SUMT+(T(5)+460!)^3 1580 KR=1.714E-10*SUMT*(R(4)-R(5)) 1590 K=KCV+KR 1600 DT=F (1) * (G/H)
- LOG ( R (4) / R (5) ) / (2 ! *PI*K) 1610 Y (5) = (T (5) +T (4) +DT)-/2 !
1620 IF N (5 THEN 1390 1630 T (5) =T ( 4) +DT 1640 LPRINT "T(5)=" T(5) I 1650-REM CALCULATE DT WITHIN SOURCE 1660 I=M(5)- 1678 J=M(6)
-1680 N=0 1690 T (6) =T (5) +200 !
1700 N=N+1 1719 TAV=(T(5)+T(6)-64!)/3.6 1720 K 1= A (I) +B (I ) * (T AV/100 ! ) +C ( I) + (T AV/100 ! ) ^2 1730 TAV=TAV+273! 1740 K2=A(J)+B(J)*(TAV/100!) 1750 TEMP =(VF1/Ki+VF2/K2) i 1760 DT=F ( 1 ) * (Q/H)
- TEMP / (4 ! *PI )
1770 T(6)=T(5)+DT
- 1780 .IF N (4 THEN 1700 1790 LPRINT "T(6)=" T(6) 1600 LPRINT 1810 LPRINT " CALC'ULATION COMPLETE" 1820 END 1
a
ENCLOSURE 3B, Rev.O Page 11 of 3 deest 191H_B GE700 G 6556 WATTS, SR~ TARGETS RADII & SOURCE HEIGHT (INCHES) 5.375 32 1a.375 7. 5 7.44 5.435 J.ATERIAt ;NDICES 4 1 4 2 3 1 VOLUME FRACTIONS OF SOURCE MTLS: NETAL, GAS
.5 .5 O F (1) F(2) ,
22410 .85 .07 TAMB= 60 T(1)= 300 T(2)= 305.3172 T(3)= 340.2648 -g- -T(4)= 340.5282 - T (5) = 383.1472 T(6)= 564.043 CALCULATION COMPLETE GE700 8 6500 WATTS, SR TARGETS RADII & SOURCE HEIG'-iT (INCHSS) - 32 180375 7. 5 7.44 .5.435 5.375 i
"!ATERIAL INDICES -
2 4 1 4 3 1 VOLUME FRACTIONS OF SOURCE MTLS: METAL, GAS
.5 .5 O F(1) F(2) ,
22185 .85 .07 TAMB= 80 T (1) u - 297. 7912 T(2)=-303.0514 T(3)= 337.7473 , T(4)= 338.0082 T(5)= 380.331 - T(6)= 559.9371 , COLCULATION COMPLETE . n-
+
i SS 3 ' FREE CONVECTION IN EN' CLOSED FLANE CAS LAYEns $33 531 FRED. CONVECTION EXPERIMENTS AND CORRELATION 25-3 [ - Further, from the theory of similarity, for air and hrobably n!so for any ' Weise calculated individual coef5cients of heat transfer from j the tem-other diatomic gases, perature drop, closo to the pate, to check the mean cochent as found yy i (Ny.)t - + (yo,)a, , - (25-21) by direct measurement. 25-3. Free Convection in Enclosed Plane Cas Layers where slightly modified Nusselt and Grashof numbers are defined by The heat transmission by free convection in horizontal and vertical ' g, 3 3, (Ns.)r - --- (2b22) plane air layers has been measured by different investigators; the most # - #2 k 2 k 7 elaborate experiments seem to be those of Mull and Reiher [1930]. and As a measure for the heat exchange in a gas layer they used an equivalent h L8 (Na,)t (ft - r3) (2FJ3) thermal conductivity, k,. This includes the eficct of convection and . 7 i radiation and is defined by From Eqs. 25-21 and 22 k, = k, + kr (25-19) k, J H TF
, -- (25-21) where k, is itself an equivalent thermal conductivity, including th'e effect
~
J"+ : *(No,)L, i of conduction and convection, and k,is another equivalent conductivity / Obviously superseding the effect of radiation. k, when (No,)t.-* O (25-25) Whereas k, can be very simply calculated from Stefan-Boltzmarm's j 7~1 law or the corresponding relations for gray or metallic radiators, the determination of k, requires special experiments under varying condi- { Cons,idering, now, first horizontal Icyers (subscript h), the experiments t Mull and Reiher used air layers between two plane surfaces, with heat flow upward showed that k,,a/k is independent of H and W. tions. Different sections were formed by thin Then, for reasons <f similitude, it will also be independent of lf/L and 40 inJ long andWin, wide. .
~
strips of balsa wood as boundaries, so that the influence of length and : W/L. IIence Eq. 25-21 simplifics to width could be studied on surfaces of 30 to 900 sq in. Air layers of ' g
= +(No,)a (2",-20) seven difierent thicknesses from M to 7M in, wero employed. An elec- "
trical henter composed of five separate sections was used with a secondary [ heating plato at the rear side and a ring heater at the edges, both insu- Mull and Reiher represented their experiments by plotting k,dk versus lated from the main heater and held at the same temperature. Thus the log No, and obtained a smooth curve in the experimental. range of heat flow was restricted to the front side, from where it crossed the air (Na,)t = 2100 to 8,800,000. Jakob [1940], however, representing these results ,m bilogarithmic coordinates, has shown that there is at Icast one f layer under consideration and afterward a cork plate which served as an i l' , auxilia?y heat-flow meter. . The whole plate system was bodded in a bend m the curve, in analogy to other cases of free convection. Figure II wc!!-insulating material and was turnable in a metal framo so that the 25-G reveals that, in analogy to the cases of a heated surface facing air layer could be brought into horizontal, vertical, or oblique position. 4 upward and a vertical surface at high Grashof numbers' g { The rato of heat flow by convcetion between a warmer surface (sub. ' S M j script 1) and a cooler, surface (subscript 2) can be expressed by ~ = 0.0GS(No,)t (25-27) - < A k, or g," = L (i - t ) 3 f25-20) .l This is valid from Nc, = 400,000 upward.
- 7. - kg (f - ts) t In the range from about 10,000 to 400,000, on the other hand' as for
,1 ~
vertical surfaces in a medium range of Grashof numbem' F
)
whero L = the thickness of the gas layer, . k,.4 p A - If.W .- tho area of this layer, If - tho height of the layer, when used in vertical guith>n, andt i [ ~il- - 0.ltisNo,M (n) % W - the width of the layer. f gg. 1
.5 -
25-3 , 2'e 3 FREE CONVEcr10N IN ENCLOSED PIANC CAS LAYEn3 537 l L30 Ft.EE-CONVECTION EXPERIMENTS AND COPJtELATION , W. Mull and Reiher. in one of their tests, kept II/L and 7 tan ! For very email Crashof numbers leg k,/k approaches zero according to l but reduced W/L from 25.7 to 12.S, i.e., by 50c/c. IIowever, th term , Eq. 25-25. This is indicated by the dotted line in FI;. 25-0. (k,,,/k).(II/L) changed only by 1.3%. IIence, omitting W/L as an The meaning of Eq. 25-27, obv2ously, ie that, above a certm,n thick-
, dependent variable in Eq. 25-24, the corresponding equation for verti-m ness L, the cocDic2cnt of heat transfer by ccavection does not change caI air layers becomes any rnore, so that there should be no difference between the heat transfcr k,,, y-through the layer and that from a single horize-tal plato facing upward. (N or)t, (25-20)
T"+ , U 7 ' As in the case of horizontal air layers, k,.,/k decreases with Nc, and
;/ approaches k,/h < 1 when No, approaches zero. IIence, at this limit,'
.r 0tsuved by McIl ofw! M"_ ll / k,,, H H
-- - sinighti:ne Ltow
.. " I Aa. 25 27 A
.( k L L (25-30)
~ :
0.8 - - - _ g f/ 4- - For very largo distances, the problem also simplifies because of the i i 7 , j vanish ng o the frictional resistance between two parallel vertical sur-
*6 f faces, very distant from cach other. Obviously ,
a __. I-, ' 3 f -f - f.,-fa . S / and 1,.." - h(f - t,,,) - h(t, - (2) j P i - f i
' O.2 / or
/ g .." - f h(t - (2) (25-31) where h is the coef!icient of heat transfer for a single vertical surface, 0, - [ 5 6 7 which may be found fro;n Eq. 25-10 or 11.
a cg (E),. From Eqs. 25-20 and 31 i Fra. 3M). Dime ionless representation.of heat transfer through borhontal air l layers by free convection. AL k. m II h II 1 h II - l k,,, - - or -.-L (25-32) 2 k L k 2 2 k L Thia may be checked by etJeulating an example. According to Eqs. 25-22 and 27, IIence, k,., becomes proportional to L for very thick air layers,.and I N the resistance ag dnst thermal convection, L/(k,..d) approaches a lirrdt. ed - 0.008k[#9 (s ('1 - '2)H The resistance against heat transfer by radiation is also constant when the surface temperatures and emissivities remain unvaried. Therefore, Q n Forti I f2 - 50 C and an atmospheric pressure of 730 mm Hg, Mu1i E the insulating power of air layers cannot be inercased infinitely by increas-and Reiher used pg/r8 - 0.110(10') m-8 C-1 and k - 23.0(10 , g .
- kcal hr-1 m-1 C-1 Employing these values and convertmg to Briti gg g g g g, g ,
technical' units, ' separating sheets or other solid 6odies. The resistances against convco-9'A" - 0.06S(23.0)10-8(0.073)0.110: 5 8 t 2 (10 )0.3018(1.8)(f -sions. tion and radiation increase almost proportionally to the number of divi-f )" Under such conditions as exist in buildings the heat resistanco has
]g F'
a maximum for vertical air loyers of about 2 in. thickness, whereas hori- '
; - 0.2770" ,
r ntallayers of 2 to 8 in. thickness have about the same resistance. o in excel ent agreement with Eq. 25-14. , For a general representation Muh and Reiher plotted (k.../h).(If/Lt -w For drrical air layers (subscript v) the conditions are less simple than for horizontal layern, becanne k,,,/h will not be independent of H and as measured, vernua log A u, und built up 27 curves with H/L na turam- g
! : i i
. f
. s 4.5k *
/ of Y ' - fuMcfunc~ (ref: Ett/C. 5 , fg4) codseq&ces of go v pgor= o psto l 66~ UAS A N /.essED G
- b is). Ber. c>>> T He' pac 7etrivE' JAcMT I' Catar: 4db Hss
.Sricara 746- 7eso.e.r.s 7a DE 4ccErrABLE. /7" is uetesvyty X l 1
Sv4 < oAre M t e rrte t. files Ev'eur ckArts q- loa;>W4.s on l Linet t;;1Mnr2 THnu 77tase Tian A 3o Fr; M r. l l 7~v4 e w % tlE, o s4ASvHE THE PA cx+1e t+eners sibe-Dcua' I 1 QN '77f5 . STEEL B&/. WE Wit t. A*Jott Y&E 71/E De~Ft.ec7rv4 ot= _. i
*THe curcic facrecrWe ,3rfeu- UHi3 et / fr Lo'+-D , "a teut n e- 7h;1' ,
\
WOLTAd7~ L-MfY o Ab%tC t'iled, T /Wrd WHW//e1 -Tife 572n*taf biSrbice FKoM- A 40" 3 rop coutp Be' Sucif 4s 70 - chose A t G-409N4 id Excess of 2-7 8 g ( n f: 4WCt 3 , f Q .. VSE CAN s.b. 37 1%M 7ABLE X of $7H - Eborrail aF posa , sinun u suess era s m ,a _ (ser A m cas a rr.). j .-. - I- A SSUPS 71M-T A-ffEL7ED TbSTro/J 01= 5/feu- 25 A 30' flC., lh SXercWeh *Be=Lo u): l el W b l
&,-, Pflyx 7= es t a
- $'I -IMPM r forar7 *
"'lof vL!
~
Assume *-/h = 1- J . . R- 0.18o5 ^ W = ~bf Soo $bs f= Y <0D = 5 5/.5*=l5.5* I >. fz.
u ~- ~- - ., 1 lof 4 2 = Bo e10 0 14),s' 7s' Iz. S t e n 4w 0.(o r > [asic,e skul MoiLutr) Mk
' '0 ' #'") l'W =- o.it,$ Gst; .11) 5> ( %nG) (. G-Q '
i Olesy' 46 set.f77ad : r $ : E*/ashe 7- ' 74,y '
= Wy_ - (asroo)(./9) -
~l- 7- (t z.) M .
kedenc. L%)eRriy 17.ca 40 ' 2@f. i '
= :-
//?, 334 -% _ /f.
IL ... r GCCHEf. Ttffsd 0./b3 ',' 7W6' SYDl'f/Af 7)1IThdle /OK .4 Vami ) k . eveu au a,n m . a,o-va, m y- a u ,a; xx.a; saura & 77tc H&r. G~ (.o AhrUC, - Welt. SE 5:<,dt fiCoM /) fe ' beo r*, -
- ~s mg. e - -- ,,
um , s c/h1 DE' idregccb us.Twosir . c6e coumnr 7w's su 4/bM:. I N .
$NflU$lO A &j 0 /l/[$ hh OTlftfL NTl TUW Oh W ?Nf(.
o
-(t.e., newh n O o w , oe u voe). ,
C~/Vt t.0h vn- " s-. 3 el f TAatz X.-Fonwet.As rom T!.AT hATCO --(COnlinufd) u.avm-.4to,.Laa ca .. yarsala te et,s. sul daAmh y-E11ig4ical. end 4 g..
*t3
*t u,. s.,,.,,d
.,l::' ~
uis.e,).-- = ,,='-e".no. _ u-) 1::: - u...nia-l'a+(a...j a,,- - u r san, u. u. ,) m u.. C "t e_g: a a, or.t.) . _ ,s,[Im + o a & + m - m.) . u. s us. , - gm -ms.q,. . . ;)
- .r - o 4 (Aps.naamate foradas by laterpeintwo bet =wa caers of ensular plate and la&setely long serrwe stro M. 4, ;q :
Eds,Ea.: to
- 38. Undare land etw (Al alge) i 2 (TA e)
- a. = 2WJ + 2 8 + ana) (Ssma 6) a = 24%3 + 2.8 + 3.41 = Mas e g
+U ~ *
" ' ~ ---- 'I (At sentar) a. = ~463 + 2 8 t 3.*)n n = 4M3 + 2.8 + 3.sare Mas y = 16ei'IP6 + 4.s + 6a*) g (Farm.das due to Premtt, M. O use saed %:3 -
cn," at o.assr) a = " log - 0317. - 0370 Ma,p= - p C4 raiar n e af radsus H1 re (Approsimmte formulas by lat.orpolatlee 't=twe,s et.as of cireular plate and inar.itely lang narrow stria Itaf. 6. e = 035 tar was y) Square, salid
~ h
. aa..
~
E.fa, no.wi.d at e (D) O ni and telow. ( >' wae.C.orners
, s .~
" va=,l::'
e - aie..
- = 5 -+"au.e u . *"y ' - " s cr.,m . d.e o tre < u. . ._ _ - . = . . _ .
r ,. .
,t... t ca. r.
.] u-, - """;;;'-"
bead dewel a E;;;ae'-da at e r) u.e = =/3{(.+ n w p g maar area of en.hus ,, et mapported below Os ends (earows free se .t - ru.)
"",f.,,
( At center. in d. agonal section) e = -- Masy = # (,
, OJ) , .. .
ai s o. % a.em) e - ='" * = um. e u ,. ... ,t. m .. eaty (ownere ira to vue)
- 33. Uniform toad ova Same na Case 31' small conceatne etr-eular ares ed red.us
,, g All edges 6smi
- 34. CaJarm load etw essas surf ace (18 esatar of each 4 , =8=
s! s) a. Mas e 030a ( Mas y - ogg (At essaar) e=- (M. 4). s (othw t=mulu w.at em mt.at. !.e. by Ti~ u- u.7. e - 03) $; 3W r a1 0 062tiat - lWee s.]
- 15. UmJorm k=1 vew k su soncensrw ear. '" mima edar enin el radius **
(A8 8'*W') M*8 8 " 2MI"
- III'8 ~M (R,f. 3) Cc Rectasavtar sobd
, . . e . 1..
9 - S Alf edenesurvorted
- 34. Umkirm tuad over e68 wee ) i. Ig3 entire surface (At centu) lias a = = = A7 use y - a g t.4 t.8 4 5 =
t I .2 3.6 3 3 {
.~Y a 0.2174 0 3762 0.4(30 0 5t70 0 St.M 0 6123 0 7134 0.7460 0.7474 0.250 0 0444 0 0618 0 0"70 e c906 0 tot? 0.1110 0 1335 e teto 0_34t7 0 1471 (Esf.11)
All afaes eu ,rerted
- =ere,2: (. ee_, _e,g[..ug.,-,.] . -
. o e
m a .e ,.d. . -* *
- h Many=ep ,
~
t i2 1.8 1.8 1 { 1. 4 no. 0 u,, 0m 0 t2, 0 On 0 042
~ 25G FORRIULAS F0ft STRESS AND STRAIN (Cn A r.10 [ FLA T PLATES 257
- 2. Micnet.L. J. II.: The Flexure of Circular Plates, Proc. Jfath. Soc. 23. Woinowsky-Krieger, S.: Berechnung ' der ringsum frei aufliegenden London, p. 223,1901. .
gleichecitigen Dreiecksplatte. Ing.-Archie, Vol 4, p. 254,19",3.
- 3. Monorr, A.:" Strength of Materials," Longmans, Green & Company, 24. JzNszN, V. P.: Analysis of Skew Slabs, Eng. Erp. Sta. Univ. lit, ButL 1919 332,1941.
