ML19340D280
| ML19340D280 | |
| Person / Time | |
|---|---|
| Site: | 07105957 |
| Issue date: | 11/17/1980 |
| From: | Voth M UNION CARBIDE CORP. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19340D281 | List: |
| References | |
| 17894, NUDOCS 8012290618 | |
| Download: ML19340D280 (4) | |
Text
, _ - _ _
yf 7/-Wl UNION CARBIDE CORPORATION MEDICAL PRODUCTS DIVISION
- w. m 3a m.t no. m a v on na m TE LE PH'JNF 914 331 2131 4
Novemter 1/y 198 f
c:
A' g
p C7 shi Mr. Charles E. Mac Donald, Chief Transportation Branch i,j
. ol!
Nfj Div. of Fuel Cycle & Material Safety Mp CP U. S. Nuclear Regulatory Commission y
2 g5 Washington, D. C.
20555 g
g
- y m
5 y
8
Dear Mr. Mac Donald:
On July 14, 1980 we requested that Certificate of Compliance 5957 for the Model BMI-l shipping cask be amended to allow shipments of a new form of content.
This request was.followed by a safety analy-sis submitted in our behalf by Battelle Columbus Laboratories on August 25, 1980. We have'been requested to provide the additional information included herewith.
Union Carbide Process Uranium Oxide Container
=
This container is described in Section 1.2.1.2(i).of the Safety Analysis Report.for the Model BMI-l Shipping Cask, Revision B, August 1, 1980. The contents will not decompose at temperatures below 0
800 F. which is well above the maximum container temperature (335 p,)
0 calculated to exist during the hypothetical fire. A revised drawing of this container, drawing' number 101501 Revision A, is attached. This drawing is also identified as replacem(nt Page number 1.32(a) for the SAR, replacing the page included with the August 25, 1980 Battelle sub-mittal. Also attached is a replacement for Page 1.7 cf the Battelle submittal; the only change being reference to Revision A of th'c con-tainer drawing.
Union Carbide Target U 235 Special Form Capsule This container is described in Se ction 1.2.l'.2(j) of the above referenced SAR.
Containment-Each of the above containers are one-time-use containers.
They will be 100 percent helium leak tested. initially with a maximum al.
3 lowable Icakage of 10-6 atm cm /sec. All containers which must be un-capped after the initial leak test will be retested using a vacuum / bubble 3
technique for a pre-shipment verification of less than 10-3 atm em /sec. 17694' 80pt1904I1 y+
p y
-=w-,-*y---g w-g w.
a-g w
y,
--s-y-
,wy--*-----r--
vpur-g, gy tvym 9
-t-"r-"-r-'
y g-1-'w9e w-WN+T gMq' g+#4y v
v--
Mr. Charles E. MacDonald
- Page 2 -
U. S. Nuclear Regulatory Co mnission November 17, 1980 Should you have further questions, please call immediately.
Yours Very truly, a
r (C
i 1
) CU M
~
FDIV:ltm Marcus H. Voth Manager Nuclear Operations Enc.
Drawing Number D-101501, Rev. A (8 copies)
Replacement for Page 1.7 Replacement for Page 1.32(a) cc:
Mr. R. J Burian, Battelle o
A
Document: 5 1.7 (h)
EMI-l Easket E2acer BMI-l Cask Basket Spacer for ALRR Converter Fuel; Ames La?> oratory Research Reactor, (Tile Drawing) Number RRM 245, dated 4 /.1/ 7 7.
(i)
Union Carbide Process Uranium Oxide Container Union Carbide uranium oxide waste form process shipping container as shown on Union Carbide Corporation Drawing No. 101501, Rev.
A.
(j)
Union Carbide Target U Special Form Capsule Union Carbide target material special form capsules having, nominal outside dimensions of 1.25 inches'OD x 18 inches long, and made of,AISI 300 Series stainless stee's.
1.2.2 Operational Features Operation of the BMI-l is discussed in Section 1.2.1.,
Section and the referenced drawings clearly explain opera-That tion of the cask and show all valves, openings, seals, etc.
