ML19290C126
| ML19290C126 | |
| Person / Time | |
|---|---|
| Site: | 07109069 |
| Issue date: | 07/13/1973 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19290C116 | List: |
| References | |
| 14907, NUDOCS 8001090513 | |
| Download: ML19290C126 (18) | |
Text
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N ATTACIIMENT III I
i I
WESTINGIIOUSE ELECTRIC CORPORATION APPLICATION FOR AMENDMENT OF LICENSE SNM-1107 FOR NFD SIIIPPING PACKAGES JULY 13, 1973 9
1728 233 W
U.
S. ATOMIC ENERGY COMMISSION DOCKET 70-1151 8001090 3
SNM-1107 Shipping - NFD ATTACHMENT III TABLE OF CONTENTS i
Section Page No.
i Revision Record 5
1 l.
Introduction 10 2.
Correspondence - Return Address 10 3.
Administrative Control 10 10 4.
R.C.C. Packaging 4.1 Packaging Description 10 4.2 Contents Description 11 4.3 Compliance with Subpart C of 10 CFR 71 12 4.4 Fissile Class II Limits 16 4.5 Fissile Class III Limits 16 4.6 Procedural Controls 16 17 5.
C.C. Packaging 17 5.1 Packaging Description 5.2 Contents Description 18 5.3 Compliance with Subpart C of 10.CFR 71 19 5.4 Fissile Class II Limits 22 5.5 Ficsile Clacs III Limits 23 5.6 Procedural Controls 23 6.
SELNI Fuel Rod Shippi"g Package 24 6.1 Packaging Description 24 6.2 Contents Description 24 6.3 Compliance with Subpart C of 10 CFR 71 25 26 6.4 Limits and Controls 7.
RCC-1 Packaging 26 26 7.1 Packaging Description 7.2 Contents Description 26 7.3 Compliance with Subpart C of 10 CPR 71 26 7.4 Limits and Controls 27 Docket 70-1151 Date: 7/13/73 Revision No.
Dafo:
Popo 1
SNM-1107 ATTACIIMENT III Shipping - NFD TABLE OF CONTENTS (continued)
I Page No.
Section g
8.
BB 250-2 Shipping Package 27 8.1 Packaging Description 27 8.2 Contents Description 27 8.3 Compliance with Subpart C of 10 CFR 71 28 8.4 Fissile Class II Limits 34 8.5 Fissile Class III Limits 34 8.6 Procedural Controls 34 9.
RCC-2 Packaging 35 9.1 Packaging Description 35 35 9.2 Content,s Description 9.3 Compliance with Subpart C of 10 CFR 71 35
^N 9.4 Limits and Controls 35 10.
RCC Fuel Rod Shipping Package 36 10.1 Packaging Description
'36 v
10.2 Contents Description 36 10.3 Compliance with Subpart C of 10 CFR 71 37 10.4 Limits and Controls 38 11.
Mixed Oxide Fuel Shipping Package 38 11.1 Packaging Description 38 11.2 Contents Description 38 31.3 Compliance with Subpart C of 10 CFR 71 39 11.4 Limits and Controls 41 I
42 12.
Super Tiger Packaging 12.1 Packaging Description 42 12.2 Contents Description 42 12.3 Compliance with Subpart C of 10 CFR 71 43 12.4 Fissile Classifications 45 12.5 Procedural Controls 45 1728 235 Docket 70-1151 Date: 7/13/73 Revision No.
Date:
Page 7
l ATTACHMENT III SNM-1107 s,
Shipping - NFD TABLE OF CONTENTS (continued)
Section Page No.
13.
Pellet Shipping Package 46 l
13.1 Packaging Description' 46 13.2 Contents Description 46 13.3 Compliance with Subpart C of 10 CFR 71 48 13.4 Fissile Class II Limits 53 13.5 Fissile Class III Limits 53 13.6 Procedural Controls 53 Appendix A - RCC Shipping Container Data Appendix B - CC Shipping Container Data Appendix C - BB 250-2 Shipping Container Sketch Appendix D - Enrichment Pattern - SCE Mixed Oxide Assembly l
Appendix E - Pellet Packing Drawing and Nuclear Criticality Safety Data Appendix K - RCC-1 Shipping Container Data 1728 236 Docket 70-1151 Dorfe: 7/13/73 Revision No.
Dofe:
Pope 1
/,
ATTACHMENT III SNM-1107 Shipping - NPD s
10.3 (continued) i If one box of loose rods and one fuel assembly are loaded i
in a single package, the resulting reactivity values would i
be some intermediate values, so that a mixed load will also be nuclearly safe.