- 4. TruosurNuo, S.: Ober die Biegung der allacitig unteestotzten reeh- 25. Evans, T. IL: Tables of Momena and Deflections for a Rectangular teckigen Platte unter Wirkung einer Einzellast, Der Bauingenieur, Plate Fired at All Edges and Carrying a Uniformly Distributed Load, Vol. 3, Jan. 31,1922. Am. Soc. If ech. Eng., Jour. Appl Af ech., Vol. 6, No.1, March,1939.
- 5. Passcorr, J.: " App!!cd ElaAielty," Longrnana, Green & Company, 2G. Vot No, D.: Clamped Rectangular Plates with a Central Concentrated 1924. Load, A m. Soc. h!cch. Eng., Paper A-114, Jot.r. Appl Mech., Vcl. G,
- 6. N ADAt, A.: Uber die Spannungsverteilung in einer durch eine Einzel- Na. 3,1939.
kraft belasteten rechteckigen Platte, Der Bauingenieur, Vol. 2, Jan.15, 27 At.ucN, J. O., nr.d A. LA5Eo:The Uniform-section Dise Spring, Trans. 1921. Am. Soc. I d .Eng., Vol 58, p. 305,1936.
- 7. TsuosaeNxo, S., and J. M. Lessetta:" Applied Eluticity," Westing- 28. Outry, E. G.: D.:flections and Momente of a Reetangular Plate Ciamped house Technical Night School Pre-s.1925. on all Edges and under Ilydrostatic Pressure, Am Soc. Afech. Eng.,
- 8. WoJTA6EAx, L A.: Stress and Deflection of Rectangular Plates, Am. Jour. Appl Alcch., Vol 14, No. 4, December,1947.
Soc. Mech. Eng. Paper A-71, Jour. Appt 2fech., Vol. 3, No. 2,1936. 29. STzvzNs, IL IL: Behavior of Circular Membrancs Stretched above the
- 9. WrertRO AAnD, IL M., and A. SLATER: Moments and Stresse. in Slabs, Elastio Limit by Air Pressure, Exp. Stress Analysis, Vol II, No.1 Proc. Am. Concrete Inst., Vol. 17,1921. 1044.
,10. Want., A. M.: Strength of Semicircular Plates and Rings under Uniform i 30. Lzvy, S.: Bending of Rectangular Plates with Large Deflections, Nat.
External Pressure, Trans. Am. Soc. Afech. Eng., Vol. 54, No. 23,1932. Adv. Comm. Aeron., Tech. Note 846,1942.
- 11. N a ru t, A.: Die FormEnderungen und die Spannungen von durch- i 31. Levy, S.: Square Plate with Clamped Edges under Normal Pressure laufenden Platten, Der Bauincenieur, Vol. 5, p.102,1924. Producing Large Dcflections, Nat. Adv. Comm. Arran., Tech. Note S47,
- 12. NADAr, A.:"Elastische Platten," Berlin,1025. 1942.
- 13. Hott., D. L.: Analysis of Thin Rectangular Plates Supported on Oppo- 32. Lrvi, S., and S. GaEENM AN: Bending with Large Deflection of a site Edges, Iotra Eng. Exp. Sta., Joica State Cottege, Bult 120,1936. Clamped Rectangular Plate with Length-width Ratio of 1.5 under
- 14. WESTEHoAARD, Il M. 8 tresses in Concrete Pavements Computed by Normal Pressure, Nat. A de. Comm. Aeron., Tech. Note 853,1942.
Thiorctical Analysis, Public Roads, U.S. Dept. of Agriculture, Bureau of 33. Cut-Tzu WANG: Nonlinear Large Def}cClion Boundary-value Problem. Public Roads, Vol 7, No. 2,192G. cf Itectangular P:stes, Nat. Adc. Comm. Arron., Tech. Note 1425,1918.
- 15. TsuosurNxo,8.:" Vibration Problems in Engineering," p. 319, D. Van 34. Cut-Tzu WANO: Benmng of Rectangular Plates with Large'Dcilections, Nostrand Company, Int,1928. Nat. Adv. Comm. A cron., Tech. Note 1462,1948.
- 16. WAy, S.: Bending of Circular Plates with Large Deflection, Trans. Am. 35. RAMBERG, W., A. E. McPurasoN, and S. Lnvr: Normal Pressure Tc.its So . Afech.-Eng., Vol 56, No. 8,1934 (see also discussion by E. O. of Rectangular Plates, Nat. Adv. Comm. Aeron., Rept. 748,1942.
- 33. CoNWAT, II. D.* The Bending of Symmetrically Loaded Circular Plates Waters).
- 17. Srvnu, R. O.c and R. L. Moont: The Behavior of Itectangular Plates of Variable Thickness, Am. Soc. Mech. Eng., Jour. Appt Jtech., Vol 15 under Concentrated Load, Am. Soc. Afech. Eng., Paper A-75, Jour. No.1, March,1948.
Appl Mech., Vol. 4, No. 2,1937. 37. Rzi&SM ANN, IIERBEnt: Bending of Cle.mped Wedge Plates, Am. Soc.
- 18. IlENCKY,11.:"Uber den Spannungszustand in kreisrunder Platten mit Mech. Eng., Jour. A ppL Mech., Vol. 20, March,1953.
verschwindender Biegungsstei6gkeit," Zeits. Math. Phys., Vol. 63, i 38. BA$sAu, W. A., and R. IL DAwoco: Ecnding of an Elastically Re-strained Circular Plate under Normal Leading on a Secar, Am. Soc.
- p. 311,1915.
- 19. WAnt, A. M.: Stresses and Deflections in Flat Circular Plates with Mech. Eng., Jour. Appt Mech., Vol. 25, No.1, March,1953.
Central Holes, Trans. A m. Soc. 3fech. Eng., Paper APM.52 3, Vol. 52(1), 39. BrasAu, W. A., and M. Nassir: Stresses and Deffections in Circular p.29,1930. Plate loaded over a Segment, Am. Soc. Afech. Eng., Jour. Appt Jfech.,
- 20. FLttoor, W.: Kreisplatten mit linear veranderlichen Belastungen, Vol. 20, No.1, March,1959.
Bauingenieur, Vol.10, No.13, p. 221,1929. 40. JttnNev, W. IL: Displacerhents and Stresses of a Laterally Loaded
- -Y 21. TruosurNxo, S., and S. Wo:NOW8ay-KRIEGER:" Theory of Platei and Semicircular Plate with Clatnped Edges, Am. Soc. Mech. Eng., Jour.
Shells," 2nd e<8., McGraw-liill Book Company,1950. Appl Mech., Vol. 26, No. 2, June 1959.
- 22. REld8MER, ]L. Uber die unsymmetriSche Biegung dQnner NtelBring* 4$. CoNWAY, H. D.: Bending of Reetangular Plates Subjected to a Unt-platte, Ing.-Archie, Vol.1, p. 72,1929. formly Distributed Lateral Ioad and to Teneile or Compressive Forces C
. M
.4
. c-n u.o>urc.c .:w I of /Y . Bgccuo Ceuuumoas m B ictosoze 3 4
'7 W Ft M GT I a +d4WSo Pef- AsMr %od E , rf//eJD1xI, fULE5 feA FUHIGE! Wrrd 7tdf 7WF G6ME78 <31r t tyt. Dxes itz'.e frvr2 sd ASHE ' BEtzrou dLL, A7YEdbtX 37 fv2 CLASS l'F F-LAUfet.
fyayert?Y af FLAate- DIsr+nou is fez tid -'f7 oF ASME .Etu) k :- 00751.bE bi6. of );s-ndiE ~ IV.77%* ' As = Tare. clots sectiw& Ms;A of kcr1 (M- bor eF 1Weth} B.b1L D ~ IdsucE 314. of ft.ituGE
- 10.Y2 " .
b- erper-rie csscer seyra$ woarn = VA. /2. . ~.1p'
.b, = basic %;4 ster Mrraf WiDrri = ^1l'2. = . S yy
- C= %r Csute >>A. = i 3. 375 *
.b = 'b iA . of 7e e.r Hetes = . 212."
(q ~ biA. Ar &hster Ecncma = f49ter ob -2b = ti. y.it}.
= **Tsh t L J e u of Hva nr Snku. EMb ~ . / G S
Ja
- 77hccM of )b!B i+r M cx of Ft As4e =j. t % = .552
}[, =- //v6 LOMTH = 3)(. ~ ./i[c "
" = 1 3 11
- ha FAc n / 5 B y - - -
N = O F Cs 8 t e r Wt DTW
=(/2 - M S$)l1. = .S88 ,
')1 = ,Mo. OF 4o t-T3 ~:- / ~2.
R = (.C- 6 )/2. - ), ~ j. )26 *
= =-
-)- Ft M4s ~Tihllhi'C *2. " -
b = '7ihLndat of S s u 73 dhtw t Fusos 11 Arr&cttd = . lir
- fp =
4b 7thttAIE59 = /. [ ' __.-.!/8 = /-Y23 ___ ..__ _ . - _.._, - . .. __. Tify. -= LIS -
%. =. ./vs .
d....=...h?J?.=.587-...-... - - -. - - . . . . . _ - _ . _ . . . . F= ( f /h. /h o.7 rv.:9: Fs' y . VA . 51.1
-f =-
Cy,/3. , L/h. ) .
= 3.yr ,
4: Ry. use -st.G
. L= t-i)lr + . P/d =:'tV 9.c. -. .-
'T -
(k/a) .
~ = l.t 'tl. F9. t/A ~rl.)
0, (gia) =. bs n
\/ r<+:
=
{ t./y,, k/A.) = 37s- Q. uA -n.3 .
cvcwsuur w
' 2 aflIf _
ref.- l=<y. UA -s11 f=-ll[Jels)^=.s4
-b s-
[ Afb) = - 3 o 4-A. Aldntt. CorJbmont bbLTEh Cmone L. H M e t e /tt. P4 M.TtET Wct.. . 3A a set /- exPtkrJeroRY -
- 2. ? cr- L.o A bs .
- Wu,=.7ss C'P 7 + '2.6 5.1+ 4 u P (Sp (D & UA-k
= 4,77/ 145 .
TvL.* /Eb fM- f tt' 3 (fr~ 'TAac #4-991 -fu SS & f 4
- W% =
3.14 6 6 y
= lo 5, o II .L4.s . . . . . . . . . . . . . _ . , ,_
' ~
Tvl yu to, coa (fyn Thus UA -M.) frv SS A U.)
- s. tea vico nca nsw . .. . . . . .
exa 5A U SElf- EtnAHMapy I
- 4. FuWG5 bEDM Bot T Lo9 .' .
._ [ ~
& ofj caddlNons : W. Wu, = W ,79/ .tjs.
& psht %Q : ly: (Am + As$$ _ (a.ss+5.s2)(go,,,,3 _
. t. 2,. . .
.. .: _ . . . .-_ . .. ....~ ... .-.- .. - - . - --
^
=-
. /4 Poo- 44r_
5 FUME noMevrs .. I s Tw ey~ a edehkr .- Ala = M2 + Nr- + H, . ~
. whuu - Np =4 l.w j Mr-= H i j O(* lle,'l4 4 . _. . . _ . . . _ ._;_ ._ - _ . _ _ . . . _ . . . . _ _ , _ . _ . _ _ . . _ -
a
~-
3 4 I& = .787 B*P
= Iz71s* L4s.
}lq . Wm,- Il = 21-77l - IC3 Yo > 7'ITI Lis l+ % . J fr G '- P = /5~3% hi . . . , . . - .
N7- = }+ -b = 2 rrrth [ **- /JD-ptt = /. 3 0 *, ys f. f 0.T]s 'rth: ~ TABLE {}k- CD
= "
~
Aqr (c --G/z_ . 7FI . 47- = (J2.+f, + lic,)/z. > /.13o
. '. Ms= 1s7tr xt%oi- 1
~
16JYo l Oq = TVZ/ * * $NI T, Til - . . rJ"r * ' bl.T" Y'^*'3* 5$ Me - 29,oloo Libt N. . . Tw jasi4- udy : No~ N(N) - -. . . .. ._. .. . i Wk: W = lbk foo tds -
. . . ' . A/o= /o't , 7/7 < /4r -
- 6. F1-bl4e Srksris
.p g, . - . . . . . .
b04an/b>U+t- H118 Sheen : $4= ,_ ,,3 ge,g my smu sg , 0 siWik% [
._ . _ . . _ _ _ ..- L t"_B . .. . .
g . . - ...-.- - , . . . . . . . , . . .
. , . h.=.
( ,,9z},,_ g . =-..d.I79:H, . .
. . .. - _ _=
~ ~ ~ ~ ~ ~^ ~^ '
- o.co&g,
~ ~
sg iGi s>xe%I.s0 +B Ha (/+4rXzPC/o.12.) ~
.Y _ . . 57 L = 6: 2 . - p)(co</r)'TF fo~ = 0.1% ko . .-
z)D.v9 J .. I
,.m-<,. -- .a n . a -e -.,.em? ~,~.-n.- ...n. _ . . , , .
-~...,,,....,. .+ _
- ENC.LO.%uxC .w V 4 /9 Au.nwssur Furace- srteza far: UA-n)
Sn L I. ssp j sg 4 sp j Sr G S.p j "[% 6 S.g ; S +]r & s.p Ar hN4krrrJ(, Cadbo 110:2 (/fo u 2.f,of o L ikt, f.3 j S f = ))joojsi, fj af E2X.L34) sraes 41musw .s. Hwy twen O o in SH .S~~w 'L- kl50 EE W0 . SA /31 /2- /H 72-. 5- 3,bb u .Y3 7 /2-1e e (6H VStt.)h (1 tn Y..T 96&7 27 (5 4 # 5 r)/2. Y, sc.:52. /uoo Ar G4scr fewix, (s.oDs ricas (Ho = /0f;7/7 wlb, f3; Sp : /Uooja ) fi </ m Su g,7ye 2-R 2.<v /.4'- G.oes Sg y,, /t, No %. g<cerin 5~r I.3,19y- /t in I.+ . ( N eSd/2.- i g6c? /( fcu 2o LSit +Sr)/2 Ir767 /lPso , I. 2 - l
- 7. Srtesces Ia 70 P PLMs- (L.ob.) -. .. .. . . ..
i Bl%.T Lo Ab = 10in,Too lb
}
Boi T up .- - ResicrMci o F GkSt.crs ia G, Uo 4 M *"b F- 1I.%,, ~~>
$' d ' .Ct2runihJLW
.- k o.n r"---d zwrve tw.s e w svez . oi= aan<e. cona ra . oi :rrsme.r.: ..
,,oo _ . _ . _ _ _ . . _
$ ~ . _ _
i l i cm,r too - . hate we (zzp) = 2,3w >4 . . . .
' --f o. [,*2. a I
.~ .
&ME (CztJ.5002.VAD06-Y) THA'i* SoLT t04% 15 ItJC.W Bf M M-tJn Tube' . otc . f9fE Lo hb - .- .-- . * .. -.
S' cf ' /f .. t'oge. : Givas rwo cg.ws in+r cea se 0262 M. 7tte- , A6ow s ervArroat: TA9u? x ; ces 2- v5 fser s.rragges copyj ft),
,p . . . - . ~ . . . . . -
Cuc. 2 : 4 t pg1 Ciro d u [ 4 , M .ft u 4 m ,
. load m co n us,e. cas m
-- -- k-2.a. -*l et- r a 'u1 v. i s q .,.st d 0 y1.
. -. . . . . . .w .- . . -
Co.x. 3 : yg CirA ;M. , k wM enA w.* w% load .
<<4I o}- rah'a
,k - u + l Io fMd L1
~~Ihh5' Bolt us' CASE ckW Be ACPAc~sw76 A S *' 7 H E S u t.g 0F 2. Loebop)Q$ 0 f ~pt E '7 Ys4=" 0 F C456 3 :
* 'nf-9 g.br -4 g .
t t k- rt.nr --+l a n.++,- - W y to6,,7co W - -fof,Too TitG Apperm d of P /2 5 ssu W C&,J SS 7-ctf5se>JrEW A S - T He Sun of A CASE 1. l A Ck9t5 3 7YPr LaAbraQ :
--, n.n r - .
p , y. .-...- .. . . ..
-4 soy > - -
W - 2,3co w/ ,. 433 j
- . .- ~71fi L;922 .41VGd Gl Sbef?tC- It/ph *,. At=Eu PA0G/J%tHeh ..-Isl..._ .
\ B4erc" (sw Listwg ff t2113 i) 7s cnt cut-krs- srxesses.
N Patonv'6 3r/2ess /Hkterer TEM o > 47' o//SA. CoAfhe ' 40 e9ap. ceaanstroa Ar Loulen. sugfAce. ^- DEGRMr s74 31 >Ab chns - 71l6 l2cktse. . '7He' ./A AokBCS ; P.L, f2. e.h id PAoCA&M ARE bup M v'k/ t4&es . o r?tme . VAA +Ms . It) 7')f2 fAsGreAn foe c.o es Ah rArroa eF Ro4Rd. Trftr Penot r: orc 711 6- Cep/MSA , ChtCULMio95 $Ac? St }dui/ on.fIcf,.. ..
. -. .e. ae
. . - s. $ e-.,
--~ 4 .
e
=m.m.-. . e gue. s. e, e -
==-.e -=ee- ,..-==see=ams v. me-*.m. -
- a. .
- .Se 4. g. ae d.m.
c^su.osuye: ot) S of JY 8 150t.r* 70f.QUE' . S/C.L . 3 6 Is. Sep - ERPt.AWAga A' . 9 VsB/2 Ario il Ly is A co aseuhrde'LY t!i64 /tcensMrred fog L. G r e M t. Kocxorib +1o rtop bJhGQ 1;G M C P o t;T~ - 4 . Ce/J set vA' -rre.f Lo *J V4wE 7'o d TovEr fscYFocteur~ 0 t= F/i c.rio.o A-r- 7We' 46ner , c=at*De;ba, -.*7Re- _.. 4doov'o 74ces, is o. 2. . T& E' 6>4ttE 7 Cast 2cEstod
! CAD /C /06,(Do $AG. "Tl/6 fdtCnod Lo.4b 15 ~)"]$A
! ' X /0 $, 200 b '2456o l.42, 7~He- Lsh/Ex Ptsis
%.- Eurs WetGH 250 + lfo Abs =- 90 AAt . -. IF. 77/r5 . ..