1.2.3 Contents of Packaging 1.2.3.1 Description of Cask Contents In accordance with the requirements of 5 71. 2 2 (b) of 10-CFR-71-Subpart B, the materials planned for shipment in the BMI-l cask are described as follows.
Rev.
B.
8-1-80
g *..:.;.. *. ;.*. C. 5.. M.. l,.
"a
..y
~. <. -
,1.e au
_......a.
1.32(a) 0]
E'] CG 00 1
e
\\
l l
s
\\
-"EV org
\\
,,_._,_ a.pt istm !D E S ^ ~'
E A gyr.
-d.: rr<r - -
j
~
.. :,8, t
. \\\\
y -
m
,1..'hy;
)
~
= "'j =\\Qf, aun.,.m n m y-.h
/n,$ 5 xc
/
+:.
.. L n
2s et 82 TuSE (EE d
.e. o o4 (n r d g_
note:
@ y rie w e,o..o.t....u...... v. c. v... -...ou n u r m,u n
.sa =o
..e 9 o,.a 5, sous.u ceuurris 1orCDrov cou=x scr.-ra ri" e
u r T u s us,,t.
s unt GD
" C'" '
' Tl H R, esto scas f
, O e
CAP 4am u i e
net. iso e c..cis a a a eum
{
t F eTl e%
Q}
}
TOP Cs P S oD S ToslE m ALLM
.O u,. o. ci,...oc covencm cyt. ore aoo.es.n
~..... -
cu 's oo iv.u -
go WA S T E FO*t M RftOtf S S i
w, o e.
n;..c.y..sgig,.,y g ;< a m 6sizrIDl....
j,
.... 101501 A lO e
rou s num
.s
@Battelle 4' '
Columbus Laboratones
/
503 lung Avenue Columous. Ohio 43201 Telephone 1614) 4244424 Teies 24 5454 A
-)
August 25, 1980
,e e
Mr. (":srles E. ' Mcdonald Transpr.atstion Certification Branch
/
Division of Fuel Cycle and Material Safety U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Mcdonald:
Docket No. 5957, certificate of Compliance for the Model BMI-l Shipoing Cask Battelle's Columbus Laboratories requests an amendment to t e subject Certificate of Compliance for the transport of process uran: tm oxide powder in the BMI-l ca.sk.
The powder is a recovery product f the Union Carbide Corpora ion's Medical products. Division. In support of,
this request we are enclosing eight (8) copies of replace =ent pages for the Safety Analysis Report for the Model BMI-1 Shipping Cask.
The replace =ent pages address the use of a specially designed Union Carbide process uranium oxide container and a special form capsule i
proposed as the containment vessel for the uranium oxide. Both of j
these contain=ents will be transported in the existing BMI-l cask and baskets. We request that the amendment specifically permit the following
- 1) Transport of up to 352 grams of [
in oxide form in each of the twenty-four (24) process containers described by Union Carbide Corporation Drawing No. 101501, Rev. O.
The maximum decay heat load per capsule is 20 watts.
- 2) Transport of a mixture of Union Carbide process containers (maxi-
=um of 352 grams of U235 in oxide form) and MTR type fuel elements in any proportion up to a combined total of twenty-four (24). The MTR type fuel elements shall comply with the specifications for MTR type fuel elements stipulated by Revision 6 of the subject Certificate of Compliance.
dy 4 odaq1 M r 1
50 Years Of Service 1929-1979 N
e
Mr. Charles E. Mcdonald 2
August 25, 1980 35
- 3) Transport of up to 100 grams of U in oxide form in each of twenty-four (24) special form capsules. The decay heat load per capsule nay vary.
However, the combined heat load of all capsules may not exceed 1500 watts (rating of the BMI-l cask).
- 4) During transport, the three types of contents described above will be securely confined in the existing BMI-l baskets so as to preclude secondary impacts during accident conditions of transport.
The fee for your review of this applicaticn was sent to you on July 14, 1980, by Mr. Marcus H. Voth, Manager, Nuclear Operations, Union Carbide Corporation.
A copy of his letter is attached for your reference.