10.'4 Limits and controls The Fissile Class II limit, Fissile Class III limit and Procedural Controls presented in Section 4.4',
7.4, or 9.4, will apply directly to this package.
- 11..
Mixed Oxide Fuel Shipping Package 11.1 Packaging Description The RCC, RCC-1 or RCC-2 Packagings described in Sections 4.1, 7.1 and/6r 9.1 will be used.
When loose rods are being shipped, the inner box of #13 Ga. steel described in Section 10.2 will be used.
11 2 Contents Description Radioactivity - 250,000 curies, maximum Identification of SNM - The SNM will be plutonium at several weight percentages (not to exceed 4.4 w/o) in natural uranium.
Form of SNM - The SNM will be in the form of plutonium oxide mixed with natural uranium oxide.
The mixture will have been pressed and sintered into pellets, clad in Zircaloy as fuel rods and possibly, assembled into clad fuel assemblies.
Tests have established that the clad fuel rods meet the criteria for special form materir_
1728 237 Docket 70-1151 Date:
7/13/73 Revision No.
Date:
Foge 38
SNM-1107 ATTACHMENT III Shipping - NFD 11.2 (continued) i Specific data on maximum parameters are:
1 Pellet Material PuO2 - UO2 PuO2 - UO2 I
Highest w/o Pu (Nom.)
3.31 w/o Fissile 3.6 w/o Fissile Diameter (Nom.)
.367"
.367" Rod Cladding Material Zircaloy Zircaloy Diameter (Nom.)
.429"
.422 i
Fuel Lgth. (Nom.)
120" 144 Cladding Thick. (Min.) 0.018" 0.018" No. of Rods per Assy or Box (Max) 180 361 Pattern (Ba sic) 14 x 14 sq.
Sq.-Close Packed Lattice Pitch
.556" (Nom)*
.556 (Max)
Outside Dimen. (Nom.)
7.8" sq.
8.2" sq.
- See Appendix D for enrichment pattern Total Pu (Max /pkg.)
29 kg 66 kg (Max /MCA) 0.97 0.977 keff Poison Pl. Reg'd OFHC Copper Steel Box
-Net Wt.
(Max.)
2500#
5500#
l, The descriptions and discussions contained in Sections v
- 4. 2, 7. 2, 9.2 and/or l'O.5 will be directly applicable if ~
references to Appendix A and Appendix K are superseded by
~
the specific data in this Section.
11 3 Compliance with Subpart C of 10CFR71 The descriptions and discussions contained in Sections 4.3, 7.3, 9.3 and 10.3 will.be directly applicable, provided that:
(1)
The references to Appendix A and Appendix K are superseded by the specific data in this Section.
(2)
The reference to the nuclear criticality safety of unmoderated uranium enriched < 5 w/o is super-seded by the statement that LEOPARD,. PDQ-03 cal-culations have established that an infinite lattice 1728 238 Do kel 70-1151 Dafo: 7/13/73 Revision No. 5 Defe: 3/19/75 Poa 39
N.
SNM-1107 ATTAC!! MENT III Shipping - NPD 11.3 (continued) of mixed oxide fuel assemblies as described in i
Section 11.2 will have k, <1 in the unmoderated 8
condition.
Therefore, any number of unmoderated packages will be nuclearly safe.
The requirements of 5 71.32 are readily fulfilled by this package.
Calculations of the stresses which would occur in the packaging shell when transporting fuel assemblies result in a computed maximum stress of s 7,250 psi for a 36,000 lb (5 X 7200 lb) uniformly distributed load.
When transporting boxed fuel ~ rods, the maximum stress is calculated to be approximately 10,300 psi.
These values both are well below the accepted yield strength value of even a mild steel, and the maximum stress values are conservative since the calculations do not consider the effects of the rest of y
the packaging structure, such as the very rigid support members that carry the shock mounts.
Basic computations are supplied in Appendix D.
With regard to pressure resistance, the package loading is restricted to clad fuel rods.
Regarding each fuel rod as the containment vessel for the fuel pellets within it, each containment vessel is designed.Tto withstand, without failure, an external pressure of 2250 psi at elevated temperatures.
The 25 psi external preasure criteria is very conservatively less than these,de,sian working parameters.
\\
\\.'fi 1728 239 r_
Docket 70-1151 Date:
7/13/73 Revision No.
Date:
Pogo 40 V
2'
SNM-1107 ATTACIIMENT III Shipping - NFD 11.3 (continued)
The nuclear criticality safety model used to evaluate i
the transportation of boxed rods is supplied in l
Appendix D.