6371AG nG~?G 4 T 5 A/Yt-tEb 7o" ND /G" JN6- Leb 44 reg 4tt.f , m u m ;is is .- .zuao/no = n.7
- b. b JthA. tJTEG/s77' - $77te77C6L Cl 770 8 Upn -basn W +
1~HE S&tM 'hdC) 1.5 Snowd CW Sneer- .3 9); AI EUT7204 P20'lxJcrs kri6 ' 210/B7 175 .AleA 15 3/. su .. .. loa.p 7perisnarren 77tbucy Se,i1 gaa$ :
= 2,2 < ( tss* + 24c) '
tov zro its bMPAcWslE Sf~$e5C /el SoliH h f u- = 5f ltl Yuao srAsst Ar wo'F = 20,700jse $$lNrT?b.1.b Y SF' C o 'ntRev(1/I- La lr.t W Att. LoAb TRHEM s 77Eb . . . . - .
= 1M a (tss" -wr of fu<&e 1 Baus) % # Gst-::r) a 2'Lt+lbs z ygg ^
395b ytr 7_ . ._ C*A4l'/LETl'llE ~ %~7-C58 JH Watt.. .ICo[FJo 1'1.L._- .
.C.., . . - - . - _ . . . . - ~ . - .
DELO Srt.tss Ar- t/co *tC * 'LD,700 )t . Sf. = . t~'L- . O
.NW -
_g e. M e 64a e &M-"M- @esip q .#*wWh**.-WW
. m-ggs ,4 .
- GWClc20f2E ?b 7 cf /+
o L o k^b 7 A / W S p n 7 7 E b ~7?hCouCH fI/C NClosS Pt-Mas ed Lib = 272 * (s70 = 176, & a W 0F NE f Clo:S PLMES = SY] U{hpe) + 730 uNCROM ftNes)
= /2 7) d loHW3 STlisS
- iYE03 lsi j bGthSTR=n3Gtfsofs~LD,hojv'
.. 3F = I. Y
/
h M419 HitE M C&1AyLM9 Bes/Didq str6sitcs, or/et;tscr-7tte CLoss f(ASES Y 49Cv.Me ' /P-L- to.44 is ce/Areb FAon Lidex 7s essr- ar 711e swe.r se w of Pi n W 4 Loesies tw rre w As you.n a : ,
+/o. r7 +
W W: N' i78 (/$[*f-7'{O +3bj { Q t, ,,, y __,t = //y,zsfr 14s CLEhrE~ A .Leh" bud 5 Perre*U As' Fouos :
,,_4 ,
. . _ _ . _ . _ . . . . _ ...W t.__.[4[-17f(lb03b)__..... ._.
so oye t(s bio.u4 = _.
)
TNG Ft EST* LO%I99 PAvrePH Chd 96^ F57 "T6J1Eh
. 4s ne m,y op 2. e.o e w p __op. esz, cases : ._.
'-+ 10 9 '-- 4 yg-AV # A V[ T . ..
i 19.p3. l __ f tw.97.r __._.g __. __ . 9
. . . . . . ~ . . . = .
. _ . . - . . . . . . -. .ac .__e
._.e e +
E^tctosv RE S b. Y of 1+ 7tte- seccab WIbitsq P.+rreitN cM ne Reetunesite
+s 7?te- nn cp 7wo cores - As fo t Lour :
- l8 % lwe+.77.r H sDs _
1-qTiTg -" h-it.ric - ).w .y i. d Ws (2e,oy? W -C,o, og
*Dtest cry.es +We Auo @e=Al hMc-rs e2 awe;0cWM by 77te " B.#rc
- froche . 'TMe 7.asut rs Ate GWay *A/ f.I'f, Re.h% of Tsahs', , Va.hu vat VE w e c,n r =- o.7 7 lb1
/M /kcr LOS C.A RAteh BY vat n= SvPPo%TS *2ilAO*W
" 1 a ?. T 4 s Lo&b IS cegAEb pf X 410-31. SOS , E'ACH WID/
cbss Sec7/odAc Alce (or hor of 7krexM.) = G< iso \ OI33 $ PLus 'f u/stss , esa v.nr & ) rRe-A 0F f * } = OII7 2 z.o e.r ' S M \ c *.oi n ) t{ y e .oir7) DO I8',' Y'r Glb Grfes.s % You'F =20,7ao lD : Sf'= 73 SoObhe-hsan $mpc# Lo&b theft &h 6)' S//r H = 'Z?? " Wi:of L D
= 2-7fr x //T
= 3/,f70 /js .
Con /A WrvE rr/2cs = 3i F70/3;
= fo 3 r ps/
'/re'Lo S7462 G y'Do */ = 24,700 .' Y ^ 20..
Lo @ CARfIGb S Y 'l-tA)e t. W4u = 27& x(ur op Up + Wr of bad-Wrof SarinM JLNFh '
= 2.~7[f'(!!S + 155' ~ Y-9 ) = QN NS JTt7?
ce n e k sv a r s r t.e n = y ,,, q ' l o si 1 1 PU v..-- - n a.< n - u , .
- SF ~ *2.o ' -
EXill6.TURE Sb 7 of~ i+ ) (b4 4 So rio n Dou/A) / M Pder- 'Ttte Bosbisig S-renc
/t) 7Wt? 74tiA b (l.lb) ALC: BEE /kTi/ G't f LO W , ?b eckie' 77tG' Ohf Lo4b /5 Th'tT k/676tff" 0l' 7Ht? Lib frse7.F.- (//5*/bs),
Wdet,4 15 pycjf L653 M tJ W hkM JHfe$gb /dA
'Ta / ~ . M Jr) /H Poc7 Tot =tafofE, tr is ca vo os.r wirgog-boitKy Gx h.s C o r AAA t.f25 9?Mr 7kG .B t:3 W ot)!, Wst s4]D b':FLEC.TbNr 144,*~ A-CCEPTAblE.
Sd.L bow s L pd~ ,
~
/
Exw o r.* 1 SthnA Lohhi% id t-irieg a4u. Ratoa Pt.AN(k. i I W= 180 (Learwit.) i- 100 [GNR- _ kikJ 1111.L & , saw n.am ,
& =
2.n 4r ii
. SVcg Log a 270p e 2.tvt 7.5bo g.:
Site 7ht. AWA1 . /fa n t /o.5 1 : C+9 u
. .' soless = 15,77o fd ~
fbA 'f4r.s C.t$g y're b NG G (WMtC3it$LE B&Oh/Sc~ )'s Odf Ws t.L g a r C ht/IS Loff of 4 nTE3A P/ OF ; 4 RAM. Mk. 7ExKrt2 Srk O Coo 'f
- 04 Yoo (/k M 2 M*Ab l 0 1%h. $+6AL =. 4~5~^ GY;tf00 : *15~,fo o . - - - .
,Sp t M,80 = 2.G
/3770'
- _ . . . . . - . . . - ~ . - . . . ..
. \
l
.._ _ . . . . . . . . _ . ~ . .
-w-g-.g 4 4
BJct.cScieAti 3b
/0 cP /Y-EXAthJC W % pas >CT' cF- )?rc~ I.%LA-rto Al s/Atsiss . o % faid)
Ho A OJT- 15 AS 2x?VELdfWb & u), F r
] . die,n v, gyp Ansus et* PdeT2 ffew Am --( f.W.
' k.--4 . p.- 7..,- d.wi. . . Wewur = /.33 ,'a .t/ g /g
= 5 57 w(A @ 770; l'EstSridig Ho4 cur Is PPk/IDc% Bf 2.*/O -% SC/62 i CQfvik" CHA A/A^t- tu u rit -( 'bt. < % Wet.hs n4 i :"
t
._. .so& .d,ru u_u _. ..
a_ hl.o [ I'N ?r*. , Mup6 lb2c5 t.t .", h ta g n o s % <. To Wed D% D B@f garwaD) nurnis powwr = r{i., + 4f, t. Y.) i.vnf - sia
. F=24r714. .
3W *& WGW5
- 2.4 y , ,,r*',,
- ftSi fso' '{tS.b.57tett @Yeo'f (ik sistn) =. 0.5Ye1.o7so = tt 38 Sf~l.'2.
Srf.ese i,) (Ae Scped
/Er.4 frAss > 9 7,hs
=
.f 4 MC7 = /3 /.1T,/ci 0!n s,c w i.]
~.
B.t wA,1wru e. n a-Et1.4whrn- hfftd:nJn4t. 7?teha<44. GRPAA'Al B57 tun =.ss bot rs Gioils. in Adp La b (Austedo nc.) tven tiepr7JG /_ab Freg *)bV fa .% 'f, C. aft oF 7?fG M A L. E n ? 4 s a ra J .* JSbLTS S 9/ kro /s *f
, A-tb 7 31 s /0 t ~!w *F
'hQ 2.)$cf,J Ar- po *F 3 + wrw
/ r : .cq/d Q
= 1 y $ </o b N o
' &< id .T. afw a.<ua.~:. # c yuty A y a L.r--
// of'@ l T4las 1-romwelas run Ts.47 Ps 41ra
# Notation: It' - total applied load (its.);is = urtit applied load (Ib. per eq. in.);i = tidekness of plate (isi,); e -* unit strese at arirlace of phte (Ib. per sq. in.); y - vertical deflection of pbte Irom original geltion (iu.); a = slope of plate measuret Im:n horisontal (rad);' 'Ej' '
# anodulus of elasticity; m - reci,siver of e, Poiswn's ratio. g denotes any given peint on the surfnee of plate; e denotes the dista_ce t.f g frora the tenter of a circular plate. Other ditnensiorts and corresponding symbols are indicated on figures. Penitive sign for e indiestes tension at upper surface and equal compression at lower surface; negative sign indicates reverse condition. Positivo sign for y insUcates, upward f eflection, negative sign downward deflection. Subscripts r, t, o, and & uned with a denote respectively radial direction, tangential stirection, direction of ditnetision a, and direction of dimension 6. All dimenairans are in inches. A!! logniithms are to the base e, ,i (log. .: - 2.30'N> logi, ). (See pp. 215,210 aud 218 for stress and drflection coefficients.) g M,
****d,
,,g c
- T ermulas le .tr.e a.d dea.etes
~. 4 m p G,, :
e-., a.
' r=.,l:/ ~
. a. .) a --g[o. u2(i -;;)] a - -3[ o. + u -(. + n;g .
M on + 198
.u]
313 fm8 - 1) #4
- v. o. * - T.mr[(3e + D.st. + o + s;i . s-lillllillli ai . ) uu . ., . . ,.s" o. + n uo ,- - 8't-
- a. 'r* w+ "' )1 .
ui +> * ,, a,r,,- - w,.
- s. g Q. ni .. , < ,., . - -5[ . u us w & - ( - o$ - o,s*+ nig' ] . - -g[- u + n t< !-(. - n$ . (. u>,# ] fe w
a ,.4
, - _m IG,' Law
- n[4.. _ ,, ..a ,e - ( ,. y,,,, a c. -toi +nda' la _r4
- a + 1 9]
g Ot t, e > .3) . = -h,f(m + 1) kg f - (a - bh + (a - D a ,f(a - 4 + (a + 1)los { - (= = bh -ja - I 4
,,,._,,,, u ... - a r o + . <. - , ->> - , "o u , ,, r -
76.E-Y l m+1 (. + lja' iJ e ggggg
% ni.. > uo . . . --E[. u- + n g,-( - o$] u-,- -q', ', ,"[t, p- 4, w & Py] f-
, r n , l i=., , - - ;- = + n- .
- t O
u u, . = m. ."-
. 1 . .
2-. a,re n. ... < . . . g[p. - n + (. + ,> %- t-- '6] mne
,-_ g , [o ,,; 7,-p, u +n
,,,. u,, ,,,,_< g .p 3 7
- o. .. , > , . - -s[~ n i.s ; u- - og _ (. - Ig] . - -g[(. - o u. . o a ; - (. - ,g - (. - ,g) !,
n ,- - n. ., a
, - _m.. v. , L o. u. + n<.. t n _ ,,_ ,,. ,,, ,s, _ , . .u... . ]
ra * -
- a. .., u....- q ; p [o- ,g ,- ~ _, ( 4,+,)) , q ,
- 4. 'I.* ( At t.i.t of lamt,h un . - . = -h,[= + (= + 11'los *y - (a - U ,
' ~ *
*""'p''d" .es Mt et - . - ptu )
(.* + 1)los E' ^. - (Mu .) '(= + 1)los4'1(= - l)
- g. 1+(a+4bs( , m+(a+Ulf , **8 p p - Edn e i.an* + me) + K a(n - 6 sn + new) # + K,(na - kn +a new5 we to P g Mn. 6.ese + e.esp) jd g,, W 1- 1[Ir(ps - 6 ps + e n) g, , t'3 4 litr(ps (em + D85 (pe 6,s 4,,p, *q*
a ( 10" + DA'** hI'* t 4)K.e* (6a t b(&= + IJK.wF . g
- Ed* 3'7m + 1) 4e + 1 se + $= + l
- x. n i ' - M5a 1- .,e m '. - e m. + u $i 3%sa.,t + 11 .. u + U-ia x.+ui a o. +1 uia u S .
!q =ry i,,..,
un y s '/c7C;' ai,-,.i u..
. &[ t + ($') % nip >] .i K -(,,*gla on.a in.soa) *
(R.f. Is
. . - . _ . --- --m.- . _ _ - _ . . . _
y
- s. ..w 48e . - h[o- + D[- (= + U) a gd [(a + 7)$-(= + n] e - 8["'~,[(#]'**] 3 g,
, us eds.) un. 8h e,- h innnn y, ,-,- m-+n un, , , , m ass - .>.-
v
=,
o w smi
- 1 [ ,
+ . ; -. ~ - -- - - - - . , - , ,- . --
/1. cF 4 4
Ia LINER LID - LISTING OF EASIC PROGRAM TO CALCULATE EENDING STRESSED 100 REM GE700 LINER, STRESSES IN TOP PLATE 110 CLEAR 120 - DIM R (7) , SR (7) , ST (7) , Y (7) 130 DEFINT I 140 FOR I=1 TO 7 ~ 150 READ R(i) 160 DATA 0,2.65,5.3.5.71,G.688,7.038,7.44 170 NEXT I 180 M=1!/.27 : T=1.5 : E=3E+07 : A=R(7) 190 SF=-3/(6.28*M*T^2) 200 YF3=-3*(M^2-1)/(6.28*E*2*T^3) 210 YF2=YF3/8! 220 LPRINT " R ( IN) ", "SR (P3I ) "5 "ST (PSI ) ", "Y (IN) " 230 LPRINT 240 REM BOLTUP LOADS 250 LPRINT " STRESSES AND DEFLECTIONS FROM DOLTUP" 260 REM LOAD COMBINATION 1 270 R0=13.375/2! W=106800! 280 FOR I=1 TO 7
- E90 GOSUB 3000 300 NEXT I.
- 310 REM LOAD COMBINATION 2 320 R0=11.414/2! : W=-106800!
330 FOR I=1 TO 7 340 GOSUB 3000 350 LPRINT R (I) , SR (I ) , ST (I) , Y (I) 360 NEXT I ' J70 LPRINT 3S0 AEM ADD PRESSURE LOADS 390 LPRINT " STRESSES AND DEFLECTIONS FROM DOLTUP PLUS PREESURE" 400 REM LOAD COMBINATION 1 410 R0=13.375/2! : W=2100! 420 FOR I=1 TO 7 ~ 430 GOSUB 3000 , 440 NEXT I 450 REM LOAD COMDINATION 2 . 460 R0=10.62/2! : W=-2300!
. 470 FOR I=1 TO 7 480 GOSUB 2000 --
490 LPRINT R (I) , SR (I ) , ST (I ) , Y (I) 500 NEXT I
-510 LPRINT 520: REM ADD LOADS FROM TOP DOWN IMPACT 530'LPRINT-"STHE99ES AND DEFLECTIONS WITH TOP-DOWN IMPACT" 540 REM LOAD COMBINATION 1 550 R0=10.59/2 : W=114238!+60048!