Also attached is an index of the replace =ent pages indicating the safaty related features of the changer.. All replacement pages are identified by the legend "Rev. B. 8-1-80" centered on the bottom margin..If only part of the text on any one page is changed, that part is identified by a v.<rtical bar in the outside page margin opposite the revised or added material. If the entire page is revised or added, no bar is used.
If you have any questions co*cerning this application, please telephone me at FTS 976-7502.
Sincerely, d
Richard J. Burian Principal Research Engineer Nuclear and Flow Systems Section RJB/ll.1 Enclosures (10) cc:
Mr. narcus H. Voth, Manager, UCC
J
/ ~.
!I J. ),.3J).@,'
UNION CARBIDE CORPORATION
- 4
N!~i i -
3 M: DICAL PRODUCTS DIVISION e.c. 30 X 324, T WX E cc. N EW v 3 8t K 1094?
TE.E8adoNE. 83 4 35122 33 July 14, 1980 Mc. Charles I. MacOonald, Chief Transportation Branch Oivisien of Fuel Cycle and Materials Safety U. S. Nuclear Regulatery Cc-. ission Washing cn, O. C. 20555 Ret Reruest fer Amendment to certificate of Cem:11ance 5957 1
Oear Mr. Mac0cnald:
Union Carbide hereby requests that Certificate of Cc=pliinc.
a 5957 fer the Model 3MI-1 shipping cask be amended to include in the cen-tents appreved for shipment, containers cf irradiated fissile target material.
Tr.is material, which is the end proiuct of our process fer irradiating and separating medical radicisetepes, has been disposed of as radioactive waste in the past.
In the future we will recover the material and ship it to a reprocessor.
The centainers we prepese to use are of sixtilar materials, dimensiens, and materials as MTR fuel elements which are already ap-preve" '~~ -he 3MI-1 shipping cask.
The same baskets can be used as are already designed fabricated and licensed.
We have engaged Batteile Celu= bus Laberatories, the primary licensee of the cask, to perfc m a safety analysis of the differences between the propcsed and already appreved contents.
The safety analysis will be sent to you directly by Battelle in early August. Since we will be shipping spent reactor fuel in the EMI-1 shipping cask during the month of September we ask that the' license be amended as soon as possible to allow us to =ake our first shipment of recialmed target material in September while we have the cask.
This matter has been discussed with Mr. Richard Cdegaarden of your s aff some weeks age.
In an attempt to expedite matters we are filing the license amendment fee at this time to avoid any delay when, the safety analysis is available to you.
Attached you will find a check for $2,800.00 to cover the fee for a miner amendment to certifi-cate of Cec:pliance 5957 Yours very truly, MMY ' --
arcus H. Voth Manager Nuclear Operations cc:
Mr. Richard J. Surian - Battelle Mr. Richard Cdegaarden - NRC q\\
day q N 4 bbl % LV w..., -
wr -
...r,.
.c
.----r
-.ev.
r-sv,
+w,
+,.,-,u-,~,~,-we 7
-.-.,y r-e.
e- -,
INDEX TO REPLACEMENT PAGES FOR REVISION B, 8-1-80, OF SAFETY ANALYSIS REPORT FOR HODEL BMI-1 SilIPPING CASK Page Humber Section Safety Related Features Removed Inserted Number Title Cover page Cover page Safety Analysis Report none for the Model BMI-1 Shipping Cask, Rev. B, 8-1-80 Tables of Contents, none Tables, and Figures 1.7, 1.8 1.7, 1.7a, 1.2.1.2(1);
Description of Product none 1.8 1.2.1.2(j)
Containers and Baskets 1.9 to 1.12 1.9 to 1.12 1.2.3.1 Description of Cask Contents (2)(b) With Leakproof Inner Container none (3) Chemical and Physi-cal Form none (5) Maximum Weight none (correct typographical error in Rev. A, 3-28-80) 1.19 1.19, 1.19(a) 1.2.3.2 Type and Form of Con-tents Material (j) Union Carbide Process Uranium oxide Containers none (k) Union Carbide 235 Target U Special Form Capsules none 1.32(a)
Union carbide Corpora-tion Drawing No.