11.4 Limits and Controls i
The Fissile Class II limit, Fissile Class III limit.and the Procedural Controls presented in Sections 4.4, 4.5, 4.6, 7.4 and/or 9.4, as appropriate, will apply directly-ly to this package.
1728 240 e.<
v Docket 70-1151 Defe: 7/13/73 Revision No.
Date:
Pogo 41
/,
s ATTACHMENT III SNM-1107 Shipping - NI'D APPENDIX D i
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h RCC GUIDE TUBE Typical 1:nrichment Pattern for Mixed Oxide Assemblics
/.
~
.. ATTACilMENT III APPENDIX D
SKETCH SHEET f onu 28577
.+
e WESTINGHOUSE ELECTRIC CORPOR ATION Ch.catarious FOR LICGNSiNCo I
I ReF. AEC n'ot Es suo pesvi.Arrons PART 7/, PAcKAblNG-RA Dio ACDV'8 HATERihL F~oR 7*RAtJSPOR7' f 0 7, 7l. 3 2.
2 oF 2."
1 ORNL-NSic-ee OAsr Persionets Guioc f 92-3 From. 1-e f. 2.
we ha.v e 2.82 UJhes rego.vdeA as a simple beast supported at its end cJong asty myor o-xis, the coSk most b e cspable of asthstasiding o. Static, loa.d nornut to e d ont formly distvibuted l
ofon oss leng &, e7 val to five times the l
40ll lcded cas/c weig ht without generatsvg
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stresses i>1. acy ma.teria.i of -the oask nu excess af
-the. yield streng th. o f -tha t-maleri cul.
Thd forti011, of the regalation osvally inferpreied a.s being opphed i5 to the outer shell alorse,,
DEFNiTiONS '
s = sue ss, Gb/i>&
moment' (in -Ib) t4 e bendin?ttf heig ht of ca.sk ia the a
on e h directiow C5 of-bendi (m.)
l a
IE cross se s on a./ memc>ct* of inerticr., (in.).
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SNF-ATTACIIMENT III SKETCH SHEET APPENDIX D
/f fe) re.
- n WESTlHGHOUSE ELECTRIC CORPOR ATION est cucAr10HJ FOR LIC G h/ SI N G i
bc Si n t 'hlCQM C Cf dG tioViSo.rt MC tr e
M = swt t = 3 (r - n +),
S" z
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pm D
T m
]e6 VALUE SOURCE C = rt
/66/?o02 L=
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crc.
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IMoROO3 bz = 2 0. 49 5 in (n +,oact) cec f cag oo z.
b, = 2 0. 4 c 6, n.
c R c.
1% Roos O ':
, S v> L _ (5)(7 2 00 lb){ i S'7 7 Fig) _ g gy, gg W
T 4
I = 5 (/ [2 o.4 9 5] 4- [20.4 06]+/ =2 S 91 in I
( 8 4 4 8 7 5 trt./h)(2 0. 4 75 / ) = '7 2 + 2 s=
(2 eg i iJ) 1728 243
(
The, cas k,utc h a_( i s ca.rboo steel)
S y =.9C, 000.
Smee che. stress > e>>e ns ed
<-t. th e..: A e tt unde r th o l
y Spets fied ccu di brous is only 72 4 2-fsi, if, e A E C fCfi// M'<!W11 T i5 nr 6 t~.
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I ATTACHMENT III Appendix D SNM-1107 7/13/73
(
ROD SHIPMENT - NUCLEAR CRITICALITY SAFETY MODEL i
1.0 INTRODUCTION
I Criticality calculations were performed as an analytical backup for a licensing request to ship PuO -UO2 rods.
Three 2
basic configurations were considered; (1) one flooded box of rods surrounded by an infinite amount of water, (2) two boxes in a single package flooded, and (3) the Maximum credible Accident (MCA) which consists of two packages crushed top-to-top with a separation of 1.7 inches between assemblies in different packages with both packages flooded.
For these configurations, two cases were used to describe the geometry of the rods, which will not be in assembly form but will be stacked in close contact.
For one case, the rods are assumed to h. ave a y
square pitch of 0.422 inches, which allows them to remain in contact with one another.
The second case assumes loose packing such that an effective square pitch of.556 inches is obtained.
This second case is more reactive and this study assumes that an effective pitch greater than.556 inches will be prevented by the method of packing the plutonium fuel rods.
Geometry and model considerations are described in the Figure on Page 5.
Atom densities and two group cross sections
~
are listed on Pages 6 and 7.
Table 1 summarizes the calculations performed.