560 FOR !=1 TO 7 - 570 GOSUB 3000 ' 580 NEXT I 590' REM LOAD COM3INATION 2 600 R0=14.13/2 : W=-114258! - ' i . e
.+ - -
- * - - *~~ ~
., gg4 310 FOR !=' TO 7 - - 620 GOSUB 3000 630 NEXT I 640 REM LOAD COMBINATION 3 650 R0=10.42/2 : Wa-60048! 660 FOR I=1 TO 7 670 GOSUD 2000 600 LPRINT R(I),SR(I),ST(I),Y(I) 690 NEXT I
'700 END 2000 REM CASE 2, ROARK TABLE X 2010 IF R(I)) RO THEN 2200 2020 P1=M+(M+1)* LOG (A/R0)-(M-1)*RO^2/(4*A^2) 2030 P2=-(3*M+1)+sR(I)^2/(4*RO^2) 2040 P3=-(M+3)*R(I)^2/(4*RO^2) 2050 SR(1)=SR(I)+W*SF*(Pl+P2) 2060 ST (!) eST (I) +W*SF* (Pl+P3 s 2070 Pi=4*A^2-S*Pa^2+R(I)^4/RO^2-(O*R(I)^2+4*RO^2)* LOG (A/RO) 2000 P2=-2* (M-11 > 00^2* ( A^2-R (I) ^2) / ( (M+1 )
- A^2) 2090 P3=8*t-p ( A^2-R ( I ) ^2) / (M+1 )
2100 Y (I) =Y (I) +Wa YF2* (Pl+P2+P3) 2110 GOTO 2400 2200 Pl = (M+1)
- LOG ( A/ R (I) )-(M-1) *RO^2/ (4* A^2) 2210 P2=(M-1)*R0^2/(4*R(I)^2) 2220 SR(I)=SR(I)+W*SF*(Pi+P2) 2230 GT(I)=ST(I)+W*SF*((M-1)+P1-P2) 2240 Pi=(12*M+4),(A^2-R(I)^2)/(M+1) 2250 P2=-2* (M-1) *RO^2* ( A^2-R (I ) ^2) / ( (M+ 1 )
- A^2) 2260 P3=-(G* R (I) ^2+4*RO^2)
- LOG ( A/ R ( I) )
2270 Y (1) =Y (I) +W*YF2* (Pl+P2+P3) . 2400 RETURN 3000 REM CASE 3 ROARK TABLE X 3010 IF R(I)) RO THEN 3200 3020 P1=(M-1)/2+(M+1)* LOG (A/R0) 3030 P2=-(M-1)*RO^2/(2*A^2) 3040 SR (I) =SR (I) +W*SF* (Pi+P2) ; 3050 ST (I) =ST (1) +W*SF* (Pl+P2) - 3060 Pl=(3*M+1)*(A^2-R(I)^2)/(2*(M+1)) 3070 P2=-( R (1) ^2 eRO^2) " LOG ( A/ RO) + ( R (I ) ^2-RO^2) 3000 P3=-(M-1)*RO^2*(A^2-R(I)^2)/(2*(M+1)*A^2) 3090 Y (I) =Y (I) +W*YF3* (Pl+P2+P3)
~~
3100 GOTO 3400 3200 Pl=(M+1)* LOG (A/R(I)) 3210'P2=(M-1)*RO^2/(2*R(I)^2) 3220 P3=-(M-1)*RO^2/(2*A^2) 3230 SR(I)=SR(I)+W*SF*(P1+P2+P3) 3240 ST (I) =ST (I) =W*SF* ( (M-1) +P1-Pa+P3) 3250 Pl=(3*M+1)*(A^2-R(I)^2)/(2*(M+1))-(R(I)^2+RO^2)*LO3;A/R(I)) 3260 P2=-(M-1 ) *Re^2* ( A^2-R (1) ^2) / (2* (M+1)
- A^2) 3270 Y (I) =Y (I) +W*YF3* (Pi+P2) 2400 RETURN s i .
3 4 4 e b
. . . + - , .- , .,-- ., -, ,,
/Y of /Y.
ANALYSIS OF GE700 CASK WITH NEUT8DN PRODUCTS LINER , ft(IN) SR(PSI) ST(PS1) Y(IN) i ST RESSES AND DEFLECTICNS FRCM BOLTUP 0 6382.82 6382.82 5.501994E-03 2.65 6332.82 6382.82 4.774858E-03 I 5. 3 6302.83 6382.Bi 2.593454E-03 l 5.71 6358.99 0 2.126049E-03 6.688 -431.5991 0 9.181204E-04 7.038 -213.5056 0 4.869167E-04 7.44 0 0 0 STRESSEG AND DEFLECTIONS FROM BOLTUP PLUS PRESSURE ~ 0 6934.557 6934.557 5.863322E-03 2.65 6835.131 6879.523 5.075533E-03
- 5. 3 6536.855 6714.422 2.738558E-03 5.71 6454.433 297.7783 2.242967E-03 6.688 ~455.0215 320.9848 9.679457E-04
- 7. c ' 3 -225.0923 294.7991 5.133411E-04 7.44 0 265.6346 0
)
STRESSES AND DEFLECTIONS WITH TOP-DOWN IMDACT 0 4123.919 4123.919 4.972629E-04 2.65 1328.11 2576.392 8.931384E-05 \
- 5. 3 ~6981.948 13872.42 -3.923448E-04 ,
4 5.71 -3213.401 12977.26 -3.575273E-04 6.688 -2628.494 10942.58 -1.832279E-04 7.03F -142.8217 10253.62 -9.854301E-05 7.44 0 7024.885 0 l. S
=*
\~
4 e
jf 7/-sic n j
~
" ' ' ' ~
nelJTROD PRODUCTS inc
~ "{ ",
f
- 22301 Aft. Ephraim Road, P.O. Box 68 l
a
,: Dickerson. Ataryland20842 USA.
t
" 301/* 6 -3001 TWX: 710-828-0342 * ) '; ,
y e ;s - # March 31, 1986
~
Mr. Charles E. MacDonald, Chief
- Transportation Branch Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Coseission . . -
Vashint ton, D.C. 20555 Refs (1) Certificate of Complie*ce No. 5942 (2) Neutron Products subst.tal dated November 11, 1985 (3) Neutron Products subu.!ttal' dated February 28, 1986 (4) Neutron Products submittal dated March 11, 1986
Dear Mr. MacDonald:
Neutron Products gives its approval for drawings submitted bv references (2) and (3) to oe filed in the Public Document Room. The note on Neutron Products drawing 240139 regarding proprietary information should be ignored. Enclosed are three copies of reference (4) and the enclosed drawing for filing in the Public Documet.t Room. t Very truly yours. . NEUTRON PRODUCTS, INC.
. r A
Frank Schwoerer, Vice President Enclosure i j. _ .c k
Nac mean me us. mucu ca copuuvxt amenso. un , es.J . <. gengas See [ /: ' d ' i ME ',; g-TELEPHONE OR VERBAL CONVERSATION RECORD @p C INCOMING CALL C OUTGOING CALL C VislT ' PEMeow CALUNG OF FICUADDMISS PHONE NUMSt,R ' EXTENSIC
. T.i ' .hikhtl lju./ , i
) i. cY ?!~ '
)
~~ -- ' i/ .
PE nsON CALt.ED OFFiCUADORf.1
' PHONE NUMBER EXTINSID
'},. #
42: 1. histbz-CONVE RSATION sus.E CT '
. ,. e J~
t; n : w, ;,; +/sa A l a w sVMMARY y L u .s('l b i ir v-.aT31tw *
's
- :. ('c ' '
/. a $ n ws_
.]
an[_
.': b l bt - )L[cz(l0,,'Cu -
'.I, .a a_
, ~ :-+ ~'0. ,n YL .<Nbl Y
.G,- ) , a . L: ? -.
- g. - - -
,u,$m;;: . ,.. ; n,l7'
, , , _ _ .. 3e i~ [ , g,. ,.,, o w -
i/ z. f
~
~
. .'.. :,Tf g ;, ^ b' - ''I " d:: A A
-sc '-d-
</
7 / i A I }') s RE FERRED TO: 7, g
' i l nt-
,s D gayggg yg op ACTION R EQUESTED ,
ACTION TAKEN. INITI ALS DATE ACTJON TAKEN
- INITIALS NRCFOAM 218 14-78)
v.s. wucts ao c CULATOnt COMMi&S80N DATE , l NT.C recu 218 , ..p.y ,
>.5 N= .
TELEPHONE OR VERBAL CONVERSATION RECORD p f ,/p. h* l O OtJTGOING CALL O vis:T INCOMING CALL OFF#CE/ADDAFS$ PHONE NUM.ER E XTENSION M M80N CALLING . m N?!YY '
' l .'
, it. It; t J.:t 'EC/
.?l} *itY /
PHONE NUMSER EXTENSION mason CALLID OFFICE / ADDRESS w f/Ehti.c l,___ / bY/,k CONVFRSATION
~
c./ L/ susACT ) .. . f hif // $ /: cit k/n. SUMMAny ,/ . f~ i . n L, .2 7 ' /fd l il -1, */,,py ( (l - a _,s , u c . '
.g 'y ,,,,,/ g j
"'~ '
/L. 46l- cm l" Y]now. ..
& ufk., ( Uaf /4.a,m-t h<].l. , /
,, + ,,); j f g,
'- cmfe g.s td +.2 (4 k k N c <l 4 e f._
w~ ,s 7
/
,,g ,. i ,
g, g o .stsL m ci ,DLd' .%.~ (.m .5< a . n h).
, /l &' -LC [2)s%C a s>< l s + +~
6"
^#
N(2at@JtGin ', )Lwti 6:s, )L 7 y.4.u .-_ o dd./ u w - Y
~ '
.L. .
/ ..
/ a. s;L.i Qt[%'. "jc % c W -- ' ;/ ~'~ ". # y j;'
i
.f* .~.- . . s LA-vrw .
~
. .t
'" '4 .; ; et' s .
cnu'<<cx ~ t q. g- l_ tmal (gwgy
- +
y , n e' v REFERRED 70: I i' O ADVISE ME OF N . /t s - i-st.- - -
- .m ACTION TAKEN.
ACTION REQUESTED 7
~V _
IJ/ ; [' Y a.-[ s.-- Y,7 v
~~ ^ $ BNITIALS W' & '*-
I v' DATE INITIALS ACTION TAKEN
+
e s -.,4, y --
---47...-m -my. -a =, _gw a , . -. - - , - -
-ww- ,-
g I CONVERSATION RECORD "):a y 7_ g g O VISIT ~" CONFERENCE @ TELEPHONE
"*"#"** '"I INCOMING LoceSon e8 Viot/ Conference: O OUTGOING NAME OF PER$0N(5) CONTACTED OR IN CONTACT ORGANilATION (Office. dept t,ureev, TELEPHONE NO WITH YOU .
etc.) A / , 3 (/ f - YU SUBJECT
.] Y &
b Y. Sco/ l
\]
r UMMARY -
.% - k~4 // A 's1 . /1fr6 y M. $b iW \ l ).) A f AWJ 4 ;
M . ph 1 L644&Q fr Y $~ d O
- UOO pho 7risa d# 6-io. K LM wyw namu null
,& _ z J2 h 4u h m < <
AlsLL Q ~Af - - La #1 taAR-4 A L ' o V
-1 m /fo m--
t'7~.Uc:C - c/ _$ A A _a NAME OF MRSON 00CUMENilNG CONVCRSATION SIGN ATURE DATE I ta mO'(/ h/~' ACTION TAKEN _ _Z_l1174
' /
/ _ ,
SIGNATURE ilTLE DATE
' '7ltofh 4 """* o v. s . .1, ...... . . ...,.... couvrasArios accono ' p,[o,N4t, gag,rgig,T,o i
L . ._
CONVERSATION RECORD "J'f 30 g '" 7//,//' f6 I TELEPHONE O 'll5IT O CONFERENCE INCOMINo Location of Visit / Conference: O ouTooiNo Haut OF MPSON' ) CONT ACTED OS,1N CONTACT ORGANIZAT60N (Qffice. OeM bures , 1ELEPHONE N7
"'[~ " h 5 /3yhp '"
.'k846[YD7 y gf D/- 3%
.$?XJ/
7 'h tr /w& _ SUM V ARY {}
- 1 -.
l' $$-l11 - Y1 $ Mc Gx t ~ / / e _ s/ c6aL g cusic & sAfL RJ
,, (fyr-4 '
/f$ M .%1 MN y S t-{ , ) _,,
WrM : *a Sbndl ~ wu W m,7ht/W'Ad ' aAN w WN/$ a Add 'o w ~9 De % a w ~ f
. .?- 1$'s 4
- V W c_ a LC- Yd
_ ~ h_b "
/Ho! S Y%$.3hdN 3
_ /lb Z~ A cn1 <] sun i . - A? / - d1 A s . ,
/ h(O'lpp .f%L h W1'3 4L w( , g&k V O O ACTION REQUIRED m
("t'M2 L't s ( 'W -c .-
/ /7 NOME OF MRSON DOCUMEN14NG CONVERSA1.ON $1GNATURE , e DATE kbNTAKEN 0ev 1 0 ifr #/ SO Y #
[ l sicNatunt TITLE DATE
. . . . . . . . . . . . . . . . . . . . . . , . . . . C NVER SATIO N R ECO R D fE gf,','}^,LE"$r*N/S's?
r l CONVERSATION RECORD "'ggjg f ,/,/gt g Vle,ti TELEPHONE 0 CONrERENCE h INCOMING "2 #21lE1 Location of Visit / Conference: O OUTGOING k $! 3 NAME OF PERSON (5) CONTACTED OR IN CONTA 1 0 % A N'1 A llON (OMire, dept.. bureau. TELEPHOP 7 NIM"~ wiTH vou ; etc ) ,, gaf 'E Norgf. l?l4 rd t! 44" 5M/ (<lnk_9Nbak" -
SUMMARY
0+ 9/f. EL_. uk(LYAwmu e
-6 14 O 00-6o w .
g%_ Ykdcob s._ k w ]L e ' Y
.7L 2L -L l4%CvGM. L.
L_L ~ rad}4a 72'-sh L @lu &
% a ikil a ,- uw__A -u ,wn _ I tm& & -
N L JE g t x Odat Al. Y aEt 4 w :m_ Wk n afusi 2%A4kwcAta
.M den _8JA<m gelLN12( hw _ m 4.. d o f '// pit d au 'T aaaL g s -- Avnus .g sn a d-flu.L ak LoifalAd / dbl *D.6.f ud L i dh $y;&L E m a Lc./ d 6 4 1 / W G M 7k Bad _a&d? d4 Ofc A b 7E. ~ O n.w 0 4t h Go $NM 1$wuda# S L 0- E d/ h _
9/10 - n og 5- o 3 ACTION REQUIRED NAME OF PLRSON DOCUMENilNG CONVERSATION SIGN ATLl'E DATE , Aksgh$N f P' - ACTION TAKENg / 7(' sicN AT URE TITLE DATE / h o . , U , ,, ,.. . . . . . . , . . . C NVERSATION RECORD 9h/ro 9/ tit 0h,0,N Lg Q ,2 gIj -g
.o...
r I - -_ j TlWE DATE CONVERSATION RECORD y vg u .a v - r4 ROUTING TYPt O courtnENCt g TtttPsoNo "*""#"* ' '"I O V8 SIT
@ INCOMING O ouTooiNo Location of Visit / Conference:
ORGANLZATION (OMece. dept., t>uteau. TELEPHONE N7 NoMC OF PCFLON($1 CONTACT [D OR IN CONT ACT WITH YOU etc ) gj ggg LY U ih 500 /
/w l ]/d
- c 5, -
SUBJECT ,
SUMMARY
IdG;myIWh> v da-d 5 M4 of Imm l% Ghya/ hECL L d w - ce W O
$. wad 6 k m wr L, r '
.f. Y75ll 6-u sawb 34 )LuawYL1N .
h k . m e d ,c A E - /h X/M ^# , b
.ist m l . 7Ee < nJ Jsa.enaulL% s M. Ji 40 L & ~ W w b d e 4 m J )kaa; i i y L L s s s Nwdd j d%iau )b
'l Hb - 3L- ea G - s 3
_dN ACT! REQUIRED DATE NAME OF Ptltsort DocuptNTING CONVERSATION SIGNATURE w'
]l1<.h, n Y.... plw L , R-29-TY L ACTION T AKEN y
-Q m) _
T. . . M(19 \N - gg',Q^,Lfy"g,rglg,7>
"'"~'" ...U...t,.....,...,.... CONVERSATION RECORD
I f l- l'" 7/uc j g 4tp neurnon anotfoers inc 22301 Mt. Ephraim Rocu, P.O. Ho YS USA Dickerson, Maryland 20S42 301/349 3001 Tli'X: 710-E28-0342 November 25, 1986 Mr. Marles E. MacDonald , 011cf Transportation Certification Branch U.S. Nuclear Regulatory Conission Washington, D.C. 20555 No. NPI-20WC-6 MK II Ref: Our Application dated August 5,1986 for Model Package 29, 1986, we w ill provide the
Dear Sir:
In response to your letter dated October 31, 1986. requested information by December
. Very truly yours.
NEUTRON IR0 DUCTS, INC. M* W Frank Schwoerer Vice President
#[' ll'Nf xN s' R.ECEIVED '?g 15na > = NOV2eigsg pli -
i 9 Lttmaru
.\. . # 2.g In, . . RY )
P
\%-
hiaUkuon ,o s
*IW
- 4, c' CDCKETED g-USNRC s
- 93. Nov2e198s ) ':i2 g li',tSS 131LitcTIotl
\q mmwn i
% to m
427d@ 9~ $0 yofg7 47
nA'% ,$ y - , . __ ,q % g-( f y-,.---- , . _ -
.-**s ,.,U L 0 T.C 11C J!.-',' :i;
- w '.t? ..m., n.i : :w a,, ..
- s L% . -. . . .: s n .a;. m; ::. x; ::.:: p.u ;;
Dace . Der 30, 1986 m f? '.A'.& C, / Mr. 01arles E. MacDonald, Chief ' O .s Transportation Certification Branch '
. f , . ' $~
U.S.11uclear Regulatoty Commission Washington, D.C. 20555 p ,d,%gggp . _ . , , , ' ' * 'wg f a zi-! an- , Re: Model 110. IPI-20WC-6 MKII Package . g, .' d"' x~ ; Decket tio. 71-9102 ve u . . ..
\;.
\' '
Daar Mr. MacDonald: . _ ~ _ _ -
'1his transmits the information requested in your letter of October 29, 1986 in connection with our application for approval of the Model 11o. IPI-20'.C-6 MKII package. Aa you requested, the informatien is submitted in the form of revised pages to our application of August 5,1986.
Also included is a copf of the enclosure to your letter, with narginal notation added identifying 'ie location of the response to each item. In the information provided, reference to a permanent tungsten alloy shielding insert within t.1e drum of the inner conta!-'er has been deleted. A recent radiation survty of a package employing the new inner container with a completely lead filled drum provided results which, when scaled to 15,000 curies, shas that the shielding requirements are met with margin. 'Ihe results of the cnvey are provided in section 5.4.3 of the enclosed documentation. A review of our previous calculations and comparisons support the conclusion and are presented in sections 5.4.1 and 5.4.2, also enclosed. Sincerely, ITEUTRON IMODUC3, INC. j.sa )
'Y,Ldsck ibn M &
m
.; .MQ.*?k '
.a <;3y Frank Schwoerer Q t', .
w g Vice President FS/kad .-
- c '. 936 7 m,
-5 '.