101501, Waste Form Process Shipping Con-tainer Outline Dwg.
none
INDEX TO REPLACEMENT PAGES FOR REVISION 11, 8-1-80, OF SAFETY ANALYSIS REPORT FOR HODEL BH1-1 SilIPPING CASK (Continued)
Page Number Section Removed Inserted Number Title Safety Related Features 2.41, 2.42 2.41 to 2.42(a) 2.8 Special Form none 2.81, 2.82 2.81 to 2.82 2.10.5 Union Carbide Process Uranium oxide Container 2.10.5.2 Normal Conditions Stresses less than the yield strength and endurance limit 2.10.5.3 Accident conditions fluckling does not occur; stresses less than the yield strength 2.107, 2.108 2.107, 2.108 2.12.1 References none 2.223, 2.224 2.12.4 Listing of PRSVSL none Computer Code 3.3, 3.4 3.3, 3.4(a) 3.1.2 Haximum and Minimum Decay llent (f) Union Carbide Pro-cess Uranium Oxide Container none (g) Union Carbide 235 Target U Special Form Capsules none 3.5, 3.6 3.5 to 3.6(a)
Table 3.1 Thermophysical Proper-none ties Employed for Lead, Steel, and Aluminum 3.21, 3.22 3.21 to 3.22 3.4 Thermal Evaluation for Normal Conditions of Transport 3.4.2 Maximum Temperatures
~
INDEX TO REPi ACEMENT PAGES FOR REVISION n. 8-1-80, OF SAFETY ANAI'.YSIS REPORT FOR HODEI. BMI-l Silli' PING CASK (Coutinued) i Page Number Section Removed Inserted Number Title Safety Related Features 3.4.2.4 Union Carbide Process Maximum Container Temperature:
Uranium oxide Contain-315*F at 130*F ambient; Tempera-ers ture is acceptable.
3.4.2.5 UgnCarbideTarget Maximum Capsule Temperature U
Special Form 1290*F at 130*F ambient; Tempera-Capsules ture is acceptable.
3.40(a) to 3.5.4 Evaluation of Package 3.40(d)
Performance for the Hyptotbetical Accideat Thermal Condition 3.5.4.2 Maximum contents Temperature (d) Union Carbide Maxista Container Temperature:
Process Uranium 586*F; acceptable Temperature.
Oxide Container (e) Union Carbide Maximum Capsule Temperature:
i Target U235 Special 1325"F; Acceptable Temperature Form Capsule for Special Form Capsule 3.41, 3.42 3.41, 3.42 3.6.1 Refe rences none i
4 6.13, 6.14 6.13, 6.14 Table 6.3 Composition of BHR's none (correct typographical Fuel Assembly error from Document 9) 6.39 6.39 to 6.49 6.8 Criticality Evaluation for Union Carbide Pro-cess Uranium oxide 6.8.2 Normal Conditions Subcritical, less than critical mass 6.8.3 Accident Conditions Subcritical, maximum k,gg ='O.833 i 0.011
- s
INDEX TO REPLACEMENT PAGES FOR REVISION B, 8-1-80, OF SAFETY ANAL.YSIS REPORT FOR HODEl. liHI-l SillPPING CASK (Continued)
Page Number Section Removed Inserted Number Title Safety Helated Features 6.8.4 Caiculational Hodel Subcritical, maximum kegg = 0.810 (Frocess tiranium Oxide
.1- 0.010 Cantainers with Inter-rpersed HTR Fuel Elements) 6.9 Criticality Evaluation for Union Carbide Special Form Capsule 6.9.2 Normal Conditions Subcritical, less than critical mass 6.9.3 Accident Conditions Subcritical, by reference to linton Carbide Process Uranium oxide Containers 6.10.1 References t
I
SAFETY ANALYSIS REPORT i
for THE MODEL BMI-l SHIPPING' CASK Revision B August 1, 1980 from i
BATTELLE'S COLUMBUS LABORATORIES 505 KING AVENUE COLUMBUS,. OHIO 43201 i
.o a.
f 5
moa 6
.,. ~..... _..
.,,.