{
i728 244
_1_
I'- *
' ' ATTACHMENT III Appendix D f
i TABLE 1 k gg For Considered Configurations e
i Configuration Pitch (Inches)
Calculated keff One assembly, flooded
.422 0.582
.556 0.818 f
One package (two boxes)
.422 0.686 i
flooded
.556 0.899 MCA
.422 0.768
.566 0.977 2.0 DISCUSSION The ARK, PDQ-03 calculational model was used to determine keff for the various configurations.
(The ARK Code is an updated versior.
of LEOPARD).
Cross sections for water for all cases correspond 3
to Vater at 68 F and density equal to 1 gm/im,
The PuO -UO2 rods to be shipped include three different plutonium 2
v enrichments.
These enrichments are nominally 4.2, 3.40, and 2.6 w/o total plutonium, where enrichment is defined by the following:
uO2 Total Plutonium Enrichment =
PuO2+UO2 Natural uranium is the constituent uranium with a.2350 weight percent of 0.711.
Although the proportion of the 4.2 w/o rods will be only approximately 70% of the total number of rods, it was assumed for calculation purposes that all rods were of the highest enrichment which was taken to be 4.4 w/o instead of 4.2 w/o.
It was further assumed that the mate. rial retained the isotopic distribution measured in July, 1971.
-s i728 245
/.>.
ATTACIIMENT III Appendix D 2.0 (continued)
That measured Pu isotopic distribution is given below:
Isotope w/o I
Pu-238 0.09 i
Pu-239 78.13 Pu-240 18.27 l
Pu-241 3.05 1
Pu-242
.47 Pu-239 + Pu-241 81.2
=
Total Pu
-The dimensions of the shipping box were taken to be 8.4" x 8.4" which is slightly larger than the nominal 8.2" x 8.2" as indicated by the shipping box drawing.
The geometric configuration was assumed to be infinitely long so B 2 = 0.0 g
for all configurations.
No cask or shippi.ng box steel was
(
included in the calculations for a single flooded assembly or single flooded package.
For the MCA a 0.15 inch thickness of steel is inserted'between the packages.
This amount (and placement) of steel is conservative.since this thickness is exceeded by the shipping boxes alone, without considering package steel.
The above ground rules and geometric configurations are similar to those discussed in a recent III criticality study for fuel assemblies.
Sealed rods of partial length containing pellets (a means of shipping Puo2-UO2 archive pellets) at compositions up to 4.4 w/o Puo2 will also be covered by the above calculations so long as the geometric conditions are the same as used for full length rods.
Neutron leakage due to the finite length of the fuel rod was not included in the calculations.
1728 246 (1)
See Appendix B of this application.
ATTACHMENT III Appendix-D x
- 2.0 (continued)
Specifically, short rods should be loaded end-to-end to 6
approximate full length rods.
They may not be interspersed 6
with long rods in a box such that a significant fraction of l
the long rods (regular fuel rods) has an effective pitch greater than 0.55o inches.
1728 247 6
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- ATTACIIMENT III Appendix D SAFETY MODEL ATOM DENSITIES (1024)
Pitch = 0.422 Inches i
Flooded Box Element Enrichment = 4.4 w/o Water l
Hydrogen 0.01435 0.0669 Oxygen 0.03332 0.0334 Zirc-2 0.007375 U-234 0.0000003749 U-235 0.00008999 U-236 0.000001075 U-238 0.01241 Pu-239 0.0004487 Pu-240 0.0001045 Pu-241 0.00001734 Pu-242 0.000002649 C
Pitch = 0.556 Inches v
Flooded Box Element Enrichment = 4.4 w/o Water Hydrogen 0.03662 0.0669 0xygen 0.03337 0.0334 Zirc 0.004249 U-234 0.0000002160 U-235 0.0C ~ 15184 U-236 0.0000006192 U-238 0.007147 Pu-239 0.0002585 Pu-240 0.00006020
~
Pu-241 0.000009994 Pu-242 0.000001526 1728 249 i.
).
ATTACHMENT III Appendix D
(
SAFETY MODEL NUCLEAR CONSTANTS (All Temperatures = 68 F)
I i
Flooded Fuel A.
Group 1
_ Pitch =.421 Pitch =.556 Water Steel D (cm) 1.199 1.217 1.2333 1.18 r,(cm-I) 0.01617
'0.0139 0.000471 0.00055 I (cm-I) 0.00355 0.0179 0.04760 0.000331 R
vr (cm-I) 0.01524 0.0113 0.0 0.0 f
B.
Group 2 (0.0 - 0.625 ev)
D (cm) 0.2825 0.2077 0.165465 0.337 r (va~)
1.011 0.407 0.022210 0.22 a
vr (cm-I) 1.717 0.6921 0.0 f
C Y
1728 250 s
149L7.