. _ . . L/
'v h l JW
-ppgeow e< (Ma . y g.-g
- - - - . ~ . - -. - . .-. . -.- - _ - - - . . . . - - - - . . - . - .-
- 1. 9E9EPAL INF0 W TIOR 1.1 Ir tr oduct i;_q ,
This application is in support of obtaining a B(U) rated Certificate of -; Ccmpliance for a radioactive material transportation paciage that is { essentially identical in ditnensions and configuration to en e::isting shipping
~
pact age. Model Number NPI-20VC-6, presently in use under Certificate of - Compliante Humter 9102, with paciage identification number USA /9102/B( ). Both pacl ages ar e for shipment of encapsulated cobalt-60 sources and cornprise a [ shielded inner container which fits snugly within an overpach rneeting DOT Specification 20WC-6 r equir ements . The overpa:1 is made up of a Wooden Protective Jaclet and i Steel Shell which encloses the Wooden Protective helet. The paclage design is service provent the e::isting containers having been , in use fer over 12 years. During this period. 2 containers of this design have t een used to mal.e more than 100 shipments per year without an adverse incident. The new pacl. age differs from the original principally in the materials used f:r construct 1:n of the shielded inner container. The structure of the shielded inner container is fabricated of Sither a normaliced high strength - tarbon steel made to fine grain ir actice, or an au?tenitic stainless steel. Ecth have superior fracture roughness properties at lov temperatures. The original pael. age. Model Number NPI-20VC-6, is authoriced for transport af a ma::imum activity of 9,500 curies and a ma::Imum internal decay heat of 150 ther mal vatts. The new paci age is presently licensed for use under Certificate Number C102 at the same ratings as the originel pac). age. It is designated as 7
"-del Number HPI-20VC-s M1,II. However, this configuration is capable of ting applicable regulatory requirements at a ma::1 mum activity of 15,000 ist of cobalt-e0 and the as sociated decay beat of 240 watts. The higher aatility results from increased lead shielding and reduced gamma streamin),,
11ch in turn results from the cotabtnation of a redu.;ed drum liner diameter and shell liner vall thiciness'as. compared with the original package. ,
~
All riferences to the new paci. age in this document are to the new j > tr anspor tation pacl age at the 15,000 curie rating. Results of development and
- retational e::perience with_ the e::1 sting tr ansportation pacl age are used, as <
appr opriate. -in support of the certification application of the new transportation pac). age, and where used ar e so identified. Revision 1 1-1 b 1 *' -
a { r 1.2 Pulere Descrirticn i 4 1.2.1 Esclarint The innec container serves as a transfer cast to mate with and enchange cobalt-60 sources with teletherapy devices, as well as providing a shielding and containment function during shipment. As a shipping / transfer cas). it is- ! designated Medel S/TC MlII. Each casl is numbered serially as TC-X. The , overpact., :ensisting of both the Wooden Protective Jaclet and the surrounding l i Steel Shell, is designated OP-Y, again numbered serially. Overpac1.s and inner ; container s are interchangeable and are used in any combination. , Figure 1.2.1 is a vertical section drawing of the Model NPI-20WC-6 MLII ' shipping packaging. Figure 1.2.2 is a hori: ental section drawing. A vertical section of the S/TC inner centainer is shown in Figure 1.2.3. The principal components of the paclaging are identified in the drawings. Drawings of the L S/TC inner container and the overpac). are provided in the fi ent and back inside
~
i , cover poclets, respectively, and are referenced in Appendin 1.3. l The $/TC shielded inner conta.ner consists of a 3/8 inch thich spherical ; shell, 24 inches inside diameter, containing a chambered, shielded Drum
- Assembly held in place by two Cover Assemblies. The Drum- As sembly fits _into ar.-
E-1/4 inch inside diameter by 3/16 inch thich horizontally criented cylinder, which forms a ",ldment with the st911 througn a steel flange. The toroidal cavity f or med ' - the hcrizontal cylinder penetrating the sphere is filled with lead. The cavit, v.ithin the cylinder Scuses the chambered s:urce positioning I Drum Assembly. , The Drum Assembly chambers carry the source holders, which may vary from one model of teletherapy machino to another. The Drum Assembly is removable i and can be interchanged with another to provide for_the different design of source holders. During shipment, the chambers, or section of chambers. that are not filled with source holders, are fitted with full diameter, steel encased lead or tungsten plugs and spacers, which restrict movement te. less than 0.25-inches laterally and 0.1 inches' radially. The Drum Assembly,-source holders and plugs are secured in the container by shielded Cever Assemblics .i bolted te the Shell Assembly at both ends of the Drum Assembly containing cylinder. The bolted Cover Assemblier are sealed using silicene rubber gaslets. The-shielded inner centainer is. enclosed within the overpack. coasisting of a Wceden Protective JacLet (WPJ) surrounded by a Steel Shell. The overpact meets the requirement of DOT Specification _20WC-6 Wooden Protective Jacket. The WPJ is a right circular cylinder consisting of 3/4 inch thich enterior- < . grade, Douglas Fir plywood discs glued together with a resorcinal resin . 1 adhesive and nailed. In addition, the WPJ is reinforced with 16 aniel. 5/8 inch diameter, full-length steel-rods. The;WPJ has a plywood sidewall of= sin inch minimum thictness and a plywood top and bottom, each of E-1/4 inch. , t hici.ne s s . The NPJ is surrounded.by she 12 gage Steel Shell.- The Steel Shell has 1 flanged. belted closure and 12 or more 1/2 inch vent holest these are . covered with durable, veatherproof tape, or fitted with plugs which relieve under pressure. 1-2
-, --..----.-_--,_,-.ua.._----
- . . - . - - - . ,,-., n, -
.._--_..-_._.__..m. .-__-
e i I 2.4.4 *to Dawn Da" free four brackets are provided for tie down of the package, should it be convenient to use them. Their use is not mandatory for safe transport of the package. , 2 The bracketc are fabricated from 3 X 3 X 3/B inch structural steel angle, placed back-to-back, and welded to a 6 inch wide. 3/16 inch thich reinforcing l support-band, which encircles the body of the Steel Shell just below the lower : closure flange. They are spaced at 900 intervals around the periphery of the shell and oriented 450 f ror. the direc*. ion of the support rails. The tie down-brackets are shown in Drawing 11 24011 'see Apper. dix 1.3.3). The brackets and package meet the specific tie down requ:rements of 10 rFR 71.4S(b). The supporting calculations are provided in Appendix 2.10.1. While not designed to be used regularly in this manner, the brackets-can be used as lifting devices. The total load would be uniformly shared between the four brackets. When used as lifting devices, the brackets and attachments meet the structural requirements of 10 CFR 71.45(a) specifically, a minimum safety factor of three against yielding. The supporting calculations are provided in l Appendix 2.10.10. l If the brackets are not used. lir.as placed across the top or around the , Steel Shell fastened to the transport vehicle will adeqvately secure the package under the requit ed loads. The support rails can also be clamped and shored for hold down. The package can be secured by any method acceptable for < the intended mode of transport. 2.5 Standards for Type B packarint r The application package meets the st.ndards for Type B packaging, as l 1 specified in the following paragraphs of 10 CFR 71: 71.43 General standards tor all rschages 71.45 Lifting and tie down standards for all packages-71.47 External radiation standaros for all packages 71.51 Additional requirements for Type B packages j 2.5.1 Lead Fecistance flot applicable 2.5.2 External pressure Demonstration that the containment vessel would suffer no loss of contents L if the package were subjected to an external pressure of. 25 pois is no longer a: rogulatory requirement. However.--both the inner contair.er.Twhich is the' .- secondary barrier, and the contained special form source capsule substantially L exceed this requirement. Both tre. internally supported and can withstand high [ hydrostatic pressures. The spheriesi shell of the inner container is: suitable for a sustained working pressure of over 500 psi. even without support. j Revision 1 { l-2-14 f
.c ~.ea e , , _ . . - - , .-
n . _-, ,.- - - ,,,.,.....-_,,..-..,n,, ,, , - . , . . - . . . , . . . - - - ,
1 There is an additional energy abscrbing mechanism for the inner container in the inverted position. The inner cask lifting bail coul: crush the wood of the protective jacket from the in:!de under the inertial loadina of the inner container. This effect was not include: in calculating the inertial loading, although it would serve to reduce the loading. An in the case of the ur"ight end drop, the inverted end drop does net result in adverse effects on either the shielding or contain:ent capability of the c3psule or inner container. The heaviest loads on the inner container are dictri;uted bearing loads and the capsule stresses are well within the elastic limit. The principal package damage would be to the Steel Shell and locally *.: the Wooden Protective Jacket. Local penetration to the Wooden Protective Jacket wou'i be less than two inches of the total top , thickness af nine inches. The integrity of the shielding and containment would be maintained. 2.7.1.2 Side Drop In the side drop most of the energy absorption is taken by crushing of thi shock rings on the Voeden Protective Jacket. The remaining energy is dissipated in deflecting tne body of the protective jacket. A small contribution to energy absorption is provided by the crushing of the enclosing Steel Shell. Crushing of the shock rings is calculated to impose a 180 g loading. Calculations are shown in Appendix 2.10.5.C. The capsul < loads will not result in stresses exceeding the elastic limit. The containment capability of the capsule will not be impaired. The limating loading on the inner container is cover bolt shear. The maximum loading on the bolts occurs if the plane of the cover face is _ perpendicular to the striking surface. The maximum load can be calculated as the product of the cover weight and the g loading, or 77 pounds X 180 = 13,900 pounds. The eight 1/2-13 UNC bolta have a minimum root diameter of 0.400 inches for a total shear area of 1.009 in.2 The associated shear stress is 13,900/1.008 = 13,800 psi. For the ASTM-193 Grade D7 bolt material at the maximum temperature of 3000F, a shear stress of 0.55 (94,200) = 51,800 psi wauld have to be exceeded to reach yield conditions (see Appendix 2.10.7, B3;. The safety facter to yield is 3.B. No change in shielding ccnfiguration results from the side drop. Damage to the package from this drop would be crushing of the shock rings O of the Wooden Protective Jacket and crushing of the external Steel Shell. Integrity of the shielding and containment would be maintained. 2.7.1.3 Corner Drop Not applicable Pevision 1 2-28 d
. t 2.7.1.4 m i n t r - r.
The oblique drop results in a strike on the cylindrical edge of the _; package. While in some orientations cru:hing of the Steel Shell appurtenances i provide some energy absorption, the principal energy dissipation mechanism is ! crushing of the edge of the Vooden Protective Jacket. With the package center of gravity directly-over the strike, the_ calculated loading of the inner i container is approximately 65 g. The results are the same for the top edge or bottom edge drop. The calculations are provided in Appendix 2.10.5.D. Loads en the capsule will not result in stresses exceeding the elastic limit and the containment capability of the capsule will not be impaired. The limiting load on the inner container taken as shear on the cover bolts ; is below the failure 1tmit by a factor of 14 l Damage to the package from this drop would be crushing the end shock rings [ of the Vooden Protective Jacket and also crushing sections of the external Steel Shell. Integrity of the shielding and containment would be maintained. 2.7.1.5 Summary of Results Discussion of the condition of the package is provided under each of the preceding drop configurations. Summary of the loadings and factors of safety are provided in Table 2.7.1.1. 2.7.2 Puncture Free drop of_the package through a distance of one meter (40 inches) onto > the standard, six inch-diameter cylindrical bar was examined analytically for all of the principal drop configurations and damage sensitive parts of the-package. The local package deflecticn and g loadings were estimated for each of the drop configurations. In all cases the strike was considered as being located directly under the center of gravity of the package. The calculations , are presented in Appendix 2.10.B. Results are summarized in Table.2.7.2.1. The_ local deflections ienge from about 0.6 inenes for a strike against the l bottom plate of the package (the bar missing the skids) to about 1.4 inches-for several of the orientations in which it was postulated that all of the energy was absorbed in crushing the wood of the protective jacket. The associated loadings range from 70 g for.the smaller deflections to 25 g for the larger ones.
~
i In all cases the overpack Stee1'Shell would experience some permanent deformation and when the. strike is directly on the 12 gage shell material.'some l perforation and tearing might occur. Since the shell is neither lead' containing or essential to fire protection, a shell_ tear does not measurably-b reduce the effectiveness of the package. The loadingsLare not high and there. would be no damage to the innor container or its contents. .; Revision l' ! 2-29 S
. - es. - _ -.--- i ..L--.-.- ,-- - -,.-:--.. .,,w.. - - - , . . - . , - ,e -
4-
- .7.3 ver-Q 2.7.3.1 Suceary of Teecerature and Pressures. Maximum package temperatures under HAC are :ummari::ed in Table 2.7.3.1 which is identical- to -
Table 3.5.1. The upper limit pressure is calculated to be 16.6 psig (see Appendix 3.6.4), although even under raximum internal heating and post fire temperature conditions the pressure w~ald likely be very little above atmospheric pressure. TABLE 2.7.2.1 PUNCTURE
SUMMARY
Deformat.on Steel or Shell S/TC Deflection (in.) Loadine, r Penetration Damare Bottom Plate strike 0.58 70 Not likely None Skid strike 1.6 25 Not likely None Top 0.9 *5 Possibly None Hone Side 0.9<[<1.4 45 Possibly Oblique (edee)_ 0.9<[<1.4 45 Possibly 'None Revision 1 2-30 e
~ ' ' ' ^
b,-, . .. .
. . - . - - . . - . . . .. .- . .- . - . . - . ~ _ - - . . _ . _ . . ~ . - - . - .
l t [ 2.10 APPENDIY , r Pare t 2.10.1 Tiedown Devices 2-35 i 2.10.2 Thermal Stress in Drum and Shell Assemblies 2-39 2.10.3 Free Drop - Normal Transport 2-41 2.10.4 Penetration 2-43 . 2.10.5 Free Drop - Hypothetical Accident Conditione 2-43 . A. End Drop - Bottom Strike B. End Drop - Top Strike . C. Side Drop D. Oblique Drop
-r 2.10.6 Dynamic Crushing Pressure of Plywood 2 2.10.7 Limiting Loadings 2-53 A. Source Capsule Loading ;
B. Cover Bolt Loading ; 2.10.0 Puncture 2-54 i 2.10.0 References 2-36 l
'A. Accident Resistant Sh8.pping Containers B. Development Tests of Wooden Overpacks 2.10.10 -Tiedown Bracket Used As Lifting Attachment 2-58 ,
w j ;; -; L := L L- Revision 1 l 2-34 P ,
. z a . . .. a,,.. ...a.z.-._,--,..,z... . . . . . ,- u. -, -
I 2.10.10 Tiedtwn Bracket ' hod As li f tine At t achnent Requireaent: "Any lifting attachment that ic a ctructural part of a pschage must be designed with a minimum safety factor of three against yielding when used to lift the package in the intended canner, and must be designec co that failure of any lifting device under excessive load would not impair the ability of the package to meet other requirerents of this subpart." (10 CFR 71.4s(a)) Load: Maximum weight of package (6,000 pounds) acting vertically upward, uniformly distributed between the brackets. Maximum ' 1,500 pounds. static load per bracket: Component Adequacy: Reference Drawing N240116 l
- 1. Bracket eye - shear Shear area e 31/32 X 3/8 X 2 X 2 = 1.45 in.2 Load capability = (y.s.)(.55)(area)
= 36,000 (.55) 1.45
= 28,700 pounds Three times maximum lead = 3 X 1,500 = 4,50's pounde 80 yielding Safety factor (l) - 6.4
- 2. Bracket - tension For a vertical load - each bracket Section area = 2 X 3 X 3 X 3/8 = 3.2 in.2 Lead capability = (y.s.)(area)
= 36,000 (3.2) = 115,000 pounds Three times maximum load = 4,500 pounds - No yielding Safety factor (I) - 25
- 3. Support band and body flange - shear Upward force on bracket to reach shear limit in support ring
and body flange cross section only Section area = 3.68 in.2 Load capability = 36,000 (.55)(3.68) = 72,800 pounds Three times maximum load = 4,500 pounds - No yielding Safety factorll) - 16 4 Bracket attachment weld - shear Veld length = 8 inches (sides only considered)
Mini. mum weld section = (1/4)(.707)(8) = 1.4 in.2 Veld efficiency = 75*. Load capability = 2(36,000)(.55)(1.4)(.75) = 41,600 pounds Three times maximum lead = 4,500 pounds - No yielding Safety factor (l) - 9.2 (1) Safety factor to 3X yield strength Revision 1 2-58 _______ . . . _ .. . .. . s
e Shel; - ten i:n I 5. Tensien in shell Area = 40.5(.1072) = 16.3 in.2 Load capability = h.000(16.3) = 587.000 p m.d: Three times raximum load e 4 X 4.500 = 1B.000 pounds No yielding Safety factor (l) - 33 (1) Safety factor to 3X yield strength Revision 1 2-59
T: :5':..r.e t.e ::s: fi.r e a : I s.: r.t s e:ci.1:etua te?: erat re, ~, when tne rac t at ion source te'r , Erat ure is s0ecified, use 13 faaCU of tnt cifferen- geometry and cour:cary ctrcit ten cases worwec out in Taole 3 of tne reference to cctain an ecuivslent neat flux. Only ecnstant neat flux solutions are availaole for tne cylincrical anc conerical geometry cases. However, the semiinfinite slac geometry. for wnic1 coth constant temcerature anc corstant heat flux soluttoms are available, is used to cevelop a constant beat flux equivalent t the impesec constant temperature concition. The ecu1 valent heat flux is used to obtain cylincrical anc spnerical geometry soluttens. The adiabatic temcerature rise, T = T - Tg, w* sere the sucscript cesignates the particular case, using the nomenclature cf the reference.
- 1. Semi-Infinite Slab, Constant Surface Temoerature -
(3=(G/f)Mt /24)l/2 (T o f
-T)i ref. ecu. 27 a (6/0. 5) C (0. 0026) (0. 5) /14- 1/2 . (13eg)
= 1330:
- 2. Semi-Infinite Slao, Constant Heat Inout The ecu1 valent Constant heat inout is cctainec from this case using tne temperature rise calculatec frem tne previous constart terecerature case.
ATx3 = (c o (tf)/(k/) ref. ecu. 28 co = ( A T k l ) / ( Of tf)
= (133) X (0.085)(0.5)/(0.00353)(0.5) = 3114 B/hr. f t.2
?, Mfini.e Cylincer, Constant Feat Input 4Te e (i c SooM tf)/Ck % d - nial ref. eau. 19
= CI(3114)(1.833) it , A 363) (02 5) ] / C0. 08S (1. 833E-1.3.!3E)3
= 1540 -
Revisten 1 3-22
I *. 5:9er?, Constart Heat Incut l [g = (3::qy2 ct,t f) / Ck(R o 3-R 3); 3 raf. ecu. 30
= E3 (3114) (; . ES3) 2 (0. 0,036310. 52 / C 0. 085 (1. 883 3--
1.3334);
= 1770F Tne Wcocen Protec: 1ve Jacket is 45 inenes hign and 44 inches in outstco diarreter anc is procacly better representec ey a senere than by an infinite cylincer. The spnerical values are used for ^
evaluating the temcerature rise using the insice and outsace diameters of the Woccen Protective Jacket as the insi.:e anc outsice diameters of the ecuivalent senere. The peak eac< face temperature, T5 p = pean inside wall temperature of tne Woocen Protective Jacket is less than, but for the present pur::ese, tawen ecual to the aciacatic ecuilibrium tem::erature, Tpg T:5 = Tcg = 192 (initial)
+ 177 (actacatic rise) = 3700F C. Pea < 5/TC Temceratures The pea < S/TC surf ace teMoerature is ecual to the peak cackface temcerature plus tne croo (ISOC) neecec t? transfer internal heat generated through tne space between overpac'< and S/TC.
T (5/TC surface, post fire maximum) = 270 + 15 = 365CF The pea < temoeratures for the S/TC become: o S/TC surface 3650F (196CC) o S/TC snell liner anc crum C.D. (local max.) 450CC (2320C) o S/TC crum liner (local max.) 5450F (2850C) o Source ca:sule surface 670 0 c (3550C) inese teuceratures are unlikely to ce reacnec because tne inner container is unlikely to remain adiabatic for 22 hours (;200e/5.43CF/nr.) af ter the termination of the fire. Nevertheless, making the evaluation of the consecuence of the hypotnetical acticent en this basist (1) there would be no lead relting; the peak leac temperature is less than 5450- (the maximum local leac temperature is lower inan the local maximum temo'rature of the crum liner) as comparec witn a melting point of 6180F; anc, (2) the maximum source capsule surface temperature 535500) remains well below the weld sensitization temcerature (above 4600C). 3-33
4 r Specifications for welds and seals are included in the purchase documentation. As discu,: sed in Chapters 2 and 3, the internal pressure under normal transport is essentially atmospheric. 9tstulating extreme circumstaness under hypothetical accident conditions results in a calculated pressure of about one atmosphere gage. - 4.1.4 Closure The closure is mechanical, using B one half inch bolts on an 11-1/4 inch: bolt circle. The cover is bolted to the Shell Assembly and the closure seal is ' provided by a flat, full diameter, 1/16 inch thich silicone rubber gasket. The bolts are tightened to firmly compress the gasket with a torque of ' j-lapproximately100 inch-pounds.
~
The overpack provides two additional closures, but these are not.gasketed and are not intended to provide a gas tight seal. 4.2 Fequirements for Hornal Conditions of Transport The source capsule qualifies as special form material. The evaluation in Chapters 2 and 3 indicates that the shipping / transfer cask will provide a secondary seal under normal transport conditions. One of'the principal functions of the seal is to prevent any external contaminants, such:as-liquidt or particulates, from reaching the source chamber. 4.2.1 Felease of Padioactive Material Hone 4.2.2 Pressurication of Containmant Vassel There are no gases that can form and/or explode in the containment chamber. There has been no evidence.of pressure build up in the sealed drum -1 chamber in practice. Any foreseeable change in chamber pressure will not reduce package effectiveness. 4.2.3 Coolant Contamination Not applicable 4.2.4 Ceolant loss Not applicable y
'4 . 3 Containment Requirements for the Hypothetical Accident Conditions The evaluation-of test information and associated analysis presented-in
- Chapters 2 and 3 show-that the package could experience-the sequence of conditions postulated in 10 CFR 71.73 without release of radioactiveLmaterial or significant change in shielding capability. In addition, the encapsulated.
. source meets.special form requirements, which are at least as stringent as the-accident conditions for the package.
Revision 1 4-5 u
ett3:ec..stiva .ecent shipments with tre entsting pa:lage. These pr ovide a
- ne ft: ::mp.rls ; vtth the nev ;aclage. The desirn guidelines fer the new parl ge n e a tua::I m m ic t e c at a o f 100 n-c ./ ht . at the accessible sur f ace of the
;a:1 age -.i 10 n r . / h . at a distance Of :ne meter fr em the sur f ace of the ;acl ue f:t not inal 1:nditicns f tr ansp r t. These are the values listed in Tal le 5.1. 2.
A t&;u lsen of the r adial gamma r e/ attenuation between the new and entsting inner container is detallei in Appenit:. 5.4.1. On a comparative tasis, the new container vill t er mit an incr ease of 54 percent in source str ength f or t he s vae c u l sur f ace dose. This facter, along with the initial shielding design margin of the casis, as sh:wn in Table 5.1.1, pr ovides a s atis f attery 15,000 curie operating limit for cobalt-60. This is further supported by a surface and one meter distant dose r ate for the paclage calculated to be 10.4 mr ./hr . and 1.4 rr./hr.. respectively, f:c a contained - 15,000 cur ie s:ur ce. This :alculati n is als: included in Ap;endin 5.4.1. Tl e ;r inc1; al ;hysleal change t: the drum of the new paclage has been to
- e:reue the dr un liar tube inside diameter f r en 2.22 to 2.56 inchet , while nalntaining the 0.0o$ in:b tube vall thitlness. In the radial litection, the
- ban;e avevnts to replating 1/2 to 2/1r inches cf steel and clear ance with an qual th :! ness Of lead. The chan;e als: redu es gamma str eaming in the anial 11 recti: b/ f atter s calculate! t; te 1.1 t: 7.2, depending upon the source
%1 der ::afigur ati:n. The supp rting calculations are provided in Appendin f
_.a. . The ::d / other p:ysleal change t: the new inner container that impacts frieliin; la the reiuttien in the cutside diameter of the Shell Assembly
. :ner . The effect is te replace a 2/1t thielnest of steel with an equivalent n:unt :: lead. The principal influence is an increase in r adial attenuatien.
This f t:t r has been included in J e tal:ulation, shown in Appendin 5.4.1. Subsequent to the calculati:ns and compac 1 sons described above, a paclage _
- ne: pu ttint; the aw inner c:nt uner :ar r ying a 6,650 curie sour ce was
;a110 3:r surveyei. The r esults are provided in Append 1:- 5.4.2. As ent w: lated to 15.000 curies, the pacinge manimum surface reading would be 24
,r./hr., as 2:miated with the design basis value of 100 me./hr. and the 10 CFE
'l. 7 11 nit of 200 nr./hr. f:r gener al tr ansport. At one meter distant, the level 90u11 be abrut one-third of the 10 me./hr. general transpect limit.
The .bange 1.i hielding effectiveness under hypothet ical at:1 dent 1:nditi:ns is due t: shifting of the inner container with ref er ence to the rutar sur f e:e of the paciate as a consequence of the 20 foot dtep. With a nanimum est: mate'l inner cont ainer shift of seven inches, the surface dcse intr esses by a f act:r of 2 eni the dose at 1 meter by about 25 percent. Both values are belev the 10 CFB 71 limit of 1.000 mR/hr. at 1 meter fer the hypothetical accident condition. There is no ciportunity for any measurable shif t :f s our ce or shielding within the inner atainer under the most severe fr ee drop condition. Gr eater detail is pr evia in Appendin 5.4.4. l Pevision 1
- c. . e.
- --' ^-- - - - - _ _ _ _ _ _ , _ . _ _ _ _ _ . _ . _ _ , _ _ _ _ _ _ _ , , _ _ _ _ __ _ __ _
5.2 Er ree Erecification 1 The :nly sour ce c'snsidered for r adiation shielding design and evaluatien
.;.I'd
-l vas the 1.17 MeV e... . 33 MeV photens produced #:cm each cobalt-60 decay.
- There is no neutron source.
t fh, -- TABLE % 1.2
~.[ %
jgs v
SUMMARY
OF MAXIMUM DOSE BATES " (mP/hr.) ? One Meter From Pacian Surface Surface of Paci. age Sids Top Ecttom Side Top Bottem f. Normal C:nditions G ar .m a <100 <100 30 <10 (10 Heutter. H/A N/A /A N/A N/A i4 / t.
'otal (100 /100 100 <10 (10 <10 Hypothetical Ac dent Conditicos Gamma <200 <2M (200 <20 <20 (20 Neut;:n N/A N/A N/A N/A B/A H/A Tatal (200 (200 (200. <20 (20 <20
.,000 1,000 1,000 y 10 CFE Part 71 Limit --- --- ---
Eevision 1 5-4
5.4 i3d=! iretificatien The : Bleldirq e'ulv ati = 15 tased cr. rceesur ements made en generally similu pa lages and determining th changes in 1.e rate due to the ccmparatively small chanres in geometty and materials. *?he changes were made by calculation empicyir.; a sirnple e::ponential attenuation model postulating an isotropic s our ce . Euildup iactor s ver e cbt ained fr Ou the Eadiological Health Handtcoi, hvis +1 Ilitica (January 10'0) . Values of me.ter ial dens ities and mass attenuation coef ficients are shevr. In Table 5.2.1 and were obtained from the s ame s: n ce. Streaming was also censidered. The calculational mcdels erployei are described in Appendices 5.4.1 and 5.4,2. Subsequently a r adiation surney c f a r ef ecenced shipp:,ng paclage nr evided r esults which ccmpared favor ably with ! the cal:Slations, n
)
f y$ TaELE ! '.1 EHIELDING ? Aptt 1ETEES Mas 2 , -bc er pt ic:. 9 Densite Coefficient > atseia: en/ : cia 2/em Tungsten alley 17 0555 i
;eal 11.2 .05S Stainless steel E.0 .05*
Cact:n steel 7.25 .054 Revision 1 5-5
. , . .. .. . = - .. .- ....: .. . . ~ . - . . . .- _ - ... . .
..7 .
;; +
a 5.4 APPENDIl i Pere
- 5.4.) : Radial Gamme ' Attenuation 5-7 ,
5.4.2 A::ial Gamma Attenuation .5-11 ., 5.4,3' Package Eadiation Measurements .5-14 : 5.4.4 Hypothetical Accident Condi' ions 5-14
.1
+
r i t
'.h P
-n Revision 1 3-6 A
k
'..('.' '
' ' - - ~ - - _a . 2- - - _ _, _ :_ :__ _
5.4 ' Puial Gwma Att enuat ion The <pecifi: shielding arrangement within the drawer or holder placed in the drum chamber may var y. However, a comparison of r adial (in the plane perpendicular to the anis of the drum) attenuation in the original with that of the new inner container can be made from the drum liner outward. This compariton, along with an overall calculation of dose rate for the new package in the calial direction, is presented in this appendir. For toth pur poses a point ;ovree model was used. For the comparison, the attenuation from chamber vall to enterior of the inner container, [I /I]S/TC c was talen as the product of the individual shielding components.
.!1.
(Ie/IlS/TC * // Bn (in X n, E) enp ( n X n) where B n is the tu11 dup factor,p n tie linear attenua.lon coefficient, X nthe t*fel. ness of the s hield compenent under consideraticn, eat n designates the Wticular shielding material comp:nent. T able 5. 4.1.1 lists the input par ameters f cr the calculCien, is well as the results. The configur ation is shovr. ichematically in Figure 5.4.1.1. The ,
- enstituent mater ial attenuations are shown fer each of the shielding component materials, as well as the total for both the original. and new inner
- ntainers. The ratio of the new to the original cast attenuation is 1.54.
Soolei et in another way, for the same surface dose, the new cas). would have t: centain a source str ength 54 percent greater. The original inner containet- vas n:t consider ed shielding limited at 9,500 curies , so that no absolute level of scurce st:ength can be determined t>y this means; however, when applied to actual pact age measurements, su:h as those shavn in Table 5.1.1, the paclage irse r ates with a 15,000 curie source couli easily meet normal shipping r equir ements . e The dese rate at the paclage surface and at one meter distant were also -
- alculated in the 7 41a1 direction. The attenuation due to shielding inside cf the source containing drum chanber and the smail attenuation due to the "
- verpack were combined with the SITC attenuation shown in Table 5.4.1.1 to provide the tot al material attenuatien of the packaging. The additional constituents, as well as the overall result, ar e presented in Table 5.4.1.2.
The everall shielding attenuation. I,/I is 5.75 X 103 Combining this with
- be source dose r ate relationship (l)~1n the abs ence of shielding I, = Dese rate at distance d,em from C curie source
= 5.2 X 100 C E/42 mr./hr.
vbere C = If>,000 curies E = Total gamma energy /disintegr atien = 2.5 Mev for cobalt-e9 d (surface) = [(43.5/2) - 1. 7 5 ) 'i . 5 , = 5 7 . 2 cm d (G 1 meter) = 157.2 cm (1) 5. Glasstone, Princirues of Naclear Enrineerini, pg. 545 , Revision 1 5-7 I l - -- _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- t 9- ;
I6E'5 s Es.huls1' CALCULATID RO A sVMA ATTINUATION CN#43!S:t Locaticn(1) ano Material -Linear New/Griginal anc. Absorption-Inner Thickness, Coefficient - Butidup Attenuation- _Oscs.aicec__ ___ict . .__ ___scs:1___ Eester_R1 _19 4L12)
- 1. Drum Liner S. S. (3)
New 0.095 0.432 1.09 1.02 Original Same as above
- 2. Drum Shielding- uecd .
New 0.782 0.655 1.47 2.53 Origina1 0.625 0.655 1.40 2.02
- 3. Drum Casing S. S.
New 0.187 0.432 1.17 -1.046-Original 0.219 0.432 1. E0 1-.056-4 Shell Liner - C. S. (3) New 0.187 0.424 1.17- 1.'044 Original C 373 0.424 1.34 1.115
- 5. Shell Shielding C. S.
New '7. 69 - 0.655 4,75 7.63 X 10' Cri;inal 7.50 0. t655 4.65. 5.68 X~10 4
- 6. Snel; 0. S.
New 0.375 0.424 1.34 1=.115 Criginal Sace as acovo S/TC Attenuat1 n, // --(weal' 2.37 X 105 S/TC Attenuatfo , F toriginal) 1.538 X 105 Rat to, 7 (new) / /7 (original)- 1.54-(1) Numcers Reyec to lacations shown in Figur*. 5.4.1.1. (2) Attenuation, lo /I = Bp x, E) .exo % x). Builduo fac or cased en-ootnt isotoote source. - (Ractological Health Hancocow, pgs. 145-146.)- (3) S.S. = stainless steel, C.S.-= careen steel Revision 1 5-8 4 4
- y- ,, - , - e e -
I t; [ 'N. 6 SH~JLL e- 5. SHELL SHIELDING
- 4. SHELL LINER
- 3. DRUM CASING
- 2. DRUM SHIELDING
- l. DRUM LINER
- SOURCE CENTER
- DRUM CENTER
/' \.
; /u I
l N \
.t. ;I +
FIG. 5.4.1.1 _ STRUCTURE & SHIELDING ARRANGEMENT KEY FOR TABLE '5.4.1.1 Revision 1 5-9
. = _ - _- - __-____ _-____- _ -____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ ____
~
s~g Y 16ELI_"1.fts isl
= -- - CALCdLATED DOSE RATE FOR. NEW PACKAGE -
1 Material' Linear and Absorption Thickness, Coeffacien'. Peilcuo: Attenuation'- Lesatien_ _ __10 3.___ ___EE! .:1_ _ __ _ - Eesit . _lgt.l_
- Source capsule Tungsten alloy _
0.437 0. 9 'e 4 1.47 h 94' . + Source enamber Statniess steel steel 0.314 0.432 1.29 -1.092 x, Source charncer to innere container surface From Tanle 5.4.1.1 2.37 X~106 Wooden protet3,e<4 Wooo , Jacxet- - 6. 0 0.0394 1.62 1.21 ; Steel snell Caroon steel , O.107 0.424 1.10 11.032 a E Total material at:enuation, source to package surface (I o/M = 5.75_X'10 b' 3 J 3'.
. Revision 1 -
'5-10 .._..
_-j.
, - + , , - -. . . ..: ..;, ., :~- , - . - - -. . ,
Yields the f ollowing surface dose: ( 5. 2 X 10$)(15.000) (2.5) /( 5.75 X 100 )(57. 2 ) 2 = 10.4 me ./hr . The dose at I meter 1s: (5.2 X 106 y 15, coo)(3,5)f (5,75 y 19 6)(157,2 )2 = 1.4 me ./hr . These values ccmpare with 200 mr ./hr . and 10 mr./hr. , respectively, f or normal shipment. The mar gin pr ovided appear s adequate f or s2 cht changes in s hield ?.ng, thici nes s , geometry , or calculational uncertainty. 5.4.2 Anial Gamm Attenuatien Evaluation of the shielding in the direction par allel to the anis of the new inner container drum involves the source loading arrangement. The loading ar r angement of a source in an international capsule is shown in Figure 4.3. This is r epresentative and one of the more frequent loading arrangements. The 2.56 inch diameter drum chamter is fitted with a stainless steel sleeve having The an outside diameter of 2.50 inches and an inside diameter of 2.060 inches. capsule is placed within the sleeve and held in the axially central region of the drum with tut tungsten alloy plugs, one on each side. The covers hold the entir e cs sembly in place. The arrangement in the original inner container is similar, encept the drum chamber is 2.31 inches in diameter and a second sleeve of 0.095 vall thici. ness, surrounding the fir st is used to fill the space and center the source. For both cenfigur ations the shielding arr angement in the anial direction is a plug of tungsten alley 0.C in:.hes long and 2.03 inches in diameter (about twice the diameter of + he sour ce f ace) surrounded by an annulus of steel with either two or thr ee nar rew air gaps. This assembly, in turn, is surrounded by a mantt in cf lead. The arr angement is shoun for the new drum in Figure
!.4.2.1.
Based on a point scurce, a simple calcult. tion shows that for a shield thic} ness of 9.8 inche. (the length of the plug and approntmate distance from the source to the f ace cf the shell assembly), the attenuation in tung: ten alloy is of erder 10iO. that in lead of ceder 107 , and in steel of ceder 104 '41th the highest lealage path being that through the annulus of steal. l a compu ative neature of attenuation between the new and the cr131nal The I arrangement can be made by traating the st.M1 annulus as a streaming path. annulus is thinner in the new arrangement. To determine the r elative itreaming, the following entressionll) for the r atio cf entering to leaving ga.nma flun was used and talen as proportional to the correspending dose rates: (1) Source: T. Recivell, Reactor 9h'elding Manuel, pg. 293 Devtsion 1 5-11 l
.1 TUNGSTEN COVER ALLOY } 1, STAINLESS STEEL _' ,
.%. s --
b} .i.'v Y X' M M [ ' W N M )( '-
\:- '
4
- 7 GASKET g
.. f e -
- .. ; /- f* 't
] -LEAD URCEi h l HC - * * * .. A , _.,_
r - 4 - 9y h l- 8___ 1
-g- - C. STEEL
/
~ 3~I 8
I8 I 4 I g
. LOO m. mm. IO 8 SILICONE GASKET
. ~9 16
(.04 0 n. min. S.S.)
. CASK (
= 10.81 FIG. 5.4.2.1 -
- DETAIL OF INTERNATIONAL C APStJLE LPOSITIONING WITHIN, INNER : CONTAINER DRUM.
( REE FIG. 4.3 )
,a x g
95 / ylt. = 1/2 77 L2 g(ce, I efp)(gg2 _2 r ) - r(R2 - r2 )l/23 The definition of the symbols and the corresponding values for both thi new and original inner containers used in the comparison are as follows: Value Oririnal S/TC's New 9 /TC's_. - ! d gamma flux - - p(ta,len proportional to dose rate) R, drum chamber radius, in. 1.405 1.280 r, shield plug radius, in. 1.02 1.02 L, comparative shield thickness, in. 9.81 C.81 Fcr the origi:.al units: q6/ 690 = 1/277(9.81)2[(cos"1 1 02/1.405)(2(1.405)2 - (1.02)2y
- 102((1.405)'4 - (1.02)2 31/2)
= 2.01 X 10-3 For the nev .its:
95 / 893= 1/2%(9.81)2t(cog-1 1,92ft,73)(2(1,73)2 - (1.02)2)
- 1.02((1.2812 - (1.02)2)1/23
= 1.095 X 10-3 The increase in attenuation is propertional to' 2.01/1.095 or '. 84, which is close to a facter of two.
Another loading arrangement that occurs frequentl'; is one in which'the entire teletherapy machine drawer, with source loaded. is- carried in the drum chamber. In the case of the AECL machine, for example, the shielied drawer. with center' positioned source, is the full length of-the drum chamber and 2.47! inches in diameter. The input values for the calculation are: Value Original S/TC's Hew S/TC's E 1.405 1.280-t 1.234 1.234 L 10.8 10.9-Revision 1 5-13 4 4 f __s
Substituting the nev values: For the original units 96 /g fo = 5.137 X 10-4 For the new units qd /g$ e = 7.01 X 10-5 The increase in attenuation for the nev units ir 5.18'/.701 = 7.3 on a factor of about seven. Other specific cases vill vary, but the improvement is significant. 5.4.3 Packare Radiation Measurements The results of a radiation survey of a package incorporating the new inner container are provided in this appendin. The survey was mada en December 4, 1986, on a package that had been prepared, foe shipment and sealed a few days before. The source strength was 6,650 curies (12/1/86). The source was fittef into an international capsule and held in the central region of the drum chamber between tungsten alloy end plugs. The remaining drum chambers were loaded with full length, lead filled plegs. Measurements were made with a calibrated G-M detector. The package surf ace measurements are shown in Figure 5.4.3.1. All of-the radiation entries are in me./hr. T1' ma:rimum reading was 15 mt ./tc. at the center of the package bottom. The highest side readings were .14 me./hr. and e mr./hr., located 180C from each other at a belt line height of 24 inches. The remaining surface readings vera between 0.6 and 5 mr./hr. at locations as-shown on Figure 5.A 3.1. All readings tahen at one meter distant from the package surface vere 1 mr./br. or less. No measurement was talen at one meter between the bottom of the paclage. Based on these measurements, the design basis 15,000 curie source would result in a manimum surface reading of (15,000/6,650) X 15 = 24 me./hr., as compared with tha design basis value of 100 mr./hr. and the 10 CFE 71.47 limit of 20T mr./br. At a one meter distance, the level would be one third of the limiting 10 me./ht . These re=u2rs also generally support the calculations provided in Appendi 5.4.1. 5.4.4 Hypothetical Accident Conditions Any change in shielding effect resulting fecm the Hypothetical Accident Conditions is due to shifting of the inner container within the overpack. There is no opportunity for any measurable shift of source or shielding in the inner container under the most severe free drop and fire conditions. E:: cept for some small clear ances, the inner container is completely filled with metal. Revision 1 5-14
NOTE: FAR SIDE READING IN ( )
. ALL READINGS IN mr/ hr.
2.5 To 3 [ 2To3
/ '
2.3 h h 5} '
]
3 To 5 2.3 To 5
/
4 UPPER PERIPHERY-NEAR SIDE O.8 ALL AROUND
;O.6
/ '
N
-_2 l
0.6 To 1.0 d 4 1.0 (O.6 To 2 ) r N I
- /
5 +(- 14 (6 ) x 3 7 3To4.5d > 0.6 03 2.3 241n. I N _
,/ /
n 4.5 / ""
}i5 {
"i" LOWER PERIPHERY FIG, 5.4.3.1
<3 ALL AROUND EXCEPT AS NOTED MEASURED PACKAGE SURFACE RADIATION LEVELS FOR A CONTAINED SOURCE OF 6650 CURIES Revision 1
e The_manimum shift of the inner container within the overpack can te - obtained from the analysis of the several hypothetical accident drop conditiens. The shift of the scurce relative to the outer surface of the package is due to.the crushing, bending, er other distortion of tie overpach-vooden protective jacket (WPJ) and steel shell (SS). The results obtained fron
+
the accident analysis are summarized in the following table: Manimum Displacement of Source Relative to Hermal Location in Component of Packages, inches Overpack Top Bottom Sid: Edge Drop Drop, Drop (l) Affected Dr oD Crush support beams (SS) 4 - - Shred shock ringe ~1PJ) - 2 Inner container movement - 1 2 Inner container penetration 4 of WPJ - 1 After fire drop, char
- 2 allowance 2 2 _
Manimum Displacement. in. 6 7 7 - IIIH ot critical for shielding. The amount of shielding material vill remain the same. The-shielding change vill result only from geometric factors. Postulating a. point isotopic source, the increased transmission due to the seven inch manimum displacement is: At the surfaces (E' 4 )2 = 1.97 24.4 . At one meter (63*' )2 = 1.26 63.8-7 As suming the surf ace radiation level under- pr e-accident. conditions was at the 100 me./hr. design basis condition, the hypothetical accident vould result
.in a surface radiation level of less than 200 me./hr. S larly, postulating the permissible 10 me./hr. pre-accident, the postaccident i meter. dose rate increase would be less than 3 mr./hr.. In.any case, bott levels are below the 10 CFB 71.51(a)(2)111mit of I rem /br. at one meter from the enternal surface of the package under hypothetical accident conditions.
Eevision 1 5-16 i
, ws e m + -
4
. 7. +. l TELETHERAPY SHIPPING / TRANSFER CASK UNLOADING AND LOADING PROCEDLTE PROCEDURE R 2014 Revision 1
~ .1 December 12, 1986 Reviewed for Radiation Safety and Approved Ab b.gh /2 f/lo N Date Frank Schwoerer Reviewed for Adequacy of Intended Purpose /
and Approved / /Is,.[8. /rh /8 - / 7-N p f fiey/ W. Cotun Date 4 n Reviewed per Quality Assurance Program 7 and Approved 'MA W . N , Sf 87[;El., Wayneb h ey g_Date ' w 9 4 1,*
.{'.
e 1 1 4 .I lg f _? . l , i
' 5* ~ j_
i- , ,_u,
lg s
-m IINLOADING AND LOADING OF NPI-20WC-6 TELETHERAPY SHIPPING PACKAGE AT THE DICKERSON HOT CELL PROCEDURE R 2014 Revision 1.
December 12, 1986 SCOPE The teletherapy shipping package, NPI-20WC-6, consists of a specially designed inner lead shielded shipping / transfer cask contained within an overpack. This procedure covers hot cell unloading and loading of dou' sly encapsulated sources out of, and into, the approved shipping /cransfer-casks, and shall be used in conjunction with " General Procedures for Hot Cell Source Operations." Enclosure of the cask within the overpack and unloading and loading the shipping package is included in the procedure. For operations at other hot cells, this procedure will be modified as-necessary. BACKGROUND' Both unloading and loading is covered here in a single procedure because the most frequent circumatance in the shipping and transfer of. taletnerapy sources is receipt of a package _containing a spent source which, af ter appropriate initial operations and surveys, is removed from the package in-the hot cell and placed in interim stcrage;-whereupon the cask is inspected, cleaned, resleeved as necessity .and -loaded with a new source tu the hot cell for subsequent shipment ofi cite. Loading an initially empty container and similarly, unloading a container to be : placed into standby or serviced in an- empty condition are included .as variatic of the procedure.
- 1. REFERENCES
- Sampling Procedure R 1002
- General Procedure for Hot Cell Sourec Operations,R 5001
. Opening Hot Cell Door ~ Af ter Processing Single and Dot 31e Encapuulated Sources R 5002.
- Applicuble Certificate of Compliance (for.' domestic destination) or Certificate of Competent Authority (for foreign destinations) '
' for the Shipping Package o - Package Loading- Procedure for Radioactive Materials, QA 1003
- Package Unloading Procedure for Radioactive Materials, QA 1004'
- Empty Radioactive Materials Packaging, 49 CFR 173.427 . l
- 2. GENERAL CONSIDERATIONS Sources shall be ;1caded only upcn written instruction ;af ter it has _been determined-that=the sources; meet all specificchions, including custe'er's;m and cask Icading specifications.
9 a M i . . . , _ 9 J
1 4 2_
- 2. GENERAL CONSIDERATIONS (Cont'd)
The shipping packages usucily contain radioactive material upon receipt and all procedures and precaations associated with handling radi active materials must be followed.
- 3. PERSONNEL AND SUPERVISION REOUIREMENTS Radioactive materials may ba loaded or unloaded from transfer containers only by experiecred hot cell operators, acting under the authority of the' Hot Cell Manager, Vice President of Services and Systems or his designee.
- 4. EQUIPMENT
- Operating Hot Cell
- Shipping / Transfer Cask
- Shipping / Transfer Cask applicable inserts
- Survey Meter capable of reading up to 2R/hr
--All.necessary tools 5 OPERATIONS 5.1 Preoarations 5.1.1 Confirm with the Production Manager, or other individual responsible for the shipment, the following:
a) source (s) identification b) activity of source (s) c) applicable Shipping / Transfer Cask and source holder d) - applicable. overpack (wooden protective jakket and ' steel shell). 5.1.2 For shipment receivod - unload the NPI-20WC-6.packa' ge .f ror. ;the truck in accordance with QA 1004. 5.1.3 Remove bolts and lids from the steel shell and wooden protective jacket, raepectivelv. Store for reuce'.. 5.1.4 Remove shipping / transfer cask from'the overpack. Do not Isave wooden protective jacket-open to vecther. . Inspect: overpack for damage and repair if necessary. Store overpack for next use with-wooden 711d and shell' cover La' place. _ 5 .1.' 5 Measure: radiation: levels to ' confirm that. handling of cask' vill.lue a-109 level operation. , l-J.l.6 Open' hot cell door per applicable _ procedure. a 4 1 3 s . .' a. Id
o 4 4 5,1.7 Place the Shipping / Transfer Cask on.the. dolly in the hot cell access area. Using the forklift, place the loaded dolly. on the cask loading rails. Renove bolts holding one of the Shipping / Transfer Cask covers. 5.1.8 Make certain end of cask faces shielded area when removing - Cover. 5.1.9 Confirm whethe- the cask contains a source by both measuriug the radiation _avel near and visually inspecting inser's at # the open face of the container. Any reading abcVe background abould be considered as indicating a loaded container. 5.1.10 If Shipping / Transfer Cask is loaded, proceed to 5.1.12. 5.1.11 If. Shipping / Transfer Cask is emptv, remove inserts, clean the inside of the container, check drum rotation (where applicable), wipe test the inside of the-container and' inserts and reinstall applicable inserts. The inside surfaces of the Shippin5/ Transfer Cask.and the inserts should net exceed a count' rate of 500 dpm per 100 cm 2
~
on the wipe test. Clean aad~re-wipe as necessary to meet this limit. 5.1.12 Load Shipping / Transfer Cask, appropriate insert or holder-and all necessary tools into cel?.. ' 5.1.13 Close hot cell door. 5.1.14 If Shipping / Transfer Cask is emotv, proceed to 5.3. . 5.1.15 If Shipping / Transfer Cask is loaded, proceed to 5.2 L 5.2 Unloading L 5.2.1 If container is loaded, remove source holders-and remove sources from holders. 5.2.2 Visually inspect source for damagv and evidence of failure of source integrity, g .3 5.2.3 Wipe test source. a l- [. # k s
, . . .~. - . . . ~
P 5.2.4 Acceptability _for source storage: 5.2.4.1 If the source passed the visual examination and~if the removable contamination determinid by the_ wipe-test is less than 0.05 uci, place thu source in storage and note in the inventory record. 5.2.4.2 If the removable contamination as_ determined by. -1 wipe test is greater than 0.05 uci, the source should be visually re-examined. If the examination reveals no sign of cladding failure, decontaminate and wipe test again. If.the results of the wipe test after decontamination is-less than 0.05 uci,- the source shall be considered acceptable a.c placed . in storage. ~ 5.2.5.3 If there is any sign o# cladding failure cr.if the wipe test after decentamination is greater than_0.05.. 1 notify the Production Manager and establish corrective action to be taken to prevent significant contamination in atorage. Note condition and action taken in the .it call log. 5.2.5 Open hot cell doc: reing reference procedures and. move emoty cask into - hot cell access area. 5.2.6 If the emety cask is to be reloaded for outgoing shipment. proceed to step 5.1.11. 5.2.7 If the empty cask'is to be shipped empty or' taken out of. service, remove inserts, clean the inside of the container and1
~
i vipe test both the inside of the container and the' inserts. The inside surface oT the shipping / transfer cask and the 2 i inserts should not exceed a count rate-of 500dpm per 100cm on the wipa tests, clean and rewipe as necessary to meet this 11=it. 5.2.8 If the emety cask is to be shipped empty, install inserts .(it appropriate), and bolt gasketedecovers.into place. Tighten bolts to; firmly compress the gasket (aporoximately 100; inch-pounds torque). Insure requirements of 49 CFR 173.427 l regarding shipment of' ecpty radioactive packaging materials ' are' met. Proceed to step 5.3.10' or an alternative special procedure.. 5.2.9 'If -the' entoy ensk is to be. taken out of service, install the covers along with any internals to be_ stored and place the-cask into storage.-
~
a
~5-t 5.3 Loading Note: Before luading, cake certain that all applicable preparation steps starting with 5.1 are completed.
5.3.1 Recove cocpl.ted and inspected source from storage. 5.2.2 visually inspect source for damage and evidence of failure of ' source integrity. 5.3.3 Wipe test source. 5.3.4 Acceptability for source shipment: 5.3.4.1 If the source passed the visual exauinction and the removable contamination deter =ined by the wipe test is less than 0.001 uci, the source is acceptable for shipment. 5.3.4.2 Repeated decontamination and wipe testing is acceptable in creting criteria. 5.3.5 Load source into appropriate holder and the holder into the designated position in the Shipping / Transfer cask. 5.3.6 Record the identification and location of each source in the cask.
~
5.3.7 Open hot cell door using referenced procedures. 5.3.8 Place cover on the Shipping / Transfer Cask. 5.3.9 Remove Shipping / Transfer Cask from hot cell and tighten bolts to fircly compress the gasket (approx!aately 100 inch-pounds torque). 5.3.10 Deconta=inate Shipping / Transfer Cask. 5.3.11 Wipe test Shipping / Transfer Cask and de:. taminate as nece ssary. 5.3.12 Measure and record maximum radiation levels at surface and at I ceter (3.3 feet) . , 5.3.13 Complete and pit.ce appropriate label on the Shipping / Transfer Cask. i
- v. =-
~6-5.3.14 Load Shipping / Transfer Cask into the_overpack and install =
wooden protective jacket cover. Belt cover 1 firmly into placa., caking _certain that all_ thread reinforcement rod ends remain recessed at leact 1.5 inches below the surface of the wo, .n;- protective jacket. 5.3.15 Bolt overpack steel shell. 5.3.16 Fit steel shell cover and bolt into place.
' 5.3.17 Affix appropriate labels for the shipment and load the NPI-20WC-6 package onto the truck in accordance with QA 1003.
- 6. RECORD RECUIREMENTS
'6.1 The Hot Cell Log Book shall contain:
Identification of tne cask that has been' loa'ded. , Identification and in-cask location of sources'that have
~
been loaded.
- Name of operator. '
- Results of all wipe tests and results of source inspections.
- Dose received by operator as read on the dosimeter.
6.2 Make the appropriate entry into the inventory record. 6.3 The Production Manager shall review the Hot Cell Log Book for compliance with the procedure at least once a day.and shallleither indicate = its adequacy by initial'.ing at the end 'of _ each days entry or shall note-and initial'any-inadequacy. The RSO shall review the Hot: Cell. Log Book at least weekly and shall make-stailar not<. ions.
-R 2014'-
Revision 0
' Diskette C-g s, .
- v. _
- Inspection' records or certificates of conformance attesting to the a:ceptance of material and components are available prior to equipment installation or use..
- Items accepted and released ate identified as to their inspection status.
8.1.1 Visual Inspections l Visual' inspections will be conducted to insut e that- the packaging is in conformance with the drawings and specifications. Welds which are part of the boundary of the lead containing cavities of the inner container vill be inspected using dye penetrant or other suitable techniques. This includes the Drums, Covers, and the Shell Assembly. Any= evidenca of weld cracking will be repaired by removal of the metal in the indicated region and satisfactorily revelding the joint. -
~
In additicn to dimensional checks, visual inspection of the Wooden Protective Jacket vill include proper bonding of the plywood sheets and installation of the reinforcing rods. The outer Steel Shell will be visually inspected for veld quality. Any questionable areas will be revelded or reinforced. 8.1.2 Structural and Pressure Tests Not applicable 8.1.3 Leak Tests In fabrication of the inner container, the chambers containing lead shielding will be leak tested before filling to assure containment integrity. Leak tests of the inner container closure are not required in normal service. 8.1.4 Component Tests Not applicable 8.1.5 Tests for Shielding Integrity Before delivery, the inner container will be tested and -inspected by nondestructive means and evidence submitted to show 'that the required homogeneity of shielding is provided to meet the shielding specifications. Tt+ outer surface of the cask will be surveyed with-a cobalt-60 radiation source it the central chamber. Normally this is done by surveying ths entire accessible surf ace of the cask. In the case of the inner container, almost all of the outer surface is accessible. As a minimum, t owever, a 14 point survey will be made- (on the surface face intersecting each of the principal axies, plus the central point on the face of each octant defined by the three principal pienes containing the centet of the spherical shell) and the values recorded. Any area showing surf ace radiation more th_ .i 15% above -the average wheru lead . shleiding thickness is comparable will be repaired and retested. , Revision 1 8-2 1 < -~ -. .. .. . . .
8.1.6 Thermal Accertance Tests Hot' applicable e.2 Maintenance Prograra The shipping package does not contain liquid shielding, coolant,_ valves, pressure gages, rupture disks, etc., thereby simplifying rege!ar maintenance. In ,ddition to periodic routine visual inspections, .the following routine maintenance is performed:
- Components of the package are checked for contamination when it is being-leaded or unloaded and decontamination is effected as required.
- When the end covers are installed or removed, the condition of the silicone gasket is inspected and.the gasket is replaced when checking, hardening, deterioration, or any damage is observed. -The gaskets are replaced within.a 12 to 18 nonth period in any event.
- Prior to each use, the Wooden Protective Jacket is inspected for defects, or conditions potentially leading to defects, such as loss of plywood bonding, crachir,g, waterlogging, excessive drying, corrosion of- the steel-rods, or any body or cover varping that would result in an inadequate cover seal. Should any of these conditions be observed, the situation shall be evaluated and a' repair made, or_the Wooden Protective Jacket-talen out of service.
- The overpack Wooden Protective Jacket and Steel Shell are inspected for damage when being put.into, or taken out of,, service. ' Space parts are Lept in stock and replacement or repair is made as required.
~
Bevision 1-l' 8-3 l
;~
l l , , - Neutron Products. Inc. Mocel tio. NPI-20WC Mk II Docket No. 71-9102 Encl to ltr dtd: E 19 E DRA',IINGS
- 1. The applicant has requested an amendment to the certificate of compliance to increase the maximum activity of the Cobalt 60 sealed source from 9,500 curies to 15,000 curies. The application (Page 1-1, Section 4.0 CC "d '
and Section 5.0) makes various statements describing tungsten shields M *' within the scaled source capsule and tungsten alloy inserts used in the / drum assembly all of which seem to be required to accommodate the increase in source strength. ,cI p, y
/77 S+. I. /
The shielding requirements should be clarified by revising the package /~,y.f% 2./ drawing to show, in detail, the arrangement of shielding materials required to accommodate the increase in source strength. ,
- 2. Drawing No. 240122, Rev. A. The drawing should identify the weld joints to be nondestructively examined, the method to be used and the code or standard for the examination procedure and acceptance criteria.
- . . m pwy. 240n2 Rev B o The drawing should note the torque requirements for the closure bol ts . - .
o The weld symbol joining Item 27 to Items 29 and 31 should be corrected to agree with the joint pictured in drawing Zone H3 *
- 3. Drawing No. 240116, Rev. B. The drawing should specify, either by note or by detail, the application of a tamperproof feature to satisfy the requirements of 10 CFR 571.43(b).
Bug 2 4-0//6 Ecx C o The drawing should previde, either by note or by detail, the marking y and identification requirements of 10 CFR 971.85(c). o The drawing should note that the 1/2-inch diameter vent holes in the steel shell should be covered with a durable weatherproof tape or equivalent device. STRUCTURAL
- 1. Demonstrate that' the tie-down brackets, which could be used as lifting 2 .4. 4-devices, are designed to meet the requirements of 10 CFR 571.45(a). 2. 10.10
- 2. The si::e of bracket attachment weld is not specified on Drawing No.
240115. All packaging weld joints-should be shown by appropriate weld symbol. Swf. 2 40// (> Eev C
-3. Demonstrate that the cover bolts for the inner container will not be 2.7. /. 7.
stressed beyond the yield stress during the 30-foot flat side drop. I i
2 SHIELDING Section 5 of the application discusses the shielding adequacy of the package as based on a ccmbination of dose comparisons with a similar existing package when loaded with Co-60 and simple poir* source calculations accounting for the differences between the new and existing package. The approach is acceptable. However, the application does not provide drawings or calculations in support of reduced streamings by factors between 2 to 7 depending upon the source holder configuration. f/ fo f-d 3C 46 / The application should provide sketches with the appropriate dimensions 5. v.1 and materials and the shielding calculations in support of the descriptions f.4t.3 - and statements both for the normal and accident conditions. f. 9. y OPERATING PROCEDURES
- 1. The operations in Procedure R 2014 which address the shipment of an empty 7. 4 /
package should make reference to 49 CFR 5173.427. 22 Zo /4 Xee /
- 2. Operation 5.3.8 should be expanded to include installation of the closure;r.= /,4,fJ~
. bolts and the torque requirement. /
ACCEPTANCE TESTS -
~ 1. In paragraph 8.1.1, Visual Inspection, specify the nondestructive 6?. /. /
examination procedures and acceptance criter sa that will be used to determine weld joint integrity.
- 2. In paragraph 8.1.5, Test for Shield Integrity, define the grid pattern ' g;j, g-that will be used to inspect 100% of the package surface.
MAINTENANCE PROGRAM
- 1. A gasket replacement schedule should be specified based on maximum gasket F.2.
service life.
- 2. The maintenance program for the wooden proted;ive jacket should address gr. 2L the conditions cited in 49 CFR 5178.194.4 I
og. %y y l0 t'<fe: j 4&
.> N> V # IMAGE EVAL.UATION / j
\
'(#'-
4$h@ TEST TARGET (MT-3) %Y e [<e.[<v$ (j
<(9 v y% # 4e 4 1
1.0 k!" "" y [,f SM
'p- '
p{ 2.0 t liuissa l*l " UW k=l.8== 1.25 i 1.4 lit i.6 i, -- L 4 150mm > 6" *
!!-? /
'fy $
g.hr cg7 <!$>%s , "Ya
- ${few, by ggr
-x#8);g,;fh.[4' i . ,.
!- I I~iiu , _
, ,_ m. a ce c u sasi _
__.q _i
- s. O.
.6 " $ n,'h. ;- (O
%y@',\>J+@ N.99". IMAGE EVALUATION \\ 9 j/
6 @,
\
- th*
; TEST TARGET (MT-3) ifg x,/ gf&
gy /g yy Rg 4g 4'Rik te
- _ +~s ;+ _.
a 221 E!! 2.2
,n " dica
~
- ". Mil 2.0 l r *- ihu#
l*l 2. l.b w l.25 I I.4 1__ in 1.6IL_
< 150mm
- 6" #
l Ne/ 97' g,& 4V,$ ,*x Q715,p m l 0 x , m i.
,g - -
,< @s m,4 ty,+V f
/ /,/, c i- , _. i n4
[ -- j!3
'Nw g
Q$ ap '& lO g k $$? IMAGE EVALU ATION 8f h?
##'k/ ((gp&g
\;gp/N *kQ$* TEST TARGET (MT-3) . 2V ,g 4g
, y, /// z
9
$+# %<<%
l.0 E a 24 u2 m20 j,j b t I:7 gi m e
^
s==ts a l.4 Pi 1.6 l.25 'h{ iL= 4 150mm
- 4 6"
- 4 4th pg+%
&) 4)% ,;_~
+4$%, );[':;,,!/fx\
- 47[4[/ fyN\
-- ~ -
my //. J,.r ' s g;,
/,/ ..
s w i _. .a N=Q A,i,
w .s s A b N'Qs w 9:,s
% ~O 99 1
IMAGE EVALUATION SO
$q,he j/
\ ^
E 'I'" O$9 TEST TARGET (MT-3) y/vg,, 8 . ' &x,, s\'f
/
s
,- y s -
p, [/ 4 4 (? \ 9++ ' % 4e<w i 1.0 ? ? "3 Gm ,3 m t au pnem 23 j,l ^ 8 0,w=8 [1.25 1 'i 1.6
- l. Bla=.4
! =- ! ==
4 150mm *
* ~
6" >
/ $P l& pp d ,p,*>\\
s:yy y &p 4sp'b gyff y 3 , g,
/ y g<p9
- r. s 55$,u~. ' . . :x s a. saxwn:8$N . .a
7/- 53(o1- W g' ' S' - e
#E2NE 2. NEUTRON JAODUCTS inc yd ,z$o%
~
Dickerson Maryland 20733 U.S.A. ( Q g comy ,% ,c-. 30)(349 3001 TWX: 710-828 0342
% w g, 4 vs t -
v> ,
"' ""*1 NI p yf$_
.! . .r.~.%
9 June 21, 19
't ?
0 g Dr. Martin A. Welt l 4 [' Q N
;f d
7 f.sg 4Q M c- " ~ ,3 Dpate y3gc g President \ -- -1 [0N 4[ Radiation Technology, Inc. g.W E 6 G39 y c% P.O. Box 185 6 ,. g h
- tut 0 g33 hj 108 Lake Denmark Road .pd ', cu.Sg$ptn g '
Rockaway, New Jersey 07866
- CP 'e cS> ,
_ g , s C
Dear Marty:
7" I an writing in response to your letter of June 7,1982. Since receiving this letter I have reviewed the facts with those of our employees whc were involved in the shipment. To the best of my knowledge, the facts are as presented below.
- 1. The number of sources contained in the shipment, per our April 20, 1982 me.:,
was based on the information we were given by your West Memphis plant manager. I have laarned that this figure was calculated by subtracting the number ci sources of each type determined by Radiation Technology' to be remaining at West Memphis aftt.: the cask was leaded, from the number of sources of each type determined by Radiation Technology to be present at West Memphis before the cask was loaded. Neither your people nor ours counted the number of sources of each type which were placed in the cask.
- 2. In unloading and reloading our shipping container in Dickerson we undertook a concerted effort to assure that all sources removed from the container were returned to the container, and we have every reason to believe that we suc-ceeded in that objective. Unfortunately, our efforts to documer.t that f act
- only add to the confusi~on in that we counted 109 C-ISS pencils removed frer the container, and 109 C-188 pencils returned to the container, but in cou- -
ing the sources in the holders in which they were temporarily placed, we counted only 10S C-188 pe- '1c. At no point did we court 107 C-188 pencils (as you say we did in yot - une 7,1982 letter), so we .re unable to confi- : your count in any respe In addition, we counted 52 GE capsules removed from the container, and 52 JE capsules r; turned tc the container, but only counted 51 GE capsules when they were in holders. Therefore, although we verified at Dickerson the calculated numbers received from yot.r West Memphis plant in both the removal of sources from the cask, and the return of sources to the cask, our total was only 159 (108 C-188's and 51 GE) sources in between these activities. 1 ( r= tv- e = p p e r-
'i 1
-gt M m u m W '
t ._
- . . _ _ ~ - - . - . -._ - -. - - . . _ .
Dr l Martin A. h'elt Radiation Technology, Inc. June 21, 1982 Page.Two-
- 3. In view of the discrepancy in the count of sources at Dickerson we undertook a concerted effort to locate any sources which might have been misplaced.
There aren't that many possibilities, and we have not located any additional' sources here. Also we re-examined our cask to check once again that no sources are hidden in ey of the tubes and car. assure you that there are not. Accord-ingly, we have to reason to believe that we failed to deliver to Rockaway any of the sources we picked up at liest Menphis. . . If you would send us a list of serial numbers of the sources in, the shipment, we would be pleased, in the course _of our next full inventory to be alert to the possibility that one or more of these sources may have indeed been mis-placed. In the interim, please be advised that the likelihood that one of your sources is hece is remote, and undertake to review your records to see if you can resolve the discrepancy within your 'wn o ecmpany. Although we do not believe there is any discrepancy between what was loaded in the cask at West Memphis and removed and reloaded at Dickerson, by copy of this letter we are, in accordance with your suggestic , notifying the Nuclear Regulatory Cc: mis-sion of the potential discrepancy. Very truly yours, NEtHRON PRO UC S, INC
/ f J." Ransoho f '
.esiden't JAR /mbn cc: li/
Enclosures:
RTI Letter dated 6/7/82 NPI Memo dated 4/20/82 Mr. Bernard Bevill, St. of Arkansas Mr. Robert E. Corcoran, St. of MD, D MI dir. Charles McDonnell, NRC hr. Carmine Smedira,.NPJ
.Mr. Marvin Turkanis, NPI
-f neurson anoouc1s.inc - -. .- .
JUN E 1982 l 805 a15 0n e C 7 D O.,0 ($ y, . n c.
- P, O. BOX 185,103 LAKE DENM ARK ROAD, ROCKAWAY, N. J 07866 WW L*
-(201) 625-8400 CERTlFlED MAIL #P30 3554108 June 7, 1982 Mr. Jack Ransohof f , President Neutron Products, Inc. - - ,
~
22301 Mt. Ephrain Road Dickerson, Maryland 20753 ,
Dear Jack:
We wish to advise you that we have now re-counted the number of sources delivered to us on Friday, May 28, 1982, and have confimed that there are only 107.AEC'.. C-188 pencils. This is two pencils less than were supposed to have been delivered in accordance with your letter dated April 20, 1982, which indicated that you vere shipping 109 AECL C-188 pencils from our West Me phis facility to our plant ir. Rockaway, New Jersey. I had centioned the apparent discrepancy to Marvin Turk:ais during our last telephone conversation, and he confirmed that prior to reloadi.; the cask for shipeent to our f acility, thrce counts were made, and he indicated that there were 109, 109 and on the final count, only 107. We tereby request th'a t y ou locate the two pencils and make delivery at the same tice that you planf to pick . up your demineralicer. Since these pencils were to have been delivered at the : ice of the final shipment, we would suggest that you make arrangements to unload the sources in our R&D pool, utilizing your A-frame hoist which you were going t o .:se in 1978 to deliver the 12 pen ils that were finally delivered on May 28, 1982. We vill assume that you will notify any of the app opriate authorities concer.ing ;- the discrepancy in the shipping papers as agaid .s what was delivered. Very
/
tt' lygo
^
-- k Martin A. Welt Ph.D. . .- . ..
President '
. MAW:ca I
l
.RADI ATION RESEARCH & PROCESS!SG FOR INDUSTRY SINCE 1968 9
^
^' __ 5 April.20, 1982 To Whoolt May Concem: . Neutron Products is shippitg 161 sources (109 AECL type CISS and 52 GE type GEP916) from Radiation Technology's West Meephis, Arkansa. facility to Radiation Technology's Rockaway, New Jersey facility, inu ..:ntal to the delivery of approximately 1,100,000 curies of Neutron Product's produced ; cobalt-60 to Radiation Technology's West Meephis facility. , Dr. Welt of Radiation Technology advises that they are licensed to possess these sources at the. Rockaway facility. Radiation Technology has dete=ined that these sources are Icak free, based on the measure =ent of the act i i v ty of the water in the storage pool at their. West Me:rphis facility, per Dr. Neit. . - Sincerely, NElfrRON PRODUCTS, .INC. . 'j Marvin'M. Turkanis -! Vice President .. .
. ~
[ tw . - l - I g L I e
- l. .
p - po
* .f ib' , , e}}